UNITED STATES OF AMERICA

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DOE/OSTI--3411/4

Prepared by

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Technical Information

Prepared for

The Office of Science

and Technology

A Bibliography

May 1999

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TECHNICAL REPORTS
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DOE/OSTI--3411/4

The Office of Environmental Management

Technical Reports

A Bibliography

May 1999

U.S. DEPARTMENT OF ENERGY

Prepared for

The Office of Science and Technology

Prepared by

Office of Scientific and Technical Information
THE OFFICE OF

ENVIRONMENTAL MANAGEMENT

TECHNICAL REPORTS

ABOUT THIS BIBLIOGRAPHY

The Office of Environmental Management’s (EM) technical reports bibliography is an annual publication that contains information on scientific and

technical reports sponsored by the Office of Environmental Management.

This bibliography contains citations for reports published in Fiscal Year 1998

(October 1, 1997–September 30, 1998). EM’s Office of Science and Technology sponsors this bibliography. Questions regarding the content of the

publication should be addressed to Diana Krop, Communication Program

Manager, at 301-903-7918 or Diana.Krop@em.doe.gov

PROGRAM ACTIVITIES

The Office of Environmental Management within the Department of

Energy (DOE) is responsible for environmental restoration, waste management, technology development and facility transition and management. This

Office was created in 1989 to consolidate responsibility within DOE for

environmental management activities. EM develops DOE policies and plans

related to environmental restoration and waste management and is working

to foster open communication with the public.

The Office of Science and Technology (OST) was established to conduct

an aggressive, national program of applied research, development, demonstration, testing, and evaluation for environmental cleanup solutions that are

safe and more time- and cost-effective than those currently available. OST

brings together experts from academia, the Federal government, and private

industry to conduct a wide range of research and development. Through

these unique partnerships, OST leverages resources to develop equipment

and methods to render waste management technologies less expensive,

safe, and commercially applicable around the globe. In doing so, OST seeks

to achieve the twin goals of sustaining our environment and creating economic prosperity.

AVAILABILITY

A searchable EM Technical Reports database and a portable document

format (PDF) downloadable version of this publication are now available from

OST’s home page via the World Wide Web. The database contains information on scientific and technical reports included in this publication and is

searchable by title, author, sponsoring/performing organization, DOE report

number, publication date, and abstract. The Internet address is:

http://www.doe.gov/html/em/emtrd.html

iii

CONTENTS

• EM's Information For

Decisions ONLINE

• How to Read a Citation

• How to Use the Indexes

• EM Technical Report

Citations

• Corporate Author Index

• Personal Author Index

• Document Ordering

Information

International Copyright, © U.S. Department of Energy, 1999,

under the provisions of the Universal Copyright Convention.

United States copyright is not asserted under the United States

Copyright Law, Title 17, United States Code.
iv

How To Read A Citation

11

13

12

6

3

9

10

18

7

4

1 2

16

8

Sample Citations

Report

18494 (DOE/ER/40438–T1) [Development of a hydrogen and

deuterium polarized gas target for application in storage rings]:

Progress report. Haeberli, W. Phys. VI collaboration. Wisconsin

Univ., Madison (USA). Dept. of Physics. [1989]. 12p. Sponsored by

DOE Energy Research. DOE Contract FG02-88ER40438.

This paper briefly discusses the Wisconsin test facility for storage

cells; results of target tests; the new UHV...

Report Analytic

18500 (INIS-SU—69, pp. 30-32) Transition energies in Nelike ions. Correlation effects. Vainshtejn, L.A. AN SSSR, Moscow.

Fizicheskij Inst. 1988. (In Russian). In Experimental and theoretical

physics. Collection. Order Number DE89780060. Available from NTIS

(US Sales Only), PC A03/MF A01; INIS.

Kratkie Soobshcheniya po Fizike.; no. 6.

SILVER IONS/energy-level transitions; XENON IONS/energylevel transitions; CORRELATIONS; D STATES; E STATES;...

54 (DOE/ER/60888-1-Vol.1, pp. 115-117) Investigation of air

pollution in house due to use of various fuels. Luo, Dayu (Chengdu

Sanitation (China)). Canada Mortgage and Housing Corp., Ottawa, ON

(Canada). 1990. (CONF-900724-Vol.1: Indoor Air ’90: 5th international

conference on indoor air quality and climate, Toronto (Canada), 29 Jul

- 3 aug 1990). In Indoor air ’90: The fifth international conference on

indoor air quality and climate. Volume 1: Final report. 786p. Order

Number DE90017786. Source: NTIS.

Air pollution in houses caused by combustion of coal is more

serious than that by combustion of natural gas and methane (primarily

by SO2 and NO2). The gas concentration after cooking is higher than

that before cooking, and it is higher in kitchen than in bedroom and

outdoor. There were mutations in the extract from TSP in 30m2 air in the

bedroom, kitchen and outdoor, where coal and natural gas were used.

The supernatant saliva activity of children whose family uses coal is

significantly lower than that of pumping streams.

9

5

14 15

17

The principal data elements included in these citations are:

 1. Abstract number within volume.

 2. Report number identification for report-type literature.

 3. Title and subtitle (non-English title may appear in

 parentheses, if applicable).

 4. Author(s). First 10 names in the data record are printed,

 then “et al.” is listed.

 5. Author affiliation. Only first one is listed, in parentheses

 after author(s) to which it applies.

 6. Collaboration, if present.

 7. Corporate author(s) identifying corporation responsible

 for document.

 8. Date of publication. If not known, a processing date is

 in brackets.

 9. Number of pages or page range. Prices are based on

 total pages unless special pricing applies.

10. Language of document if non-English.

11. Monograph title if citation is an analytic (part, chapter,

 or paper) of a larger monograph.

12. Sponsoring organization.

13. Contract or grant number.

14. Secondary identifying number; may be a conference

 number.

15. Conference title, location, and date, if applicable.

16. Drop note or explanatory statement.

17. Abstract.

18. Subject descriptors. Listed only if no abstract or only a

 brief statement is included.

9
Two indexes are provided for approaching the content of The Office of Environmental Management Technical

Reports. Descriptions of entries in these indexes follow.

Corporate Author Index

The corporation, organization, or institution responsible for the issuance of the document is listed in

this index. The entries are arranged alphabetically

and provide the title and citation number of the reference. For example, the listing for the "Report"

sample citation would appear as shown at right.

Personal Author Index

Each author’s name listed on a document cited in

this issue is indexed. An index entry provides title

and citation number; for secondary and other

names, a cross-reference is given to the primary

author name where the full index entry is located.

How To Use the Indexes

v

Wisconsin Univ., Madison (USA). Dept. of Physics

 [Development of a hydrogen and deuterium polarized gas

 target for application in storage rings]: Progress report,

 15:18494 (R;US)

Wisconsin Univ., Madison (USA). Lab. of Genetics

 Organization of the R chromosome region in maize: Final

 progress report, June 1, 1983–May 31, 1986, 15:18255

 (R;US)

Hadley, D.L., See Lee, A.D., 15:17651

Haeberli, W., [Development of a hydrogen and deuterium

 polarized gas target for application in storage rings]: Prog-

 ress report, 15:18494 (R;US)
Environmental Management Technical Reports

Environmental Management Technical Reports

ENVIRONMENTAL MANAGEMENT

1

(ANL–98/1)

Surveillance of Site A and Plot M report for 1997.

Golchert, N.M. Argonne National Lab., IL (United States).

May 1998. 106p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE

Contract W-31109-ENG-38. Order Number DE98006038.

Source: OSTI; NTIS; INIS; GPO Dep.

The results of the environmental surveillance program

conducted at Site A/Plot M in the Palos Forest Preserve

area for 1997 are presented. The surveillance program is

the ongoing remedial action that resulted from the 1976–

1978 radiological characterization of the site. That study

determined that very low levels of hydrogen-3 (as tritiated

water) had migrated from the burial ground and were

present in two nearby hand-pumped picnic wells. The current program consists of sample collection and analysis of

air, surface and subsurface water, and bottom sediment.

The results of the analyses are used to: (1) monitor the migration pathway of water from the burial ground (Plot M) to

the hand-pumped picnic wells, (2) establish if buried radionuclides other than hydrogen-3 have migrated, and (3)

generally characterize the radiological environment of the

area. Hydrogen-3 in the Red Gate Woods picnic wells was

still detected this year, but the average and maximum

concentrations were significantly less than found earlier. Tritiated water continues to be detected in a number of wells,

boreholes, dolomite holes, and a surface stream. For many

years it was the only radionuclide found to have migrated in

measurable quantities. Analyses since 1984 have indicated

the presence of low levels of strontium-90 in water from a

number of boreholes next to Plot M. The available data

does not allow a firm conclusion as to whether the presence

of this nuclide represents recent migration or movement that

may have occurred before Plot M was capped. The results

of the surveillance program continue to indicate that the radioactivity remaining at Site A/Plot M does not endanger the

health or safety of the public visiting the site, using the picnic area, or living in the vicinity.

2

(ANL–98/9)

A data base and a standard material for use in acceptance testing of low-activity waste products. Wolf, S.F.;

Ebert, W.L.; Luo, J.S.; Strachan, D.M. Argonne National

Lab., Chemical Technology Div., IL (United States). Apr

1998. 199p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract W-31109-ENG-38. Order Number DE98007004.

Source: OSTI; NTIS; INIS; GPO Dep.

The authors have conducted replicate dissolution tests following the product consistency test (PCT) procedure to

measure the mean and standard deviation of the solution

concentrations of B, Na, and Si at various combinations of

temperature, duration, and glass/water mass ratio. Tests

were conducted with a glass formulated to be compositionally similar to low-activity waste products anticipated for

Hanford to evaluate the adequacy of test methods that have

been designated in privatization contracts for use in product

acceptance. An important finding from this set of tests is

that the solution concentrations generated in tests at 20 C

will likely be too low to measure the dissolution rates of

waste products reliably. Based on these results, the authors

recommend that the acceptance test be conducted at 40 C.

Tests at 40 C generated higher solution concentrations,

were more easily conducted, and the measured rates were

easily related to those at 20 C. Replicate measurements of

other glass properties were made to evaluate the possible

use of LRM-1 as a standard material. These include its composition, homogeneity, density, compressive strength, the

Na leachability index with the ANSI/ANS 16.1 leach test,

and if the glass is characteristically hazardous with the toxicity characteristic leach procedure. The values of these

properties were within the acceptable limits identified for

Hanford low-activity waste products. The reproducibility of

replicate tests and analyses indicates that the glass would

be a suitable standard material.

3

(ANL–98/10)

Formulation of a candidate glass for use as an acceptance test standard material. Ebert, W.L.; Strachan, D.M.;

Wolf, S.F. Argonne National Lab., Chemical Technology

Div., IL (United States). Apr 1998. 41p. Sponsored by USDOE Office of Environmental Management, Washington, DC

(United States). DOE Contract W-31109-ENG-38. Order

Number DE98007058. Source: OSTI; NTIS; INIS; GPO Dep.

In this report, the authors discuss the formulation of a

glass that will be used in a laboratory testing program designed to measure the precision of test methods identified in

the privatization contracts for the immobilization of Hanford

low-activity wastes. Tests will be conducted with that glass

to measure the reproducibility of tests and analyses that

must be performed by glass producers as a part of the product acceptance procedure. Test results will be used to

determine if the contractually required tests and analyses

are adequate for evaluating the acceptability of likely immobilized low-activity waste (ILAW) products. They will also be

used to evaluate if the glass designed for use in these tests

can be used as an analytical standard test material for verifying results reported by vendors for tests withg ILAW

products. The results of those tests and analyses will be

presented in a separate report. The purpose of this report is

to document the strategy used to formulate the glass to be

used in the testing program. The low-activity waste reference glass LRM that will be used in the testing program was

formulated to be compositionally similar to ILAW products to

be made with wastes from Hanford. Since the ILAW product

compositions have not been disclosed by the vendors

participating in the Hanford privatization project, the composition of LRM was formulated based on simulated Hanford

1
ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

waste stream and amounts of added glass forming chemicals typical for vitrified waste forms. The major components

are 54 mass % SiO2, 20 mass % Na2O, 10 mass % Al2O3,

8 mass % B2O3, and 1.5 mass % K2O. Small amounts of

other chemicals not present in Hanford wastes were also included in the glass, since they may be included as chemical

additives in ILAW products. This was done so that the use

of LRM as a composition standard could be evaluated.

Radionuclides were not included in LRM because a nonradioactive material was desired.

4

(ANL–98/17)

Ultrasonic viscometer and methods of measuring solids

concentration. Sheen, S.H.; Chien, H.T. Argonne National

Lab., Energy Technology Div., IL (United States). Jun 1998.

31p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

W-31109-ENG-38. Order Number DE99001066. Source:

OSTI; NTIS; INIS; GPO Dep.

This report describes the progress made in FY 1997 on

the development of an on-line ultrasonic instrument for measuring fluid density, viscosity, and solids concentration in a

slurry transport line. The instrument was developed to support the tank-waste transport effort undertaken by the US

Department of Energy to treat low-level nuclear waste. A

prototype instrument was built and performance-tested at

Oak Ridge National Laboratory. Significant measurement biases were detected in both fluid density and viscosity data.

The biases were mainly the result of process temperature

variation, which changes the signals that propagate in transducer wedges. With proper temperature calibration, the

instrument can achieve an accuracy of 1% and 3% when

used to measure density and viscosity, respectively. Ultrasonic attenuation and speed-of-sound techniques are

involved when the instrument is used to measure solids concentration. Test results show that the attenuation techniques

give a better correlation with solids concentration and can

be used to monitor solids concentrations up to 30% by

weight for ka <1 (where k = ultrasonic wave number and a

= particle diameter). Measurement problems and suggested

remediations are discussed.

5

(ANL/CHM/CP–92698)

Chemistry, radiation, and interfaces in suspensions of

nuclear waste simulants. Meisel, D.; Cook, A.; Camaioni,

D.; Orlando, T. Argonne National Lab., IL (United States);

Battelle Memorial Inst., Columbus, OH (United States).

1997. 10p. Sponsored by USDOE Office of Energy Research, Washington, DC (United States). DOE Contract

W-31109-ENG-38 ; AC06-76RL01830. (CONF-970805–:

192. meeting of the Electrochemical Society and 48. annual

meeting of the International Society of Electrochemistry,

Paris (France), 31 Aug - 5 Sep 1997). Order Number

DE97053261. Source: OSTI; NTIS; INIS; GPO Dep.

We focus in this report on three issues that are of central

importance in the management of radioactive high-level liquid waste (HLLW). We show that the only reducing radical

that lasts longer than a few ps in typical HLLW, and is capable of generating hydrogen, is NO3

2. We measured the

lifetime of this species across the whole pH range (3  pH 

14) and found it to be shorter than 15 s, before is dissociates to give strongly oxidizing NO2 radicals. We found that

it reacts with many proton donors (H+ phosphate, borate,

NH4

+, amines) in a reaction that is not merely an acid-base

equilibrium reaction. Using high-level ab initio calculations

we estimate its redox potential and pKa. We have developed

methodologies to study the degradation of organic additives

to the HLLW (to CO2 or carbonate) by NO2. Relative rates of

degradation of several complexants were determined using

competition kinetics and 13C NMR and proton NMR detection

techniques. Direct absorption of the radiation (low-energy

electrons as well as photons above the ionization threshold)

in NaNO3 single crystal at the solid/vacuum interface led to

production of NO, O, and O- as the major products.

6

(ANL/CHM/CP–93218)

In-situ mineralization of actinides for groundwater

cleanup: Laboratory demonstration with soil from the

Fernald Environmental Management Project. Nash, K.L.

(Argonne National Lab., IL (United States). Chemistry Div.);

Jensen, M.P.; Schmidt, M.A. Argonne National Lab., IL

(United States). [1997]. 17p. Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract W-31109-ENG-38. (CONF-970962–:

214. American Chemical Society meeting, Las Vegas, NV

(United States), 7-13 Sep 1997). Order Number

DE98050529. Source: OSTI; NTIS; GPO Dep.

An attractive approach to decreasing the probability of actinide migration in the subsurface is to transform the ions

into less mobile forms by remote treatment. The process described herein relies on a polyfunctional organophosphorus

complexant to sequester the mobile metal ions by complexation/cation exchange in the near term. The cation exchanger

is designed to subsequently decompose, transforming the

actinides into insoluble phosphate mineral forms as the

medium of stable long-term isolation. This material can be

generated in situ in the subsurface thus eliminating the need

for excavation to immobilize the actinide ions. Previous investigations have identified a suitable organophosphorus

reagent and profiled its decomposition kinetics, verified the

formation of phosphate mineral phases upon decomposition

of the reagent, determined solubility limits for appropriate

metal phosphates under groundwater conditions, and examined the cation exchange behavior of the calcium salt of the

organophosphorus reagent. In this report, the focus is on a

laboratory-scale demonstration of the concept using a soil

sample from the Fernald Environmental Management Plant.

7

(ANL/CMT/CP–91771)

An AEM study of glass-palagonite interfaces formed in

Hawaiian basalt glasses. Luo, J.S.; Ebert, W.L.; Dietz,

N.L.; Bates, J.K. Argonne National Lab., IL (United States).

[1997]. 10p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract W-31109-ENG-38. (CONF-970568–3: 99. annual

meeting of the American Ceramic Society, Cincinnati, OH

(United States), 4-7 May 1997). Order Number

DE97053127. Source: OSTI; NTIS; INIS; GPO Dep.

Basalt glass has been used as a natural analogue of highlevel waste glass because both types of glass have similar

Si contents. Most important for identifying the dominant

long-term corrosion process is the exact chemical nature of

the glass-palagonite boundary. In this paper, the authors

present the results of a detailed study of alteration interfaces

formed in subaerially altered Hawaiian basalt glasses (400

2
Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

to 700 years old) and analyzed with high resolution transmission electron microscopy (TEM) and nanometer-size

energy dispersive x-ray spectrometric (EDS) probe. The

study reveals a sharp contact between fresh glass and alteration products at nanometer scale. The alteration products,

which were typically several nanometers in size, were found

to be iron oxide hydroxide (goethite), aluminum hydroxide

hydrate (scarbroite), and an Si-Fe-Al rich amorphous phase.

The EDS line profile across the boundary showed a zone of

60–130 nm thickness that is depleted in alkali elements but

exhibits no variation for silicon. These results point to a

dominant dissolution-precipitation mechanism plus a limited

ion-exchange process under subaerial conditions.

8

(ANL/CMT/CP–92648)

Short-term consistency testing vs. long-term behavior.

Ebert, W.L.; Bakel, A.J.; Wolf, S.F.; Strachan, D.M. Argonne

National Lab., IL (United States). 1997. 13p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract W-31109-ENG-38.

(CONF-970537–8: 18. annual DOE low-level radioactive

waste management conference, Salt Lake City, UT (United

States), 20-22 May 1997). Order Number DE97007068.

Source: OSTI; NTIS; INIS; GPO Dep.

The authors conducted Product Consistency Tests (PCTs)

with a surrogate low-activity waste (LAW) glass to (1) evaluate the possible use of various test conditions in a

specification test for LAW waste forms, (2) measure the

reproducibility of the test at low temperatures, and (3) determine if the rates calculated from 7-day PCTs bound the

rates measured in PCT conducted for longer durations,

which represent more advanced corrosion. The effects of

temperature and pH on the dissolution rate in PCTs are

much less than the effects observed in dilute solutions due

to the buildup of dissolved glass components in the PCTs.

The precision of replicate 7-day tests at 20 and 40C was

limited by the analytical uncertainty. The dissolution rates at

all temperatures decreased with the test duration initially.

However, the dissolution rates in tests at 70 and 90C increased when certain alteration phases formed after about

100 and 500 days, respectively; the rates in some tests exceeded that measured in a 7-day PCT. While the 7-day PCT

does not provide a bounding rate for this glass at 70 or

90C, tests for longer durations are needed to determine if a

7-day test provides a bounding rate at lower temperatures.

9

(ANL/CMT/CP–92880)

Plutonium alteration phases from lanthanide borosilicate glass. Fortner, J.A.; Mertz, C.J.; Chamberlain, D.C.;

Bates, J.K. Argonne National Lab., IL (United States).

[1997]. 7p. Sponsored by USDOE Assistant Secretary for

Human Resources and Administration, Washington, DC

(United States). DOE Contract W-31109-ENG-38. (CONF970844–3: Plutonium futures: the science, Santa Fe, NM

(United States), 25-27 Aug 1997). Order Number

DE97008381. Source: OSTI; NTIS; INIS; GPO Dep.

A prototype lanthanide borosilicate (LaBS) glass containing 10 mass % plutonium was reacted with water vapor at

200 C for periods of 14 to 56 days. These tests, while not

designed to replicate specific conditions that may be found

in a potential geologic repository (e.g., Yucca Mountain),

have been shown to accelerate alteration phase formation.

The surfaces of the glass samples, along with alteration

phases, were examined with a transmission electron microscope (TEM). Tests of 14 days produced macroscopic ( 20

f microg m) crystallites of a plutonium-lanthanide silicate. An

extensive alteration layer was found on the glass surface

containing amorphous aluminosilicate layered with bands of

a cryptocrystalline plutonium silicate. After 56 days of testing, additional alteration phases were formed, including a

strontium lanthanide oxide phase. One of the options for disposal of surplus plutonium, particularly for impure residues

that may be unfit for production of MOX fuel, is vitrification

followed by geologic disposal. Since geologic disposal requires a passive system to isolate the radiotoxic elements

from the biosphere, it is important to understand the possible corrosion mechanisms of the waste form.

10

(ANL/CMT/CP–92884)

Microscopic analysis of Pu-contaminated incinerator

ash: Implications for immobilization. Buck, E.C.

(Argonne National Lab., IL (United States). Chemical Technology Div.). Argonne National Lab., IL (United States).

[1997]. 5p. Sponsored by USDOE Assistant Secretary for

Human Resources and Administration, Washington, DC

(United States). DOE Contract W-31109-ENG-38. (CONF970844–5: Plutonium futures: the science, Santa Fe, NM

(United States), 25-27 Aug 1997). Order Number

DE97008379. Source: OSTI; NTIS; INIS; GPO Dep.

In this paper, a nanometer-scale mineralogical study with

analytical transmission electron microscopy (AEM) of

plutonium-bearing incinerator ash from the Rocky Flats

Environmental Technology Site (RFETS) in Colorado is described. The findings from this work may have implications

for the present effort to immobilize plutonium waste. Around

70% of the plutonium ash in the DOE weapons complex is

stored at RFETS. The ash was formed from the combustion

of contaminated wastes generated from plutonium processing. The RFETS incinerator ash composition has been

determined by Blum et al. The ash was formed at temperatures estimated to be between 200 C and 900 C and

contains up to 14 wt% Pu. Ash is a generic term used to describe the by-product of combustion and owing to the

variability in the inorganic components.

11

(ANL/CMT/CP–92918)

Pu and Gd chemistry of zirconolite polytypes in a titanate ceramic. Bakel, A.J. (Argonne National Lab., IL

(United States). Chemical Technology Div.); Buck, E.C.;

Ebbinghaus, B. Argonne National Lab., IL (United States).

[1997]. 4p. Sponsored by USDOE Assistant Secretary for

Human Resources and Administration, Washington, DC

(United States). DOE Contract W-31109-ENG-38. (CONF970844–4: Plutonium futures: the science, Santa Fe, NM

(United States), 25-27 Aug 1997). Order Number

DE97008380. Source: OSTI; NTIS; INIS; GPO Dep.

Titanate-based ceramics are being developed as possible

candidates for immobilizing excess plutonium from dismantled nuclear weapons. Evidence from testing of similar

ceramics and natural analogues suggests that this material

is very resistant to aqueous corrosion. The purpose of this

work is to describe the phase(s) present in these ceramics.

In particular the authors are interested in the disposition of

important elements such as Pu and Gd (to be incorporated

into the wasteform as a neutron absorber). In concert with

data from corrosion tests, this characterization will allow one

3
ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

to describe the release behaviors of important elements

from this type of ceramic. This is particularly difficult and important due to the heterogeneous nature of the material.

12

(ANL/CMT/CP–94430)

Effect of alteration phase formation on the glass dissolution rate. Ebert, W.L. Argonne National Lab., IL (United

States). 1997. 8p. Sponsored by USDOE Office of Civilian

Radioactive Waste Management, Washington, DC (United

States). DOE Contract W-31-109-ENG-38. (CONF9708128–: CEA-Valrho workshop on glass: scientific

research toward high performance containment conference,

Mejannes-le-Clap (France), 31 Aug - 7 Sep 1997). Order

Number DE97054270. Source: OSTI; NTIS; INIS; GPO Dep.

The dissolution rates of many glasses have been observed to increase upon the formation of certain alteration

phases. It is important to understand the mechanism by

which alteration phases affect glass corrosion behavior and

the glass dissolution rate to reliably predict whether or not

similar effects will occur in a disposal environment and the

impact of phase formation on the long-term performance of

waste glass. While solid state transformation of a glass to

thermodynamically more stable phases in kinetically prohibitive, contact by water provides an energetically favorable

pathway for this transformation to occur by a dissolutionreprecipitation mechanism. The kinetics of the

transformation depends on the dissolution kinetics of the

glass and the precipitation kinetics of the alteration phases.

The rates of these two processes are linked primarily

through the solution activity of orthosilicic acid (and perhaps

also that of an aluminum-bearing species).

13

(ANL/CTD/PP–86307)

Gas evolution during vitrification of sodium sulfate and

silica. Ebert, W.L. (Argonne National Lab., IL (United

States). Chemical Technology Div.); Bakel, A.J.; Rosine,

S.D. Argonne National Lab., IL (United States). [1997]. 18p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

W-31109-ENG-38. Order Number DE97008113. Source:

OSTI; NTIS; INIS; GPO Dep.

This paper describes the operation of an apparatus designed to identify species evolved during vitrification of

hazardous waste materials and to measure the temperatures at which they are evolved. To demonstrate the utility of

the apparatus for designing off-gas systems, the authors

present the results of heating various sulfates alone and in

the presence of silica. During vitrification, the decomposition

behavior of some waste components will be affected by the

chemical composition of the melt. For example, they found

that when silica is present during heating, SOx gases are

evolved at lower temperatures than when pure sodium sulfate is heated. Such analyses will be important in the design

of off-gas units for waste vitrification systems.

14

(ANL/D&D–97-1)

Decontamination and dismantlement of the JANUS Reactor at Argonne National Laboratory-East. Project final

report. Fellhauer, C.R. (Argonne National Lab., IL (United

States). Technology Development Div.); Clark, F.R.; Garlock, G.A. Argonne National Lab., IL (United States). Oct

1997. 111p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract W-31109-ENG-38. Order Number DE98001522.

Source: OSTI; NTIS; INIS; GPO Dep.

The decontamination and dismantlement of the JANUS

Reactor at Argonne National Laboratory-East (ANL-E) was

completed in October 1997. Descriptions and evaluations of

the activities performed and analyses of the results obtained

during the JANUS D and D Project are provided in this Final

Report. The following information is included: objective of

the JANUS D and D Project; history of the JANUS Reactor

facility; description of the ANL-E site and the JANUS Reactor facility; overview of the D and D activities performed;

description of the project planning and engineering; description of the D and D operations; summary of the final status

of the JANUS Reactor facility based upon the final survey

results; description of the health and safety aspects of the

project, including personnel exposure and OSHA reporting;

summary of the waste minimization techniques utilized and

total waste generated by the project; and summary of the final cost and schedule for the JANUS D and D Project.

15

(ANL/D&D–98-1)

Decontamination and Decommissioning activities photobriefing book FY 1997. Argonne National Lab., IL (United

States). Apr 1998. 90p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States).

DOE Contract W-31109-ENG-38. Order Number

DE98004979. Source: OSTI; NTIS; INIS; GPO Dep.

The Decontamination and Decommissioning (D and D)

Program at Argonne National Laboratory-East (ANL-E) is

dedicated to the safe and cost effective D&D of surplus nuclear facilities. There is currently a backlog of more than

7,000 contaminated US Department of Energy facilities nationwide. Added to this are 110 licensed commercial nuclear

power reactors operated by utilities learning to cope with

deregulation and an aging infrastructure that supports the

commercial nuclear power industry, as well as medical and

other uses of radioactive materials. With this volume it becomes easy to understand the importance of addressing the

unique issues and objectives associated with the D&D of

surplus nuclear facilities. This photobriefing book summarizes the decontamination and decommissioning projects

and activities either completed or continuing at the ANL-E

site during the year.

16

(ANL/DIS/PP–90117)

Analysis of disposition alternatives for radioactively

contaminated scrap metal. Nieves, L.A.; Chen, S.Y.;

Kohout, E.J.; Nabelssi, B.; Tilbrook, R.W.; Wilson, S.E. Argonne National Lab., IL (United States). [1997]. 17p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

W-31109-ENG-38. Order Number DE97002663. Source:

OSTI; NTIS; INIS; GPO Dep.

Millions of tonnes of slightly radioactive, scrap iron and

steel, stainless steel, and copper are likely to become available as nuclear and other facilities and equipment are

withdrawn from service. Disposition of this material is an international policy issue under consideration currently. The

major alternatives for managing this material are to either

develop a regulatory process for decontamination and recycling that will safeguard human health or to dispose of the

4
Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

scrap and replace the metal stocks. To evaluate the alternatives, we estimate quantities of scrap arising from nuclear

power plant decommissioning, evaluate potential price impacts of recycling on regional markets, and assess the

health and environmental impacts of the management alternatives. We conclude that decontaminating and recycling

the scrap is the superior alternative.

17

(ANL/EA/CP–90804)

A comparative review of accident studies from recent

assessments of emergency planning zone boundaries.

Mueller, C.J.; Kier, P.H.; Folga, S.M. Argonne National Lab.,

IL (United States). [1997]. 4p. Sponsored by USDOE Office

of Environmental Management, Washington, DC (United

States). DOE Contract W-31-109-ENG-38. (CONF-970419–

5: 6. American Nuclear Society (ANS) topical meeting on

emergency preparedness and response, San Francisco, CA

(United States), 22-25 Apr 1997). Order Number

DE97004692. Source: OSTI; NTIS; INIS; GPO Dep.

Hazards assessments and accompanying accident and

human health and risk calculations are routinely done to establish Emergency Planning Zone (EPZ) boundaries for

facilities managing hazardous and/or radioactive materials.

This paper reviews the underlying US DOE guidance, assesses the degree of conformance to the guidance in recent

hazards assessments performed to support selection of EPZ

boundaries, and compares the consistency of the accident

analysis approaches and underlying key assumptions. Recommendations are made on the basis of these reviews, as

well as from knowledge of the approaches used in safety

assessments performed in support of safety analysis reports

(SARs) and environmental impact statements (EISs).

18

(ANL/EA/CP–90893)

Conceptual framework and technical basis for clearance

of materials with residual radioactivity. Chen, S.Y.

Argonne National Lab., IL (United States). [1997]. 4p. Sponsored by USDOE Office of Environmental Management,

Washington, DC (United States). DOE Contract W-31-109-

ENG-38. (CONF-970322–2: International conference on

radiation dosimetry and safety, Taipei (Taiwan, Province of

China), 31 Mar - 2 Apr 1997). Order Number DE97004695.

Source: OSTI; NTIS; INIS; GPO Dep.

The primary impediment to the release of materials containing residual radioactivity from a controlled environment is

the lack of a suitable framework within which release

standards can be developed. Recently, the ’risk-based’ approach has been proposed as an appropriate means of

setting standards. The term ’clearance’ has been introduced

by the International Atomic Energy Commission as a regulatory process for releasing radioactive materials posing trivial

risks. A ’trivial’ risk level has been determined to be on the

order of 10[sup -6] to 10[sup -7] annual risk to an exposed

individual, and a population risk of no more than 0.1 annually. Under these strict constraints, exposure scenarios may

account for processing, disposal, and product end-use of

materials. This paper discusses these scenarios and also

describes the technical basis for deriving release levels under the suggested risk (or dose) constraints.

19

(ANL/EA/CP–91190)

Legal precedents regarding use and defensibility of risk

assessment in Federal transportation of SNF and HLW.

Bentz, E.J. Jr. (E.J. Bentz and Associates, inc., Alexandria,

VA (United States)); Bentz, C.B.; O’Hora, T.D.; Chen, S.Y.

Argonne National Lab., IL (United States). [1997]. 13p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

W-31109-ENG-38. (CONF-970335–43: Waste Management

‘97, Tucson, AZ (United States), 2-7 Mar 1997). Order Number DE97004677. Source: OSTI; NTIS; INIS; GPO Dep.

Risk assessment has become an increasingly important

and essential tool in support of Federal decision-making regarding the handling, storage, disposal, and transportation

of spent nuclear fuel (SNF) and high-level radioactive waste

(HLW). This paper analyzes the current statutory and regulatory framework and related legal precedents with regard to

SNF and HLW transportation. The authors identify key

scientific and technical issues regarding the use and defensibility of risk assessment in Federal decision-making

regarding anticipated shipments.

20

(ANL/EA/CP–91830)

Release process for non-real property containing residual radioactive material. Ranek, N.L. (Argonne National

Lab., IL (United States)); Chen, S.Y.; Kamboj, S.; Hensley,

J.; Burns, D.; Fleming, R.; Warren, S.; Wallo, A. Argonne

National Lab., IL (United States). [1997]. 10p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract W-31109-ENG-38.

(CONF-970360–1: Environmental restoration ‘97, Tucson,

AZ (United States), 5-6 Mar 1997). Order Number

DE97001995. Source: OSTI; NTIS; INIS; GPO Dep.

It is DOE’s objective to operate its facilities and to conduct

its activities so that radiation exposures to members of the

public are maintained within acceptable limits and exposures to residual radioactive materials are controlled. To

accomplish this, DOE has adopted Order DOE 5400.51 ’Radiation Protection of the Public and the Environment’, and

will be promulgating IO CR Part 834 to codify and clarify the

requirements of DOE 5400.5. Under both DOE 5400.5 and

10 CR Part 834, radioactively contaminated DOE property is

prohibited from release unless specific actions have been

completed prior to the release. This paper outlines a tenstep process that, if followed, will assist DOE Operations

and contractor personnel in ensuring that the required actions established by Order DOE 5400.5 and 10 CR Part 834

have been appropriately completed prior to the release for

reuse or recycle of non-real property (e.g., office furniture,

computers, hand tools, machinery, vehicles and scrap

metal). Following the process will assist in ensuring that radiological doses to the public from the released materials

will meet applicable regulatory standards and be as low as

reasonably achievable (ALARA).

21

(ANL/EA/CP–92219)

Consistency in accident analyses in DOE safety, environmental, and emergency planning documents.

Mueller, C.; Kier, P.; Folga, S. Argonne National Lab., IL

(United States). [1997]. 8p. Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract W-31109-ENG-38. (CONF-970661–

10: 1997 safety analysis workshop, Oakland, CA (United

States), 9-13 Jun 1997). Order Number DE97006978.

Source: OSTI; NTIS; INIS; GPO Dep.

5
ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

A consistency review of accident analyses in US Department of Energy (DOE) safety, environmental, and

emergency planning documents is presented. The range of

and key differences in driving assumptions used in accident

definition and frequency assessment, radiological source

term generation, and atmospheric transport and fate modeling across recent environmental impact statements (EISs)

and emergency planning documents and the effects of these

differences on results are summarized. Considerable variation in both the assumptions and the underlying level of

conservatism is shown to exist. Recommendations are

made for source term generation and assumed meteorological conditions to reduce inconsistencies without being overly

prescriptive. Recommendations also are made to improve

consistency in assessing the frequencies of various generic

accident sequences traditionally analyzed in EIS and emergency planning documents. All recommendations are shown

to be consistent with currently applicable DOE guidance.

22

(ANL/EA/CP–92259)

Nevada Risk Assessment/Management Program

scientific peer review. Bentz, E.J. Jr. (E.J. Bentz and Associates, Inc., Alexandria, VA (United States)); Bentz, C.B.;

O’Hora, T.D.; Chen, S.Y. Argonne National Lab., IL (United

States). [1997]. 7p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE

Contract W-31109-ENG-38. (CONF-970322–3: International

conference on radiation dosimetry and safety, Taipei (Taiwan, Province of China), 31 Mar - 2 Apr 1997). Order

Number DE97004699. Source: OSTI; NTIS; INIS; GPO Dep.

The 1,350 square-mile Nevada Test Site and additional

sites in Nevada served as the continental sites for US nuclear weapons testing from 1951 to 1992. The Nevada Risk

Assessment/Management Program (NRAMP) is a currently

on-going effort of the Harry Reid Center for Environmental

Studies at the University of Nevada, Las Vegas (UNLV) and

the firm of E. J. Bentz and Associates, Inc., in cooperation

with the US Department of Energy (DOE) Environmental

Management Program. Argonne National Laboratory is one

of several public and private organizations supporting personnel appointed by the NRAMP to the NRAMP Scientific

Peer Review Panel. The NRAMP is part of a national effort

by the DOE to develop new sources of information and

approaches to risk assessment, risk management, risk communication, and public outreach relevant to the ecological

and human health effects of radioactive and hazardous materials management and site remediation activities. This

paper describes the development, conduct, and current results of the scientific peer review process which supports

the goals of the NRAMP.

23

(ANL/EA/CP–94676)

Environmental risk assessment. MacDonell, M.M. Argonne National Lab., IL (United States). [1997]. 12p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

W-31109-ENG-38. (CONF-9710136–: Eco-Informa ’97, Munich (Germany), 6-9 Oct 1997). Order Number

DE98050139. Source: OSTI; NTIS; GPO Dep.

This paper presents a current overview of the basic elements of environmental risk assessment within the basic

four-step process of hazard identification, exposure assessment, toxicity assessment, and risk characterization. These

general steps have been applied to assess both human and

ecological risks from environmental exposures. Approaches

used to identify hazards and exposures are being refined,

including the use of optimized field sampling and more

representative, rather than conservative,upper-bound estimates. In addition, toxicity data are being reviewed more

rigorously as US and European harmonization initiatives

gain strength, and the classification of chemicals has become more qualitative to more flexibly accommodate new

dose-response information as it is developed. Finally, more

emphasis is being placed on noncancer end points, and human and ecological risks are being weighed against each

other more explicitly at the risk characterization phase. Recent advances in risk-based decision making reflect the

increased transparency of the overall process, with more explicit incorporation of multiple trade-offs. The end result is a

more comprehensive life-cycle evaluation of the risks associated with environmental exposures at contaminated sites.

24

(ANL/EAD/TM–78)

Review of processes for the release of DOE real and

non-real property for reuse and recycle. Ranek, N.L.;

Kamboj, S.; Hensley, J.; Chen, S.Y.; Blunt, D. Argonne National Lab., IL (United States). Nov 1997. 92p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract W-31109-ENG-38. Order

Number DE98001779. Source: OSTI; NTIS; INIS; GPO Dep.

This report summarizes the underlying historical and regulatory framework supporting the concept of authorizing

release for restricted or unrestricted reuse or recycle of real

and non-real U.S. Department of Energy (DOE) properties

containing residual radioactive material. Basic radiation protection principles as recommended by the International

Commission on Radiological Protection are reviewed, and

international initiatives to investigate radiological clearance

criteria are reported. Applicable requirements of the U.S.

Nuclear Regulatory Commission, the Environmental Protection Agency, DOE, and the State of Washington are

discussed. Several processes that have been developed for

establishing cleanup and release criteria for real and nonreal DOE property containing residual radioactive material

are presented. Examples of DOE real property for which

radiological cleanup criteria were established to support unrestricted release are provided. Properties discussed include

Formerly Utilized Sites Remedial Action Project sites, Uranium Mill Tailings Remedial Action Project sites, the

Shippingport decommissioning project, the south-middle and

south-east vaults in the 317 area at Argonne National Laboratory, the Heavy Water Components Test Reactor at DOE’s

Savannah River Site, the Experimental Boiling Water Reactor at Argonne National Laboratory, and the Weldon Spring

site. Some examples of non-real property for which DOE

sites have established criteria to support unrestricted release are also furnished. 10 figs., 4 tabs.

25

(ANL/EAD/TM–82)

Evaluation of the area factor used in the RESRAD code

for the estimation of airborne contaminant concentrations of finite area sources. Chang, Y.S.; Yu, C.; Wang,

S.K. Argonne National Lab., Environmental Assessment

Div., IL (United States). Jul 1998. 32p. Sponsored by USDOE Assistant Secretary for Environment, Safety, and

Health, Washington, DC (United States);USDOE Office of

6
Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

Environmental Management, Washington, DC (United

States). DOE Contract W-31109-ENG-38. Order Number

DE99000492. Source: OSTI; NTIS; INIS; GPO Dep.

The area factor is used in the RESRAD code to estimate

the airborne contaminant concentrations for a finite area of

contaminated soils. The area factor model used in RESRAD

version 5.70 and earlier (referred to as the old area factor)

was a simple, but conservative, mixing model that tended to

overestimate the airborne concentrations of radionuclide

contaminants. An improved and more realistic model for the

area factor (referred to here as the new area factor) is

described in this report. The new area factor model is designed to reflect site-specific soil characteristics and

meteorological conditions. The site-specific parameters considered include the size of the source area, average particle

diameter, and average wind speed. Other site-specific parameters (particle density, atmospheric stability, raindrop

diameter, and annual precipitation rate) were assumed to be

constant. The model uses the Gaussian plume model combined with contaminant removal processes, such as dry and

wet deposition of particulates. Area factors estimated with

the new model are compared with old area factors that were

based on the simple mixing model. In addition, sensitivity

analyses are conducted for parameters assumed to be constant. The new area factor model has been incorporated into

RESRAD version 5.75 and later.

26

(ANL/ED/CP–92749)

Statistical signal processing and artificial intelligence

applications in the nondestructive assay of U/Pu bearing

materials. Aumeier, S.E.; Forsmann, J.H. Argonne National

Lab., Idaho Falls, ID (United States). [1997]. 5p. Sponsored

by USDOE Assistant Secretary for Nuclear Energy,

Washington, DC (United States). DOE Contract W-31109-

ENG-38. (CONF-970844–6: Plutonium futures: the science,

Santa Fe, NM (United States), 25-27 Aug 1997). Order

Number DE97008378. Source: OSTI; NTIS; INIS; GPO Dep.

Over the years a number of techniques have been developed to determine the quantity and distribution of radiative

isotopes contained in given assay samples through the

measurement and analysis of penetrating characteristic radiations. An active technique of particular utility when

assaying samples containing very small quantities of fissionable material or when high gamma ray backgrounds are

encountered is the delayed neutron nondestructive assay

(DN-NDA) technique. Typically, analysis of the delayed neutron signal involves relating the gross delayed neutron count

observed following neutron irradiation of an assay sample to

total fissionable material present via a linear calibration

curve. In this way, the technique is capable of yielding the

mass of a single dominant fissionable isotope or the total fissionable mass contained in a sample. Using this approach

the only way to determine the mass of individual fissionable

isotopes contained in a sample is to correlate total fissionable mass to individual isotopics via calculations or other

means, yielding an indirect measure of isotopics. However,

there is isotope specific information in the temporal delayed

neutron signal due to differences in the delayed neutron

precursor yields resulting from the fissioning of different isotopes. The authors present the results of an analysis to

evaluate the feasibility of using Kalman filters and genetic

algorithms to determine multiple specific fissionable isotopic

masses contained in an assay sample from a cumulative

delayed neutron signal measured following neutron irradiation of the sample.

27

(ANL/ED/CP–94173)

Deactivation of the EBR-II complex. Michelbacher, J.A.

(and others); Earle, O.K.; Henslee, S.P. Argonne National

Lab., IL (United States). 1997. 9p. Sponsored by USDOE

Office of Environmental Management, Washington, DC

(United States). DOE Contract W-31-109-ENG-38. (CONF971222–: Exchange 1997, Miami, FL (United States), 4 Dec

1997). Order Number DE97054217. Source: OSTI; NTIS;

INIS; GPO Dep.

In January of 1994, the Department of Energy mandated

the termination of the Integral Fast Reactor (IFR) Program,

effective October 1, 1994. To comply with this decision, Argonne National Laboratory-West (ANL-W) prepared a plan

providing detailed requirements to place the Experimental

Breeder Reactor-II (EBR-II) in a radiologically and industrially safe condition, including removal of all irradiated fuel

assemblies from the reactor plant, and removal and stabilization of the primary and secondary sodium, a liquid metal

used to transfer heat within the reactor plant. The ultimate

goal of the deactivation process is to place the EBR-II complex in a stable condition until a decontamination and

decommissioning (D&D) plan can be prepared, thereby minimizing requirements for maintenance and surveillance and

maximizing the amount of time for radioactive decay. The final closure state will be achieved in full compliance with

federal, state and local environmental, safety, and health

regulations and requirements. The decision to delay the development of a detailed D&D plan has necessitated this

current action. The EBR-II is a pool-type reactor. The primary system contains approximately 87,000 gallons of

sodium, while the secondary system has 13,000 gallons. In

order to properly dispose of the sodium in compliance with

the Resource Conservation and Recovery Act (RCRA), a facility has been built to react the sodium to a dry carbonate

powder in a two stage process. Deactivation of a liquid

metal fast breeder reactor (LMFBR) presents unique concerns. Residual amounts of sodium remaining in the primary

and secondary systems must be either reacted or inerted to

preclude future concerns with sodium-air reactions that generate explosive mixtures of hydrogen and leave corrosive

compounds. Residual amounts of sodium on components

will effectively “solder” components in place, making future

operation or removal unfeasible.

28

(ANL/EMO/CP–92504)

Production-scale LLW and RMW solidification system

operational testing at Argonne National Laboratory-East

(ANL-E). Wescott, J. (Argonne National Lab., IL (United

States)); Wagh, A.; Singh, D.; Nelson, R.; No, H. Argonne

National Lab., IL (United States). [1997]. 11p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract W-31109-ENG-38.

(CONF-970335–41: Waste Management ‘97, Tucson, AZ

(United States), 2-7 Mar 1997). Order Number

DE97004694. Source: OSTI; NTIS; INIS; GPO Dep.

Argonne National Laboratory-East (ANL-E) has begun

production-scale testing of a low-level waste and radioactive

mixed waste solidification system. This system will be used

to treat low-level and mixed radioactive waste to meet land

burial requirements. The system can use any of several

7
ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

types of solidification media, including a chemically bonded

phosphate ceramic developed by ANL-E scientists. The final

waste product will consist of a solidified mass in a standard

208-liter drum. The system uses commercial equipment and

incorporates several unique process control features to ensure proper treatment. This paper will discuss the waste

types requiring treatment, the system configuration, and operation results for these waste streams.

29

(ANL/EMO/SUMM–93614)

The restoration of an Argonne National Laboratory

foundry. Shearer, T.; Pancake, D.; Shelton, B. Argonne National Lab., IL (United States). 1997. 4p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract W-31109-ENG-38.

(CONF-971125–12-Summ.: 1997 American Nuclear Society

(ANS) winter meeting, Albuquerque, NM (United States), 16-

20 Nov 1997). Order Number DE97053542. Source: OSTI;

NTIS; INIS; GPO Dep.

The Environmental Management Operations’ Waste Management Department (WMD) at Argonne National

Laboratory-East (ANL-E) undertook the restoration of an unused foundry with the goal of restoring the area for general

use. The foundry was used in the fabrication of reactor components for ANL’s research and development programs;

many of the items fabricated in the facility were radioactive,

thereby contaminating the foundry equipment. This paper

very briefly describes the dismantling and decontamination

of the facility. The major challenges associated with the safe

removal of the foundry equipment included the sheer size of

the equipment, a limited overhead crane capability (4.5

tonne), the minimization of radioactive and hazardous

wastes, and the cost-effective completion of the project, the

hazardous and radioactive wastes present, and limited process knowledge (the facility was unused for many years).

30

(ANL/EMO/SUMM–93615)

Argonne National Laboratory’s photo-oxidation organic

mixed waste treatment system - installation and startup

testing. Shearer, T.L.; Nelson, R.A.; Torres, T.; Conner, C.;

Wygmans, D. Argonne National Lab., IL (United States).

1997. 5p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract W-31109-ENG-38. (CONF-971125–11-Summ.: 1997

American Nuclear Society (ANS) winter meeting, Albuquerque, NM (United States), 16-20 Nov 1997). Order

Number DE97053541. Source: OSTI; NTIS; INIS; GPO Dep.

This paper describes the installation and startup testing of

the Argonne National Laboratory (ANL-E) Photo-Oxidation

Organic Mixed Waste Treatment System. This system will

treat organic mixed (i.e., radioactive and hazardous) waste

by oxidizing the organics to carbon dioxide and inorganic

salts in an aqueous media. The residue will be treated in the

existing radwaste evaporators. The system is installed in the

Waste Management Facility at the ANL-E site in Argonne,

Illinois. 1 fig.

31

(ANL/ESH-HP–98/02)

Characterization report for Building 301 Hot Cell Facility. Argonne National Lab., IL (United States). Jul 1998.

[400p.] Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

W-31109-ENG-38. Order Number DE99000494. Source:

OSTI; NTIS; INIS; GPO Dep.

During the period from October, 1997, through March,

1998, ANL-E Health Physics conducted a pre-D and D characterization of Building 301, referred to as the Hot Cell

Facility. While primary emphasis was placed on radiological

evaluation, the presence of non-nuclear hazardous and toxic

material was also included in the scope of the characterization. This is one of the early buildings on the ANL-E site,

and was heavily used in the 1950’s and 1960’s for various

nuclear reaction and reactor design studies. Some degree

of cleanup and contamination fixation was done in the

1970’s, so that the building could be used with a minimum

of risk of personnel contamination. Work records are largely

nonexistent for the early history of the building, so that any

assumptions about extent and type of contamination had to

be kept very open in the survey planning process. The primary contaminant was found to be painted-over Cs-137

embedded in the concrete floors, although a variety of other

nuclides consistent with the work said to have been performed were found in smaller quantities. Due to leaks and

drips through the floor, a relatively modest amount of soil

contamination was found in the service trench under the

building, not penetrating deeply. Two contaminated, disconnected drain lines leaving the building could not be traced

by site records, and remain a problem for remediation. The

D and D Characterization Plan was fulfilled.

32

(ANL/ES/RP–93122)

Argonne National Laboratory puts alternative-fuel vehicles to the test. Argonne National Lab., IL (United States).

[1997]. 4p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract W-31109-ENG-38. Order Number DE97006977.

Source: OSTI; NTIS; GPO Dep.

This paper describes the participation in the alternativefueled vehicles (AFV) program at Argonne National

Laboratory. Argonne maintains a fleet of 300 vehicles, including AFV’s.

33

(ANL/ET/CP–92453)

Regulatory concerns for leakage testing of packagings

with three O-ring closure seals. Oras, J.J. (Argonne National Lab., IL (United States)); Towell, R.H.; Wangler, M.E.

Argonne National Lab., IL (United States). [1997]. 5p. Sponsored by USDOE Office of Environmental Management,

Washington, DC (United States). DOE Contract W-31109-

ENG-38. (CONF-970744–: 38. annual meeting of the

Institute of Nuclear Materials management, Phoenix, AZ

(United States), 20-24 Jul 1997). Order Number

DE97053876. Source: OSTI; NTIS; INIS; GPO Dep.

The American National Standard for Radioactive

Materials–Leakage Tests on Packages for Shipment (ANSI

N14.5) provides guidance for leakage rate testing to show

that a particular packaging complies with regulatory

requirements and also provides guidance in determining appropriate acceptance criteria. Recent radioactive packagings

designs have incorporated three O-ring closure seals, the

middle O-ring being the containment seal. These designs

have the potential for false positive results of leakage rate

tests. The volume between the containment O-ring and the

inner O-ring is used for the helium gas required for the leakage rate tests to reduce both the amount of helium used and

8
Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

the time required to conduct the tests. A leak detector samples the evacuated volume between the outer O-ring and the

containment O-ring. False positive results can be caused in

two ways, a large leakage in the containment seal or leakage in the inner seal. This paper will describe the problem

together with possible solutions/areas that need to be addressed in a Safety Analysis Report for Packagings before a

particular packaging design can be certified for transport.

34

(ANL/ET/CP–93070)

Method of estimating the leakage of multiple barriers in

a radioactive materials shipping package. Towell, R.H.

(Eagle Research Group, Inc., Germantown, MD (United

States)); Kapoor, A.; Moses, S.B.; Oras, J.J. Argonne National Lab., IL (United States). 1997. 7p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract W-31109-ENG-38.

(CONF-970778–1: 1997 ASME pressure vessels and piping

conference, Orlando, FL (United States), 27-31 Jul 1997).

Order Number DE97007121. Source: OSTI; NTIS; INIS;

GPO Dep.

This paper presents the results of a theoretical study of

the performance of multiple leaky barriers in containing radioactive materials in a shipping package. The methods

used are reasoned analysis and finite element modeling barriers. The finite element model is developed and evaluated

with parameters set to bracket 6M configurations with three

to six nested plastic jars, food-pack cans, and plastic bags

inside Department of Transportation (DOT) Specification 2R

inner containers with pipe thread closures. The results show

that nested barriers reach the regulatory limit of 1x106 A2/

hr in 11 to 52 days, even though individually the barriers

would exceed the regulatory limit by a factor of as much as

370 instantaneously. These times are within normal shipping

times. The finite element model is conservative because it

does not consider the deposition and sticking of the leaking

radioactive material on the surfaces inside each boundary.

35

(ANL/ET/CP–93397)

Leakage testing of packagings with three-O-ring closure

seals. Oras, J.J. (Argonne National Lab., IL (United

States)); Towell, R.H.; Wangler, M.E. Argonne National Lab.,

IL (United States). Oct 1997. 7p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States). DOE Contract W-31109-ENG-38. (CONF-980507–:

PATRAM ’98: 12. international conference on packaging

and transportation of radioactive material, Paris (France),

10-15 May 1998). Order Number DE98050328. Source:

OSTI; NTIS; INIS; GPO Dep.

Both the American National Standard for Radioactive

Materials–Leakage Tests on Packages for Shipment (ANSI

N14.5) and the ISO 12807:1996 Safe Transport of Radioactive Materials–Leakage Testing on Packages provide

guidance for leakage rate testing to show that a particular

packaging complies with regulatory requirements; both also

provide guidance for determining appropriate acceptance

criteria. Recent radioactive packaging designs have incorporated three-O-ring closure seals, the middle O-ring being the

containment seal. These designs have the potential for false

positive results in leakage rate tests. The volume between

the containment O-ring and the inner O-ring is used for the

helium gas required for the leakage rate tests, in order to reduce both the amount of helium used and the time required

to conduct the tests. A leak detector samples the evacuated

volume between the outer O-ring and the containment Oring. False positive results can have two causes: a large

leakage in the containment seal or leakage in the inner seal.

This paper describes the problem, together with possible solutions and areas that should be addressed in a Safety

Analysis Report for Packaging (SARP) before a particular

packaging design can be certified for transport. Ultimately,

the SARP should provide justification that the requirements

for leakage rate testing procedures, including the length of

time needed to conduct the tests, will ensure that the containment closure seal is properly tested.

36

(ANL/ET/CP–93781)

Immobilization of fission products in phosphate ceramic

waste forms. Singh, D.; Wagh, A. Argonne National Lab.,

IL (United States). 1997. 4p. Sponsored by USDOE Office

of Environmental Management, Washington, DC (United

States). DOE Contract W-31-109-ENG-38. (CONF-970148–:

Efficient Separations and Processing (ESP) Crosscutting

Program FY 1997 technical exchange meeting, Gaithersburg, MD (United States), 28-30 Jan 1997). Order Number

DE97053710. Source: OSTI; NTIS; INIS; GPO Dep.

Argonne National Laboratory (ANL) is developing chemically bonded phosphate ceramics (CBPCs) to treat low-level

mixed wastes, particularly those containing volatiles and pyrophorics that cannot be treated by conventional thermal

processes. This work was begun under ANL’s Laboratory

Directed Research and Development funds, followed by further development with support from EM-50’s Mixed Waste

Focus Area.

37

(ANL/ET/CP–94482)

An ultrasonic instrument for measuring density and viscosity of tank waste. Sheen, S.H.; Chien, H.T.; Raptis,

A.C. Argonne National Lab., IL (United States). 1997. 8p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

W-31109-ENG-38. (CONF-970962–: 214. American Chemical Society meeting, Las Vegas, NV (United States), 7-13

Sep 1997). Order Number DE98000286. Source: OSTI;

NTIS; INIS; GPO Dep.

An estimated 381,000 m3/1.1 x 109 Ci of radioactive

waste are stored in high-level waste tanks at the Hanford

Savannah River, Idaho Nuclear Engineering and Environmental Laboratory, and West Valley facilities. This nuclear

waste has created one of the most complex waste management and cleanup problems that face the United States.

Release of radioactive materials into the environment from

underground waste tanks requires immediate cleanup and

waste retrieval. Hydraulic mobilization with mixer pumps will

be used to retrieve waste slurries and salt cakes from storage tanks. To ensure that transport lines in the hydraulic

system will not become plugged, the physical properties of

the slurries must be monitored. Characterization of a slurry

flow requires reliable measurement of slurry density, mass

flow, viscosity, and volume percent of solids. Such measurements are preferably made with on-line nonintrusive sensors

that can provide continuous real-time monitoring. With the

support of the U.S. Department of Energy (DOE) Office of

Environmental Management (EM-50), Argonne National

Laboratory (ANL) is developing an ultrasonic instrument for

9
ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

in-line monitoring of physical properties of radioactive tank

waste.

38

(ANL/ET/CP–94812)

Evaluation of gamma radiation shielding for nuclear

waste shipping casks. Liu, Y.Y. (Argonne National Lab., IL

(United States). Energy Technology Div.); Carlson, R.D.;

Primeau, S.J.; Wangler, M.E. Argonne National Lab., IL

(United States). May 1998. 10p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States). DOE Contract W-31109-ENG-38. (CONF-980507–:

PATRAM ’98: 12. international conference on packaging

and transportation of radioactive material, Paris (France),

10-15 May 1998). Order Number DE98050530. Source:

OSTI; NTIS; INIS; GPO Dep.

A method has been developed for evaluating gamma radiation shielding of shipping casks that are used to transport

nuclear waste with ill-defined radionuclide contents. The

method is based on calculations that establish individual limits for a comprehensive list of radionuclides in the waste,

assuming that each radionuclide is uniformly distributed in a

volumetric source in the cask. For multiple radionuclide mixtures, a linear fraction rule is used to restrict the total

amount of radionuclides such that the sum of the fractions

does not exceed 1. As long as the radionuclide limits and

the linear fraction rule are followed, it can be shown that the

regulatory dose rate requirements for a cask will be satisfied

under normal conditions of transport and in a hypothetical

accident during which the shielding thickness of the cask

has been reduced by 40%.

39

(ANL/RA/CP–92135)

VIM: Initial ENDF/B-VI experience. Blomquist, R.N.

Argonne National Lab., IL (United States). 1997. 5p. Sponsored by USDOE Office of Environmental Management,

Washington, DC (United States). DOE Contract W-31109-

ENG-38. (CONF-970607–31: ARS ’97: American Nuclear

Society (ANS) international meeting on advanced reactors

safety, Orlando, FL (United States), 1-5 Jun 1997). Order

Number DE97007097. Source: OSTI; NTIS; INIS; GPO Dep.

The VIM Monte Carlo particle transport code uses detailed continuous-energy cross sections produced from

ENDF/B data by a set of specialized codes developed or

adapted for use at Argonne National Laboratory. ENDF/B-IV

data were used until about 1979, and Version V data since

then. These VIM libraries were extensively benchmarked

against the MC2-2 code and against ZPR and ZPPR criticals

for fast spectrum calculations, as well as other fast and thermal experiments and calculations. Recently, the cross

section processing codes have been upgraded to accommodate ENDF/B-VI files, and a small library has been tested.

Several fundamental tasks comprise the construction of a

faithful representation of ENDF data for VIM calculations:

(1) The resolved resonance parameters are converted to

Doppler-broadened continuous-energy cross sections with

energy grids suitable for linear-linear interpolation. (2) The

unresolved resonance parameter distributions are sampled

to produce many (40-400) resonance ladders in each energy band. These are converted to Doppler-broadened

continuous energy resonance cross sections that are then

binned by cross section, accumulating ladders until statistical convergence, the result being probability tables of total

cross sections and conditional mean scattering and fission

cross sections. VIM samples these tables at run time, and

File 3 back ground cross sections are added. (3) Anisotropic

angular distribution data are converted to angular probability

tables. All other ENDF data are unmodified, except for format.

40

(ANL/TD/CP–92637)

Systems engineering based planning for DOE D&D projects. Craig, K.A. (NES, Inc., Danbury, CT (United States));

Rose, R.W. Argonne National Lab., IL (United States). 1997.

7p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

W-31109-ENG-38. (CONF-970952–6: Decontamination,

decommissioning and reutilization of commercial and government facilities, Knoxville, TN (United States), 7-12 Sep

1997). Order Number DE97053226. Source: OSTI; NTIS;

INIS; GPO Dep.

A primary concern in any D&D project is the detailed process of utilizing a systems analysis approach to achieve

efficient planning and implementation of D&D projects. This

includes such items as project management and document

preparation, in addition to the hands-on field work. There

are detailed analyses which can be performed to accurately

determine the risk and hazards of a site which will be a primary concern during D&D at a DOE Facility. Scheduling and

cost estimates must also be performed to assist in the D&D

planning process.

41

(ANL/TD/CP–92675)

Deployment of remote dismantlement systems at the

CP-5 reactor. Black, D.B.; Ditch, R.W.; Henley, D.R.;

Seifert, L.S. Argonne National Lab., IL (United States).

1997. 8p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE

Contract W-31109-ENG-38. (CONF-970952–5: Decontamination, decommissioning and reutilization of commercial and

government facilities, Knoxville, TN (United States), 7-12

Sep 1997). Order Number DE97053225. Source: OSTI;

NTIS; INIS; GPO Dep.

The Chicago Pile 5 (CP-5) Reactor Facility is currently undergoing decontamination and decommissioning (D&D) at

the Argonne National Laboratory (ANL) Illinois site. CP-5

was the principal nuclear reactor used to produce neutrons

for scientific research at Argonne from 1954 to 1979. The

CP-5 reactor was a heavy-water moderated, enriched

uranium-fueled reactor with a graphite reflector. The CP-5

D&D project includes the disassembly and removal of all radioactive components, equipment, and structures associated

with the CP-5 facility. The Department of Energy’s Robotics

Technology Development Program along with the Federal

Energy Technology Center, Morgantown Office, have

provided teleoperated, remote systems for use in the dismantlement of the CP-5 reactor structure for tasks requiring

remote dismantlement. These systems include the dual-arm

work platform, the Rosie mobile D&D vehicle, the swingreduced crane control system, and a remotely-operated

crane control system. The dual-arm work platform is a

robotic dismantlement system that includes a pair of

Schilling Titan III hydraulic manipulators mounted on a special platform, a hydraulic power unit and an operator

console. The Rosie mobile D&D work system developed by

RedZone Robotics, Inc. is an electro-hydraulic omnidirectional locomotor platform with a heavy manipulator

10
Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

mounted on its deck. The Rosie vehicle moves about the

floor around the CP-5 reactor block and is operated from a

console in the control room. The swing-reduced crane control system has been installed on the CP-5 polar crane, and

allows a load suspended from the crane hook to be moved

while reducing the induced swing in the load. A remote control system and a rotating crane hook have also been added

to the CP-5 polar crane. This paper discusses the status of

these remote systems at CP-5 and the facility changes

made to allow for their use in the dismantlement of the reactor structure internals. 4 refs., 3 figs.

42

(ANL/TD/CP–92727)

Large-scale demonstration of D&D technologies. Bhattacharyya, S.K. (and others); Black, D.B.; Rose, R.W.

Argonne National Lab., IL (United States). 1997. 9p. Sponsored by USDOE Office of Environmental Management,

Washington, DC (United States). DOE Contract W-31109-

ENG-38. (CONF-970531–8: 5. ASME/SFEN/JSME

international conference on nuclear engineering: nuclear advances through global cooperation, Nice (France), 26-30

May 1997). Source: American Society of Mechanical Engineers, 345 E. 47th St., New York, NY 10017 (United States).

It is becoming increasingly evident that new technologies

will need to be utilized for decontamination and decommissioning (D&D) activities in order to assure safe and cost

effective operations. The magnitude of the international D&D

problem is sufficiently large in anticipated cost (100’s of billions of dollars) and in elapsed time (decades), that the

utilization of new technologies should lead to substantial improvements in cost and safety performance. Adoption of

new technologies in the generally highly contaminated D&D

environments requires assurances that the technology will

perform as advertised. Such assurances can be obtained

from demonstrations of the technology in environments that

are similar to the actual environments without being quite as

contaminated and hazardous. The Large Scale Demonstration Project (LSDP) concept was designed to provide such a

function. The first LSDP funded by the U.S. Department Of

Energy’s Environmental Management Office (EM) was on

the Chicago Pile 5 (CP-5) Reactor at Argonne National Laboratory. The project, conducted by a Strategic Alliance for

Environmental Restoration, has completed demonstrations

of 10 D&D technologies and is in the process of comparing

the performance to baseline technologies. At the conclusion

of the project, a catalog of performance comparisons of

these technologies will be developed that will be suitable for

use by future D&D planners.

43

(ANL/TD/CP–92728)

D&D of a reactor, hot cells and gloveboxes - an integrated experience. Yule, T.J.; Fellhauer, C.R.; Rose, R.W.;

Bhattacharyya, S.K. Argonne National Lab., IL (United

States). 1997. 9p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE

Contract W-31109-ENG-38. (CONF-970531–7: 5.

ASME/SFEN/JSME international conference on nuclear engineering: nuclear advances through global cooperation,

Nice (France), 26-30 May 1997). Source: American Society

of Mechanical Engineers, 345 E. 47th St., New York, NY

10017 (United States).

Performing Decontamination and Decommissioning (D&D)

operations at a multi-use laboratory containing small sites

which run the gamut of nuclear facility types within the DOE

Complex provides engaging challenges, as well as many

unique opportunities. While the relatively small scale of the

D&D work performed at Argonne National Laboratory (ANLE) does not present the significant environmental, safety and

health risks which might be encountered at large production

sites, the types of issues are representative of the most significant problems. Being a small site with relatively low risks

and an exceptional rapport with local stakeholders provides

for the development and demonstration of technologies and

methodologies which could be utilized at the larger sites.

44

(ANL/TD/CP–94598)

Incorporation of pollution prevention and waste minimization practices during the decommissioning of

Building 310 at Argonne National Laboratory-East.

Mezaraups, J. (Argonne National Lab., IL (United States));

Krstich, M.A.; Yerace, P.J.; Gresalfi, M.J. Argonne National

Lab., IL (United States). Oct 1997. 5p. Sponsored by USDOE Office of Environmental Management, Washington, DC

(United States). DOE Contract W-31109-ENG-38. (CONF971121–: X-Change ’97, Miami, FL (United States), 30 Nov

- 4 Dec 1997). Order Number DE98050099. Source: OSTI;

NTIS; INIS; GPO Dep.

The decommissioning of radiologically contaminated

buildings at Department of Energy (DOE) sites provides a

major opportunity to include pollution prevention and waste

minimization (P2/WMin) practices to minimize waste using

authorized release opportunities, and recycle and reuse (R2)

activities on a complex-wide basis. The “P2/WMin Users

Guide for Decommissioning Projects” (a.k.a. Users Guide or

Guide) will be used to incorporate P2/WMin practices into

the decommissioning and dismantlement (D and D) of Building 310 retention tanks at Argonne National Laboratory-East

(ANL-E). The Building 310 service floor retention-tank facility

contains ten isolated retention tanks that served to store

excess radioactive liquids generated during process operations. The building consists of three rooms containing three

tanks each and a larger room containing one tank. Due to a

concern that the deteriorating facility could expose personnel working in the vicinity to radioactive contamination, a

decision was made to decommission the building. The

Users Guide, a document prepared under the auspices of

the Office of Pollution Prevention (EM-77), details a step-bystep approach for incorporating P2/WMin options into a

project’s documentation and subsequent decommissioning

activities. It is a compilation of lessons learned and strategic

P2/WMin initiatives from across the DOE complex. The benefits derived from using P2/WMin initiatives for the D and D

of Building 310 include an accelerated decommissioning

schedule, reduction in health risk, and the elimination of six

release sites from the DOE EM-40 list. The benefits derived

from implementation of P2/WMin initiatives into this project

include cost savings, reduction in long-term liability, and deployment of technologies without impacting scope or

schedule for the project.

45

(BHI–00139-Rev.3)

Environmental Restoration Disposal Facility Waste Acceptance Criteria. Dronen, V.R. Bechtel Hanford, Inc.,

Richland, WA (United States). Jun 1998. 36p. Sponsored by

USDOE, Washington, DC (United States);USDOE Office of

Environmental Management, Washington, DC (United

11
ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

States). DOE Contract W-7405-ENG-48. DE-AC06-93RL12367. Order Number DE98057634. Source: OSTI; INIS;

NTIS; GPO Dep.

The Hanford Site is operated by the U. S. Department of

Energy (DOE) with a primary mission of environmental

cleanup and restoration. The Environmental Restoration

Disposal Facility (ERDF) is an integral part of the DOE environmental restoration effort at the Hanford Site. The purpose

of this document is to establish the ERDF waste acceptance

criteria for disposal of materials resulting from Hanford Site

cleanup activities. Definition of and compliance with the requirements of this document will enable implementation of

appropriate measures to protect human health and the environment, ensure the integrity of the ERDF liner system,

facilitate efficient use of the available space in the ERDF,

and comply with applicable environmental regulations and

DOE orders. To serve this purpose, the document defines

responsibilities, identifies the waste acceptance process,

and provides the primary acceptance criteria and regulatory

citations to guide ERDF users. The information contained in

this document is not intended to repeat or summarize the

contents of all applicable regulations.

46

(BHI–00217-Rev.2)

Bechtel Hanford, Inc., RCRA Permit Implementation

Plan. Robinson, G.S. Bechtel Hanford, Inc., Richland, WA

(United States). Oct 1997. 54p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States). DOE Contract AC06-93RL12367. Order Number

DE98051322. Source: OSTI; NTIS; INIS; GPO Dep.

A Resource Conservation and Recovery Act of 1976

(RCRA) Permit was issued to the U.S. Department of Energy and its contractors operating facilities at the Hanford

Site. The permit took effect on September 28, 1994, allowing for the treatment, storage, and/or disposal of dangerous

waste within the respective authorities of the U.S. Environmental Protection Agency and the Washington State

Department of Ecology. The purpose of this document is to

provide information clarifying permit conditions and guidance for implementing the Hanford Facility RCRA Permit.

47

(BHI–00288-Rev.3)

Unit-Specific Contingency Plan for the 183-H Solar

Evaporation Basins. Edens, V.G. Bechtel Hanford, Inc.,

Richland, WA (United States). Apr 1998. 10p. Sponsored by

USDOE, Washington, DC (United States);USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract W-7405-ENG-48. DE-AC06-93RL12367. Order Number DE98054478. Source: OSTI; INIS;

NTIS; GPO Dep.

This document is a supplement to DOE/RL-93-75,

’Hanford Contingency Plan.’ It provides the unit-specific information needed to fully comply with the Washington

Administrative Code. General emergency and response information is contained in the Hanford Facility Contingency

Plan and is not repeated in this supplement. The 183-H Solar Evaporation Basins were four concrete internal surfaces,

which contained radiologically and hazardous contaminated

waste. The 183-H Basin area is a final status treatment,

storage, and disposal unit undergoing Resource Conservation and Recovery Act modified post- closure care.

48

(BHI–00301-Rev.1)

1301-N Liquid Waste Disposal Facility Supplemental Information to the Hanford Facility Contingency Plan.

Edens, V.G. Bechtel Hanford, Inc., Richland, WA (United

States). Apr 1998. 10p. Sponsored by USDOE, Washington,

DC (United States);USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

W-7405-ENG-48. DE-AC06-93RL-12367. Order Number

DE98054488. Source: OSTI; NTIS; GPO Dep.

The 1301-N Liquid Waste Disposal Facility located at the

100-N Area of the Hanford Site was the primary liquid radioactive waste disposal system for the N Reactor. Use of

the facility began at the time of reactor start-up in 1963 and

was discontinued in September 1985. From 1963 until 1985,

liquid wastes disposed of in the 1301-N Facility were generated in the 105-N Reactor and the 109-N Heat Exchanger

buildings. Waste streams routed to 1301-N were reactor

coolant system bleed off, spent fuel storage basin cooling

water overflow, reactor periphery cooling systems bleed off,

reactor primary coolant loop decontamination rinse solution,

and building drains containing radioactive waste generated

from reactor support facilities.Specific information on types

of waste discharged to 1301-N are contained within the Part

A, Form 3, Permit application of this unit. Currently, them

are no waste streams entering 130 1 -N.

49

(BHI–00304-Rev.1)

1325-N Liquid Waste Disposal Facility Supplemental Information to the Hanford Facility Contingency Plan

(DOE/RL-93-75). Edens, V.G. Bechtel Hanford, Inc., Richland, WA (United States). Mar 1998. 10p. Sponsored by

USDOE, Washington, DC (United States);USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract W-7405-ENG-48. DE-AC06-93RL12367. Order Number DE98054489. Source: OSTI; INIS;

NTIS; GPO Dep.

The 1325-N Liquid Waste Disposal Facility located at the

100-N Area of the Hanford Site started receiving part of the

N Reactor liquid radioactive effluent flow in 1983. In

September 1985, the 1325-N Facility became the primary

liquid waste disposal system for the N Reactor. The facility

is located approximately 60 feet above and 2000 feet east

of the shore of the Columbia River. Waste stream discharges were ceased in April 1991.Specific information on

types of waste discharged to 1325-N are contained within

the Part A, Form 3, Permit application of this unit.

50

(BHI–00351-Rev.1)

Chemical Hygiene Plan for Onsite Measurement and

Sample Shipping Facility Activities. Price, W.H. Bechtel

Hanford, Inc., Richland, WA (United States). Jan 1998.

118p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC06-93RL12367. Order Number DE98052279. Source:

OSTI; NTIS; INIS; GPO Dep.

This chemical hygiene plan presents the requirements established to ensure the protection of employee health while

performing work in mobile laboratories, the sample shipping

facility, and at the onsite radiological counting facility. This

document presents the measures to be taken to promote

safe work practices and to minimize worker exposure to

hazardous chemicals. Specific hazardous chemicals present

12
Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

in the mobile laboratories, the sample shipping facility, and

in the radiological counting facility are presented in Appendices A through G.

51

(BHI–00823-Rev.2)

Site-Specific Health and Safety Plan, 233-S Decontamination and Decommissioning. Hobbs, B.J. Bechtel

Hanford, Inc., Richland, WA (United States). Jan 1998. 36p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC06-93RL12367. Order Number DE98052280. Source:

OSTI; NTIS; INIS; GPO Dep.

The 233-S Facility operated from January 1952 until July

1967, at which time the building entered the U.S. Department of Energy’s Surplus Facility Management Program as

a retired facility. The facility has since undergone severe

degradation due to exposure to extreme weather conditions.

A freeze and thaw cycle occurred at the Hanford Site during

February 1996, which caused cracking failure of portions of

the building roof. This resulted in significant infiltration of water into the facility, which creates a pathway for potential

release of radioactive material into the environment (air and/

or ground). Additionally, the weather caused existing cracks

in concrete structures of the building to lengthen, thereby increasing the potential for failed confinement of the building’s

radioactive material. Differential settlement has also occurred, causing portions of the facility to separate from the

main building structure, increasing the potential for release

of radioactive material to the environment. An expedited

response is proposed to remove this threat and ensure protection of human health and the environment.

52

(BHI–00853-Rev.1)

Hazard Classification and Auditable Safety Analysis for

the 1300-N Emergency Dump Basin. Kloster, G.L., Bechtel Hanford Inc. Bechtel Hanford, Inc., Richland, WA (United

States). 22 Jul 1998. 21p. Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract W-7405-ENG-48. Order Number

DE98058266. Source: OSTI; NTIS; INIS; GPO Dep.

This document combines three analytical functions consisting of (1) the hazards baseline of the Emergency Dump

Basin (EDB) for surveillance and maintenance, (2) the final

hazard classification for the facility, and (3) and auditable

safety analysis. This document also describes the potential

hazards contained within the EDB at the N Reactor complex

and the vulnerabilities of those hazards. The EDB segment

is defined and confirmed its independence from other segments at the site by demonstrating that no potential adverse

interactions exist between the segments. No EDB hazards

vulnerabilities were identified that require reliance on either

active, mitigative, or protective measures; adequate facility

structural integrity exists to safely control the hazards.

53

(BHI–00858)

Environmental Restoration Project - Systems Engineering Management Plan. Anderson, T.D. Bechtel Hanford,

Inc., Richland, WA (United States). Jun 1998. 13p. Sponsored by USDOE, Washington, DC (United States);USDOE

Office of Environmental Management, Washington, DC

(United States). DOE Contract W-7405-ENG-48. DE-AC06-

93RL-12367. Order Number DE98057635. Source: OSTI;

INIS; NTIS; GPO Dep.

This Environmental Restoration (ER) Project Systems Engineering Management Plan (SEMP) describes relevant

Environmental Restoration Contractor (ERC) management

processes and shows how they implement systems engineering. The objective of this SEMP is to explain and

demonstrate how systems engineering is being approached

and implemented in the ER Project. The application of systems engineering appropriate to the general nature and

scope of the project is summarized in Section 2.0. The basic

ER Project management approach is described in Section

3.0. The interrelation and integration of project practices and

systems engineering are outlined in Section 4.0. Integration

with sitewide systems engineering under the Project Hanford Management Contract is described in Section 5.0.

54

(BHI–00898)

Operations and Maintenance Manual for the Temporary

Septic Holding Tank at the 100-C Remedial Action Support Facility. Palmquist, C.A. Bechtel Hanford, Inc.,

Richland, WA (United States). Dec 1997. 35p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract W-7405-ENG-48. DEAC06-93RL-12367. Order Number DE98052486. Source:

OSTI; INIS; NTIS; GPO Dep.

The purpose of this document is to provide detailed information regarding the operations and maintenance of the

septic holding tank system at the 100-C Remedial Action

Restroom Facility. Specific information provided in this

document includes the type and frequency of required maintenance and failure response procedures.

55

(BHI–00920)

Operations and Maintenance Manual for the Temporary

Septic Holding Tank at the 100-C Remedial Action Restroom Facility. Palmquist, C.A. Bechtel Hanford, Inc.,

Richland, WA (United States). Nov 1997. 25p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract W-7405-ENG-48. DEAC06-93RL-12367. Order Number DE98052487. Source:

OSTI; INIS; NTIS; GPO Dep.

The purpose of this document is to provide detailed information regarding the operations and maintenance of the

septic holding tank system at the 100-C Remedial Action

Restroom Facility. Specific information provided in this

document includes the type and frequency of required maintenance and failure response procedures.

56

(BHI–00934-Rev.2)

Code of accounts. Management overview volume: Environmental restoration. Fox, M.B.; Birkholz, H.L. Bechtel

Hanford, Inc., Richland, WA (United States). Oct 1997.

359p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC06-93RL12367. Order Number DE98051271. Source:

OSTI; NTIS; INIS; GPO Dep.

The purpose of this procedure is to provide the requirement for assigning cost collection codes and the structure of

these codes for all costs incurred for the Environmental

13
ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

Restoration Contract. The coding structure will be used in

the budgeting and control of project costs.

57

(BHI–00968-Rev.1)

Final Hazard Classification and Auditable Safety Analysis for the N Basin Segment. Kloster, G.L. Bechtel

Hanford, Inc., Richland, WA (United States). Aug 1998. 80p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC06-93RL12367. Order Number DE98058386. Source:

OSTI; NTIS; INIS; GPO Dep.

The purposes of this report are to serve as the auditable

safety analysis (ASA) for the N Basin Segment, during

surveillance and maintenance preceding decontamination

and decommissioning; to determine and document the final

hazard classification (FHC) for the N Basin Segment. The

result of the ASA evaluation are: based on hazard analyses

and the evaluation of accidents, no activity could credibly result in an unacceptable exposure to an individual; controls

are identified that serve to protect worker health and safety.

The results of the FHC evaluation are: potential exposure is

much below 10 rem (0.46 rem), and the FHC for the N

Basin Segment is Radiological.

58

(BHI–00987-Rev.1-Vol.1)

The Necessary and Sufficient Closure Process Completion Report for Purex FacilitySurveillance and

Maintenance. Gerald, J.W. Bechtel Hanford, Inc., Richland,

WA (United States). Oct 1997. 45p. Sponsored by USDOE

Office of Environmental Management, Washington, DC

(United States). DOE Contract AC06-93RL12367. Order

Number DE98051324. Source: OSTI; NTIS; INIS; GPO Dep.

This document completes the U.S. Department of Energy

Closure Process for Necessary and Sufficient Sets of Standards process for the Plutonium Uranium Extraction facility

located at the Hanford Site in Washington State. This documentation is provided to support the Work Smart Standards

set identified for the long-term surveillance and maintenance

of PUREX. This report is organized into two volumes. Volume 1 contains the following sections: Section 1: Provides

an introduction for the document Section 2: Provides a basis for initiating the N&S process Section 3: Defines the

work and hazards to be addressed Section 4: Identifies the

N&S set of standards and requirements Section 5: Provides

the justification for adequacy of the work smart standards

Section 6: Shows the criteria and qualifications of the teams

Section 7: Describes the stakeholder participation and concerns Section 8: Provides a list of references used within

the document.

59

(BHI–01010-Rev.1)

Survey Method for Radiological Surveys of 300-FF-1 Operable Unit Soils and Material. Brehm, D.M. Bechtel

Hanford, Inc., Richland, WA (United States). Jun 1998. 28p.

Sponsored by USDOE, Washington, DC (United

States);USDOE Office of Environmental Management,

Washington, DC (United States). DOE Contract AC06-

93RL12367. Order Number DE98057684. Source: OSTI;

NTIS; INIS; GPO Dep.

This technical basis is to be used to survey soils at the

300-FF-1 Operable Unit during remediation of the site. Its

purpose is to provide a basis for the survey methods to be

employed by radiological control technician (RCTs) to guide

the excavation effort in accordance with the 300-FF-1 waste

site Record of Decision (ROD). The ROD for the 300-FF-1

Operable Unit requires selective excavation, removal, and

disposal of contaminated soil above 350 pCi/g total uranium

activity. Soil above this level will be disposed of as radioactive waste. The remaining soil will remain onsite.

60

(BHI–01020)

Data Quality Objectives Report for the 115-B Gas Tunnel. Bauer, R.G. Bechtel Hanford, Inc., Richland, WA

(United States). May 1998. 96p. Sponsored by USDOE,

Washington, DC (United States);USDOE Office of Environmental Management, Washington, DC (United States). DOE

Contract W-7405-ENG-48. DE-AC06-93RL-12367. Order

Number DE98057476. Source: OSTI; INIS; NTIS; GPO Dep.

This workbook assisted the Data Quality Objectives Team

in implementing the Data Quality Objectives Process

through the use of a template which lists the important elements of the DQO. The completion of this workbook is a

required element of the BHI-EE-01, Procedure 1.2, ’Data

Quality Objectives.’ The objective of this project is to define

the sampling and analysis requirements for isolation and decontamination and decommissioning release of the 115- B

Gas Tunnel. The 115-B Gas Tunnel is an underground concrete pipe tunnel that houses piping used to recirculate

helium gas between the 105-B Reactor Building and the

115-B/C Gas Recirculation System.

61

(BHI–01022)

Sampling and Analysis Instruction for the 120-F-1 Glass

Dump Site. Brown, T.M. Bechtel Hanford, Inc., Richland,

WA (United States). Mar 1998. 18p. Sponsored by USDOE,

Washington, DC (United States);USDOE Office of Environmental Management, Washington, DC (United States). DOE

Contract W-7405-ENG-48. DE-AC06-93RL-12367. Order

Number DE98053048. Source: OSTI; INIS; NTIS; GPO Dep.

This sampling and analysis instruction has been prepared

to clearly define the sampling and analysis activities to be

performed to develop the basis for surveillance and maintenance of the 120-F-1 Glass Dumpsite. The purpose of this

investigation is to augment historical information and obtain

data to establish a technical basis for surveillance and maintenance at the site.

62

(BHI–01052)

Description of Work for a Vadose Zone Characterization

Borehole at the 216-B-2-2 Ditch. Faurote, J.M.; Wittreich,

C.D. Bechtel Hanford, Inc., Richland, WA (United States).

Oct 1997. 70p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE

Contract AC06-93RL12367. Order Number DE98051318.

Source: OSTI; NTIS; INIS; GPO Dep.

This Description of Work details the characterization activities related to a proposed borehole in the 200-BP-11

Operable Unit, and will serve as a guide for those performing the work. The 216-B-2-2 Ditch was selected for

characterization based on the Waste Site Grouping Report

for 200 Area Soil Investigations which identified this ditch as

a representative site for the Gable Mountain Pond/B- Pond

and Ditches Cooling Water Group. The scope of work includes drilling the proposed borehole, Well ID Number

14
Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

B8079, to refine the conceptual model, assessing the nature

and extent of subsurface contaminants, and supporting remedial action/closure decisions for the Gable Mountain

Pond/B-Pond and Ditches Cooling Water Group.

63

(BHI–01054-Rev.2)

Technical Basis to Describe the Use of the Eberline E600. Brehm, D.M. Bechtel Hanford, Inc., Richland, WA

(United States). Mar 1998. 17p. Sponsored by USDOE,

Washington, DC (United States);USDOE Office of Environmental Management, Washington, DC (United States). DOE

Contract AC06-93RL12367. Order Number DE98054477.

Source: OSTI; NTIS; INIS; GPO Dep.

This technical basis document describes the parameters

and conditions under which the Eberline E-600 rate meter

and the associated detectors can be operated to quantify

ionizing radiation and radiological contamination.

64

(BHI–01109)

Sampling and Analysis Plan for the 216-A-29 Ditch. Petersen, S.W. Bechtel Hanford, Inc., Richland, WA (United

States). Jun 1998. 21p. Sponsored by USDOE, Washington,

DC (United States);USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

W-7405-ENG-48. DE-AC06-93RL-12367. Order Number

DE98057636. Source: OSTI; INIS; NTIS; GPO Dep.

This sampling and analysis plan defines procedures to be

used for collecting and handling samples to be obtained

from the 216-A-29 Ditch, and identifies requirements for field

and laboratory measurements. The sampling strategy describes here is derived from a Data Quality Objectives

workshop conducted in January 1997 to support sampling to

assure worker safety during construction and to assess the

validity of a 1988 ditch sampling campaign and the effectiveness of subsequent stabilization. The purpose of the

proposed sampling and analysis activities is to characterize

soil contamination in the vicinity of a proposed road over the

216-A-29 Ditch.

65

(BHI–01128-Rev.1)

Site-Specific Waste Management Instruction - 100-DR-1

Group 2 Sites. Jackson, R.W. Bechtel Hanford, Inc., Richland, WA (United States). Jan 1998. 27p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract W-7405-ENG-48. DEAC06-93RL-12367. Order Number DE98052485. Source:

OSTI; INIS; NTIS; GPO Dep.

This site-specific waste management instruction (SSWMI)

provides guidance for the management of wastes that may

be generated during the excavation and remediation of the

100-DR-1 Group 2 sites. The management of waste generated as a result of these activities will be as directed in this

SSWMI. This SSWMI will be revised to incorporate guidance

for management of wastes encountered that are not addressed in this SSWMI.

66

(BHI–01130)

N Area Final Project Program Plan. Day, R.S.; Duncan,

G.M; Trent, S.J. Bechtel Hanford, Inc., Richland, WA (United

States). Jul 1998. 134p. Sponsored by USDOE, Washington, DC (United States);USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract AC06-93RL12367. Order Number DE98057659.

Source: OSTI; NTIS; INIS; GPO Dep.

The N Area Final Project Program Plan is issued for information and use by the U.S. Department of Energy (DOE),

the Environmental Restoration Contractor (ERC) for the

Hanford Site, and other parties that require workscope

knowledge for the deactivation of N Reactor facilities and remediation of the 100-N Area. This revision to the program

plan contains the updated critical path schedule to deactivate N Reactor and its supporting facilities, cleanout of the

N Reactor Fuel Storage Basin (105-N Basin), and remediate

the 100-N Area. This document reflects notable changes in

the deactivation plan for N Reactor, including changes in deactivation status, the N Basin cleanout task, and 100-N Area

remediation.

67

(BHI–01146)

Annular Kinetic Impactor Air Sampler. Moroney, J.D.

Bechtel Hanford, Inc., Richland, WA (United States). Jan

1998. 5p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract W-7405-ENG-48. DE-AC06-93RL-12367. Order

Number DE98052488. Source: OSTI; INIS; NTIS; GPO Dep.

This technical basis document describes and documents

the parameters under which the Annular Kinetic Impactor

can be operated to quantify alpha and beta airborne radioactivity concentrations.

68

(BHI–01151)

Final Hazard Classification and Auditable Safety Analysis for the 105-F Building Interim Safe Storage Project.

Rodovsky, T.J.; Bond, S.L. Bechtel Hanford, Inc., Richland,

WA (United States). Jul 1998. 172p. Sponsored by USDOE,

Washington, DC (United States);USDOE Office of Environmental Management, Washington, DC (United States). DOE

Contract AC06-93RL12367. Order Number DE98057563.

Source: OSTI; NTIS; INIS; GPO Dep.

The auditable safety analysis (ASA) documents the authorization basis for the partial decommissioning and facility

modifications to place the 105-F Building into interim safe

storage (ISS). Placement into the ISS is consistent with the

preferred alternative identified in the Record of Decision (58

FR). Modifications will reduce the potential for release and

worker exposure to hazardous and radioactive materials, as

well as lower surveillance and maintenance (S&M) costs.

This analysis includes the following: A description of the activities to be performed in the course of the 105-F Building

ISS Project. An assessment of the inventory of radioactive

and other hazardous materials within the 105-F Building.

Identification of the hazards associated with the activities of

the 105-F Building ISS Project. Identification of internally

and externally initiated accident scenarios with the potential

to produce significant local or offsite consequences during

the 105-F Building ISS Project. Bounding evaluation of the

consequences of the potentially significant accident

scenarios. Hazard classification based on the bounding consequence evaluation. Associated safety function and

controls, including commitments. Radiological and other employee safety and health considerations.

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

69

(BHI–01154)

118-C-4 Horizontal Rod Cave Characterization Report.

Encke, B.D.; Thoren, R.A. Fermi National Accelerator Lab.,

Batavia, IL (United States). Mar 1998. 81p. Sponsored by

USDOE, Washington, DC (United States);USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract W-7405-ENG-48. DE-AC06-93RL12367. Order Number DE98053049. Source: OSTI; INIS;

NTIS; GPO Dep.

This report addresses the characterization data collected

from 118-C- 4 Horizontal Rod Cave in December 1996 and

August 1997. The characterization activities evaluated the

radiological status and identified hazardous materials locations. The scope of this report is limited to the 118-C-4

Facility Structure. Information in this report can be used to

identify the waste streams, provide specific chemical and

radiological data to aid in planning decontamination and decommissioning (D&D) activities, and allow proper disposal of

the demolition debris, as required by the Comprehensive

Environmental Response, Compensation, and Liability Act

of 1980.

70

(BHI–01158)

Cleanup Verification Package for the 107-D5 Trench.

Corpuz, F.M.; Fancher, J.D.; Blumenkranz, D.B. Fermi National Accelerator Lab., Batavia, IL (United States). Mar

1998. 42p. Sponsored by USDOE, Washington, DC (United

States);USDOE Office of Environmental Management,

Washington, DC (United States). DOE Contract W-7405-

ENG-48. DE-AC06-93RL-12367. Order Number

DE98053050. Source: OSTI; NTIS; INIS; GPO Dep.

This document presents the results of remedial action objectives performed at the 107-D5 Sludge Trench, located at

the 100-DR-1 Operable Unit in the 100 Area of the Hanford

Site in southeastern Washington State. The 107-D5 Sludge

Trench is also identified in the Hanford Waste Information

Data System as Waste Site 100-D-4 (site code). The selected remedial action was (1) excavation of the site to the

extent required to meet specified soil cleanup levels, (2)

disposal of contaminated excavation materials at the Environmental Restoration and Disposal Facility at the 200 Area

of the Hanford Site, and (3) backfilling the site with clean

soil to adjacent grade elevations.

71

(BHI–01160)

ALARA Review for the Sediment Relocation and Removal from the 105-N Fuel Storage Basin. Demers, J.W.

Fermi National Accelerator Lab., Batavia, IL (United States).

Mar 1998. 17p. Sponsored by USDOE, Washington, DC

(United States);USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

W-7405-ENG-48. DE-AC06-93RL-12367. Order Number

DE98053051. Source: OSTI; NTIS; INIS; GPO Dep.

This as low as reasonable achievable (ALARA) review

revision provides a description of the engineering and administrative controls used to manage personnel exposure,

control contamination levels, and airborne radioactivity concentrations during sediment relocation and removal in the

105-N Fuel Storage Basin. This document updates and

supercedes the ALARA review of the sediment-related activities contained in 100-N Basin Stabilization Project As Low

As Reasonably Achievable Plan (BHI 1995).

72

(BHI–01161)

Inspection, Monitoring, and Maintenance Plan for the

300 Area Process Trenches. Buckmaster, M.A. Bechtel

Hanford, Inc., Richland, WA (United States). Mar 1998. 7p.

Sponsored by USDOE, Washington, DC (United

States);USDOE Office of Environmental Management,

Washington, DC (United States). DOE Contract W-7405-

ENG-48. DE-AC06-93RL-12367. Order Number

DE98057497. Source: OSTI; INIS; NTIS; GPO Dep.

This plan describes inspection, monitoring, and maintenance activities for the 300 Area Process Trenches (APT).

The 300 APT is located within the 300-FF-1 Operable Unit

of the U. S. Department of Energy’s Hanford Site. The 300

APT was constructed and began operations in 1975 as the

316-S Process Trenches. The 300 APT received effluent discharges from the 300 Area process sewer system. The site

was closed to liquid discharges of dangerous waste in 1994.

73

(BHI–01162)

111-B Metal Examination Facility Concrete Tank Interim

Characterization Report. Encke, D.B.; Thoren, R.A. Bechtel Hanford, Inc., Richland, WA (United States). Jul 1998.

212p. Sponsored by USDOE, Washington, DC (United

States);USDOE Office of Environmental Management,

Washington, DC (United States). DOE Contract AC06-

93RL12367. Order Number DE98057854. Source: OSTI;

NTIS; INIS; GPO Dep.

This report addresses the characterization data collected

from the 111-B Metal Examination Facility from December

1996 through November 1997. The characterization activities identified and evaluated the radiological and suspect

hazardous materials within the tanks. The scope of this report is limited to the 111-B tank structure and concrete

foundation surrounding the tanks. Radiological surveys were

conducted to provide data on average levels and distribution

of contamination and dose rates within the tanks. The dose

rates were collected to estimate potential doses workers

might receive during the D&D and remedial action activities.

Dose rates can also be used to calculate total curie content

in the tanks when used in conjunction with sample data.

Large area wipes were obtained to determine if smearable

radioactive contamination was present on equipment and facility surfaces. The radiological survey data are provided in

Appendix A.

74

(BHI–01171)

Vadose Zone Clean Closure Report for the 300 Area Process Trenches. Lerch, J.A. Bechtel Hanford, Inc., Richland,

WA (United States). May 1998. 43p. Sponsored by USDOE,

Washington, DC (United States);USDOE Office of Environmental Management, Washington, DC (United States). DOE

Contract W-7405-ENG-48. DE-AC06-93RL-12367. Order

Number DE98057498. Source: OSTI; INIS; NTIS; GPO Dep.

This report documents the achievement of closure performance standards for the 300 Area Process Trenches (300

APT) located within the 300-FF-1 Operable Unit (OU). The

report is intended to supplement the 300 Area Process

Trenches Verification Package (BHI 1998C), which documents the achievement of the remedial action objectives

specified in the 300-FF-1 Remedial Design Report/Remedial

Action Work Plan (RDR/RAWP) (DOE-RL 1997). Upon

16
Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

acceptance of this document by the Washington State Department of Ecology, a 60-day period will begin to certify

closure of the the process trenches.

75

(BHI–01177)

Borehole Summary Report for the 216-B-2-2 Ditch. Rohay, V.J.; Weekes, D.C. Bechtel Hanford, Inc., Richland,

WA (United States). Jun 1998. 117p. Sponsored by USDOE, Washington, DC (United States);USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract AC06-93RL12367. Order Number

DE98057564. Source: OSTI; NTIS; INIS; GPO Dep.

The purpose of this borehole summary report is to provide

the results of the drilling and sampling as a data package.

The 216-B-2-2 Ditch borehole data will be evaluated with

other existing data during remedial investigation/feasibility

study (RI/FS) work plan development for the Gable Mountain Pond/B-Pond and Ditches Cooling Water Group

(200-CW-1 ). Additional characterization needs for the ditch,

as well as for the 200-CW-1 Waste Group in general, will be

defined in an RI/FS work plan for the 200-CW-1 Waste

Group planned for preparation in fiscal year 1999. After

characterization activities have been completed for the

waste group, the information (including the 216-B-2-2 borehole data) will be collectively evaluated and documented in

a remedial investigation report.

76

(BHI–01178)

105-DR Large Sodium Fire Facility Supplemental Information to the Hanford Facility Contingency Plan (DOE/

RL-93-75). Edens, V.G. Bechtel Hanford, Inc., Richland, WA

(United States). May 1998. 11p. Sponsored by USDOE,

Washington, DC (United States);USDOE Office of Environmental Management, Washington, DC (United States). DOE

Contract W-7405-ENG-48. DE-AC06-93RL-12367. Order

Number DE98057319. Source: OSTI; INIS; NTIS; GPO Dep.

This document is a unit-specific contingency plan for the

105-DR Large Sodium Fire Facility and is intended to be

used as a supplement to DOE/RL-93-75, Hanford Facility

Contingency Plan (DOE-RL 1993). This unit-specific plan is

to be used to demonstrate compliance with the contingency

plan requirements of Washington Administrative Code

(WAC) 173-303 for certain Resource Conservation and Recovery Act of 1976 (RCRA) waste management units.The

LSFF occupied the former ventilation supply fan room and

was established to provide a means of investigating fire and

safety aspects associated with large sodium or other metal

alkali fires. The unit was used to conduct experiments for

studying the behavior of molten alkali metals and alkali

metal fires. This unit had also been used for the storage and

treatment of alkali metal dangerous waste. Additionally, the

Fusion Safety Support Studies programs sponsored

intermediate-size safety reaction tests in the LSFF with

lithium and lithium-lead compounds. The LSFF, which is a

RCRA site, was partially clean closed in 1995 and is documented in ’Transfer of the 105-DR Large Sodium Fire

Facility to Bechtel Hanford, Inc.’ (BHI 1998). In summary,

the 105-DR supply fan room (1720-DR) has been demolished, and a majority of the surrounding soils were

clean-closed. The 117-DR Filter Building, 116-DR Exhaust

Stack, 119- DR Sampling Building, and associated ducting/

tunnels were not covered under this closure.

77

(BHI–01188)

105-DR Large Sodium Fire Facility Inspection Plan.

Zoric, J.P. Bechtel Hanford, Inc., Richland, WA (United

States). May 1998. 5p. Sponsored by USDOE, Washington,

DC (United States);USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

W-7405-ENG-48. DE-AC06-93RL-12367. Order Number

DE98057499. Source: OSTI; INIS; NTIS; GPO Dep.

This document provides the inspection plan for the 105-

DR Large Sodium Fire Facility (LSFF). The 105-DR LSFF is

a partially closed Resource Conservation and Recovery Act

(RCRA) facility. Included in this plan are the details concerning necessary surveillance and inspection for proper sign

posting and other factors that may affect the integrity of the

facility. A checklist shall be completed by personnel conducting the inspection.

78

(BHI–01196)

ALARA Review for the Decontamination, Deactivation

and Housekeeping of the 233-S Viewing Room. Kornish,

M.J. Bechtel Hanford, Inc., Richland, WA (United States).

Jun 1998. 17p. Sponsored by USDOE, Washington, DC

(United States);USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC06-93RL12367. Order Number DE98057660. Source:

OSTI; NTIS; INIS; GPO Dep.

A formal as low as reasonably achievable (ALARA) review

is required by BHI-SH-02, Vol. 1, Safety and Health Procedures, Procedure 1.22, ’Planning Radiological Work’, when

radiological conditions exceed trigger level. The level of contamination inside the viewing room of the 233-S Facility

meets this criterion. This ALARA review is for task instructions 1997-03-18-005-8.3.1, ’Instructions for Routine Entries

and Minor Maintenance Work at 233-S,’ and 8.3.2, ’Instructions for Deactivation, Decon, and Housekeeping in Viewing

Room.’ The radiological work permit (RWP) request broke

the two task instructions into nine separate tasks. The nine

tasks identified in the RWP request were used to estimate

airborne concentrations and the total exposure.

79

(BHI–01201)

ALARA Review of the Activation/Repair of Fire Detectors in Zone Three at the 233-S Facility. Kornish, M.J.

Bechtel Hanford, Inc., Richland, WA (United States). Jul

1998. 19p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract AC06-93RL12367. Order Number DE98058351.

Source: OSTI; NTIS; INIS; GPO Dep.

A formal as low as reasonably achievable (ALARA) review

is required by BHI-SH-02, Vol. 1, Procedure 1.22, ’Planning

Radiological Work’, when radiological conditions exceed trigger levels. The level of contamination inside the viewing

room meets this criterion. This ALARA review is for task instruction 1997-03-18-005-8.3.3 (mini task instruction to a

living work package), ’Instructions for D&D Support of Fire

Detector Troubleshooting and Minor Maintenance Work at

233-S,’ and DynCorp 2G-98-7207C, ’233-S Reconnect

Smoke Detectors Zone 3.’ The Radiological Work Permit

(RWP) request broke these two task instructions into four

separate tasks. The four tasks identified in the RWP request

were used to estimate airborne concentrations and the total

exposure.

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

80

(BHI–01208)

ALARA Review for the 202-S Plutonium Loadout Hood

Sampling. Winslow, R.C. Bechtel Hanford, Inc., Richland,

WA (United States). Aug 1998. 16p. Sponsored by USDOE,

Washington, DC (United States);USDOE Office of Environmental Management, Washington, DC (United States). DOE

Contract AC06-93RL12367. Order Number DE98058385.

Source: OSTI; NTIS; INIS; GPO Dep.

This as low as reasonably achievable (ALARA) review

provides a description of the engineering and administrative

controls used to manage personnel exposure, control

contamination levels, and control airborne radioactivity concentrations while preparing for sampling of the 202-S

Facility plutonium loadout hood under task instruction

19980325002, ’202-S Plutonium Loadout Hood Sampling’.

Preparation for sampling includes pre-job surveys of the

area around the Plutonium Loadout Hood and decontamination as required to allow set up for sampling activities. The

Reduction-Oxidation (REDOX) Facility separations process

was implemented at the 202-S Canyon Building in January

1951 and was discontinued at the end of 1966. The REDOX

process used several organic solvent extraction steps that

allowed continuous separation of both plutonium and uranium from dissolved fuel rod solution. The plutonium loadout

hood and the plutonium concentration system have been

identified for potential removal and disposal.

81

(BJC/OR–6)

In-Process Analysis Program for the Isolock sampler at

the Gunite and Associated Tanks, Oak Ridge National

Laboratory, Oak Ridge, Tennessee. Bechtel Jacobs Co.,

Oak Ridge, TN (United States);Providence Group, Inc.,

Knoxville, TN (United States). May 1998. 18p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract AC05-98OR22700. Order

Number DE98005153. Source: OSTI; NTIS; INIS; GPO Dep.

The In-Process Analysis Program documents the requirements for handling, transporting, and analyzing waste slurry

samples gathered by the Bristol Isolock slurry sampler from

the Gunite and Associated Tanks at Oak Ridge National

Laboratory in Oak Ridge, Tennessee. Composite samples

will be gathered during sludge retrieval operations, labeled,

transported to the appropriate laboratory, and analyzed for

physical and radiological characteristics. Analysis results will

be used to support occupational exposure issues, basic

process control management issues, and prediction of radionuclide flow.

82

(BJC/OR–15/R1)

Work plan for denaturing waste in the Old Hydrofracture

Tanks at Oak Ridge National Laboratory, Oak Ridge,

Tennessee. Oak Ridge National Lab., TN (United States).

Jun 1998. 16p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE

Contract AC05-98OR22700. Order Number DE98005705.

Source: OSTI; NTIS; INIS; GPO Dep.

The Environmental Management Program at Oak Ridge

National Laboratory (ORNL) is managing a project to remove the contents of the Old Hydrofracture (OHF) Tanks,

located in Melton Valley. CDM Federal is responsible for

sluicing the sludge and supernate from the OHF Tanks and

transferring the slurry into the Melton Valley Storage Tanks

(MVSTs), ORNL’s active liquid low-level waste system. Before the material can be sluiced to the MVSTs, it must meet

the requirements of WM-LWS-WAC, Waste Acceptance Criteria for Liquid Low-Level Waste System, Process Waste

Treatment Complex-Building 3544, and Process Waste

Treatment Complex-Building 3608, which contains requirements for ratios of fissile to nonfissionable isotopes.

Because the sludge and supernate contain uranium with

increased ratios of U-233 and U-235 to U-238, depleted uranium must be added to the tanks to dilute the isotopic ratio

of the contents before they can be sluiced. This work plan

describes the denaturing activities, namely adding depleted

uranyl nitrate solution, to be performed to ensure that the

material meets requirements. Personnel from the ORNL

Chemical Technology Division are responsible for the denaturing activity described in this work plan.

83

(BJC/OR–18)

Evaluation of the Molten Salt Reactor Experiment drain

tanks for reuse in salt disposal, Oak Ridge National Laboratory, Oak Ridge, Tennessee. Bechtel Jacobs Co., Oak

Ridge, TN (United States). May 1998. 73p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract AC05-98OR22700. Order

Number DE98005245. Source: OSTI; NTIS; INIS; GPO Dep.

This report was prepared to identify the source documentation used to evaluate the drain tanks in the Molten Salt

Reactor Experiment (MSRE) at Oak Ridge National Laboratory (ORNL). The evaluation considered the original quality

of the tanks, their service history, and their intended use

during the removal of fluoride salts. It also includes recommendations for a quality verification plan. The estimates of

corrosion damage to the salt containing system at the MSRE

are low enough to lend optimism that the system will be fit

for its intended use, which is disposal of the salt by transferring it to transport containers. The expected corrosion to

date is estimated between 10 and 50 mil, or 2 to 10% of the

shell wall. The expected corrosion rate when the tanks are

used to remove the salt at 110 F is estimated to be .025 to

0.1 mil per hour of exposure to HF and molten salt. To provide additional assurance that the estimates of corrosion

damage are accurate, cost effective nondestructive examination (NDE) has been recommended. The NDE procedures

are compared with industry standards and give a perspective

for the extent of additional measures taken in the recommendation. A methodology for establishing the remaining life

has been recommended, and work is progressing towards

providing an engineering evaluation based upon thickness

and design conditions for the future use of the tanks. These

extra measures and the code based analysis will serve to

define the risk of salt or radioactive gases leaking during

processing and transfer of the salt as acceptable.

84

(BJC/OR–44)

Contingency plan for the Old Hydrofracture Facility

Tanks Sluicing Project at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Bechtel Jacobs Co. LLC, Oak

Ridge, TN (United States). Jun 1998. 30p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract AC05-98OR22700. Order

Number DE98005706. Source: OSTI; NTIS; INIS; GPO Dep.

This revised contingency plan addresses potential scenarios involving the release of radioactively contaminated waste

18
Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

from the Old Hydrofracture Facility Tanks Contents Removal

project to the environment. The tanks are located at the Oak

Ridge National Laboratory. The project involves sluicing the

contents of the five underground tanks to mix the sludge and

supernatant layers, and pumping the mixture to the Melton

Valley Storage Tanks (MVST) for future processing. The

sluicing system to be used for the project consists of a spray

nozzle designated the “Borehole Miner,” with an associated

pump; in-tank submersible pumps to transfer tank contents

from the sluice tanks to the recycle tank; high-pressure

pumps providing slurry circulation and slurry transport to the

MVST; piping; a ventilation system; a process water system;

an instrumentation and control system centered around a

programmable logic controller; a video monitoring system;

and auxiliary equipment. The earlier version of this plan,

which was developed during the preliminary design phase of

the project, identified eight scenarios in which waste from

the tanks might be released to the environment as a result

of unanticipated equipment failure or an accident (e.g., vehicular accident). One of those scenarios, nuclear criticality,

is no longer addressed by this plan because the tank waste

will be isotopically diluted before sluicing begins. The other

seven scenarios have been combined into three, and a

fourth, Borehole Miner Failure, has been added as follows:

(1) underground release from the tanks; (2) aboveground release or spill from the sluicing system, a tank riser, or the

transfer pipeline; (3) release of unfiltered air through the

ventilation system; and (4) Borehole Miner arm retraction

failure. Methods for preventing, detecting, and responding to

each release scenario are set out in the plan.

85

(BJC/OR–53)

Project management plan for Waste Area Grouping 5

Old Hydrofracture Facility tanks contents removal at

Oak Ridge National Laboratory, Oak Ridge, Tennessee.

Oak Ridge National Lab., TN (United States);CDM Federal

Programs Corp., Oak Ridge, TN (United States). Jun 1998.

23p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC05-98OR22700. Order Number DE98005707. Source:

OSTI; NTIS; INIS; GPO Dep.

On January 1, 1992, the US Department of Energy (DOE),

the US Environmental Protection Agency (EPA) Region IV,

and the Tennessee Department of Environment and Conservation (TDEC) signed a Federal Facility Agreement (FFA)

concerning the Oak Ridge Reservation. The FFA requires

that inactive liquid low-level (radioactive) waste (LLLW)

tanks at Oak Ridge National Laboratory (ORNL) be remediated in accordance with requirements of the Comprehensive

Environmental Response, Compensation, and Liability Act

(CERCLA). This revision is to update the schedule and designation of responsibilities for the Old Hydrofracture Facility

(OHF) tanks contents removal project. The scope of this

project is to transfer inventory from the five inactive LLLW

tanks at the OHF into the active LLLW system.

86

(BJC/OR–55)

Guidance for treatment of variability and uncertainty in

ecological risk assessments of contaminated sites.

Bechtel Jacobs Co., Oak Ridge, TN (United States). Jun

1998. 49p. Sponsored by USDOE Office of Financial Management and Controller, Washington, DC (United

States);USDOE Office of Environmental Management,

Washington, DC (United States). DOE Contract AC05-

98OR22700. Order Number DE98005806. Source: OSTI;

NTIS; INIS; GPO Dep.

Uncertainty is a seemingly simple concept that has

caused great confusion and conflict in the field of risk assessment. This report offers guidance for the analysis and

presentation of variability and uncertainty in ecological risk

assessments, an important issue in the remedial investigation and feasibility study processes. This report discusses

concepts of probability in terms of variance and uncertainty,

describes how these concepts differ in ecological risk assessment from human health risk assessment, and

describes probabilistic aspects of specific ecological risk assessment techniques. The report ends with 17 points to

consider in performing an uncertainty analysis for an ecological risk assessment of a contaminated site.

87

(BNL–64595)

Northeast Waste Management Enterprise (NEWME) 1996

annual/final report. Goland, A. (Brookhaven National Lab.,

Upton, NY (United States)); Kaplan, E.; Palmedo, P. Wortman, J. Brookhaven National Lab., Upton, NY (United

States). [1997]. 130p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States).

DOE Contract AC02-76CH00016. Order Number

DE98000148. Source: OSTI; NTIS; INIS; GPO Dep.

The Northeast Waste Management Enterprise was created in response to Dr. Clyde Frank’s vision of a new

partnership between research, industrial, and financial sectors, with the goal of speeding development and use

(particularly at U.S. Department of Energy [DOE] facilities)

of environmental remediation technologies. It was anticipated that this partnership would also strengthen the

international competitiveness of the U.S. environmental industry. Brookhaven National Laboratory’s (BNL) response to

Dr. Frank was a proposal to create the Northeast Waste

Management Alliance, later renamed the Northeast Waste

Management Enterprise (NEWME). Recognizing the need to

supplement its own technical expertise with acumen in

business, financial management, and venture capital development, BNL joined forces with the Long Island Research

Institute (LIRI). Since its inception at the end of FY 1993,

NEWME has achieved several significant accomplishments

in pursuing its original business and strategic plans.

However, its successes have been constrained by a fundamental mismatch between the time scales required for

technology commercialization, and the immediate need for

available environmental technologies of those involved with

ongoing environmental remediations at DOE facilities.

88

(BNL–64969)

Overview of environmental decision support software.

Sullivan, T.M. (Brookhaven National Lab., Upton, NY

(United States)); Moskowitz, P.D.; Gitten, M. Brookhaven

National Lab., Upton, NY (United States). [1997]. 29p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC02-76CH00016. (CONF-9705216–: Toxicology in risk assessment conference, Bethesda, MD (United States), 14-16

May 1997). Order Number DE98001628. Source: OSTI;

NTIS; GPO Dep.

Regulatory exposure limits form the basis for making decisions on the characterization, monitoring, and remediation of

19
ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

environmental contamination. This paper discusses the

development of Decision Support Software (DSS) tools developed to support decisions pertaining to environmental

management. Decision support software packages are

computer-based programs that facilitate the use of data,

models, and structured decision processes in decision making. They incorporate the information into an integrated

package that presents results in a format useful for making

environmental decisions. Six major analysis functions of

DSS tools have been identified: site characterization, plume

characterization, risk assessment including regulatory compliance assessment, remedy selection, remedy design

optimization, and cost/benefit analysis. Decision support

software is relatively new and is now beginning to see application in the field. This paper discusses existing DSS and

the strengths and limitations of some of the DSS packages.

General limitations of decision support software are also discussed.

89

(BNL–65039)

Commercialization of the polyethylene macroencapsulation process. Lageraaen, P.R. (Brookhaven National Lab.,

Upton, NY (United States)); Kalb, P.D.; Hellstrom, G.W.;

Vance, J.K. Brookhaven National Lab., Upton, NY (United

States). Jan 1998. 7p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States).

DOE Contract AC02-76CH00016. (CONF-960804–: SPECTRUM ’96: international conference on nuclear and

hazardous waste management, Seattle, WA (United States),

18-23 Aug 1996). Order Number DE98003076. Source:

OSTI; NTIS; INIS; GPO Dep.

With support from the US Department of Energy Office of

Science and Technology (DOE OST) and assistance from

Brookhaven National Laboratory (BNL), Envirocare of Utah,

Inc. (Envirocare) is commercializing the polyethylene

macroencapsulation process. Envirocare, currently the only

commercially licensed mixed waste disposal facility in the

US, will initially demonstrate the process by treating and disposing up to 227,000 kg (500,000 lbs) of radioactively

contaminated lead. This waste, considered mixed due to

both radioactive and hazardous constituents, is currently being stored at various sites throughout the DOE complex.

Following this initial work for DOE, the process will be available for the treatment of other applicable wastes. Throughout

commercialization of this process, BNL has provided Envirocare with technical support for engineering and permitting.

90

(CONF-9606392–Summ.)

The Keystone Center final technical report. Keystone

Center, Keystone, CO (United States). 22 Jan 1998. [100p.]

Sponsored by USDOE Office of Energy Research, Washington, DC (United States);USDOE Office of Environmental

Management, Washington, DC (United States). DOE

Contract FG03-96ER62220. (CONF-9606393–Summ.: Environmental Management Science Program (EMSP)

workshop; Environmental management science program

workshop; Environmental management science program

workshop; Environmental management science program

workshop, Savannah River, SC (Un Order Number

DE98004409. Source: OSTI; NTIS; INIS; GPO Dep.

The Keystone Center began its work with the Environmental Management Science Program (EMSP) in May,

1996, when The Center agreed to design, organize, and facilitate stakeholder meetings at two DOE sites: Savannah

River and Hanford. These meetings were held June 24–25,

1996 for the purpose of discussing the role of EMSP in constructing a site-specific basic research agenda that maps

site cleanup needs to basic science areas. Summaries of

the discussions from these meetings as well as lists of the

stakeholders who were invited are included as Attachment

1. In August/September 1996, the Keystone Center was

asked to convene two additional site meetings using funds

that remained in their contract. These meetings were held in

October 1996 at Oak Ridge and Idaho National Engineering

Laboratory. Summaries from these meetings and participant

lists are included as Attachment 2.

91

(CONF-970126–)

Proceedings for the nondestructive assay and

nondestructive examination waste characterization conference. No. 5. Lockheed Idaho Technologies Co., Idaho

Falls, ID (United States). 1997. 521p. Sponsored by USDOE

Office of Environmental Management, Washington, DC

(United States). DOE Contract AC07-94ID13223. From 5.

nondestructive assay/nondestructive examination waste

characterization conference; Salt Lake City, UT (United

States); 14-16 Jan 1997. Order Number DE97052960.

Source: OSTI; NTIS; INIS; GPO Dep.

This report contains paper presented at the 5th Nondestructive Assay and nondestructive Examination Waste

Characterization conference. Topics included compliance,

neutron NDA techniques, gamma NDA techniques, tomographic methods, and NDA modality and information

combination techniques. Individual reports have been processed separately for the United States Department of

Energy databases.

92

(CONF-970148–1)

Solvent extraction of radionuclides from aqueous tank

waste. Moyer, B.A. (Oak Ridge National Lab., TN (United

States). Chemical and Analytical Sciences Div.); Bonnesen,

P.V.; Sachleben, R.A.; Leonard, R.A.; Lumetta, G.J. Oak

Ridge National Lab., TN (United States). [1997]. 8p. Sponsored by USDOE Office of Environmental Management,

Washington, DC (United States). DOE Contract AC05-

96OR22464. From Efficient Separations and Processing

(ESP) Crosscutting Program FY 1997 technical exchange

meeting; Gaithersburg, MD (United States); 28-30 Jan 1997.

Order Number DE97001645. Source: OSTI; NTIS; INIS;

GPO Dep.

This task aims toward the development of efficient solventextraction processes for the removal of the fission products

99Tc, 90Sr, and 137Cs from alkaline tank wastes. Processes

already developed or proposed entail direct treatment of the

waste solution with the solvent and subsequent stripping of

the extracted contaminants from the solvent into a dilute

aqueous solution. Working processes to remove Tc(and SR)

separately and Cs separately have been developed; the feasibility of a combined process is under investigation. Since

Tc, Sr, and Cs will be vitrified together in the high-level fraction, however, a process that could separate Tc, Sr, and Cs

simultaneously, as opposed to sequentially, potentially offers

the greatest impact. A figure presents a simplified diagram

of a proposed solvent-extraction cycle followed by three

possible treatments for the stripping solution. Some degree

20
Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

of recycle of the stripping solution (option a) is expected.

Simple evaporation (option c) is possible prior to vitrification;

this offers the greatest possible volume reduction with simple operation and no consumption of chemicals, but it is

energy intensive. However, if the contaminants are concentrated (option b) by fixed-bed technology, the energy penalty

of evaporation can be avoided and vitrification facilitated

without any additional secondary waste being produced.

93

(CONF-970208–4)

Degradation of trichloroethylene (TCE) and polychlorinated biphenyls (PCBs) by Fe and Fe-Pd bimetals in the

presence of surfactants and cosolvents. Gu, B. (Oak

Ridge National Lab., TN (United States)); Liang, L.; West,

O.R.; Cameron, P.; Davenport, D. Oak Ridge National Lab.,

TN (United States). [1997]. 10p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States). DOE Contract AC05-96OR22464. From International containment technology conference and exhibition; St.

Petersburg, FL (United States); 9-12 Feb 1997. Order Number DE97001366. Source: OSTI; NTIS; INIS; GPO Dep.

Surfactants and cosolvents are being used to enhance

the removal of dense non-aqueous phase liquids (DNAPL)

such as trichloroethylene (TCE) and polychlorinated

biphenyls (PCBS) from contaminated soils. However, the

waste surfactant solution containing TCE and PCBs must be

treated before it can be disposed. This study evaluated the

use of zero-valence iron and palladized iron fillings on the

dechlorination of TCE and a PCB congener in a dihexylsulfosuccinate surfactant solution. Batch experimental results

indicated that TCE can be rapidly degraded by palladized

iron filings with a half-life of 27.4 min. PCB was degraded at

a slower rate than TCE with a half-life ranging from 100 min

to 500 min as the concentration of surfactant increased. In

column flow-through experiments, both TCE and PCBs degrade at an enhanced rate with a half-life about 1.5 and 6

min because of an increased solid to solution ratio in the

column than in the batch experiments. Results of this work

suggest that Fe-Pd filings may be potentially applicable for

ex-situ treatment of TCE and PCBs in the surfactant solutions that are generated during surfactant washing of the

contaminated soils.

94

(CONF-970208–7)

A case study: using a multi-grout barrier to control 90Sr

release at ORNL. Long, J.D. (Lockheed Martin Energy Systems, Inc., Oak Ridge, TN (United States)); Huff, D.D.;

Naudts, A.A. Oak Ridge National Lab., TN (United States).

[1997]. 8p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract AC05-96OR22464. From International containment

technology conference and exhibition; St. Petersburg, FL

(United States); 9-12 Feb 1997. Order Number

DE97003335. Source: OSTI; NTIS; INIS; GPO Dep.

During summer 1996, low-pressure permeation grouting

was performed inside portions of four unlined, shallow waste

disposal trenches at a radioactive waste burial ground that

was opened in 1951 at the Oak Ridge National Laboratory

(ORNL). The objective was to selectively control sources

that release about 25 percent of all strontium 90 (90Sr) discharged from the ORNL complex. A unique grouting

methodology was adapted to control interaction of wastes

with natural runoff at this humid site. Driven sleeve pipes

were injected 4 to 5 times with multiple formulae of type III

portland cement- based grouts, ultra fine cement-based

grouts, and acrylamide grouts. Multiple-hole grout injection

was monitored continuously using real time monitoring

equipment. Apparent Lugeon values were calculated during

grouting operations and grout formulae were continually adjusted during injection to maximize permeation, durability,

and economy. Over 500 cubic meters of combined grout

types were emplaced. At the completion of production grouting, the effectiveness of grout spread and in situ hydraulic

conductivity of the grouted mass were assessed. The average residual hydraulic conductivity measured in more than

20 check pipes was less than I x 10’ cm/sec. Hydrologic

monitoring has been established to determine the overall effectiveness of the project for 9OSr control.

95

(CONF-970208–11)

Bear Creek Valley characterization area mixed wastes

passive in situ treatment technology demonstration

project - status report. Watson, D. (Oak Ridge National

Lab., TN (United States)); Leavitt, M.; Moss, D. Oak Ridge

National Lab., TN (United States). 1997. 7p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract AC05-96OR22464. From

International containment technology conference and exhibition; St. Petersburg, FL (United States); 9-12 Feb 1997.

Order Number DE97003184. Source: OSTI; NTIS; INIS;

GPO Dep.

Historical waste disposal activities within the Bear Creek

Valley (BCV) Characterization Area (CA), at the U.S. Department of Energy (DOE) Oak Ridge Y-12 plant, have

contaminated groundwater and surface water above human

health risk levels and impacted the ecology of Bear Creek.

Contaminates include nitrate, radioisotopes, metals, volatile

organic chemicals (VOCS), and common ions. This paper

provides a status report on a technology demonstration

project that is investigating the feasibility of using passive in

situ treatment systems to remove these contaminants. Although this technology may be applicable to many locations

at the Oak Ridge Y-12 Plant, the project focuses on collecting the information needed to take CERCLA removal actions

in 1998 at the S-3 Disposal Ponds site. Phase 1 has been

completed and included site characterization, laboratory

screening of treatment media (sorbents; and iron), and limited field testing of biological treatment systems. Batch tests

using different Y-12 Plant waters were conducted to evaluate the removal efficiencies of most of the media. Phase 1

results suggest that the most promising treatment media are

Dowex 21 k resin, peat moss, zero-valent iron, and iron oxides. Phase 2 will include in-field column testing of these

media to assess loading rates, and concerns with clogging,

by-products, and long-term treatment efficiency and media

stability. Continued testing of wetlands and algal mats

(MATs) will be conducted to determine if they can be used

for in-stream polishing of surface water. Hydraulic testing of

a shallow trench and horizontal well will also be completed

during Phase 2. 4 refs., 3 tabs.

96

(CONF-970208–Proc.)

International Containment Technology Conference: proceedings. USDOE, Washington, DC (United States). [1997].

1140p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States);Environmental

21
ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

Protection Agency, Washington, DC (United

States);Department of the Air Force, Washington, DC

(United States);American Society of Civ From International

containment technology conference and exhibition; St. Petersburg, FL (United States); 9-12 Feb 1997. Order Number

DE98001967. Source: OSTI; NTIS; INIS; GPO Dep.

This document contains the manuscripts of the papers

and posters presented at the 1997 International Containment Technology Conference and Exhibition. These

manuscripts represent a valuable compilation of information

and data on the environmental challenges and technologybased solutions associated with containment technologies.

The purpose of the conference was to promote the

advancement of containment technologies by providing a forum from which participants from related disciplines could

meet to exchange ideas and information on recent developments. Selected papers were indexed separately for

inclusion in the Energy Science and Technology Database.

97

(CONF-970321–2)

Cesium removal flow studies using ion exchange. Lee,

D.D. (and others); Walker, J.F. Jr.; Taylor, P.A. Oak Ridge

National Lab., TN (United States); Westinghouse Hanford

Co., Richland, WA (United States). 1997. 40p. Sponsored

by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract AC05-96OR22464 ;

AC06-87RL10930. From National spring meeting and petrochemical exposition of the American Institute of Chemical

Engineers (AIChE) and 2. plant operations and design conference; Houston, TX (United States); 10-13 Mar 1997.

Order Number DE97003333. Source: OSTI; NTIS; INIS;

GPO Dep.

Cesium and strontium radionuclides are a small fraction of

the mainly sodium and potassium salts in underground storage tank supernatant at US Department of Energy (DOE)

sites at Hanford, Oak Ridge, Savannah River, and Idaho

that DOE must remediate. Cesium-137 (137Cs) is the primary gamma radiation source in the dissolved tank waste at

these sites, and its removal from the supernatant can reduce the hazard and waste classification of the treated

waste reducing the further treatment and disposal costs.

Several cesium removal sorbents have been developed by

private industry and the US DOE’s Office of Science and

Technology. Several of these removal technologies have

been previously tested in small batch and column tests using simulated and a few actual supernatant under DOE’s

Environmental Management (EM) programs including the

Tanks Focus Area (TFA) and the Efficient Separations and

Processing (ESP) Cross-Cutting Program.

98

(CONF-970321–4)

Tank Focus Area pretreatment activities. McGinnis, C.P.

(Oak Ridge National Lab., TN (United States)); Welch, T.D.;

Manke, K.L. Oak Ridge National Lab., TN (United States);

Pacific Northwest National Lab., Richland, WA (United

States). [1997]. 20p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States).

DOE Contract AC05-96OR22464 ; AC06-76RL01830. From

National spring meeting and petrochemical exposition of the

American Institute of Chemical Engineers (AIChE) and 2.

plant operations and design conference; Houston, TX

(United States); 10-13 Mar 1997. Order Number

DE97004113. Source: OSTI; NTIS; INIS; GPO Dep.

Plans call for the high-level wastes to be retrieved from

the tanks and immobilized in a stable waste form suitable for

long-term isolation. Chemistry and chemical engineering operations are required to retrieve the wastes, to condition the

wastes for subsequent steps, and to reduce the costs of the

waste management enterprise. Pretreatment includes those

processes between retrieval and immobilization, and

includes preparation of suitable feed material for immobilization and separations to partition the waste into streams that

yield lower life-cycle costs. Some of the technologies being

developed by the Tank Focus Area (TFA) to process these

wastes are described. These technologies fall roughly into

three areas: (1) solid/liquid separation (SLS), (2) sludge pretreatment, and (3) supernate pretreatment.

99

(CONF-970335–15)

The mixed waste focus area mercury working group: an

integrated approach for mercury treatment and disposal. Conley, T.B. (Oak Ridge National Lab., TN (United

States)); Morris, M.I.; Holmes-Burns, H.; Petersell, J.;

Schwendiman, L. Oak Ridge National Lab., TN (United

States). [1997]. 8p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE

Contract AC05-96OR22464. From Waste Management ‘97;

Tucson, AZ (United States); 2-7 Mar 1997. Order Number

DE97003084. Source: OSTI; NTIS; INIS; GPO Dep.

In May 1996, the U.S. Department of Energy (DOE)

Mixed Waste Focus Area (MWFA) initiated the Mercury

Work Group (HgWG), which was established to address and

resolve the issues associated with mercury- contaminated

mixed wastes. Three of the first four technology deficiencies

identified during the MWFA technical baseline development

process were related to mercury amalgamation, stabilization, and separation/removal. The HgWG will assist the

MWFA in soliciting, identifying, initiating, and managing all

the efforts required to address these deficiencies. The focus

of the HgWG is to better establish the mercury-related treatment needs at the DOE sites, refine the MWFA technical

baseline as it relates to mercury treatment, and make recommendations to the MWFA on how to most effectively

address these needs. The team will initially focus on the

sites with the most mercury-contaminated mixed wastes,

whose representatives comprise the HgWG. However, the

group will also work with the sites with less inventory to

maximize the effectiveness of these efforts in addressing the

mercury- related needs throughout the entire complex.

100

(CONF-970344–1)

Seismic reflection processing for characterization of a

hazardous waste site. Liu, Z.-M. (Oklahoma Univ.,

Norman, OK (United States). School of Geology and Geophysics); Doll, W.E. Oak Ridge National Lab., TN (United

States). [1997]. 9p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE

Contract AC05-96OR22464. From SAGEEP ’97: 10. annual

symposium on the application of geophysics to environmental and engineering problems; Reno, NV (United States);

23-26 Mar 1997. Order Number DE97003087. Source:

OSTI; NTIS; INIS; GPO Dep.

Seismic reflection data have been acquired by the Kansas

Geological Survey near the Oak Ridge K-25 Plant on the

Oak Ridge Reservation, Tennessee, to assist in the selection of ground water monitoring well locations. The data

22
Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

were recorded in uncorrelated format to allow flexibility in

enhancement of stacked images. During the summer of

1996, five of the thirteen seismic reflection lines acquired

were processed. An unconventional correlation procedure,

”Vibroseis Whitening” (VSW) (Coruh and Costain, 1983) has

been applied to produce improved seismic sections. Refraction statics corrections, which remove the detrimental effect

of an irregular weathered layer, have also been utilized to

improve the seismic sections. The seismic data were

stacked using the velocities obtained from a standard semblance velocity analysis tool. Locations and orientations of

faults or fault zones can be interpreted from these stacked

sections, and they are in agreement with the interpretations

of the surface mapping in the area. This paper concludes

that VSW and refraction statics can be important to nearsurface swept source seismic data processing.

101

(CONF-970462–1)

RoboCon: A general purpose telerobotic control center.

Draper, J.V. (Oak Ridge National Lab., TN (United States).

Robotics and Process Systems Div.); Noakes, M.W.;

Schempf, H.; Blair, L.M. Oak Ridge National Lab., TN

(United States). [1997]. 7p. Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract AC05-96OR22464. From 7. American Nuclear Society topical meeting on robotics and remote

handling; Savannah, GA (United States); 27 Apr - 1 May

1997. Order Number DE97001649. Source: OSTI; NTIS;

INIS; GPO Dep.

This report describes human factors issues involved in the

design of RoboCon, a multi-purpose control center for use in

US Department of Energy remote handling applications.

RoboCon is intended to be a flexible, modular control center

capable of supporting a wide variety of robotic devices.

102

(CONF-970462–3)

Dual Arm Work Package performance estimates and

telerobot task network simulation. Draper, J.V. (Oak

Ridge National Lab., TN (United States). Robotics and Process Systems Div.); Blair, L.M. Oak Ridge National Lab., TN

(United States). [1997]. 8p. Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract AC05-96OR22464. From 7. American Nuclear Society topical meeting on robotics and remote

handling; Savannah, GA (United States); 27 Apr - 1 May

1997. Order Number DE97001647. Source: OSTI; NTIS;

INIS; GPO Dep.

This paper describes the methodology and results of a

network simulation study of the Dual Arm Work Package

(DAWP), to be employed for dismantling the Argonne National Laboratory CP-5 reactor. The development of the

simulation model was based upon the results of a task analysis for the same system. This study was performed by the

Oak Ridge National Laboratory (ORNL), in the Robotics and

Process Systems Division. Funding was provided the US

Department of Energy’s Office of Technology Development,

Robotics Technology Development Program (RTDP). The

RTDP is developing methods of computer simulation to estimate telerobotic system performance. Data were collected

to provide point estimates to be used in a task network

simulation model. Three skilled operators performed six repetitions of a pipe cutting task representative of typical

teleoperation cutting operations.

103

(CONF-970464–5)

Strategies for redundancy resolution of dual-arm systems with passive elements for tank waste removal.

Dubey, R. (Univ. of Tennessee, Knoxville, TN (United

States). Dept. of Mechanical Engineering); Love, L.J. Oak

Ridge National Lab., TN (United States). [1997]. 8p. Sponsored by USDOE Office of Environmental Management,

Washington, DC (United States);Oak Ridge Inst. for Science

and Education, TN (United States). DOE Contract AC05-

96OR22464. From 7. American Nuclear Society topical

meeting on robotics and remote systems; Augusta, GA

(United States); 27 Apr - 1 May 1997. Order Number

DE97002988. Source: OSTI; NTIS; INIS; GPO Dep.

The work described in this paper focuses on the coordination and control of two manipulators coupled by passive

elements operating in a confined space. An example of one

such system is the hardware used for the environmental response treatability study funded by the Department of

Energy at Oak Ridge National Laboratory (ORNL). The motivation for this project is to establish the methodology

necessary to extract large volumes of hazardous waste from

underground storage facilities. The hardware used at ORNL

consists of two long-reach manipulators. The first robot, the

Modified Light Duty Utility Arm (MLDUA), is an 8-degree-offreedom long-reach manipulator. The second arm, the Hose

Management Arm (HMA), has two active degrees-offreedom and provides hardware to break up and extract

materials from the tank. Current strategies call for the MLDUA to grasp a combined sluicing end-effector attached, by

a long flexible hose, to the HMA. The MLDUA will then

move the combined system through the waste, extracting

material. This paper describes many of the issues related to

redundancy resolution and the coordinated control of these

two robots. First, the authors provide a brief outline of the

project and the existing hardware. This is followed by a description of existing redundancy resolution techniques and

the impact redundancy has on the success of the project.

Finally, preliminary simulation results show the effect cooperative control has on the level of forces generated between

the dual-arm systems when coupled by an elastic exhaust

hose. These results show a significant reduction in forces

when both arms are active and have a combined manipulation strategy.

104

(CONF-970464–6)

Control of flexible robots with prismatic joints and hydraulic drives. Love, L.J. (Oak Ridge Inst. for Science and

Education, TN (United States)); Kress, R.L.; Jansen, J.F.

Oak Ridge National Lab., TN (United States). [1997]. 9p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC05-96OR22464. From 7. American Nuclear Society topical meeting on robotics and remote systems; Augusta, GA

(United States); 27 Apr - 1 May 1997. Order Number

DE97002980. Source: OSTI; NTIS; INIS; GPO Dep.

The design and control of long-reach, flexible manipulators has been an active research topic for over 20 years.

Most of the research to date has focused on single link,

fixed length, single plane of vibration test beds. In addition,

actuation has been predominantly based upon electromagnetic motors. Ironically, these elements are rarely found in

the existing industrial long-reach systems. One example is

the Modified Light Duty Utility Arm (MLDUA) designed and

23
ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

built by Spar Aerospace for Oak Ridge National Laboratory

(ORNL). This arm operates in larger, underground waste

storage tanks located at ORNL. The size and nature of the

tanks require that the robot have a reach of approximately

15 ft and a payload capacity of 250 lb. In order to achieve

these criteria, each joint is hydraulically actuated. Furthermore, the robot has a prismatic degree-of-freedom to ease

deployment. When fully extended, the robot’s first natural

frequency is 1.76 Hz. Many of the projected tasks, coupled

with the robot’s flexibility, present an interesting problem.

How will many of the existing flexure control algorithms perform on a hydraulic, long-reach manipulator with prismatic

links? To minimize cost and risk of testing these algorithms

on the MLDUA, the authors have designed a new test bed

that contains many of the same elements. This manuscript

described a new hydraulically actuated, long-reach manipulator with a flexible prismatic link at ORNL. Focus is directed

toward both modeling and control of hydraulic actuators as

well as flexible links that have variable natural frequencies.

105

(CONF-970464–7)

The Virtual Robotics Laboratory. Kress, R.L. (Oak Ridge

National Lab., TN (United States)); Love, L.J. Oak Ridge

National Lab., TN (United States). [1997]. 10p. Sponsored

by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract AC05-96OR22464.

From 7. American Nuclear Society topical meeting on

robotics and remote systems; Augusta, GA (United States);

27 Apr - 1 May 1997. Order Number DE97002986. Source:

OSTI; NTIS; INIS; GPO Dep.

The growth of the Internet has provided a unique opportunity to expand research collaborations between industry,

universities, and the national laboratories. The Virtual

Robotics Laboratory (VRL) is an innovative program at Oak

Ridge National Laboratory (ORNL) that is focusing on the issues related to collaborative research through controlled

access of laboratory equipment using the World Wide Web.

The VRL will provide different levels of access to selected

ORNL laboratory equipment to outside universities, industrial researchers, and elementary and secondary education

programs. In the past, the ORNL Robotics and Process Systems Division (RPSD) has developed state-of-the-art robotic

systems for the Army, NASA, Department of Energy, Department of Defense, as well as many other clients. After

proof of concept, many of these systems sit dormant in the

laboratories. This is not out of completion of all possible

research topics, but from completion of contracts and generation of new programs. In the past, a number of visiting

professors have used this equipment for their own research.

However, this requires that the professor, and possibly his

students, spend extended periods at the laboratory facility.

In addition, only a very exclusive group of faculty can gain

access to the laboratory and hardware. The VRL is a tool

that enables extended collaborative efforts without regard to

geographic limitations.

106

(CONF-970464–8)

Adaptive controller for hyperthermia robot. Kress, R.L.

Oak Ridge National Lab., TN (United States). [1997]. 8p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC05-96OR22464. From 7. American Nuclear Society topical meeting on robotics and remote systems; Augusta, GA

(United States); 27 Apr - 1 May 1997. Order Number

DE97002987. Source: OSTI; NTIS; GPO Dep.

This paper describes the development of an adaptive

computer control routine for a robotically, deployed focused,

ultrasonic hyperthermia cancer treatment system. The control algorithm developed herein uses physiological models of

a tumor and the surrounding healthy tissue regions and transient temperature data to estimate the treatment region’s

blood perfusion. This estimate is used to vary the specific

power profile of a scanned, focused ultrasonic transducer to

achieve a temperature distribution as close as possible to

an optimal temperature distribution. The controller is evaluated using simulations of diseased tissue and using limited

experiments on a scanned, focused ultrasonic treatment

system that employs a 5-Degree-of-Freedom (D.O.F.) robot

to scan the treatment transducers over a simulated patient.

Results of the simulations and experiments indicate that the

adaptive control routine improves the temperature distribution over standard classical control algorithms if good

(although not exact) knowledge of the treated region is

available. Although developed with a scanned, focused

ultrasonic robotic treatment system in mind, the control algorithm is applicable to any system with the capability to vary

specific power as a function of volume and having an unknown distributed energy sink proportional to temperature

elevation (e.g., other robotically deployed hyperthermia

treatment methods using different heating modalities).

107

(CONF-970464–9)

Simulation tools for hazardous waste removal. Bills, K.C.

(Oak Ridge National Lab., TN (United States)); Love, L.J.

Oak Ridge National Lab., TN (United States). [1997]. 7p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC05-96OR22464. From 7. American Nuclear Society topical meeting on robotics and remote systems; Augusta, GA

(United States); 27 Apr - 1 May 1997. Order Number

DE97002979. Source: OSTI; NTIS; INIS; GPO Dep.

The primary mission of Oak Ridge National Laboratory

(ORNL) during World War 2 was the processing of pure

plutonium metal in support of the Manhattan Project. Byproducts of this process include radioactive cesium-137 and

strontium-90. Between 1943 and 1951, the Gunite and Associated Tanks (GAAT) at ORNL were built to collect,

neutralize, and storage these by-products. Currently, twelve

gunite tanks and four stainless steel tanks are located on

the ORNL complex. Characterization studies of these tanks

in 1994 indicated that the structural integrity of some of the

tanks is questionable. These risks provided the motivation

for remediation and relocation of waste stored in the ORNL

tanks. A number of factors complicate the remediation process. The material stored in these tanks ranges from liquid

to sludge and solid and is composed of organic materials,

heavy metals, and radionuclides. Furthermore, the tanks,

which range from 12 to 50 ft in diameter, are located below

ground and in the middle of the ORNL complex. The only

access to these tanks is through one of three access ports

that are either 12 or 24 in. in diameter. These characteristics

provide a daunting challenge: how can material be safely removed from such a confined structure? This paper describes

the existing strategy and hardware projected for use in the

remediation process. This is followed by a description of an

integrated hardware system model. This investigation has

isolated a few key areas where further work may be needed.

24
Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

108

(CONF-970464–10)

Hydraulic manipulator research at ORNL. Kress, R.L.

(Oak Ridge National Lab., TN (United States)); Jansen, J.F.;

Love, L.J. Oak Ridge National Lab., TN (United States).

[1997]. 8p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract AC05-96OR22464. From 7. American Nuclear Society

topical meeting on robotics and remote systems; Augusta,

GA (United States); 27 Apr - 1 May 1997. Order Number

DE97002981. Source: OSTI; NTIS; INIS; GPO Dep.

Recently, task requirements have dictated that manipulator payload capacity increase to accommodate greater

payloads, greater manipulator length, and larger environmental interaction forces. General tasks such as waste

storage tank cleanup and facility dismantlement and decommissioning require manipulator life capacities in the range of

hundreds of pounds rather than tens of pounds. To meet the

increased payload capacities demanded by present-day

tasks, manipulator designers have turned once again to hydraulics as a means of actuation. In order to successfully

design, build, and deploy a new hydraulic manipulator (or

subsystem), sophisticated modeling, analysis, and control

experiments are usually needed. Oak Ridge National Laboratory (ORNL) has a history of projects that incorporate

hydraulics technology, including mobile robots, teleoperated

manipulators, and full-scale construction equipment. In addition, to support the development and deployment of new

hydraulic manipulators, ORNL has outfitted a significant

experimental laboratory and has developed the software capability for research into hydraulic manipulators, hydraulic

actuators, hydraulic systems, modeling of hydraulic systems, and hydraulic controls. The purpose of this article is to

describe the past hydraulic manipulator developments and

current hydraulic manipulator research capabilities at ORNL.

Included are example experimental results from ORNL’s

flexible/prismatic test stand.

109

(CONF-970464–11)

An investigation of a passively controlled haptic interface. Davis, J.T. (Oak Ridge National Lab., TN (United

States)); Book, W.J. Oak Ridge National Lab., TN (United

States). [1997]. 9p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States);National Science Foundation, Washington, DC

(United States). DOE Contract AC05-96OR22464. Grant

IRI-9526322. From 7. American Nuclear Society topical

meeting on robotics and remote systems; Augusta, GA

(United States); 27 Apr - 1 May 1997. Order Number

DE97002982. Source: OSTI; NTIS; INIS; GPO Dep.

Haptic interfaces enhance cooperation between humans

and robotic manipulators by providing force and tactile feedback to the human user during the execution of arbitrary

tasks. The use of active actuators in haptic displays

presents a certain amount of risk since they are capable of

providing unacceptable levels of energy to the systems

upon which they operate. An alternative to providing numerous safeguards is to remove the sources of risk altogether.

This research investigates the feasibility of trajectory control

using passive devices, that is, devices that cannot add energy to the system. Passive actuators are capable only of

removing energy from the system or transferring energy

within the system. It is proposed that the utility of passive

devices is greatly enhanced by the use of redundant actuators. In a passive system, once motion is provided to the

system, presumably by a human user, passive devices may

be able to modify this motion to achieve a desired resultant

trajectory. A mechanically passive, 2-Degree-of-Freedom

(D.O.F.) manipulator has been designed and built. It is

equipped with four passive actuators: two electromagnetic

brakes and two electromagnetic clutches. This paper gives

a review of the literature on passive and robotics and describes the experimental test bed used in this research.

Several control algorithms are investigated, resulting in the

formulation of a passive control law.

110

(CONF-9705112–1)

In situ global method for measurement of oxygen

demand and mass transfer. Klasson, K.T. (Oak Ridge National Lab., TN (United States). Chemical Technology Div.);

Lundbaeck, K.M.O.; Clausen, E.C.; Gaddy, J.L. Oak Ridge

National Lab., TN (United States). [1997]. 13p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract AC05-96OR22464. From

19. symposium on biotechnology for fuels and chemicals;

Colorado Springs, CO (United States); 4-8 May 1997. Order

Number DE97005994. Source: OSTI; NTIS; GPO Dep.

Two aerobic microorganisms, Saccharomycopsis lipolytica

and Brevibacterium lactofermentum, have been used in a

study of mass transfer and oxygen uptake from a global perspective using a closed gas system. Oxygen concentrations

in the gas and liquid were followed using oxygen electrodes,

and the results allowed for easy calculation of in situ oxygen

transport. The cell yields on oxygen for S. lipolytica and B.

lactofermentum were 1.01 and 1.53 g/g respectively. The

mass transfer coefficient was estimated as 10 h1 at 500

rpm for both fermentations. The advantages with this

method are noticeable since the use of model systems may

be avoided, and the in situ measurements of oxygen demand assure reliable data for scale-up.

111

(CONF-9705140–1)

The use of carbonate lixiviants to remove uranium from

uranium-contaminated soils. Francis, C.W. (Oak Ridge

National Lab., TN (United States)); Lee, S.Y.; Wilson, J.H.;

Timpson, M.E.; Elless, M.P. Oak Ridge National Lab., TN

(United States). [1997]. 21p. Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract AC05-96OR22464. From SIS ’97: 7.

international conference on separation of ionic solutes; Piestany Spa (Slovakia); 18-23 May 1997. Order Number

DE97007765. Source: OSTI; NTIS; INIS; GPO Dep.

The objective of this research was to design an extraction

media and procedure that would selectively remove uranium

without adversely affecting the soils’ physicochemical characteristics or generating secondary waste forms difficult to

manage or dispose of. Investigations centered around determining the best lixivant and how the various factors such as

pH, time, and temperature influenced extraction efficiency.

Other factors investigated included the influence of attrition

scrubbing, the effect of oxidants and reductants and the recycling of lixiviants. Experimental data obtained at the

bench- and pilot-scale levels indicated 80 to 95% of the uranium could be removed from the uranium-contaminated

soils by using a carbonate lixiviant. The best treatment was

25
ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

three successive extractions with 0.25 M carbonatebicarbonate (in presence of KMnO4 as an oxidant) at 40 C

followed with two water rinses.

112

(CONF-970675–1)

Admixture enhanced controlled low-strength material

for direct underwater injection with minimal crosscontamination. Hepworth, H.K.; Davidson, J.S.; Hooyman,

J.L. Oak Ridge National Lab., TN (United States). 1997.

16p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC05-96OR22464. From American Society for Testing and

Materials (ASTM) symposium on the design and application

of CLSM (flowable fill); St. Louis, MO (United States); 19-20

Jun 1997. Order Number DE97004112. Source: OSTI;

NTIS; INIS; GPO Dep.

Commercially available admixtures have been developed

for placing traditional concrete products under water. This

paper evaluates adapting anti-washout admixture (AWA)

and high range water reducing admixture (HRWRA) products to enhance controlled low-strength materials (CLSMs)

for underwater placement. A simple experimental scale

model (based on dynamic and geometric similitude) of

typical grout pump emplacement equipment has been developed to determine the percentage of cementing material

washed out. The objective of this study was to identify proportions of admixtures and underwater CLSM emplacement

procedures which would minimize the cross-contamination

of the displaced water while maintaining the advantages of

CLSM. Since the displaced water from radioactively contaminated systems must be subsequently treated prior to

release to the environment, the amount of crosscontamination is important for cases in which cementing

material could form hard sludges in a water treatment facility

and contaminate the in-place CLSM stabilization medium.

113

(CONF-9706113–12)

Implications of electron attachment to highly-excited

states in pulsed-power discharges. Pinnaduwage, L.A.

(Oak Ridge National Lab., TN (United States)). Oak Ridge

National Lab., TN (United States). 1997. 7p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States);National Science Foundation, Washington, DC (United States). DOE Contract AC05-96OR22464.

NSF Contract ECS-9626217. From 11. IEEE international

pulsed power conference; Baltimore, MD (United States); 29

Jun - 2 Jul 1997. Order Number DE97007788. Source:

OSTI; NTIS; INIS; GPO Dep.

The author points out the possible implications of electron

attachment to highly-excited states of molecules in two

pulsed power technologies. One involves the pulsed H2

discharges used for the generation of H ion beams for magnetic fusion energy and particle accelerators. The other is

the power modulated plasma discharges used for material

processing.

114

(CONF-970795–1)

Introduction to naturally occurring radioactive material.

Egidi, P. Oak Ridge National Lab., Grand Junction, CO

(United States). [1997]. 54p. Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract AC05-96OR22464. From Health

Physics Society annual meeting; San Antonio, TX (United

States); 1 Jul 1997. Order Number DE97008455. Source:

OSTI; NTIS; INIS; GPO Dep.

Naturally occurring radioactive material (NORM) is everywhere; we are exposed to it every day. It is found in our

bodies, the food we eat, the places where we live and work,

and in products we use. We are also bathed in a sea of natural radiation coming from the sun and deep space. Living

systems have adapted to these levels of radiation and radioactivity. But some industrial practices involving natural

resources concentrate these radionuclides to a degree that

they may pose risk to humans and the environment if they

are not controlled. Other activities, such as flying at high altitudes, expose us to elevated levels of NORM. This session

will concentrate on diffuse sources of technologicallyenhanced (TE) NORM, which are generally large-volume,

low-activity waste streams produced by industries such as

mineral mining, ore benefication, production of phosphate

Fertilizers, water treatment and purification, and oil and gas

production. The majority of radionuclides in TENORM are

found in the uranium and thorium decay chains. Radium and

its subsequent decay products (radon) are the principal radionuclides used in characterizing the redistribution of

TENORM in the environment by human activity. We will

briefly review other radionuclides occurring in nature (potassium and rubidium) that contribute primarily to background

doses. TENORM is found in many waste streams; for example, scrap metal, sludges, slags, fluids, and is being

discovered in industries traditionally not thought of as affected by radionuclide contamination. Not only the forms

and volumes, but the levels of radioactivity in TENORM

vary. Current discussions about the validity of the linear no

dose threshold theory are central to the TENORM issue.

TENORM is not regulated by the Atomic Energy Act or other

Federal regulations. Control and regulation of TENORM is

not consistent from industry to industry nor from state to

state. (Abstract truncated)

115

(CONF-970926–2)

Nuclear criticality safety controls for uranium deposits

during D and D at the Oak Ridge Gaseous Diffusion

Plant. Haire, M.J. (Oak Ridge National Lab., TN (United

States)); Jordan, W.C.; Jollay, L.J. III; Dahl, T.L. Oak Ridge

National Lab., TN (United States). [1997]. 9p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract AC05-96OR22464. From

American Nuclear Society (ANS) topical meeting on criticality safety challenges in the next decade; Chelan, WA

(United States); 7-11 Sep 1997. Order Number

DE97001039. Source: OSTI; NTIS; INIS; GPO Dep.

The US Department of Energy (DOE) Deputy Assistant

Secretary of Energy for Environmental Management has issued a challenge to complete DOE environmental cleanup

within a decade. The response for Oak Ridge facilities is in

accordance with the DOE ten-year plan which calls for completion of > 95% of environmental management work by the

year 2006. This will result in a 99% risk reduction and in a

significant savings in base line costs in waste management

(legacy waste); remedial action (groundwater, soil, etc.); and

decontamination and decommissioning (D and D). It is assumed that there will be long-term institutional control of

cascade equipment, i.e., there will be no walk away from

sites, and that there will be firm radioactivity release limits

by 1999 for recycle metals. An integral part of these plants

26
Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

is the removal of uranium deposits which pose nuclear criticality safety concerns in the shut down of the Oak Ridge

Gaseous Diffusion Plant. DOE has initiated the Nuclear Criticality Stabilization Program to improve nuclear criticality

safety by removing the larger uranium deposits from unfavorable geometry equipment. Nondestructive assay (NDA)

measurements have identified the location of these deposits. The objective of the K-25 Site Nuclear Criticality

Stabilization Program is to remove and place uranium deposits into safe geometry storage containers to meet the

double contingency principle. Each step of the removal process results in safer conditions where multiple controls are

present. Upon completion of the Program, nuclear criticality

risks will be greatly reduced.

116

(CONF-970926–4)

Criticality safety considerations for MSRE fuel drain

tank uranium aggregation. Hollenbach, D.F. (Oak Ridge

National Lab., TN (United States). Computational Physics

and Engineering Div.); Hopper, C.M. Oak Ridge National

Lab., TN (United States). [1997]. 11p. Sponsored by USDOE Office of Environmental Management, Washington, DC

(United States). DOE Contract AC05-96OR22464. From

American Nuclear Society (ANS) topical meeting on criticality safety challenges in the next decade; Chelan, WA

(United States); 7-11 Sep 1997. Order Number

DE97003663. Source: OSTI; NTIS; INIS; GPO Dep.

This paper presents the results of a preliminary criticality

safety study of some potential effects of uranium reduction

and aggregation in the Molten Salt Reactor Experiment

(MSRE) fuel drain tanks (FDTs) during salt removal operations. Since the salt was transferred to the FDTs in 1969,

radiological and chemical reactions have been converting

the uranium and fluorine in the salt to UF6 and free fluorine.

Significant amounts of uranium (at least 3 kg) and fluorine

have migrated out of the FDTs and into the off-gas system

(OGS) and the auxiliary charcoal bed (ACB). The loss of

uranium and fluorine from the salt changes the chemical

properties of the salt sufficiently to possibly allow the reduction of the UF4 in the salt to uranium metal as the salt is

remelted prior to removal. It has been postulated that up to

9 kg of the maximum 19.4 kg of uranium in one FDT could

be reduced to metal and concentrated. This study shows

that criticality becomes a concern when more than 5 kg of

uranium concentrates to over 8 wt% of the salt in a favorable geometry.

117

(CONF-970926–10)

Heterogeneous reactivity effects in medium- and highenriched uranium metal-water systems. Lichtenwalter,

J.J. Oak Ridge National Lab., TN (United States). 1997. 6p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States);Oak Ridge Inst. for

Science and Education, TN (United States). DOE Contract

AC05-96OR22464. From American Nuclear Society (ANS)

topical meeting on criticality safety challenges in the next

decade; Chelan, WA (United States); 7-11 Sep 1997. Order

Number DE97006433. Source: INIS; OSTI; NTIS; INIS;

GPO Dep.

The effect of heterogeneity on reactivity of low-, medium-,

and high-enriched, water-moderated uranium metal systems

has been examined for various hydrogen-to-fissile (H/X) ratios using the CSAS1X sequence in SCALE and MCNP. For

the calculations, an infinite array of close-packed unit cells

was modeled which consisted of centered uranium metal

spheres surrounded by water. The enrichments used correspond to the average enrichments of fragmented fuel plates

in three proposed waste shipments from Oak Ridge National

Laboratory. The analysis performed to obtain peak reactivity

for each enrichment as a function of particle size and H/X

ratio led to the development of the topic discussed in this

paper.

118

(CONF-970952–1)

Isotopes facilities deactivation project at Oak Ridge National Laboratory. Eversole, R.E. Oak Ridge National Lab.,

TN (United States). 1997. 8p. Sponsored by USDOE Office

of Environmental Management, Washington, DC (United

States). DOE Contract AC05-96OR22464. From Decontamination, decommissioning and reutilization of commercial and

government facilities; Knoxville, TN (United States); 7-12

Sep 1997. Order Number DE97005999. Source: OSTI;

NTIS; INIS; GPO Dep.

The production and distribution of radioisotopes for medical, scientific, and industrial applications has been a major

activity at Oak Ridge National Laboratory (ORNL) since the

late 1940s. As the demand for many of these isotopes grew

and their sale became profitable, the technology for the production of the isotopes was transferred to private industry,

and thus, many of the production facilities at ORNL became

underutilized. In 1989, the U.S. Department of Energy

(DOE) instructed ORNL to identify and prepare various isotopes production facilities for safe shutdown. In response,

ORNL identified 19 candidate facilities for shutdown and established the Isotopes Facilities Shutdown Program. In

1993, responsibility for the program was transitioned from

the DOE Office of Nuclear Energy to the DOE Office of

Environmental Management and Uranium Enrichment Operation’s Office of Facility Transition and Management. The

program was retitled the Isotopes Facilities Deactivation

Project (IFDP), and implementation responsibility was transferred from ORNL to the Lockheed Martin Energy Systems,

Inc. (LMES), Environmental Restoration (ER) Program.

119

(CONF-970952–3)

Measuring the accomplishments of public participation

programs: Overview of a methodological study performed for DOE’s Office of Environmental Management.

Schweitzer, M.; Carnes, S.A.; Peelle, E.B.; Wolfe, A.K. Oak

Ridge National Lab., TN (United States). 1997. 9p. Sponsored by USDOE Office of Environmental Management,

Washington, DC (United States). DOE Contract AC05-

96OR22464. From Decontamination, decommissioning and

reutilization of commercial and government facilities;

Knoxville, TN (United States); 7-12 Sep 1997. Order Number DE97006333. Source: OSTI; NTIS; INIS; GPO Dep.

Recently, staff at Oak Ridge National Laboratory performed a study for the Office of Intergovernmental and Public

Accountability within the U.S. Department of Energy’s (DOE)

Office of Environmental Management (EM), examining how

to measure the success of public participation programs.

While the study began with a thorough literature review, the

primary emphasis of this research effort was on getting key

stakeholders to help identify attributes of successful public

participation in EM activities and to suggest how those attributes might be measured. Interviews were conducted at

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

nine DOE sites that provided substantial variety in terms of

geographic location, types of environmental management

activities undertaken, the current life-cycle stage of those

EM efforts, and the public participation mechanisms utilized.

Approximately 12 to 15 oral interviews were conducted at

each site, and each respondent also was asked to complete

a written survey. Those interviewed included: non-regulatory

state and local government officials; project managers and

public participation staff for DOE and its management and

operations contractors; non-government groups concerned

with environmental protection, public safety, and health issues; federal and state environmental regulators; business

organizations; civic groups; and other interested parties.

While this study examined only those public participation

programs sponsored by DOE, the resulting findings also

have applicability to the public involvement efforts sponsored by many other public and private sector organizations.

120

(CONF-970952–4)

The independent verification process in decommissioning, decontamination, and reutilization activities -

description, benefits, and lessons learned. Egidi, P.V.

Oak Ridge National Lab., TN (United States). 1997. 6p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC05-96OR22464. From Decontamination, decommissioning and reutilization of commercial and government facilities;

Knoxville, TN (United States); 7-12 Sep 1997. Order Number DE97007500. Source: OSTI; NTIS; INIS; GPO Dep.

Oak Ridge National Laboratory Environmental Technology

Section has been performing Independent Verification (IV)

activities for U.S. DOE sites since 1986. DOE has successfully used IV in the Uranium Mill Tailings Remedial Action

Program, Decontamination and Decommissioning projects,

and Formerly Utilized Sites Remedial Action Projects/

Surplus Facilities Management Program. Projects that have

undergone IV range from small residential properties to

large, industrial sites. The IV process provides a third-party

review conducted by an independent organization. The purpose is to verify accuracy and completeness of contractor

field measurements and final documentation, evaluate the

credibility of procedures, and independently assess postcleanup conditions versus decommissioning project plans

and release criteria. Document reviews of plans, dose

models, procedures, and reports are some IV activities undertaken. Independent measurements are also collected

during field visits to confirm the contractor’s findings. Corrective actions for discrepancies are suggested if necessary.

Finally, archival and reporting of the final site environmental

conditions for project closeout and certification are completed. The IV contractor reports to DOE headquarters and

acts as a quality assurance feedback mechanism. An IV

also provides additional assurance that projects are

planned, carried out, and documented properly. Decommissioning projects benefit from the IV process by: (1) cost and

time savings from early identification of potential problems,

(2) assurance that cleanup meets regulatory guidelines, and

(3) technical reviews and consultation with experts in field

instrumentation, sampling strategy, etc. Some lessons

learned from the IV process include avoiding: (1) improper

survey techniques, (2) reporting data in units not comparable with guideline values, (3) premature release of surfaces,

(4) poor decommissioning project planning, (5) misapplication of release guidelines. 20 refs.

121

(CONF-970962–2)

Comparative testing of slurry monitors. Hylton, T.D. (Oak

Ridge National Lab., TN (United States)); Bayne, C.K.; Anderson, M.S.; Van Essen, D.C. Oak Ridge National Lab., TN

(United States). 1997. 5p. Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract AC05-96OR22464. From 214. American Chemical Society meeting; Las Vegas, NV (United

States); 7-13 Sep 1997. Order Number DE98000127.

Source: OSTI; NTIS; INIS; GPO Dep.

The U.S. Department of Energy (DOE) has millions of gallons of radioactive liquid and sludge wastes stored in

underground tanks. These wastes must be retrieved, transferred to treatment facilities, and processed for disposal.

Before removal from the storage tanks, the sludge and liquid

wastes will typically be combined to create a mixture of suspended solids, generally referred to as a slurry; the slurry is

then pumped from the tank to the treatment facilities by

pipelines. Since the wastes are radioactive, it is critically important that the slurries are transported safely and

successfully. The consequences of pipeline plugging are unacceptable from the perspectives of schedule, cost, and

safety. The baseline method of ensuring that the transport

properties of the slurries are correct is to sample the slurry

in the tank and analyze the sample in the laboratory. This

method has some problems. First, there is a delay between

the time that the sample is taken and the time that the analytical results are reported. For some types of analysis, this

delay could be from 24 to 48 hours. Second, although the

tank is being mixed to keep tile solids in suspension during

this period, there is no way to determine whether the contents of the tank are homogenous unless multiple samples

are collected at various depths and locations. Therefore, an

on-line system that monitors slurry transport properties in

real time is needed to evaluate the slurry prior to and during

transfer.

122

(CONF-970962–3)

Solids Control in Sludge Pretreatment. Beahm, E.C., Weber, C.F., Hunt, R.D., Dillow, T.A. Oak Ridge National Lab.,

TN (United States). 1997. 14p. Sponsored by USDOE Office

of Environmental Management, Washington, DC (United

States). DOE Contract AC05-84OR21400. From 214. American Chemical Society meeting; Las Vegas, NV (United

States); 7-13 Sep 1997. Order Number DE98000120.

Source: OSTI; NTIS; INIS; GPO Dep.

Sludge pretreatment will likely involve washing, followed

by caustic or acidic leaching and washing of sludge residues

after leaching. The principal goal of pretreatment is to obtain

a low-volume high-activity waste stream and a high-volume

low-activity waste stream. Also, some waste constituents

such as chromium and phosphate can be included in glass

formulations only at very low concentrations; therefore, it is

desirable to remove them from high-level waste streams.

Two aspects of sludge treatment and subsequent separations should be well delineated and predictable: (1) the

distribution of chemical species between aqueous solutions

and solids and (2) potential problems due to chemical interactions that could result in process difficulties or safety

concerns.Before any treatment technology is adopted, it

must be demonstrated that the process can be carried out

as planned. Three pretreatment methods were considered in

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

the Tri-Party (Washington State Ecology, U.S. Environmental Protection Agency, and U.S. Department of Energy)

negotiations: (1) sludge washing with corrosion- inhibiting

water, (2) Enhanced Sludge Washing, and (3)acidic dissolution with separations processes. Enhanced Sludge Washing

is the baseline process. In Enhanced Sludge Washing,

sludge is first washed with corrosion-inhibiting water; it is

then leached with caustic (sodium hydroxide solution) and

washed again with corrosion- inhibiting water. The initial

concern is whether a pretreatment technique is effective in

separating sludge components. This can be evaluated by

bench-scale tests with sludge specimens from underground

storage tanks. The results give data on the distribution of

important species such as aluminum, phosphate, and radionuclides between wash and leach solutions and solid

sludge residues.

123

(CONF-971032–1)

Performance of in situ chemical oxidation field demonstrations at DOE sites. Cline, S.R.; West, O.R.; Siegrist,

R.L.; Holden, W.L. Oak Ridge National Lab., TN (United

States). 1997. 10p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE

Contract AC05-96OR22464. From In situ remediation of the

geoenvironment conference; Minneapolis, MN (United

States); 5-7 Oct 1997. Order Number DE97004725. Source:

OSTI; NTIS; INIS; GPO Dep.

Researchers at the Oak Ridge National Laboratory

(ORNL) have been investigating the use of in situ chemical

oxidation to remediate organic contaminants (VOCs,

SVOCs, and PCBs) in soils and groundwater at the laboratory and field scales. Field scale design parameters (e.g.,

oxidant loading rates and oxidant delivery techniques) are

often dictated by site conditions (e.g., soil properties and initial contaminant concentrations). Chemical destruction of

organic compounds can be accomplished using a variety of

oxidants. Recent research has involved field scale in situ

chemical oxidation demonstrations using H2O2 and KMnO4

in conjunction with soil mixing as the oxidant delivery mechanism. A description of some of these fields activities and

future field-scale work is presented here.

124

(CONF-971143–1)

Field technologies for the measurement of PCBs. Dindal,

A.B. (Oak Ridge National Lab., TN (United States)); Bayne,

C.K.; Jenkins, R.A.; Carden, D.M.; Billets, S. Oak Ridge National Lab., TN (United States). [1997]. 6p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States);Environmental Protection Agency,

Washington, DC (United States). DOE Contract AC05-

96OR22464. From 20. world energy engineering congress;

Atlanta, GA (United States); 19 Nov 1997. Order Number

DE97008485. Source: OSTI; NTIS; GPO Dep.

The collaborative effort between the US Environmental

Protection Agency (EPA), US Department of Energy (DOE),

and the Oak Ridge National Laboratory (ORNL) represents

a viable team to administer, plan, execute, and report on

demonstrations of commercially available field characterization and monitoring technologies. This effort is part of the

EPA’s Environmental Technology Verification (ETV) Program. One of the overriding goals of this effort is to develop

regulatory-accepted and cost effective alternatives to conventional fixed laboratory analyses through the identification

and evaluation of innovative, field technologies. A technology demonstration of polychlorinated biphenyl (PCB) field

analytical techniques will occur during July 22 through 30,

1997. The demonstration will be conducted at a DOE site

(ORNL) where there is a substantial repository of PCBcontaminated materials from multiple DOE sites. Technology

developers with PCB monitoring instrumentation will be

evaluated. These instruments will include field portable gas

chromatographs with surface acoustic wave and electron

capture detectors, and field analysis kits, such as

immunoassay and ion specific electrode kits. These instruments are suitable for the quantification of PCBs in a variety

of matrices. Soil and surface samples will be evaluated during the demonstration. The demonstration will focus on the

current DOE-Oak Ridge analytical needs to support Toxic

Substance and Control Act (TSCA) decisions, while allowing

developers to showcase the features of their technologies.

125

(DOE/AL/58309–68)

Evaluation of the WIPP Project’s compliance with the

EPA radiation protection standards for disposal of

transuranic waste. Neill, R.H. (Environmental Evaluation

Group, Albuquerque, NM (United States)); Chaturvedi, L.;

Rucker, D.F.; Silva, M.K.; Walker, B.A.; Channell, J.K.;

Clemo, T.M. Environmental Evaluation Group, Albuquerque,

NM (United States);Environmental Evaluation Group, Carlsbad, NM (United States). Mar 1998. 622p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract AC04-89AL58309 ;

AC04-78AL10752. (EEG–68). Order Number DE98004586.

Source: OSTI; NTIS; INIS; GPO Dep.

The US Environmental Protection Agency’s (EPA) proposed rule to certify that the Waste Isolation Pilot Plant

(WIPP) meets compliance with the long-term radiation protection standards for geologic repositories (40CFR191

Subparts B and C), is one of the most significant milestones

to date for the WIPP project in particular, and for the nuclear

waste issue in general. The Environmental Evaluation

Group (EEG) has provided an independent technical oversight for the WIPP project since 1978, and is responsible for

many improvements in the location, design, and testing of

various aspects of the project, including participation in the

development of the EPA standards since the early 1980s.

The EEG reviewed the development of documentation for

assessing the WIPP’s compliance by the Sandia National

Laboratories following the 1985 promulgation by EPA, and

provided many written and verbal comments on various aspects of this effort, culminating in the overall review of the

1992 performance assessment. For the US Department of

Energy’s (DOE) compliance certification application (CCA),

the EEG provided detailed comments on the draft CCA in

March, 1996, and additional comments through unpublished

letters in 1997 (included as Appendices 8.1 and 8.2 in this

report). Since the October 30, 1997, publication of the EPA’s

proposed rule to certify WIPP, the EEG gave presentations

on important issues to the EPA on December 10, 1997, and

sent a December 31, 1997 letter with attachments to clarify

those issues (Appendix 8.3). The EEG has raised a number

of questions that may have an impact on compliance. In

spite of the best efforts by the EEG, the EPA reaction to reviews and suggestions has been slow and apparently driven

by legal considerations. This report discusses in detail the

questions that have been raised about containment requirements. Also discussed are assurance requirements,

29
ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

groundwater protection, individual protection, and an evaluation of EPA’s responses to EEG’s comments.

126

(DOE/AL/62350–89-Rev.2)

Long-term surveillance plan for the Green River, Utah

disposal site. Revision 2. Jacobs Engineering Group, Inc.,

Albuquerque, NM (United States). Jul 1998. [100p.] Sponsored by USDOE Office of Environmental Management,

Washington, DC (United States). DOE Contract AC04-

91AL62350. Order Number DE99000970. Source: OSTI;

NTIS; INIS; GPO Dep.

The long-term surveillance plan (LTSP) for the Green

River, Utah, Uranium Mill Tailings Remedial Action (UMTRA)

Project disposal site describes the surveillance activities for

the Green River disposal cell. The US Department of Energy (DOE) will carry out these activities to ensure that the

disposal cell continues to function as designed. This final

LTSP was prepared as a requirement for acceptance under

the US Nuclear Regulatory Commission (NRC) general license for custody and long-term care of residual radioactive

materials (RRM). This LTSP documents whether the land

and interests are owned by the United States or an Indian

tribe and details how the long-term care of the disposal site

will be carried out.

127

(DOE/AL/62350–236-Rev.(5/98))

Long-term surveillance plan for the Burro Canyon disposal cell, Slick Rock, Colorado. Jacobs Engineering

Group Inc., Albuquerque, NM (United States). May 1998.

40p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC04-91AL62350. Order Number DE99001098. Source:

OSTI; NTIS; INIS; GPO Dep.

This long-term surveillance plan (LTSP) describes the US

Department of Energy (DOE) long-term care program for the

Uranium Mill Tailings Remedial Action (UMTRA) Project

Burro Canyon disposal cell in San Miguel County, Colorado.

The US Nuclear Regulatory Commission (NRC) developed

regulations for the issuance of a general license for the custody and long-term care of UMTRA Project disposal sites in

10 CFR Part 40. The purpose of this general license is to

ensure that the UMTRA Project disposal sites are cared for

in a manner that protects the public health and safety and

the environment. Before each disposal site is licensed, the

NRC requires the DOE to submit a site-specific LTSP. The

DOE prepared this LTSP to meet this requirement for the

Burro Canyon disposal cell. The general license becomes

effective when the NRC concurs with the DOE’s determination that remedial action is complete at the Burro Canyon

disposal cell and the NRC formally accepts this LTSP. Attachment 1 contains the concurrence letters from NRC. This

LTSP describes the long-term surveillance program the

DOE will implement to ensure that the Burro Canyon disposal cell performs as designed. The program is based on

site inspections to identify threats to disposal cell integrity.

Ground water monitoring will not be required at the Burro

Canyon disposal cell because the ground water protection

strategy is supplemental standards based on low yield from

the uppermost aquifer.

128

(DOE/AL/62350–247-Pt.2)

Long-term surveillance plan for the Maybell, Colorado

Disposal Site. Jacobs Engineering Group, Inc., Albuquerque, NM (United States). Dec 1997. 39p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract AC04-91AL62350. Order

Number DE98005074. Source: OSTI; NTIS; INIS; GPO Dep.

This long-term surveillance plan (LTSP) describes the U.S.

Department of Energy’s (DOE) long-term care program for

the Uranium Mill Tailings Remedial Action (UMTRA) Project

Maybell disposal site in Moffat County, Colorado. The U.S.

Nuclear Regulatory Commission (NRC) has developed regulations for the issuance of a general license for the custody

and long-term care of UMTRA Project disposal sites in 10

CFR Part 40. The purpose of this general license is to ensure that the UMTRA Project disposal sites are cared for in

a manner that protects the public health and safety and the

environment. Before each disposal site is licensed, the NRC

requires the DOE to submit a site-specific LTSP. The DOE

prepared this LTSP to meet this requirement for the Maybell

disposal site. The general license becomes effective when

the NRC concurs with the DOE’s determination that remedial

action is complete for the Maybell site and the NRC formally

accepts this LTSP. This document describes the long-term

surveillance program the DOE will implement to ensure the

Maybell disposal site performs as designed. The program is

based on site inspections to identify threats to disposal cell

integrity. The LTSP is based on the UMTRA Project longterm surveillance program guidance document and meets

the requirements of 10 CFR x40.27(b) and 40 CFR x192.03.

129

(DOE/AL/62350–247-Pt.3)

1997 Monitoring report for the Gunnison, Colorado Wetlands Mitigation Plan. Jacobs Engineering Group, Inc.,

Albuquerque, NM (United States). Nov 1997. 62p. Sponsored by USDOE Office of Environmental Management,

Washington, DC (United States). DOE Contract AC04-

91AL62350. Order Number DE98005075. Source: OSTI;

NTIS; INIS; GPO Dep.

Under the Uranium Mill Tailings Remedial Action (UMTRA)

Project, the U.S. Department of Energy (DOE) cleaned up

uranium mill tailings and other surface contamination near

the town of Gunnison, Colorado. Remedial action resulted in

the elimination of 4.3 acres (ac) (1.7 hectares [ha]) of wetlands. This loss is mitigated by the enhancement of six

spring-fed areas on Bureau of Land Management (BLM)

land (mitigation sites). Approximately 254 ac (1 03.3 ha)

were fenced at the six sites to exclude grazing livestock. Of

the 254 ac (103.3 ha), 17.8 ac (7.2 ha) are riparian plant

communities; the rest are sagebrush communities. Baseline

grazed conditions of the riparian plant communities at the

mitigation sites were measured prior to fencing. This report

discusses results of the fourth year of a monitoring program

implemented to document the response of vegetation and

wildlife to the exclusion of livestock. Three criteria for determining success of the mitigation were established: plant

height, vegetation density (bare ground), and vegetation diversity. By 1996, Prospector Spring, Upper Long’s Gulch,

and Camp Kettle met the criteria. The DOE requested transfer of these sites to BLM for long-term oversight. The 1997

evaluation of the three remaining sites, discussed in this report, showed two sites (Houston Gulch and Lower Long’s

Gulch) meet the criteria. The DOE will request the transfer

of these two sites to the BLM for long-term oversight. The

last remaining site, Sage Hen Spring, has met only two of

the criteria (percent bare ground and plant height). The third

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

criterion, vegetation diversity, was not met. The vegetation

appears to be changing from predominantly wet species to

drier upland species, although the reason for this change is

uncertain. It may be due to below-normal precipitation in recent years, diversion of water from the spring to the stock

tank, or manipulation of the hydrology farther up gradient.

130

(DOE/AL/62350–249)

Remedial action plan for the inactive uranium processing site at Naturita, Colorado. Remedial action selection

report: Attachment 2, geology report; Attachment 3,

ground water hydrology report; Attachment 4, supplemental information. Jacobs Engineering Group, Inc.,

Albuquerque, NM (United States). Mar 1998. 516p. Sponsored by USDOE Office of Environmental Management,

Washington, DC (United States). DOE Contract AC04-

91AL62350. Order Number DE98005077. Source: OSTI;

NTIS; INIS; GPO Dep.

The uranium processing site near Naturita, Colorado, is

one of 24 inactive uranium mill sites designated to be

cleaned up by the U.S. Department of Energy (DOE) under

the Uranium Mill Tailings Radiation Control Act of 1978

(UMTRCA), 42 USC x 7901 et seq. Part of the UMTRCA requires that the U.S. Nuclear Regulatory Commission (NRC)

concur with the DOE’s remedial action plan (RAP) and certify that the remedial action conducted at the site complies

with the standards promulgated by the U.S. Environmental

Protection Agency (EPA). This RAP serves two purposes.

First, it describes the activities that are proposed by the

DOE to accomplish remediation and long-term stabilization

and control of the radioactive materials at the inactive uranium processing site near Naturita, Colorado. Second, this

RAP, upon concurrence and execution by the DOE, the

state of Colorado, and the NRC, becomes Appendix B of

the cooperative agreement between the DOE and the state

of Colorado.

131

(DOE/AL/62350–T17)

Addendum to the 1996 Gunnison Monitoring Report for

the Gunnison, Colorado Wetlands Mitigation Plan. Jacobs Engineering Group, Inc., Albuquerque, NM (United

States). Oct 1997. 28p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States).

DOE Contract AC04-91AL62350. Order Number

DE98005076. Source: OSTI; NTIS; INIS; GPO Dep.

This document is an addendum to the 1996 Gunnison

Monitoring Report for the Gunnison, Colorado, Wetlands

Mitigation Report, dated July 1997. The purpose of this addendum is to: (1) modify how information on plant height

and plant species criteria are presented; and (2) provide

more detailed information regarding the evaluation of the

bare ground criteria at the Camp Ketle site. The information

in this addendum is provided at the request of the Bureau of

Land Management to aid in future monitoring and evaluation

of the wetland mitigation sites.

132

(DOE/AL/62350–T18)

Uranium Mill Tailings Remedial Action Project fiscal year

1997 annual report to stakeholders. Dept. of Energy, Office of Environmental Management, Washington, DC (United

States). 31 Dec 1997. 38p. Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract AC04-91AL62350. Order Number

DE99000968. Source: OSTI; NTIS; INIS; GPO Dep.

The fiscal year (FY) 1997 annual report is the 19th report

on the status of the US Department of Energy’s (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project. In

1978, Congress directed the DOE to assess and clean up

contamination at 24 designated former uranium processing

sites. The DOE is also responsible for cleaning up properties in the vicinity of the sites where wind and water erosion

deposited tailings or people removed them from the site for

use in construction or landscaping. Cleanup has been undertaken in cooperation with state governments and Indian

tribes within whose boundaries the sites are located. It is being conducted in two phases: the surface project and the

groundwater project. This report addresses specifics about

the UMTRA surface project.

133

(DOE/AL/76406–T1)

Improved risk estimates for carbon tetrachloride.

Project status report and technical progress report.

Benson, J.M. (Lovelace Biomedical and Environmental Research Inst., Albuquerque, NM (United States). Lovelace

Respiratory Research Inst.); Nikula, K.J.; Barr, E.B.;

Springer, D.L.; Thrall, K.D. Lovelace Biomedical and Environmental Research Inst., Albuquerque, NM (United States).

[1997]. 8p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract FC04-96AL76406. Order Number DE97009333.

Source: OSTI; NTIS; GPO Dep.

Carbon tetrachloride (CCl4) has been used extensively

within the Department of Energy (DOE) nuclear weapons facilities. High levels of CCl4 at these facilities represent a

potential health hazard for workers conducting cleanup operations and for surrounding communities. The overall

purpose of these studies is to improve the scientific basis for

assessing the health risk associated with human exposure

to CCl4. Specifically, the authors will determine the toxicokinetics of inhaled and ingested CCl4 in F344/Crl rats.

B6C3F1 mice, and Syrian hamsters. They will also evaluate

species differences in the metabolism of CCl4 by rats, mice,

hamsters, and man. Dose-response relationships will be determined in all these studies. This information will be used to

improve the physiologically based pharmacokinetic (PBPK)

model for CCl4 originally developed by Paustenbach et al.

(1988) and more recently revised by Thrall and Kenny

(1996). The authors will also provide scientific evidence that

CCl4, like chloroform, is a hepatocarcinogen only when exposure results in cell damage, cell killing, and regenerative

cell proliferation.

134

(DOE/CH/10639–T1)

Field evaluation of recycled plastic lumber (RPL) pallets. Final project report. Krishnaswamy, P. (Battelle,

Columbus, OH (United States)); Miele, C.R.; Francini, R.B.;

Yuracko, K.; Yerace, P. Battelle, Columbus, OH (United

States). [1997]. 86p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States).

DOE Contract FG02-95CH10639. Order Number

DE98000726. Source: OSTI; NTIS; GPO Dep.

One significant component of the waste stream, discarded

plastic products and packaging, continues to be a growing

portion of the municipal solid waste (MSW). There has been

considerable work done in characterizing the quantity and

31
ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

types of plastics in different waste streams, collection

methods, separation, sorting as well as technologies for processing post-consumer mixed plastics. The focus in recent

years has been the development of markets for recycled

plastic products, which constitutes the second half of the

material flow diagram cycle shown in Figure 1. One key

product that holds significant promise for plastics recycling to

be both technically feasible and economically viable is Recycled Plastic Lumber (RPL). The contents of this report forms

the second phase of a two-phase pilot project on developing

specifications and standards for a product fabricated from

RPL. Such standards and specifications are needed to prepare procurement guidelines for state and federal agencies

interested in purchasing products made from recycled materials. The first phase focused on establishing a procedure to

evaluate RPL product,s such as pallets, in a laboratory setting while this phase focuses on field evaluation of RPL

pallets in service. This effort is critical in the development of

new markets for RPL products. A brief summary of the findings from Phase 1 of this effort is presented next.

135

(DOE/CH/10865–1)

Description of the U.S. Geological Survey’s waterquality sampling and water-level monitoring program at

the Hallam Nuclear Facility, June through September

1996. Geological Survey, Lincoln, NE (United States).

[1997]. 7p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract AI02-96CH10865. Order Number DE97008069.

Source: OSTI; NTIS; INIS; GPO Dep.

A water-quality and water-level program of the US Department of Energy (USDOE) in cooperation with the US

Geological Survey (USGS) was re-established in June 1996

to develop six new USDOE observation wells, collect one

set of water-quality samples from 17 of the 19 USDOE observation wells, and take monthly water-level measurements

for a 3-month period in all 19 USDOE observation wells at

the Hallam Nuclear Facility, Hallam, Nebraska. Thirteen of

the observation wells were installed by HWS Consulting

Group, Inc., in June 1993 and the remaining six were installed by Applied Research Associates in August 1995.

136

(DOE/CH/10898–T1)

Description of the U.S. Geological Survey’s waterquality sampling and water-level monitoring program at

the Hallam Nuclear Facility, August through September

1997. Geological Survey, Water Resources Div., Lincoln, NE

(United States). 14 Nov 1997. 8p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States). DOE Contract AI02-97CH10898. Order Number

DE99000095. Source: OSTI; NTIS; INIS; GPO Dep.

A water-quality and water-level program between the US

Department of Energy (USDOE) and the US Geological Survey (USGS) was re-established in August 1997 to (1) collect

one set of water-quality samples from 17 of the 19 USDOE

monitor wells, and (2) make five water-level measurements

during a 2-month period from the 19 USDOE monitor wells

at the Hallam Nuclear Facility, Hallam, Nebraska. Data from

these wells are presented.

137

(DOE/EIS–0200-F-Vol.2)

Final waste management programmatic environmental

impact statement for managing treatment, storage, and

disposl of radioactive and hazardous waste. Volume II.

USDOE Assistant Secretary for Environmental Management, Washington, DC (United States). [1997]. 769p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). Order Number

DE97007519. Source: OSTI; NTIS; INIS; GPO Dep.

The Final Waste Management Programmatic Environmental Impact Statement (WM PEIS) examines the potential

environmental and cost impacts of strategic management

alternatives for managing five types of radioactive and hazardous wastes that have resulted and will continue to result

from nuclear defense and research activities at a variety of

sites around the United States. The five waste types are

low-level mixed waste, low-level waste, transuranic waste,

high-level waste, and hazardous waste. The WM PEIS

provides information on the impacts of various siting alternatives which the Department of Energy (DOE) will use to

decide at which sites to locate additional treatment, storage,

and disposal capacity for each waste type.Volume II is an

integral part of the Office of Environmental Management’s

(EM’s) Waste Management Programmatic Environmental

Impact Statement (WM PEIS), which portrays the impacts of

EM’s waste management activities at each of the 17 major

DOE sites evaluated in the WM PEIS.

138

(DOE/EIS–0200-F-Vol.3)

Final waste management programmatic environmental

impact statement for managing treatment, storage, and

disposal of radioactive and hazardous waste. Volume III

of V. USDOE Assistant Secretary for Environmental Management, Washington, DC (United States). [1997]. 650p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). Order Number

DE97007520. Source: OSTI; NTIS; INIS; GPO Dep.

The Final Waste Management Programmatic Environmental Impact Statement (WM PEIS) examines the potential

environmental and cost impacts of strategic management

alternatives for managing five types of radioactive and hazardous wastes that have resulted and will continue to result

from nuclear defense and research activities at a variety of

sites around the United States. The five waste types are

low-level mixed waste, low-level waste, transuranic waste,

high-level waste, and hazardous waste. The WM PEIS

provides information on the impacts of various siting alternatives which the Department of Energy (DOE) will use to

decide at which sites to locate additional treatment, storage,

and disposal capacity for each waste type.

139

(DOE/EIS–0200-F-Vol.4)

Final waste management programmatic environmental

impact statement for managing treatment, storage, and

disposal of radioactive and hazardous waste. Volume IV

of V. USDOE Assistant Secretary for Environmental Management, Washington, DC (United States). [1997]. 514p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). Order Number

DE97007521. Source: OSTI; NTIS; INIS; GPO Dep.

The Final Waste Management Programmatic Environmental Impact Statement (WM PEIS) examines the potential

environmental and cost impacts of strategic management

alternatives for managing five types of radioactive and hazardous wastes that have resulted and will continue to result

32
Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

from nuclear defense and research activities at a variety of

sites around the United States. The five waste types are

low-level mixed waste, low-level waste, transuranic waste,

high-level waste, and hazardous waste. The WM PEIS

provides information on the impacts of various siting alternatives which the Department of Energy (DOE) will use to

decide at which sites to locate additional treatment, storage,

and disposal capacity for each waste type.Transportation is

an integral component of the alternatives being considered

for each type of radioactive waste in the U.S. Department of

Energy (DOE) Waste Management Programmatic Environmental Impact Statement (WM PEIS). The types of

radioactive waste considered in Part I are high-level waste

(HLW), low-level waste (LLW), transuranic waste (TRUW),

and low-level mixed waste (LLMW). For some alternatives,

radioactive waste would be shipped among the DOE sites at

various stages of the treatment, storage, and disposal (TSD)

process. The magnitude of the transportation-related activities varies with each alternative, ranging from minimal

transportation for decentralized approaches to significant

transportation for some centralized approaches. The human

health risks associated with transporting various waste materials were assessed to ensure a complete appraisal of the

impacts of each PEIS alternative being considered.

140

(DOE/EIS–0200-F-Vol.5)

Final waste management programmatic environmental

impact statement for managing treatment, storage, and

disposal of radioactive and hazardous waste. Volume V

of V. USDOE Assistant Secretary for Environmental Management, Washington, DC (United States). [1997]. 900p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). Order Number

DE97007522. Source: OSTI; NTIS; INIS; GPO Dep.

The Final Waste Management Programmatic Environmental Impact Statement (WM PEIS) examines the potential

environmental and cost impacts of strategic management

alternatives for managing five types of radioactive and hazardous wastes that have resulted and will continue to result

from nuclear energy research and the development, production, and testing of nuclear weapons at a variety of sites

around the United States. The five waste types are low-level

mixed waste, low-level waste, transuranic waste, high-level

waste, and hazardous waste. The WM PEIS provides information on the impacts of various siting alternatives, which

the Department of Energy (DOE) will use to decide at which

sites to locate additional treatment, storage, and disposal

capacity for each waste type. This information includes the

cumulative impacts of combining future siting configurations

for the five waste types and the collective impacts of other

past, present, and reasonably foreseeable future activities.

The selected waste management facilities being considered

for these different waste types are treatment and disposal

facilities for low-level mixed waste; treatment and disposal

facilities for low-level waste; treatment and storage facilities

for transuranic waste in the event that treatment is required

before disposal; storage facilities for created (vitrified) highlevel waste canisters; and treatment of nonwastewater

hazardous waste by DOE and commercial vendors. In addition to the No Action Alternative, which includes only existing

of approved waste management facilities, the alternatives

for each of the waste-type configurations include Decentralized, Regionalized, and Centralized Alternatives for using

existing and operating new waste management facilities.

However, the siting, construction, and operations of any new

facility at a selected site will not be decided until completion

of a sitewide or project-specific environmental impact review.

141

(DOE/EIS–0290-D)

Advanced mixed waste treatment project draft environmental impact statement. USDOE Idaho Operations

Office, Office of Environmental Management, Idaho Falls, ID

(United States). Jul 1998. [400p.] Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States);USDOE Idaho Operations Office, Idaho Falls, ID

(United States). Order Number DE98007360. Source: OSTI;

NTIS; INIS; GPO Dep.

The AMWTP DEIS assesses the potential environmental

impacts associated with four alternatives related to the construction and operation of a proposed waste treatment

facility at the INEEL. Four alternatives were analyzed: The

No Action Alternative, the Proposed Action, the NonThermal Treatment Alternative, and the Treatment and

Storage Alternative. The proposed AMWTP facility would

treat low-level mixed waste, alpha-contaminated low-level

mixed waste, and transuranic waste in preparation for disposal. Transuranic waste would be disposed of at the Waste

isolation Pilot Plant in New Mexico. Low-level mixed waste

would be disposed of at an approval disposal facility depending on decisions to be based on DOE’s Final Waste

Management Programmatic Environmental Impact Statement. Evaluation of impacts on land use, socio-economics,

cultural resources, aesthetic and scenic resources, geology,

air resources, water resources, ecological resources, noise,

traffic and transportation, occupational and public health and

safety, INEEL services, and environmental justice were included in the assessment. The AMWTP DEIS identifies as

the Preferred Alternative the Proposed Action, which is the

construction and operation of the AMWTP facility.

142

(DOE/EM–0328)

Environmental management activities. USDOE Office of

Environmental Management, Washington, DC (United

States). 1997. 72p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States).

Order Number DE97006924. Source: OSTI; NTIS; INIS;

GPO Dep.

The Office of Environmental Management (EM) has been

delegated the responsibility for the Department of Energy’s

(DOE’s) cleanup of the nuclear weapons complex. The

nature and magnitude of the waste management and environmental remediation problem requires the identification of

technologies and scientific expertise from domestic and foreign sources. Within the United States, operational DOE

facilities, as well as the decontamination and decommissioning of inactive facilities, have produced significant amounts

of radioactive, hazardous, and mixed wastes. In order to ensure worker safety and the protection of the public, DOE

must: (1) assess, remediate, and monitor sites and facilities;

(2) store, treat, and dispose of wastes from past and current

operations; and (3) develop and implement innovative

technologies for environmental restoration and waste management. The EM directive necessitates looking beyond

domestic capabilities to technological solutions found outside US borders. Following the collapse of the Soviet

regime, formerly restricted elite Soviet scientific expertise

33
ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

became available to the West. EM has established a cooperative technology development program with Russian

scientific institutes that meets domestic cleanup objectives

by: (1) identifying and accessing Russian EM-related technologies, thereby leveraging investments and providing

cost-savings; (2) improving access to technical information,

scientific expertise, and technologies applicable to EM

needs; and (3) increasing US private sector opportunities in

Russian in EM-related areas.

143

(DOE/EM–0330)

Fiscal year 1996 progress in implementing Section 120

of the Comprehensive Environmental Response, Compensation, and Liability Act. Tenth annual report to

Congress. USDOE, Washington, DC (United States). Dec

1997. 155p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). Order Number DE98001810. Source: OSTI; NTIS; GPO Dep.

Congress passed the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) (Public

Law 96-510), commonly known as Superfund, in 1980. The

Superfund Amendments and Reauthorization Act (SARA)

(Public Law 99-499), which amended CERCLA in 1986,

added Section 120 regarding the cleanup of contaminated

sites at Federal facilities. Under Section 120(e)(5) of CERCLA, each department, agency, or instrumentality of the

Federal government responsible for compliance with Section

120 must submit an annual report to Congress concerning

its progress in implementing the requirements of Section

120. The report must include information on the progress in

reaching Interagency Agreements (IAGs), conducting remedial investigation and feasibility studies (RI/FSs), and

performing remedial actions. Federal agencies that own or

operate facilities on the National Priorities List (NPL) are required to begin an RI/FS for these facilities within 6 months

after being placed on the NPL. Remediation of these facilities is addressed in an IAG between the Federal agency,

the US Environmental Protection Agency (EPA), and in

some instances the state within which the facility is located.

144

(DOE/EM–0332)

1996 annual report on low-level radioactive waste management progress. Report to Congress. USDOE

Assistant Secretary for Environmental Management, Washington, DC (United States). Nov 1997. 31p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). Order Number DE98001966. Source:

OSTI; NTIS; INIS; GPO Dep.

This report is prepared in response to the Low-Level Radioactive Waste Policy Act (the Act), Public Law 96-573,

1980, as amended by the Low-Level Radioactive Waste Policy Amendments Act of 1985, Public Law 99-240. The report

summarizes the activities during calendar year 1996 related

to the establishment of new disposal facilities for

commercially-generated low-level radioactive waste. The report emphasizes significant issues and events that have

affected progress in developing new disposal facilities, and

also includes an introduction that provides background

information and perspective on US policy for low-level radioactive waste disposal.

145

(DOE/EM–0341)

Equity of commercial low-level radioactive waste disposal fees. Report to Congress. USDOE Assistant

Secretary for Environmental Management, Washington, DC

(United States). Feb 1998. 18p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States). Order Number DE98004690. Source: OSTI; NTIS;

INIS; GPO Dep.

In the Report accompanying the Fiscal Year 1997 Senate

Energy and Water Development Appropriations Bill, the

Senate Appropriations Committee directed the Department

of Energy (DOE) to prepare a study of the costs of operating

a low-level radioactive waste (LLW) disposal facility such as

the one at Barnwell, South Carolina, and to determine

whether LLW generators are paying equitable disposal fees.

The disposal costs of four facilities are reviewed in this report, two operating facilities and two planned facilities. The

operating facilities are located at Barnwell, South Carolina,

and Richland, Washington. They are operated by ChemNuclear, LLC, (Chem-Nuclear), and US Ecology, Inc., (US

Ecology), respectively. The planned facilities are expected

to be built at Ward Valley, California, and Sierra Blanca,

Texas. They will be operated by US Ecology and the State

of Texas, respectively. This report found that disposal fees

vary significantly among facilities for a variety of reasons.

However, the information suggests that at each disposal facility, LLW generators pay equitable disposal fees.

146

(DOE/EM–0343)

ROTO PEEN Scalar and VAC-PAC system. Dept. of Energy, Washington, DC (United States). Feb 1998. 36p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). Source: OSTI (Free

of Charge); INIS; DOE and DOE contractors free from OSTI

(United States); public availability from Center for

Environmental Management Information (United States), 1-

800-736-3282.

The Pentek, Inc., milling technology, comprising the

ROTO PEEN Scaler and the VAC-PAC waste collection

system, is a fully developed and commercialized technology

used to remove hazardous coatings from concrete and steel

floors, walls, ceilings, and structural components. This report

describes a demonstration of the Pentek, Inc., milling system to remove the paint coating from 650 ft2 of concrete

flooring on the service floor of the Chicago Pile-5 (CP-5) Research Reactor. CP-5 is a heavy-water moderated and

cooled, highly enriched, uranium-fueled thermal reactor designed to supply neutrons for research. The reactor had a

thermal-power rating of 5 megawatts and was operated continuously for 25 years until its final shutdown in 1979. These

25 years of operation produced activation and contamination

characteristics representative of other nuclear facilities

within the Department of Energy (DOE) complex and the

commercial nuclear sector. CP-5 contains many of the

essential features of other DOE and commercial nuclear facilities and can be used safely as a demonstration facility for

the evaluation of innovative technologies for the future D

and D of much larger, more highly contaminated facilities.

147

(DOE/EM–0344)

Rotary peening with captive shot. Dept. of Energy, Washington, DC (United States). Feb 1998. 38p. Sponsored by

34
Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

USDOE Office of Environmental Management, Washington,

DC (United States). Source: OSTI (Free of Charge); INIS;

DOE and DOE contractors free from OSTI (United States);

public availability from Center for Environmental Management Information (United States), 1-800-736-3282.

Roto Peen with captive shot removes coatings and surface contamination from concrete floors. The objective of

treating radioactively contaminated concrete floors during

the Deactivation and Decommissioning (D and D) process is

to reduce the surface contamination levels to meet regulatory criteria for unrestricted use. The US Department of

Energy (DOE) Chicago Operations office and DOE’s Federal Energy Technology Center (FETC) jointly sponsored a

Large-Scale Demonstration Project (LSDP) at the Chicago

Pile-5 Research Reactor (CP-5) at Argonne National

Laboratory-East (ANL). The objective of the LSDP is to

demonstrate potentially beneficial D and D technologies in

comparison with current baseline technologies. As part of

the LSDP, roto Peen with captive shot was demonstrated

March 17–20, 1997, to treat a 20 x 25 ft area of radioactively contaminated concrete floor on the service level of the

CP-5 building.

148

(DOE/EM–0345)

GammaCam radiation imaging system. Dept. of Energy,

Washington, DC (United States). Feb 1998. 33p. Sponsored

by USDOE Office of Environmental Management, Washington, DC (United States). Source: OSTI (Free of Charge);

INIS; DOE and DOE contractors free from OSTI (United

States); public availability from Center for Environmental

Management (United States), 1-800-736-3282.

GammaCam, a gamma-ray imaging system manufactured by AIL System, Inc., would benefit a site that needs to

locate radiation sources. It is capable of producing a twodimensional image of a radiation field superimposed on a

black and white visual image. Because the system can be

positioned outside the radiologically controlled area, the radiation exposure to personnel is significantly reduced and

extensive shielding is not required. This report covers the

following topics: technology description; performance; technology applicability and alternatives; cost; regulatory and

policy issues; and lessons learned. The demonstration of

GammaCam in December 1996 was part of the LargeScale Demonstration Project (LSDP) whose objective is to

select and demonstrate potentially beneficial technologies at

the Argonne National Laboratory-East (ANL) Chicago Pile-5

Research Reactor (CP-5). The purpose of the LSDP is to

demonstrate that by using innovative and improved decontamination and decommissioning (D and D) technologies

from various sources, significant benefits can be achieved

when compared to baseline D and D technologies.

149

(DOE/EM–0346)

Centrifugal shot blast system. Dept. of Energy, Washington, DC (United States). Feb 1998. 42p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). Source: OSTI (Free of Charge); INIS;

DOE and DOE contractors free from OSTI (United States);

public availability from Center for Environmental Management Information (United States), 1-800-736-3282.

This report describes a demonstration of Concrete cleaning, Inc., modified centrifugal shot blast technology to

remove the paint coating from concrete flooring. This

demonstration is part of the Chicago Pile-5 (CP-5) LargeScale Demonstration Project (LSDP) sponsored by the US

Department of Energy (DOE), office of Science and Technology (OST), Deactivation and Decommissioning Focus Area

(DDFA). The objective of the LSDP is to select and demonstrate potentially beneficial technologies at the Argonne

National Laboratory-East (ANL) CP-5 Research Reactor.

The purpose of the LSDP is to demonstrate that using innovative and improved decontamination and decommissioning

(D and D) technologies from various sources can result in

significant benefits, such as decreased cost and increased

health and safety, as compared with baseline D and D

technologies. Potential markets exist for the innovative centrifugal shot blast system at the following sites: Fernald

Environmental Management Project, Los Alamos, Nevada,

Oak Ridge Y-12 and K-25, Paducah, Portsmouth Gaseous

Diffusion site, and the Savannah River Site. This information

is based on a revision to the OST Linkage Tables dated August 4, 1997.

150

(DOE/EM–0347)

Surface Contamination Monitor and Survey Information

Management System. Dept. of Energy, Washington, DC

(United States). Feb 1998. 29p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States). Source: OSTI (Free of Charge); INIS; DOE and

DOE contractors free from OSTI (United States); public

availability from Center for Environmental Management Information (United States), 1-800-736-3282.

Shonka Research Associates, Inc.’s (SRA) Surface Contamination Monitor and Survey Information management

System (SCM/SIMS) is designed to perform alpha and beta

radiation surveys of floors and surfaces and document the

measured data. The SRA-SCM/SIMS technology can be

applied to routine operational surveys, characterization surveys, and free release and site closure surveys. Any large

nuclear site can make use of this technology. This report describes a demonstration of the SRA-SCM/SIMS technology.

This demonstration is part of the chicago Pile-5 (CP-5)

Large-Scale Demonstration Project (LSDP) sponsored by

the US Department of Energy (DOE), Office of Science and

Technology (ST), Deactivation and Decommissioning Focus

Area (DDFA). The objective of the LSDP is to select and

demonstrate potentially beneficial technologies at the Argonne National Laboratory-East’s (ANL) CP-5 Research

Reactor Facility. The purpose of the LSDP is to demonstrate

that by using innovative and improved deactivation and decommissioning (D and D) technologies from various

sources, significant benefits can be achieved when compared to baseline D and D technologies.

151

(DOE/EM–0349)

Proceedings of a workshop on uses of depleted uranium in storage, transportation and repository facilities.

Dept. of Energy Assistant Secretary for Environmental Management, Office of the Deputy Assistant Secretary for

Science and Technology, Washington, DC (United States).

[1997]. [200p.] Sponsored by USDOE Office of Environmental Management, Washington, DC (United States);USDOE

Office of Civilian Radioactive Waste Management, Washington, DC (United States);USDOE Assistant Secretary for

Nuclear Energy, Washington, DC (CONF-970793–PROC.:

US Department of Energy workshop on uses of depleted

35
ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

uranium in storage, transportation and repository facilities,

Las Vegas, NV (United States), 15-17 Jul 1997). Order Number DE99000797. Source: OSTI; NTIS; INIS; GPO Dep.

A workshop on the potential uses of depleted uranium

(DU) in the repository was organized to coordinate the planning of future activities. The attendees, the original

workshop objective and the agenda are provided in Appendices A, B and C. After some opening remarks and

discussions, the objectives of the workshop were revised to:

(1) exchange information and views on the status of the Department of Energy (DOE) activities related to repository

design and planning; (2) exchange information on DU management and planning; (3) identify potential uses of DU in

the storage, transportation, and disposal of high-level waste

and spent fuel; and (4) define the future activities that would

be needed if potential uses were to be further evaluated and

developed. This summary of the workshop is intended to be

an integrated resource for planning of any future work related to DU use in the repository. The synopsis of the first

day’s presentations is provided in Appendix D. Copies of

slides from each presenter are presented in Appendix E.

152

(DOE/EM–0350)

Integrated process analyses studies on mixed low level

and transuranic wastes. Summary report. Dept. of Energy, Office of Science and Technology, Washington, DC

(United States). Dec 1997. 107p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States). Order Number DE99000888. Source: OSTI; NTIS;

INIS; GPO Dep.

Options for integrated thermal and nonthermal treatment

systems for mixed low-level waste (MLLW) are compared

such as total life cycle cost (TLCC), cost sensitivities, risk,

energy requirements, final waste volume, and aqueous and

gaseous effluents. The comparisons were derived by requiring all conceptual systems to treat the same composition of

waste with the same operating efficiency. Thus, results can

be used as a general guideline for the selection of treatment

and disposal concepts. However, specific applications of individual systems will require further analysis. The potential

for cost saving options and the research and development

opportunities are summarized.

153

(DOE/EM–0351)

Polyethylene macroencapsulation - mixed waste focus

area. OST reference No. 30. USDOE Office of Science and

Technology, Washington, DC (United States). Research and

Technical Assessment Div. Feb 1998. 19p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). Source: OSTI (Free of Charge); INIS;

DOE and DOE contractors free from OSTI (United States);

public availability from Center for Environmental Management Information (United States), 1-800-736-3282.

The lead waste inventory throughout the US Department

of Energy (DOE) complex has been estimated between 17

million and 24 million kilograms. Decontamination of at least

a portion of the lead is viable but at a substantial cost. Because of various problems with decontamination and its

limited applicability and the lack of a treatment and disposal

method, the current practice is indefinite storage, which is

costly and often unacceptable to regulators. Macroencapsulation is an approved immobilization technology used to

treat radioactively contaminated lead solids and mixed

waste debris. (Mixed waste is waste materials containing

both radioactive and hazardous components). DOE has

funded development of a polyethylene extrusion macroencapsulation process at Brookhaven National Laboratory

(BNL) that produces a durable, leach-resistant waste form.

This innovative macroencapsulation technology uses commercially available single-crew extruders to melt, convey,

and extrude molten polyethylene into a waste container in

which mixed waste lead and debris are suspended or supported. After cooling to room temperature, the polyethylene

forms a low-permeability barrier between the waste and the

leaching media.

154

(DOE/EM–0352)

Cyanide destruction/immobilization of residual sludge -

mixed waste focus area. Innovative Technology

Summary Report. USDOE Office of Environmental Management, Washington, DC (United States). Feb 1998. 16p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). Source: OSTI (Free

of Charge); INIS; DOE and DOE contractors free from OSTI

(United States); public availability from Center for

Environmental Management Information (United States), 1-

800-736-3282.

Innovative Technology Summary Reports are designed to

provide potential users with the information they need to

quickly determine if a technology would apply to a particular

environmental management problem. They are also designed for readers who may recommend that a technology

be considered by prospective users. Each report describes

a technology, system, or process that has been developed

and tested with funding from DOE’s Office of Science and

Technology (OST). A report presents the full range of problems that a technology, system, or process will address and

its advantages to the DOE cleanup in terms of system performance, cost, and cleanup effectiveness. Most reports

include comparisons to baseline technologies as well as

other competing technologies. Information about commercial

availability and technology readiness for implementation is

also included. Innovative Technology Summary Reports are

intended to provide summary information. References for

more detailed information are provided in an appendix. Efforts have been made to provide key data describing the

performance, cost, and regulatory acceptance of the technology. If this information was not available at the time of

publication, the omission is noted.

155

(DOE/EM–0353)

FRHAM-TEX cool suit - OST reference No. 1854. Deactivation and decommissioning focus area. USDOE Office

of Science and Technology, Washington, DC (United

States). Office of Program Analysis. Feb 1998. 15p. Sponsored by USDOE Office of Environmental Management,

Washington, DC (United States). Source: OSTI (Free of

Charge); INIS; DOE and DOE contractors free from OSTI;

public availability from Center for Environmental Management Information, 1-800-736-3282.

This paper describes a demonstration project for the

FRHAM-TEX Cool Suit manufactured by FRHAM Safety

Products. It is a one-piece, disposable, breathable, waterproof coverall designed to permit moisture generated by the

wearer to be transmitted outside the suit. The performance

of this suit was compared to a Tyvek suit as a baseline.

36
Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

The suit is proposed as safety ware for workers at decontamination and decommissioning projects.

156

(DOE/EM–0354)

NuFab anti-contamination suit - OST reference No.

1855. Deactivation and decommissioning focus area.

USDOE Office of Science and Technology, Washington, DC

(United States). Office of Program Analysis. Feb 1998. 15p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). Source: OSTI (Free

of Charge); INIS; DOE and DOE contractors free from OSTI;

public availability from Center for Environmental Management Information, 1-800-736-3282.

Radiation workers at all US Department of Energy (DOE)

sites require some form of protective clothing when performing radiological work. A large number of contaminated

facilities at DOE site are currently or will eventually undergo

some form of decontamination and decommissioning (D&D),

requiring some type of protective clothing, often in multiple

layers. Protective clothing that does not allow perspiration to

escape causes heat stress, which lowers worker comfort

and productivity. This report describes the NuFab anticontamination. The suit is a one-piece, disposable,

breathable, waterproof coverall with a single front zipper.

Constructed of tri-laminated composite material using spunbonded polypropylene and microporous film layers, the suit

is certified as incineratorable.

157

(DOE/EM–0355)

Pipe Crawler internal piping characterization system -

deactivation and decommissioning focus area. Innovative Technology Summary Report. USDOE Office of

Environmental Management, Washington, DC (United

States). Feb 1998. 36p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States).

Source: OSTI (Free of Charge); INIS; DOE and DOE contractors free from OSTI (United States); public availability

from Center for Environmental Management Information

(United States), 1-800-736-3282.

Pipe Crawler is a pipe surveying system for performing

radiological characterization and/or free release surveys of

piping systems. The technology employs a family of manually advanced, wheeled platforms, or crawlers, fitted with

one or more arrays of thin Geiger Mueller (GM) detectors

operated from an external power supply and data processing unit. Survey readings are taken in a step-wise fashion. A

video camera and tape recording system are used for video

surveys of pipe interiors prior to and during radiological surveys. Pipe Crawler has potential advantages over the

baseline and other technologies in areas of cost, durability,

waste minimization, and intrusiveness. Advantages include

potentially reduced cost, potential reuse of the pipe system,

reduced waste volume, and the ability to manage pipes in

place with minimal disturbance to facility operations. Advantages over competing technologies include potentially

reduced costs and the ability to perform beta-gamma surveys that are capable of passing regulatory scrutiny for free

release of piping systems.

158

(DOE/EM–0356)

In situ permeable flow sensor - OST reference No. 99.

Subsurface contaminants focus area. USDOE Office of

Science and Technology, Washington, DC (United States).

Office of Program Analysis. Feb 1998. 19p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). Source: OSTI (Free of Charge); INIS;

DOE and DOE contractors free from OSTI; public availability

from Center for Environmental Management Information, 1-

800-736-3282.

This summary reports describes the In Situ Permeable

Flow Sensor (ISPFS) developed to directly measure the

direction and velocity of groundwater flow at a point in saturated soil sediments. The ISPFS provides information for

locating, designing, and monitoring waste disposal sites,

and for monitoring remediated waste sites. The design and

performance are described and compared to alternative

methods. Economic, regulatory, and policy issues are discussed. Applicability of the ISPFS to specific situations is

also summarized. 8 refs., 7 figs., 3 tabs.

159

(DOE/EM–0357-Vol.1)

Report to Congress on the U.S. Department of Energy’s

Environmental Management Science Program: Research funded and its linkages to environmental

cleanup problems. Volume 1 of 3 – Report and Appendix A. Department of Energy, Office of Environmental

Management, Washington, DC (United States). Apr 1998.

153p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). Order Number

DE98005102. Source: OSTI; NTIS; INIS; GPO Dep.

This report is submitted in response to a Congressional

request and is intended to communicate the nature, content,

goals, and accomplishments of the Environmental Management Science Program (EMSP) to interested and affected

parties in the Department and its contractors, at Federal

agencies, in the scientific community, and in the general

public. The EMSP was started in response to a request to

mount an effort in longer term basic science research to

seek new and innovative cleanup methods to replace current

conventional approaches which are often costly and ineffective. Section 1, “Background of the Program,” provides

information on the evolution of the EMSP and how it is managed, and summarizes recent accomplishments. Section 2,

“Research Award Selection Process,” provides an overview

of the ongoing needs identification process, solicitation development, and application review for scientific merit and

programmatic relevance. Section 3, “Linkages to Environmental Cleanup Problems,” provides an overview of the

major interrelationships (linkages) among EMSP basic research awards, Environmental Management problem areas,

and high cost projects. Section 4, “Capitalizing on Science

Investments,” discusses the steps the EMSP plans to use to

facilitate the application of research results in Environmental

Management strategies through effective communication

and collaboration. Appendix A contains four program notices

published by the EMSP inviting applications for grants.

160

(DOE/EM–0357-Vol.2)

Report to Congress on the U.S. Department of Energy’s

Environmental Management Science Program: Research funded and its linkages to environmental

cleanup problems, and Environmental Management Science Program research award abstracts. Volume 2 of 3

– Appendix B. Department of Energy, Office of Environmental Management, Washington, DC (United States). Apr

37
ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

1998. 448p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). Order Number DE98005103. Source: OSTI; NTIS; INIS; GPO Dep.

The Department of Energy’s Environmental Management

Science Program (EMSP) serves as a catalyst for the application of scientific discoveries to the development and

deployment of technologies that will lead to reduction of the

costs and risks associated with cleaning up the nation’s nuclear complex. Appendix B provides details about each of

the 202 research awards funded by the EMSP. This information may prove useful to researchers who are attempting

to address the Department’s environmental management

challenges in their work, program managers who are

planning, integrating, and prioritizing Environmental Management projects, and stakeholders and regulators who are

interested in the Department’s environmental challenges.

The research award information is organized by the state

and institution in which the lead principal investigator is located. In many cases, the lead principal investigator is one

of several investigators at a number of different institutions.

In these cases, the lead investigator (major collaborator) at

each of the additional institutions is listed. Each research

award abstract is followed by a list of high cost projects that

can potentially be impacted by the research results. High

cost projects are Environmental Management projects that

have total costs greater than $50 million from the year 2007

and beyond, based on the March 1998 Accelerating

Cleanup: Paths to Closure Draft data, and have costs or

quantities of material associated with an Environmental

Management problem area. High cost projects which must

remain active in the year 2007 and beyond to manage high

risk are also identified. Descriptions of these potentially related high cost Environmental Management projects can be

found in Appendix C. Additional projects in the same problem area as a research award can be located using the

Index of High Cost Environmental Management Projects by

Problem Area, at the end of Appendices B and C.

161

(DOE/EM–0357-Vol.3)

Report to Congress on the U.S. Department of Energy’s

Environmental Management Science Program: Research funded and its linkages to environmental

cleanup problems, and high out-year cost environmental management project descriptions. Volume 3 of 3 –

Appendix C. Department of Energy, Office of Environmental Management, Washington, DC (United States). Apr

1998. 314p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). Order Number DE98005104. Source: OSTI; NTIS; INIS; GPO Dep.

The Department of Energy’s Environmental Management

Science Program (EMSP) serves as a catalyst for the application of scientific discoveries to the development and

deployment of technologies that will lead to reduction of the

costs and risks associated with cleaning up the nation’s nuclear complex. Appendix C provides details about each of

the Department’s 82 high cost projects and lists the EMSP

research awards with potential to impact each of these projects. The high cost projects listed are those having costs

greater than $50 million in constant 1998 dollars from the

year 2007 and beyond, based on the March 1998 Accelerating Cleanup: Paths to Closure Draft data, and having costs

of quantities of material associated with an environmental

management problem area. The high cost project information is grouped by operations office and organized by site

and project code. Each operations office section begins with

a list of research needs associated with that operations office. Potentially related research awards are listed by

problem area in the Index of Research Awards by Environmental Management Problem Area, which can be found at

the end of appendices B and C. For projects that address

high risks to the public, workers, or the environment, refer

also the Health/Ecology/Risk problem area awards. Research needs are programmatic or technical challenges that

may benefit from knowledge gained through basic research.

162

(DOE/EM–0360)

Tanks focus area. Annual report. Frey, J. USDOE Office

of Environmental Management, Washington, DC (United

States). 1997. 26p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States).

Order Number DE98005229. Source: OSTI; NTIS; INIS;

GPO Dep.

The U.S. Department of Energy Office of Environmental

Management is tasked with a major remediation project to

treat and dispose of radioactive waste in hundreds of underground storage tanks. These tanks contain about

90,000,000 gallons of high-level and transuranic wastes. We

have 68 known or assumed leaking tanks, that have allowed

waste to migrate into the soil surrounding the tank. In some

cases, the tank contents have reacted to form flammable

gases, introducing additional safety risks. These tanks must

be maintained in the safest possible condition until their

eventual remediation to reduce the risk of waste migration

and exposure to workers, the public, and the environment.

Science and technology development for safer, more efficient, and cost-effective waste treatment methods will speed

up progress toward the final remediation of these tanks. The

DOE Office of Environmental Management established the

Tanks Focus Area to serve as the DOE-EM’s technology development program for radioactive waste tank remediation in

partnership with the Offices of Waste Management and

Environmental Restoration. The Tanks Focus Area is responsible for leading, coordinating, and facilitating science

and technology development to support remediation at

DOE’s four major tank sites: the Hanford Site in Washington

State, Idaho National Engineering and Environmental Laboratory in Idaho, Oak Ridge Reservation in Tennessee, and

the Savannah River Site in South Carolina. The technical

scope covers the major functions that comprise a complete

tank remediation system: waste retrieval, waste

pretreatment, waste immobilization, tank closure, and characterization of both the waste and tank. Safety is integrated

across all the functions and is a key component of the Tanks

Focus Area program.

163

(DOE/EM–0361)

Subsurface Contaminants Focus Area annual report

1997. USDOE Office of Environmental Management, Subsurface Contaminants Focus Area, Washington, DC (United

States). [1997]. 21p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States).

Order Number DE98005486. Source: OSTI; NTIS; INIS;

GPO Dep.

In support of its vision for technological excellence, the

Subsurface Contaminants Focus Area (SCFA) has identified

three strategic goals. The three goals of the SCFA are:

Contain and/or stabilize contamination sources that pose an

38
Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

imminent threat to surface and ground waters; Delineate

DNAPL contamination in the subsurface and remediate

DNAPL-contaminated soils and ground water; and Remove

a full range of metal and radionuclide contamination in soils

and ground water. To meet the challenges of remediating

subsurface contaminants in soils and ground water, SCFA

funded more than 40 technologies in fiscal year 1997.

These technologies are grouped according to the following

product lines: Dense Nonaqueous-Phase Liquids; Metals

and Radionuclides; Source Term Containment; and Source

Term Remediation. This report briefly describes the SCFA

1997 technologies and showcases a few key technologies in

each product line.

164

(DOE/EM–0362)

Accelerating cleanup: Paths to closure. Dept. of Energy,

Office of Environmental Management, Washington, DC

(United States). Jun 1998. [300p.] Sponsored by USDOE

Office of Environmental Management, Washington, DC

(United States). Order Number DE98007081. Source: OSTI;

NTIS; INIS; GPO Dep.

This report describes the status of Environmental Management’s (EM’s) cleanup program and a direction forward

to complete achievement of the 2006 vision. Achieving the

2006 vision results in significant benefits related to accomplishing EM program objectives. As DOE sites accelerate

cleanup activities, risks to public health, the environment,

and worker safety and health are all reduced. Finding more

efficient ways to conduct work can result in making compliance with applicable environmental requirements easier to

achieve. Finally, as cleanup activities at sites are completed,

the EM program can focus attention and resources on the

small number of sites with more complex cleanup challenges. Chapter 1 describes the process by which this

report has been developed and what it hopes to accomplish,

its relationship to the EM decision-making process, and a

general background of the EM mission and program. Chapter 2 describes how the site-by-site projections were

constructed, and summarizes, for each of DOE’s 11 Operations/Field Offices, the projected costs and schedules for

completing the cleanup mission. Chapter 3 presents summaries of the detailed cleanup projections from three of the

11 Operations/Field Offices: Rocky Flats (Colorado), Richland (Washington), and Savannah River (South Carolina).

The remaining eight Operations/Field Office summaries are

in Appendix E. Chapter 4 reviews the cost drivers,

budgetary constraints, and performance enhancements underlying the detailed analysis of the 353 projects that

comprise EM’s accelerated cleanup and closure effort.

Chapter 5 describes a management system to support the

EM program. Chapter 6 provides responses to the general

comments received on the February draft of this document.

165

(DOE/EM–0365)

Annual report of waste generation and pollution prevention progress 1997. Dept. of Energy, Albuquerque

Operations Office, NM (United States). Sep 1998. 144p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). Order Number

DE98006498. Source: OSTI; NTIS; INIS; GPO Dep.

This sixth Annual Report presents and analyzes DOE

Complex-wide waste generation and pollution prevention activities at 36 reporting sites from 1993 through 1997. In May

1996, the Secretary of Energy established a 50 percent

Complex-Wide Waste Reduction Goal (relative to the 1993

baseline) for routine operations radioactive and hazardous

waste generation, to be achieved by December 31, 1999.

Excluding sanitary waste, routine operations waste generation increased three percent from 1996 to 1997, and

decreased 61 percent overall from 1993 to 1997. DOE has

achieved its Complex-Wide Waste Reduction Goals for routine operations based upon a comparison of 1997 waste

generation to the 1993 baseline. However, it is important to

note that increases in low-level radioactive and low-level

mixed waste generation could reverse this achievement.

From 1996 to 1997, low-level radioactive waste generation

increased 10 percent, and low-level mixed waste generation

increased slightly. It is critical that DOE sites continue to reduce routine operations waste generation for all waste

types, to ensure that DOE’s Complex-Wide Waste Reduction Goals are achieved by December 31, 1999.

166

(DOE/EM–0368)

Innovative technology summary report: Houdini I and

II remotely operated vehicle. Dept. of Energy, Office of

Environmental Management, Washington, DC (United

States). Jul 1998. 31p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States).

Order Number DE98007484. Source: OSTI; NTIS; INIS;

Public inquiries to Center for Environmental Management Information, 1-800-736-3282 (United States); DOE and DOE

contractors receive free stock copies from OSTI while they

last; GPO Dep.

The US Department of Energy (DOE) is responsible for

cleaning up and closing 273 large, aging, underground

tanks the department has used for storing approximately 1

million gal of high- and low-level radioactive and mixed

waste. The waste’s radioactivity precludes humans from

working in the tanks. A remote-controlled retrieval method

must be used. The Houdini robot addresses the need for

vehicle-based, rugged, remote manipulation systems that

can perform waste retrieval, characterization, and inspection

tasks. Houdini-I was delivered to ORNL in September 1996,

deployed in a cold test facility in November, and first deployed in the gunite tanks in June 1997. Since then, it has

seen continuous (still on-going) service at ORNL, providing

a critical role in the cleanup of two gunite tanks, W-3 and W4, in the GAAT NTF. Houdini-I has proven rugged, capable

of waste retrieval, and able to withstand high reaction force

operations such as wall core sampling. It’s even able to operate while hanging, which was the case when Houdini was

used to cut and remove cables and steel pipes hanging below manways in Tank W-3. Based upon the lessons learned

at ORNL, Houdini’s design has been completely overhauled.

A second generation system, Houdini-II, is now being built.

167

(DOE/EM–0371)

Innovative technology summary report: Transportable

vitrification system. Dept. of Energy, Office of Environmental Management, Washington, DC (United States). Sep

1998. 44p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). Order Number DE99000452. Source: OSTI; NTIS; INIS; Public

inquiries to Center for Environmental Management Information, 1-800-736-3282 (United States); DOE and DOE

39
ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

contractors receive free stock copies from OSTI while they

last; GPO Dep.

At the end of the cold war, many of the Department of Energy’s (DOE’s) major nuclear weapons facilities refocused

their efforts on finding technically sound, economic, regulatory compliant, and stakeholder acceptable treatment

solutions for the legacy of mixed wastes they had produced.

In particular, an advanced stabilization process that could

effectively treat the large volumes of settling pond and treatment sludges was needed. Based on this need, DOE and its

contractors initiated in 1993 the EM-50 sponsored development effort required to produce a deployable mixed waste

vitrification system. As a consequence, the Transportable

Vitrification System (TVS) effort was undertaken with the

primary requirement to develop and demonstrate the technology and associated facility to effectively vitrify, for

compliant disposal, the applicable mixed waste sludges and

solids across the various DOE complex sites. After 4 years

of development testing with both crucible and pilot-scale

melters, the TVS facility was constructed by Envitco,

evaluated and demonstrated with surrogates, and then successfully transported to the ORNL ETTP site and

demonstrated with actual mixed wastes in the fall of 1997.

This paper describes the technology, its performance, the

technology applicability and alternatives, cost, regulatory

and policy issues, and lessons learned.

168

(DOE/EM–0372)

Innovative technology summary report: Confined sluicing end effector. Dept. of Energy, Office of Environmental

Management, Washington, DC (United States). Sep 1998.

18p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). Order Number

DE98007489. Source: OSTI; NTIS; INIS; Public inquiries to

Center for Environmental Management Information, 1-800-

736-3282 (United States); DOE and DOE contractors

receive free stock copies from OSTI while they last; GPO

Dep.

A Confined Sluicing End-Effector (CSEE) was field tested

during the summer of 1997 in Tank W-3, one of the Gunite

and Associated Tanks (GAAT) at the Oak Ridge Reservation

(ORR). It should be noted that the specific device used at

the Oak Ridge Reservation demonstration was the Sludge

Retrieval End-Effector (SREE), although in common usage it

is referred to as the CSEE. Deployed by the Modified LightDuty Utility Arm (MLDUA) and the Houdini remotely

operated vehicle (ROV), the CSEE was used to mobilize

and retrieve waste from the tank. After removing the waste,

the CSEE was used to scarify the gunite walls of Tank W-3,

removing approximately 0.1 in of material. The CSEE uses

three rotating water-jets to direct a short-range pressurized

jet of water to effectively mobilize the waste. Simultaneously,

the water and dislodged tank waste, or scarified materials,

are aspirated using a water-jet pump-driven conveyance

system. The material is then pumped outside of the tank,

where it can be stored for treatment. The technology, its performance, uses, cost, and regulatory issues are discussed.

169

(DOE/EM–0374)

Innovative technology summary report: Concrete

grinder. Dept. of Energy, Office of Environmental Management, Washington, DC (United States). Sep 1998. 33p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). Order Number

DE98007485. Source: OSTI; NTIS; INIS; Public inquiries to

Center for Environmental Management Information, 1-800-

736-3282 (United States); DOE and DOE contractors

receive free stock copies from OSTI while they last; GPO

Dep.

The Flex concrete grinder is a lightweight, hand-held concrete and coating removal system used for decontaminating

or stripping concrete surfaces. The US Department of Energy has successfully demonstrated it for decontaminating

walls and floors for free release surveys prior to demolition

work. The grinder is an electric-powered tool with a vacuum

port for dust extraction and a diamond grinding wheel. The

grinder is suitable for flat or slightly curved surfaces and results in a smooth surface, which makes release surveys

more reliable. The grinder is lightweight and produces very

little vibration, thus reducing worker fatigue. The grinder is

more efficient than traditional baseline, tools at removing

contamination from concrete surfaces (more than four times

faster than hand-held pneumatic scabbling and scaling

tools). Grinder consumables (i.e., replacement diamond

grinding wheel) are more expensive than the replacement

carbide parts for the scaler and scabbler. However, operating costs are outweighed by the lower purchase price of the

grinder (50% of the price of the baseline scaler and 8% of

the price of the baseline scabbler). Overall, the concrete

grinder is an attractive alternative to traditional scabbling

and scaling pneumatic tools. To this end, in July 1998, the

outer rod room exposed walls of the Safe Storage Enclosure

(SSE), an area measuring approximately 150 m2, may be

decontaminated with the hand-held grinder. This concrete

grinder technology was demonstrated for the first time at the

DOE’s Hanford Site. Decontamination of a sample room

walls was performed at the C Reactor to free release the

walls prior to demolition. The demonstration was conducted

by onsite D and D workers, who were instructed by the vendor prior to and during the demonstration.

170

(DOE/EM–0375)

Innovative technology summary report: High-speed

clamshell pipe cutter. Dept. of Energy, Office of Environmental Management, Washington, DC (United States). Sep

1998. 28p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). Order Number DE98007486. Source: OSTI; NTIS; INIS; Public

inquiries to Center for Environmental Management Information, 1-800-736-3282 (United States); DOE and DOE

contractors receive free stock copies form OSTI while they

last; GPO Dep.

The Hanford Site C Reactor Technology Demonstration

Group demonstrated the High-Speed Clamshell Pipe Cutter

technology, developed and marketed by Tri Tool Inc. (Rancho Cordova, California). The models demonstrated are

portable, split-frame pipe lathes that require minimal radial

and axial clearances for severing and/or beveling in-line

pipe with ranges of 25 cm to 41 cm and 46 cm to 61 cm

nominal diameter. The radial clearance requirement from

the walls, floors, or adjacent pipes is 18 cm. The lathes

were supplied with carbide insert conversion kits for the

cutting bits for the high-speed technique that was demonstrated. Given site-specific factors, this demonstration

showed the cost of the improved technology to be approximately 30% higher than the traditional (baseline) technology

40
Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

(oxyacetylene torch) cost of $14,400 for 10 cuts of contaminated 41-cm and 61-cm-diameter pipe at C Reactor. Actual

cutting times were faster than the baseline technology; however, moving/staging the equipment took longer. Unlike the

baseline torch, clamshell lathes do not involve applied heat,

flames, or smoke and can be operated remotely, thereby

helping personal exposures to be as low as reasonably

achievable. The baseline technology was demonstrated at

the C Reactor north and south water pipe tunnels August

19–22, 1997. The improved technology was demonstrated

in the gas pipe tunnel December 15–19.

171

(DOE/EM–0376)

Innovative technology summary report: System for

Tracking Remediation, Exposure, Activities and Materials. Dept. of Energy, Office of Environmental Management,

Washington, DC (United States). Sep 1998. 29p. Sponsored

by USDOE Office of Environmental Management, Washington, DC (United States). Order Number DE98007487.

Source: OSTI; NTIS; INIS; Public inquiries to Center for Environmental Management Information, 1-800-736-3282

(United States); DOE and DOE contractors receive free

stock copies from OSTI while they last; GPO Dep.

The System for Tracking Remediation, Exposure, Activities, and Materials (STREAM) technology is a multi-media

database that consolidates project information into a single,

easily-accessible place for day-to-day work performance

and management tracking. Information inputs can range

from procedures, reports, and references to waste generation logs and manifests to photographs and contaminant

survey maps. Key features of the system are quick and easy

information organization and retrieval, versatile information

display options, and a variety of visual imaging methods.

These elements enhance productivity and compliance and

facilitate communications with project staff, clients, and

regulators. Use of STREAM also gives visual access to contaminated areas, reducing the number of physical entries

and promoting safety and as low as reasonably achievable

(ALARA) principles. The STREAM system can be customized to focus on the information needs of a specific

project, and provides a capability and work process improvement well beyond the usual collection of paperwork

and independent databases. Especially when incorporated

early in project planning and implemented to the fullest extent, it is a systematic and cost-effective tool for controlling

and using project information. The STREAM system can

support up to 50 different work stations. This report covers

the period February through October 1997, when the

STREAM software program, owned by Delphinus Engineering, was demonstrated at the Hanford Site’s Reactor Interim

Safe Storage (ISS) Project.

172

(DOE/EM–0377)

Innovative technology summary report: Sealed-seam

sack suits. Dept. of Energy, Office of Environmental Management, Washington, DC (United States). Sep 1998. 25p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). Order Number

DE98007490. Source: OSTI; NTIS; INIS; Public inquiries to

Center for Environmental Management Information, 1-800-

736-3282 (United States); DOE and DOE contractors

receive free stock copies from OSTI while they last; GPO

Dep.

Sealed-seam sack suits are an improved/innovative safety

and industrial hygiene technology designed to protect workers from dermal exposure to contamination. Most of these

disposable, synthetic-fabric suits are more protective than

cotton suits, and are also water-resistant and gas permeable. Some fabrics provide a filter to aerosols, which is

important to protection against contamination, while allowing

air to pass, increasing comfort level of workers. It is easier

to detect body-moisture breakthrough with the disposable

suits than with cotton, which is also important to protecting

workers from contamination. These suits present a safe and

cost-effective (6% to 17% less expensive than the baseline)

alternative to traditional protective clothing. This report covers the period from October 1996 to August 1997. During

that time, sealed-seam sack suits were demonstrated during

daily activities under normal working conditions at the C Reactor and under environmentally controlled conditions at the

Los Alamos National Laboratory (LANL).

173

(DOE/EM–98003908)

EM international activities: May 1998 highlights. Dept. of

Energy, Office of Environmental Management, Washington,

DC (United States). May 1998. 33p. Sponsored by USDOE

Office of Environmental Management, Washington, DC

(United States). Order Number DE98003908. Source: OSTI;

NTIS; INIS; GPO Dep.

This publication is produced twice a year by the International Technology Systems Application staff. This issue is

divided into the following sections: (1) Global Issues Facing

Environmental Management; (2) Activities in Western

Europe; (3) Activities in Central and Eastern Europe; (4) Activities in Russia; (5) Activities in Asia and the Pacific Rim;

(6) Activities in South America; (7) Activities in North America; (8) Country studies; and (9) International Organizations.

Some topics discussed are nuclear materials management,

radioactive waste and hazardous waste management, and

remedial action programs.

174

(DOE/EM–98006440)

United States-Russia: Environmental management activities, Summer 1998. Office of Science and Technology,

International Program Office, Washington, DC (United

States). Sum 1998. 80p. Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

States). Order Number DE98006440. Source: OSTI; NTIS;

INIS; GPO Dep.

A Joint Coordinating Committee for Environmental

Restoration and Waste Management (JCCEM) was formed

between the US and Russia. This report describes the areas

of research being studied under JCCEM, namely: Efficient

separations; Contaminant transport and site characterization; Mixed wastes; High level waste tank remediation;

Transuranic stabilization; Decontamination and decommissioning; and Emergency response. Other sections describe:

Administrative framework for cooperation; Scientist

exchange; Future actions; Non-JCCEM DOE-Russian activities; and JCCEM publications.

175

(DOE/ER–433/V2)

Old hydrofracture facility tanks contents removal action

operations plan at the Oak Ridge National Laboratory,

Oak Ridge, Tennessee. Volume 2: Checklists and work

41
ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

instructions. CDM Federal Programs Corp., Oak Ridge, TN

(United States). May 1998. 194p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States). DOE Contract AC05-98OR22700. Order Number

DE98005139. Source: OSTI; NTIS; INIS; GPO Dep.

This is volume two of the ORNL old hydrofracture facility

tanks contents removal action operations plan. This volume

contains checklists and work instructions.

176

(DOE/EW/50625–T36)

Environmental hazards assessment program. Quarterly

report (extended quarter), April 1997–September 1997.

Medical Univ. of South Carolina, Charleston, SC (United

States). 31 Oct 1997. 52p. Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract FG01-92EW50625. Order Number

DE98000869. Source: OSTI; NTIS; GPO Dep.

On June 23, 1992, the United States Department of

Energy (DOE) signed Assistance Instrument Number DEFG01-92EW50625 with the Medical University of South

Carolina (MUSC) to support the Environmental Hazards Assessment Program (EHAP). Dr. James B. Edwards,

President of the Medical University of South Carolina, suggested, “Good health is not the result of good doctorin’ but

the result of a healthy society in a healthy, economic, political and biological environment”. To further good health, it is

appropriate that an educational institution such as MUSC

utilize grant funds to help people from all walks of life understand better what truly does affect human health, what does

not, and why. EHAP is an integrated, multidisciplinary program, employing a range of initiatives to identify, address

and resolve environmental health risk issues.

177

(DOE/EW/50625–T37)

Environmental hazards assessment program (extended

year). Annual report, July 1, 1996–September 30, 1997.

Medical Univ. of South Carolina, Charleston, SC (United

States). 31 Oct 1997. 80p. Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract FG01-92EW50625. Order Number

DE98000870. Source: OSTI; NTIS; GPO Dep.

On June 23, 1992, the United States Department of

Energy (DOE) signed Assistance Instrument Number DEFG01-92EW50625 with the Medical University of South

Carolina (MUSC) to support the Environmental Hazards Assessment Program (EHAP). Dr. James B. Edwards,

President of the Medical University of South Carolina, suggested, “Good health is not the result of good doctorin’ but

the result of a healthy society in a healthy, economic, political and biological environment.” To further good health, it is

appropriate that an educational institution such as MUSC

utilize grant funds to help people from all walks of life understand better what truly does affect human health, what does

not, and why. The objectives of EHAP stated in the proposal

to DOE are to: (1) develop a holistic, national basis for risk

assessment, risk management, and risk communications

that recognizes the direct impact of environmental hazards

on the health and well-being of all; (2) develop a pool of talented scientists and experts in cleanup activities, especially

in human health aspects; and (3) identify needs and develop

programs addressing the critical shortage of well-educated,

highly-skilled technical and scientific personnel to address

the health-oriented aspects of environmental restoration and

waste management.

178

(DOE/EW/50625–T38)

Environmental hazards assessment program. Summary

report, June 23, 1992–September 30, 1997. Medical Univ.

of South Carolina, Charleston, SC (United States). 31 Dec

1997. 78p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract FG01-92EW50625. Order Number DE98002537.

Source: OSTI; NTIS; INIS; GPO Dep.

This summary report describes activities and reports for

the grant period from June 1992 to September 1997. It reports progress against grant objectives and the Program

Implementation Plan published during the first year of the

grant program. The program consists of six major elements:

(1) public and professional outreach, (2) clinical science, (3)

biomedical research, (4) information systems, (5) education,

and (6) community development. Research is focused on

toxicological and epidemiological investigation into environmental problems that pose a direct risk to human health,

and methods to translate basic research into risk assessment and preventive medicine applications for health care

providers.

179

(DOE/EW/50625–T39)

Environmental Hazards Assessment Program summary

report, June 23, 1992–September 30, 1997. Medical Univ.

of South Carolina, Charleston, SC (United States). 31 Dec

1997. 76p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract FG01-92EW50625. Order Number DE98001832.

Source: OSTI; NTIS; GPO Dep.

On June 23, 1992, the US Department of Energy (DOE)

signed an agreement with the Medical University of South

Carolina (MUSC) to support the Environmental Hazards Assessment Program (EHAP). The objectives of EHAP are to:

(1) develop a holistic, national basis for risk assessment,

risk management and risk communication that recognizes

the direct impact of environmental hazards on the health

and well-being of all; (2) develop a pool of talented scientists and experts in cleanup activities, especially in human

health aspects and (3) identify needs and develop programs

addressing the critical shortage of well-educated, highlyskilled technical and scientific personnel to address the

health-oriented aspects of environmental restoration and

waste management. In this report, the highlights listed describe a summary of the primary accomplishments made by

the projects ongoing at the end of Year Five. It reports

progress against the objectives and the Program Implementation Plan published at the end of the first year of the grant.

180

(DOE/EW/55094–26)

Investigation of waste glass pouring behavior over a

knife edge. Ebadian, M.A. Florida International Univ., Miami, FL (United States). Jan 1998. 26p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract FG21-95EW55094. Order

Number DE98059424. Source: OSTI; NTIS; INIS; GPO Dep.

The development of vitrification technology for converting

radioactive waste into a glass solid began in the early

42
Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

1960s. Some problems encountered in the vitrification process are still waiting for a solution. One of them is wicking.

During pouring, the glass stream flows down the wall of the

pour spout until it reaches an angled cut in the wall. At this

point, the stream is supposed to break cleanly away from

the wall of the pour spout and fall freely into the canister.

However, the glass stream is often pulled toward the wall

and does not always fall into the canister, a phenomenon

known as wicking. Phase 1 involves the assembly, construction, and testing of a melter capable of supplying molten

glass at operational flow rates over a break-off point knife

edge. Phase 2 will evaluate the effects of glass and pour

spout temperatures as well as glass flow rates on the glass

flow behavior over the knife edge. Phase 3 will identify the

effects on wicking resulting from varying the knife edge diameter and height as well as changing the back-cut angle of

the knife edge. The following tasks were completed in FY97:

Design the experimental system for glass melting and pouring; Acquire and assemble the melter system; and Perform

initial research work.

181

(DOE/EW/55094–29)

Sensor for viscosity and shear strength measurement.

Ebadian, M.A.; Dillion, J.; Moore, J.; Jones, K. Florida International Univ., Miami, FL (United States). Jan 1998. 92p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States);USDOE Assistant

Secretary for Fossil Energy, Washington, DC (United

States). DOE Contract FG21-95EW55094. Order Number

DE98059427. Source: OSTI; NTIS; GPO Dep.

Measurement of the physical properties (viscosity and

density) of waste slurries is critical in evaluating transport

parameters to ensure turbulent flow through transport pipes.

The environment for measurement and sensor exposure is

extremely harsh; therefore, reliability and ruggedness are

critical in the sensor design. Two different viscometer techniques are being investigated in this study, based on:

magnetostrictive pulse generated acoustic waves; and an

oscillating cylinder. Prototype sensors have been built and

tested which are based on both techniques. A base capability instrumentation system has been designed, constructed,

and tested which incorporates both of these sensors. It requires manual data acquisition and off-line calculation. A

broad range of viscous media has been tested using this

system. Extensive test results appear in this report. The

concept for each technique has been validated by these test

results. This base capability system will need to be refined

further before it is appropriate for field tests. The mass of

the oscillating system structure will need to be reduced. A

robust acoustic probe assembly will need to be developed.

In addition, in March 1997 it was made known for the first

time that the requirement was for a deliverable automated

viscosity instrumentation system. Since then such a system

has been designed, and the hardware has been constructed

so that the automated concept can be proved. The rest of

the hardware, which interfaced to a computer, has also

been constructed and tested as far as possible. However,

for both techniques the computer software for automated

data acquisition, calculation, and logging had not been completed before funding and time ran out.

182

(DOE/EW/55094–30)

Melting, solidification, remelting, and separation of

glass and metal. Ebadian, M.A.; Xin, R.C.; Liu, Y.Z. Florida

International Univ., Miami, FL (United States). Jan 1998.

36p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

FG21-95EW55094. Order Number DE98059428. Source:

OSTI; NTIS; INIS; GPO Dep.

Several high-temperature vitrification technologies have

been developed for the treatment of a wide range of mixed

waste types in both the low-level waste and transuranic

(TRU) mixed waste categories currently in storage at DOE

sites throughout the nation. The products of these processes are an oxide slag phase and a reduced metal phase.

The metal phase has the potential to be recycled within the

DOE Complex. Enhanced slag/metal separation methods

are needed to support these processes. This research

project involves an experimental investigation of the melting,

solidification, remelting, and separation of glass and metal

and the development of an efficient separation technology.

The ultimate goal of this project is to find an efficient way to

separate the slag phase from the metal phase in the molten

state. This two-year project commenced in October 1995

(FY96). In the first fiscal year, the following tasks were accomplished: (1) A literature review and an assessment of

the baseline glass and metal separation technologies were

performed. The results indicated that the baseline technology yields a high percentage of glass in the metal phase,

requiring further separation. (2) The main melting and solidification system setup was established. A number of melting

and solidification tests were conducted. (3) Temperature distribution, solidification patterns, and flow field in the molten

metal pool were simulated numerically for the solidification

processes of molten aluminum and iron steel. (4) Initial designs of the laboratory-scale DCS and CS technologies

were also completed. The principal demonstration separation units were constructed. (5) An application for a patent

for an innovative liquid-liquid separation technology was

submitted and is pending.

183

(DOE/EW/55094–31)

Plant stress analysis technology deployment. Ebadian,

M.A. Florida International Univ., Miami, FL (United States).

Jan 1998. 14p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE

Contract FG21-95EW55094. Order Number DE98059429.

Source: OSTI; NTIS; GPO Dep.

Monitoring vegetation is an active area of laser-induced

fluorescence imaging (LIFI) research. The Hemispheric

Center for Environmental Technology (HCET) at Florida International University (FIU) is assisting in the transfer of the

LIFI technology to the agricultural private sector through a

market survey. The market survey will help identify the key

eco-agricultural issues of the nations that could benefit from

the use of sensor technologies developed by the Office of

Science and Technology (OST). The principal region of interest is the Western Hemisphere, particularly, the rapidly

growing countries of Latin America and the Caribbean. The

analysis of needs will assure that the focus of present and

future research will center on economically important issues

facing both hemispheres. The application of the technology

will be useful to the agriculture industry for airborne crop

analysis as well as in the detection and characterization of

contaminated sites by monitoring vegetation. LIFI airborne

and close-proximity systems will be evaluated as standalone technologies and additions to existing sensor

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

technologies that have been used to monitor crops in the

field and in storage.

184

(DOE/EW/55094–32)

Assessment of strippable coatings for decontamination

and decommissioning. Ebadian, M.A. Florida International

Univ., Miami, FL (United States). Jan 1998. 39p. Sponsored

by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract FG21-95EW55094.

Order Number DE98059430. Source: OSTI; INIS; NTIS;

GPO Dep.

Strippable or temporary coatings were developed to assist

in the decontamination of the Three Mile Island (TMI-2) reactor. These coatings have become a viable option during

the decontamination and decommissioning (D and D) of

both US Department of Energy (DOE) and commercial nuclear facilities to remove or fix loose contamination on both

vertical and horizontal surfaces. A variety of strippable coatings are available to D and D professionals. However, these

products exhibit a wide range of performance criteria and

uses. The Hemispheric Center for Environmental Technology (HCET) at Florida International University (FIU) was

commissioned to perform a 2-year investigation into strippable coatings. This investigation was divided into four

parts: (1) identification of commercially available strippable

coating products; (2) survey of D and D professionals to determine current uses of these coatings and performance

criteria; (3) design and implementation of a non-radiological

testing program to evaluate the physical properties of these

coatings; and (4) design and implementation of a radiological testing program to determine decontamination factors

and effects of exposure to ionizing radiation. Activities during fiscal year 1997 are described.

185

(DOE/EW/55094–33)

Microwave combustion and sintering without isostatic

pressure. Ebadian, M.A. Florida International Univ., Miami,

FL (United States). Jan 1998. 31p. Sponsored by USDOE

Office of Environmental Management, Washington, DC

(United States). DOE Contract FG21-95EW55094. Order

Number DE98059431. Source: OSTI; NTIS; INIS; GPO Dep.

In recent years interest has grown rapidly in the application of microwave energy to the processing of ceramics,

composites, polymers, and other materials. Advances in the

understanding of microwave/materials interactions will facilitate the production of new ceramic materials with superior

mechanical properties. One application of particular interest

is the use of microwave energy for the mobilization of uranium for subsequent redeposition. Phase III (FY98) will

focus on the microwave assisted chemical vapor infiltration

tests for mobilization and redeposition of radioactive species

in the mixed sludge waste. Uranium hexachloride and uranium (IV) borohydride are volatile compounds for which the

chemical vapor infiltration procedure might be developed for

the separation of uranium. Microwave heating characterized

by an inverse temperature profile within a preformed ceramic matrix will be utilized for CVI using a carrier gas.

Matrix deposition is expected to commence from the inside

of the sample where the highest temperature is present. The

preform matrix materials, which include aluminosilicate

based ceramics and silicon carbide based ceramics, are all

amenable to extreme volume reduction, densification, and

vitrification. Important parameters of microwave sintering

such as frequency, power requirement, soaking temperature, and holding time will be investigated to optimize

process conditions for the volatilization of uranyl species using a reactive carrier gas in a microwave chamber.

186

(DOE/EW/55094–35)

Large-bore pipe decontamination. Ebadian, M.A. Florida

International Univ., Miami, FL (United States). Jan 1998.

49p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

FG21-95EW55094. Order Number DE98059433. Source:

OSTI; NTIS; INIS; GPO Dep.

The decontamination and decommissioning (D and D) of

1200 buildings within the US Department of Energy-Office of

Environmental Management (DOE-EM) Complex will require

the disposition of miles of pipe. The disposition of large-bore

pipe, in particular, presents difficulties in the area of decontamination and characterization. The pipe is potentially

contaminated internally as well as externally. This situation

requires a system capable of decontaminating and characterizing both the inside and outside of the pipe. Current

decontamination and characterization systems are not designed for application to this geometry, making the direct

disposal of piping systems necessary in many cases. The

pipe often creates voids in the disposal cell, which requires

the pipe to be cut in half or filled with a grout material. These

methods are labor intensive and costly to perform on large

volumes of pipe. Direct disposal does not take advantage of

recycling, which could provide monetary dividends. To facilitate the decontamination and characterization of large-bore

piping and thereby reduce the volume of piping required for

disposal, a detailed analysis will be conducted to document

the pipe remediation problem set; determine potential technologies to solve this remediation problem set; design and

laboratory test potential decontamination and characterization technologies; fabricate a prototype system; provide a

cost-benefit analysis of the proposed system; and transfer

the technology to industry. This report summarizes the activities performed during fiscal year 1997 and describes the

planned activities for fiscal year 1998. Accomplishments for

FY97 include the development of the applicable and

relevant and appropriate regulations, the screening of decontamination and characterization technologies, and the

selection and initial design of the decontamination system.

187

(DOE/FT/34337–1)

The NGA-DOE grant to examine critical issues related to

radioactive waste and materials disposition involving

DOE facilities. Quarterly report, October 1–December 31,

1997. Beauchesne, A.M. National Governors’ Association,

Center for Best Practices, Washington, DC (United States).

[1997]. 8p. Sponsored by USDOE Assistant Secretary for

Fossil Energy, Washington, DC (United States);USDOE Office of Environmental Management, Washington, DC (United

States). DOE Contract FG26-97FT34337. Order Number

DE98054553. Source: OSTI; NTIS; GPO Dep.

Topics explored through this project include: decisions involving disposal of mixed, low-level, and transuranic (TRU)

waste and disposition of nuclear materials; decisions involving DOE budget requests and their effect on environmental

cleanup and compliance at DOE facilities; strategies to treat

mixed, low-level, and transuranic (TRU) waste and their effect on individual sites in the complex; changes to the FFCA

44
Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

site treatment plans as a result of proposals in the EM 2006

cleanup plans and contractor integration analysis; interstate

waste and materials shipments; and reforms to existing

RCRA and CERCLA regulations/guidance to address regulatory overlap and risks posed by DOE wastes. The work

accomplished by the NGA project team during the past four

months can be categorized as follows: maintained open

communication with DOE on a variety of activities and issues within the DOE environmental management complex;

and maintained communication with NGA Federal Facilities

Compliance Task Force members regarding DOE efforts to

formulate a configuration for mixed low-level waste and lowlevel treatment and disposal, DOE activities in the area of

the Hazardous Waste Identification Rule, and DOE’s proposed National Dialogue.

188

(DOE/ID–10631)

Plutonium stabilization and disposition focus area, FY

1999 and FY 2000 multi-year program plan. Lockheed

Martin Idaho Technologies Co., Idaho Falls, ID (United

States). Mar 1998. 52p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States).

DOE Contract AC07-94ID13223. Order Number

DE98054114. Source: OSTI; NTIS; INIS; GPO Dep.

Consistent with the Environmental Management’s (EM’s)

plan titled, “Accelerating Cleanup: Paths to Closure”, and

ongoing efforts within the Executive Branch and Congress,

this Multi-Year Program Plan (MYPP) for the Plutonium Focus Area was written to ensure that technical gap projects

are effectively managed and measured. The Plutonium

Focus Area (PFA) defines and manages technology development programs that contribute to the effective stabilization

of nuclear materials and their subsequent safe storage and

final disposition. The scope of PFA activities includes the

complete spectrum of plutonium materials, special isotopes,

and other fissile materials. The PFA enables solutions to

site-specific and complex-wide technology issues associated

with plutonium remediation, stabilization, and preparation for

disposition. The report describes the current technical activities, namely: Plutonium stabilization (9 studies); Highly

enriched uranium stabilization (2 studies); Russian collaboration program (2 studies); Packaging and storage

technologies (6 studies); and PFA management work package/product line (3 studies). Budget information for FY 1999

and FY 2000 is provided.

189

(DOE/ID/13220–T9)

Magnetically controlled deposition of metals using gas

plasma. Quarterly progress report, October–December

1996. Idaho Univ., Moscow, ID (United States). [1997]. 27p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

FG07-93ID13220. Order Number DE97003651. Source:

OSTI; NTIS; GPO Dep.

Thin layers of secondary material are plated on substrates

either by plating or spraying processes. Plating operations

produce large amounts of hazardous liquid waste. Spraying,

while one of the less waste intensive methods, produces

“over spray” which is waste that is a result of uncontrolled

nature of the spray stream. In many cases the over spray

produces a hazardous waste. Spray coating is a mature process with many uses. Material can be deposited utilizing

spraying technology in three basic ways: “Flame spraying”,

direct spraying of molten metals and/or plasma spraying.

This project is directed at controlling the plasma spraying

process and thereby minimizing the waste generated in that

process. The proposed process will utilize a standard

plasma spray gunsmith the addition of magnetic fields to focus and control the plasma. In order to keep development

cost at a minimum, the project was organized in phases.

The first and current phase involves developing an analytical

model that will prove the concept and be used to design a

prototype. Analyzing the process and using the analysis has

the potential to generate significant hardware cost savings.

190

(DOE/ID/13220–T10)

Magnetically controlled deposition of metals using gas

plasma. Quarterly progress report, January 1997–March

1997. Idaho Univ., Moscow, ID (United States). [1997]. 12p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

FG07-93ID13220. Order Number DE97005978. Source:

OSTI; NTIS; INIS; GPO Dep.

Thin layers of secondary material are plated on substrates

either by plating or spraying processes. Plating operations

produce large amounts of hazardous liquid waste. Spraying,

while one of the less waste intensive methods, produces

“over spray,” or waste that is a result of uncontrolled nature

of the spray stream. In many cases the over spray may produce a hazardous waste, requiring special processing.

Spray coating is a mature process with many uses. Material

can be deposited utilizing spraying technology in three basic

ways: “Flame spraying”, direct spraying of molten metals

and/or plasma spraying. This project is directed at controlling the plasma spraying process and thereby minimizing

the waste generated in that process. The proposed process

will utilize a standard plasma spray gun with the addition of

magnetic fields to focus and control the plasma. In order to

keep development cost at a minimum, the project was organized in phases. The first and current phase involves

developing an analytical model that will prove the concept

and be used to design a prototype. Analyzing the process

and using the analysis has the potential to generate significant hardware cost savings.

191

(DOE/ID/13220–T11)

Magnetically controlled deposition of metals using gas

plasma. Quarterly progress report, April–June 1997.

Idaho Univ., Moscow, ID (United States). Coll. of Engineering. [1997]. 10p. Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract FG07-93ID13220. Order Number

DE97007318. Source: OSTI; NTIS; INIS; GPO Dep.

The objective of the grant is to develop a method of

spraying materials on a substrate in a controlled manner to

eliminate the waste inherent in present plating processes.

The process under consideration is magnetically controlled

plasma spraying. As noted in the last several quarterly reports, the project is no longer on schedule. Difficulties with

modeling compressible flow caused a slip in the schedule.

The field equations have been cast in a format that allows

solution using Finite Element (FE) techniques. The development of the computer code that will allow evaluation of the

proposed technique and design of an experiment to prove

the proposed process is complete. Work last quarter was

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

centered on validating the magnetic field equation and developing the mesh for the final plasma torch flow problem.

Results of a test problem used to validate the magnetic calculation were included with the second quarterly report in

1997. The effort this quarter focused on running the actual

plasma spray model on the finite element code, and developing a stand alone code (SPRAY.for) that will be used to

calculate the trajectory of the particles used for plating the

substrate.

192

(DOE/ID/13220–T13)

Magnetically controlled deposition of metals using gas

plasma. Final report. Idaho Univ., Moscow, ID (United

States). Coll. of Engineering. 2 Apr 1998. 38p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract FG07-93ID13220. Order

Number DE98005144. Source: OSTI; NTIS; GPO Dep.

This is the first phase of a project that has the objective to

develop a method of spraying materials on a substrate in a

controlled manner to eliminate the waste and hazardous

material generation inherent in present plating processes.

The project is considering plasma spraying of metal on a

substrate using magneto-hydrodynamics to control the

plasma/metal stream. The process being developed is considering the use of commercially available plasma torches to

generate the plasma/metal stream. The plasma stream is

collimated, and directed using magnetic forces to the extent

required for precise control of the deposition material. The

project will be completed in phases. Phase one of the

project, the subject of this grant, is the development of an

analytical model that can be used to determine the feasibility

of the process and to design a laboratory scale demonstration unit. The contracted time is complete, and the research

is still continuing. This report provides the results obtained

to date. As the model and calculations are completed those

results will also be provided. This report contains the results

of the computer code that have been completed to date. Results from a ASMEE Benchmark problem, flow over a

backward step with heat transfer, Couette flow with magnetic forces, free jet flow are presented along with several

other check calculations that are representative of the cases

that were calculated in the course of the development process. The final cases that define a velocity field in the exit of

a plasma spray torch with and without a magnetic field are

in process. A separate program (SPRAY) has been developed that can track the plating material to the substrate and

describe the distribution of the material on the substrate.

When the jet calculations are complete SPRAY will be used

to compare the distribution of material on the substrate with

and without the effect of the magnetic focus.

193

(DOE/ID/13223–T12)

Task 7: Die soldering during host site testing. Final report, January1–December 31, 1997. Goodwin, F.E.

(International Lead Zinc Research Organization, Inc., Research Triangle Park, NC (United States)); Walkington, W.G.

International Lead Zinc Research Organization, Research

Triangle Park, NC (United States). 31 Jan 1998. 35p. Sponsored by USDOE Office of Environmental Management,

Washington, DC (United States). DOE Contract AC07-

94ID13223. Order Number DE98004395. Source: OSTI;

NTIS; GPO Dep.

To provide industrial confirmation of laboratory results produced in Task 6 of this project, five industrial trials were

organized with cooperative die casters in the USA. Components cast during these trials ranged from functional

electronic heat sinks to decorative household plumbing components. Whereas laboratory work indicated that die

temperature and draft angle were the most important process factors influencing solder accumulation, it was not

possible to vary draft angle on the established production

dies used for these trials. Substantial variations in die temperature were realized however and also die surface

conditions were varied, confirming the influence of a secondary variable in the laboratory investigation. Substantial

evidence from the trials indicated that die surface temperature is the most important factor for controlling solder build

up. The surface roughness of the die casting die greatly influenced the number of castings that could be run before

solder initially appeared. Development of careful thermal

management techniques, now judged to be beyond the capabilities of most US die casters, will be necessary to

control incidences of die soldering found in typical production. Thermal control will involve both control of the bulk die

temperature through use of thermally controlled cooling

lines, and also regulation of surface temperature by well

controlled cooling lines, and also regulation of surface temperature by well controlled die spraying (lubrication)

techniques. Further research, development and technology

transfer to enhance thermal control capabilities of US die

casters is recommended.

194

(DOE/ID/13450–T1)

Precision agriculture in the 21st Century: Geospatial

and information technologies in crop management. Department of Agriculture, Washington, DC (United States).

1997. 127p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States);Department

of Agriculture, Washington, DC (United States). DOE Contract AI07-96ID13450. Source: National Academy Press,

2101 Constitution Avenue, N.W., Lockbox 285, Washington,

DC 20055, (United States); (800) 624-6242 or (202) 334-

3313 (in the Washington metropolitan area).

Agricultural managers have for decades taken advantage

of new technologies, including information technologies, that

enabled better management decision making and improved

economic efficiency of operations. The extent and rate of

change now occurring in the development of information

technologies have opened the way for significant change in

crop production management and agricultural decision making. This vision is reflected in the concept of precision

agriculture. Precision agriculture is a phrase that captures

the imagination of many concerned with the production of

food, feed, and fiber. The concepts embodied in precision

agriculture offer the promise of increasing productivity while

decreasing production costs and minimizing environmental

impacts. Precision agriculture conjures up images of farmers

overcoming the elements with computerized machinery that

is precisely controlled via satellites and local sensors and

using planning software that accurately predicts crop

development. This image has been called the future of agriculture. Such high-tech images are engaging. Precision

agriculture, however, is in early and rapidly changing phases

of innovation. Techniques and practices not anticipated by

the committee will likely become common in the future, and

some techniques and practices thought to hold high promise

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

today may turn out to be less desirable than anticipated.

This report defines precision agriculture as a management

strategy that uses information technologies to bring data

from multiple sources to bear on decisions associated with

crop production. Precision agriculture has three components:

capture of data at an appropriate scale and frequency, interpretation and analysis of that data, and implementation of a

management response at an appropriate scale and time.

The most significant impact of precision agriculture is likely

to be on how management decisions address spatial and

temporal variability in crop production systems.

195

(DOE/ID/13462–T2)

The greenhouse of the future: Using a sponsored competition in a capstone course. Bates, R.M.; Baumbauer,

D. Montana State Univ., Bozeman, MT (United States). 18

Feb 1998. 10p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE

Contract FG07-96ID13462. Order Number DE98003238.

Source: OSTI; NTIS; GPO Dep.

Educational objectives of capstone courses such as

critical-thinking and problem-solving skills are among the

most cited needs in curriculum revitalization efforts. Sponsored competitions present an important vehicle for

achieving these educational objectives. Opportunities such

as the Greenhouse of the Future Competition provide students a diverse range of critical experiences not easily

simulated in traditional classroom settings. The objective of

the competition was to provide an opportunity for US university students to conceptualize, design, integrate, fabricate,

and demonstrate innovative greenhouse or controlled environment ideas. The students achieved a great sense of

accomplishment and satisfaction by converting their ideas

into proposals, developing proposals into experiments,

tracking the data generated by the experiments and translating that data into a meaningful communication locally and to

the scientific community at large. Most of these important

learning experiences would have remained as components

of the project even if the team had not advanced as the winning entry.

196

(DOE/ID/13505–T1)

Report for slot cutter proof-of-principle test, Buried

Waste Containment System project. Revision 1. RAHCO

International, Inc., Spokane, WA (United States). 21 May

1998. 80p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract AC07-97ID13505. Order Number DE98007207.

Source: OSTI; NTIS; INIS; GPO Dep.

Several million cubic feet of hazardous and radioactive

waste was buried in shallow pits and trenches within many

US Department of Energy (US DOE) sites. The pits and

trenches were constructed similarly to municipal landfills

with both stacked and random dump waste forms such as

barrels and boxes. Many of the hazardous materials in

these waste sites are migrating into groundwater systems

through plumes and leaching. On-site containment is one of

the options being considered for prevention of waste migration. This report describes the results of a proof-of-principle

test conducted to demonstrate technology for containing

waste. This proof-of-principle test, conducted at the RAHCO

International, Inc., facility in the summer of 1997, evaluated

equipment techniques for cutting a horizontal slot beneath

an existing waste site. The slot would theoretically be used

by complementary equipment designed to place a cement

barrier under the waste. The technology evaluated consisted

of a slot cutting mechanism, muck handling system, thrust

system, and instrumentation. Data were gathered and analyzed to evaluate the performance parameters.

197

(DOE/ID/13507–T1)

Greenhouse of the future. Final report. Cavin, B. III. Cal

Poly Pomona Foundation, Pomona, CA (United States). 3

Jul 1998. 47p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE

Contract FG07-97ID13507. Order Number DE98007026.

Source: OSTI; NTIS; GPO Dep.

This greenhouse of the future is located at the Center for

Regenerative Studies (CRS) at Cal Poly Pomona. The building design was driven by desired environmental conditions.

The primary objective was to keep the interior space warm

during winter for the breeding of fish and other greenhouse

activities, especially in the winter. To do this, a highly insulating envelope was needed. Straw bales provide excellent

insulation with an R-value of approximately 50 and also help

solve the environmental problems associated with this agricultural waste product. A summary of the construction

progress, construction costs and operating costs are included.

198

(DOE/LLW–245)

The basics in transportation of low-level radioactive

waste. Allred, W.E. Lockheed Martin Idaho Technologies

Co., Idaho Falls, ID (United States). Jun 1998. 30p. Sponsored by USDOE Office of Environmental Management,

Washington, DC (United States). DOE Contract AC07-

94ID13223. Order Number DE98058449. Source: OSTI;

NTIS; INIS; GPO Dep.

This bulletin gives a basic understanding about issues

and safety standards that are built into the transportation

system for radioactive material and waste in the US. An excellent safety record has been established for the transport

of commercial low-level radioactive waste, or for that matter,

all radioactive materials. This excellent safety record is primarily because of people adhering to strict regulations

governing the transportation of radioactive materials. This

bulletin discusses the regulatory framework as well as the

regulations that set the standards for packaging, hazard

communications (communicating the potential hazard to

workers and the public), training, inspections, routing, and

emergency response. The excellent safety record is discussed in the last section of the bulletin.

199

(DOE/LLW–246)

Life cycle costs for disposal and assured isolation of

low-level radioactive waste in Connecticut. Chau, B.;

Sutherland, A.A.; Baird, R.D. Rogers and Associates Engineering Corp., Salt Lake City, UT (United States). Mar 1998.

106p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC07-94ID13223. Order Number DE98054115. Source:

OSTI; NTIS; INIS; GPO Dep.

This document presents life cycle costs for a low-level

radioactive disposal facility and a comparable assured isolation facility. Cost projections were based on general plans

47
ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

and assumptions, including volume projections and operating life, provided by the Connecticut Hazardous Waste

Management Service, for a facility designed to meet the

State’s needs. Life cycle costs include the costs of preconstruction activities, construction, operations, closure, and

post-closure institutional control. In order to provide a better

basis for understanding the relative magnitude of near-term

costs and future costs, the results of present value analysis

of ut-year costs are provided.

200

(DOE/LLW–250a-Vol.1)

Licensing an assured isolation facility for low-level radioactive waste. Volume 1: Licensing strategy and

issues. Silverman, D.J. (Morgan, Lewis and Bockius, Washington, DC (United States)); Bauser, M.A.; Baird, R.D.

Morgan, Lewis and Bockius, Washington, DC (United

States);Rogers and Associates Engineering Corp., Salt Lake

City, UT (United States). Jul 1998. 29p. Sponsored by USDOE Office of Environmental Management, Washington, DC

(United States). DOE Contract AC07-94ID13223. Order

Number DE98058448. Source: OSTI; NTIS; INIS; GPO Dep.

This report provides a detailed set of proposed criteria

and guidance for the preparation of a license application for

an assured isolation facility (AIF). The report is intended to

provide a detailed planning basis upon which a prospective

applicant may begin pre-licensing discussions with the Nuclear Regulatory Commission and initiate development of a

license application. The report may also be useful to the

NRC or to state regulatory agencies that may be asked to

review such an application. Volume 1 of this report provides

background information, and describes the licensing

approach and methodology. Volume 2 identifies specific information that is recommended for inclusion in a license

application.

201

(DOE/LLW–250b.Vol.2)

Licensing an assured isolation facility for low-level radioactive waste. Volume 2: Recommendations on the

content and review of an application. Silverman, D.J.

(Morgan, Lewis and Bockius, Washington, DC (United

States)); Bauser, M.A.; Baird, R.D. Morgan, Lewis and

Bockius, Washington, DC (United States);Rogers and Associates Engineering Corp., Salt Lake City, UT (United

States). Jul 1998. [250p.] Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract AC07-94ID13223. Order Number

DE98007459. Source: OSTI; NTIS; INIS; GPO Dep.

This report provides a detailed set of proposed criteria

and guidance for the preparation of a license application for

an assured isolation facility (AIF). The report is intended to

provide a detailed planning basis upon which a prospective

applicant may begin pre-licensing discussions with the Nuclear Regulatory Commission and initiate development of a

license application. The report may also be useful to the

NRC or to state regulatory agencies that may be asked to

review such an application. Volume 1 of this report provides

background information, and describes the licensing

approach and methodology. Volume 2 identifies specific information that is recommended for inclusion in a license

application.

202

(DOE/LLW–98052630)

LLW Forum meeting report, May 7–9, 1997. Norris, C.;

Brown, H. (eds.); Lovinger, T.; Scheele, L.; Shaker, M.A.

Afton Associates, Inc., Washington, DC (United States).

[1997]. 12p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE

Contract AC07-94ID13223. (CONF-9705249–: Low-level radioactive waste forum meeting, Chicago, IL (United States),

7-9 May 1997). Order Number DE98052630. Source: OSTI;

NTIS; INIS; GPO Dep.

The Low-Level Radioactive Waste Forum met in Chicago,

Illinois, on may 7–9, 1997. Twenty-three Forum Participants,

Alternate Forum Participants, and meeting designees representing 20 compacts and states participated. A report on the

meeting is given under the following subtitles: New developments in states and compacts; Upgrading an existing

disposal facility; Revisions to DOE Order 5820 re DOE

waste management; Conference of radiation control program directors: Recent and upcoming activities; National

Conference of State Legislatures’ (NCSL) low-level radioactive waste working group: Recent and upcoming activities;

Executive session; LLW forum business session; Public involvement and risk communication: Success at West Valley,

New York; DOE low-level waste management program; impact of the International Atomic Energy Agency’s convention

on waste; Panel discussion: The environmental justice

concept–Past, present and future; New technologies for processing and disposal of LLRW; High-level and low-level

radioactive waste: A dialogue on parallels and intersections;

Draft agreement re uniform application of manifesting procedures; Regulatory issues focus; LLW forum October 1997

agenda planning; Resolutions; LLW forum regulatory issues

discussion group meets; and Attendance.

203

(DOE/LLW–98052631)

LLW Forum meeting report, October 20–22, 1997. Norris,

C.; Brown, H. (eds.); Lovinger, T.; Scheele, L.; Shaker, M.A.

Afton Associates, Inc., Washington, DC (United States).

[1997]. 12p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE

Contract AC07-94ID13223. (CONF-9710189–: Low-level radioactive waste forum meeting, Annapolis, MD (United

States), 20-22 Oct 1997). Order Number DE98052631.

Source: OSTI; NTIS; INIS; GPO Dep.

The Low-Level Radioactive Waste Forum met in Annapolis, Maryland, on October 20–22, 1997. Twenty-six Forum

Participants, Alternate Forum Participants, and meeting designees representing 22 compacts and states participated. A

report on the meeting is given under the following subtitles:

New developments in states and compacts; Discussion with

NRC Commissioner McGaffigan; Regulatory issues session;

Executive session; LLW forum business session; DOE lowlevel waste management program; Transportation of

radioactive waste; Environmental equity: Title VI; Congressional studies on Ward Valley Site; Implementation of DOE’s

strategy for waste management; Relicensing Envirocare;

Draft agreement for uniform application of manifesting

procedures; CRCPD report; Panel: Future of low-level radioactive waste management; Agenda planning: February

1998; Resolutions; and Attendance.

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

204

(DOE/LLW–98052641)

LLW Notes, Volume 12, Number 8. Norris, C.; Brown, H.

(eds.); Gedden, R.; Lovinger, T.; Scheele, L.; Shaker, M.A.

Afton Associates, Inc., Washington, DC (United States). Win

1997. 44p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract AC07-94ID13223. Order Number DE98052641.

Source: OSTI; NTIS; INIS; GPO Dep.

Contents include articles entitled: Chem-Nuclear documents new plan for Barnwell; Nebraska releases technical

analysis of LLRW facility; Southeast Compact suspends

funding for NC facility development; NC governor and

Southeast Compact differ on proposed MOU; Midwest Compact to return export fees; State legislators’ group revises

radioactive waste policy; Internal documents discuss administration’s policy on Ward Valley; BLM issues EA for Ward

Valley testing; California DHS, NRC criticize DOI’s testing

protocols; Army removes training mines from Ward Valley

site; The 1997 gubernatorial elections and a look ahead to

1998; Court throws out case challenging Pennsylvania’s siting law; DOE files notice of appeal in WCS suit; Central

Compact moves to dismiss “Veto” authority suit; Congress

exempts NAS from FACA; Judge sets schedule for Ward

Valley case; Court won’t order DOE to accept spent fuel by

deadline; NRC chairman expresses concern re CERCLA

reauthorization; Senators question EPA’s guidance on

remediation; EPA issues guidance, criticizes NRC decommissioning rule; Members of Congress clarify FUSRAP

transfer; HLW legislation passes House by wide margin; Takings legislation passes House; Energy and water bill signed

into law; and Senate confirms 5 of 6 DOE appointees.

205

(DOE/LLW–98052642)

LLW Notes, Volume 12, Number 9. Norris, C.; Brown, H.

(eds.); Gedden, R.; Lovinger, T. Afton Associates, Inc.,

Washington, DC (United States). Dec 1997. 24p. Sponsored

by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract AC07-94ID13223.

Order Number DE98052642. Source: OSTI; NTIS; INIS;

GPO Dep.

Contents include articles entitled: Senators criticize DOE

use of Envirocare and Molten Metal; Officials express concern re implications of WCS ruling; DOE files notice of

appeal in WCS suit; WCS responds to critics re implications

of ruling; Background: Prior correspondence between the

Senators and DOE re Envirocare; Waste control specialists

authorized to conduct additional operations at Texas site;

Molten Metal files for bankruptcy protection; Envirocare of

Texas receives first approval for hazardous waste permit;

Envirocare of Utah applies to NRC for SNM license; NRDC

alleges death threats and financial intimidation by Envirocare; DOE and NRC sign off on external regulation pilot

program; and NRDC requests Inspector General probe re

Envirocare.

206

(DOE/LLW–98056089)

LLW (Low-Level Waste) Notes, Volume 13, Number 1,

February 1998. Afton Associates, Inc., Washington, DC

(United States). Feb 1998. 44p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States). DOE Contract AC07-94ID13223. Order Number

DE98056089. Source: OSTI; NTIS; INIS; GPO Dep.

LLW Notes is a newsletter distributed to Low-Level Radioactive Waste Forum Participants and other state and

compact officials. The LLW Forum provides an opportunity

for state and compact officials to share information with one

another and to exchange views with officials of federal

agencies and other interested parties. This issue focuses on

the following topics: DOI approves Ward Valley permit application; Project evidentiary hearings begin in Texas; and

Summary judgment motions in California breach of contract

action.

207

(DOE/MC/29112–5399)

Intelligent mobile sensor system for drum inspection

and monitoring: Topical report, October 1, 1993–April

22, 1995. Lockheed Martin Astronautics, Littleton, CO

(United States). [1997]. 103p. Sponsored by USDOE Office

of Environmental Management, Washington, DC (United

States). DOE Contract AC21-92MC29112. Order Number

DE97002136. Source: OSTI; NTIS; INIS; GPO Dep.

The objective of the Intelligent Mobile Sensor System

(IMSS) project is to develop an operational system for monitoring and inspection activities for waste storage facility

operations at several DOE sites. Specifically, the product of

this effort is a robotic device with enhanced intelligence and

maneuverability capable of conducting routine inspection of

stored waste drums. The system has an integrated sensor

suite for problem-drum detection, and is linked to a site database both for inspection planning and for data correlation,

updating, and report generation. The system is capable of

departing on an assigned mission, collecting required data,

recording which portions of its mission had to be aborted or

modified due to environmental constraints, and reporting

back when the mission is complete. Successful identification

of more than 96% of drum defects has been demonstrated

in a high fidelity waste storage facility mockup. Identified

anomalies included rust spots, rust streaks, areas of corrosion, dents, and tilted drums. All drums were positively

identified and correlated with the site database. This development effort is separated into three phases of which phase

two is now complete. The second phase demonstrated a

prototype system appropriate for operational use in an actual storage facility. The prototype provides an integrated

design that considers operational requirements, hardware

costs, maintenance, safety, and robustness. The final phase

will demonstrate commercial viability using the prototype vehicle in a pilot waste operations and inspection project. This

report summarizes the design and evaluation of the new

IMSS Phase 2 system and vehicle. Several parts of the

IMSS Phase 1 Topical (Final) Report, which describes the

requirements, design guidelines, and detailed design of the

Phase 1 IMSS vehicle, are incorporated here, with modifications to reflect the changes in the design and the new

elements added during the Phase 2 work.

208

(DOE/MC/29113–5599)

Interactive Computer-Enhanced Remote Viewing System (ICERVS): Final report, November 1994–September

1996. Mechanical Technology, Inc., Latham, NY (United

States). [1997]. 241p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States).

DOE Contract AC21-92MC29113. Order Number

DE97002246. Source: OSTI; NTIS; INIS; GPO Dep.

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

The Interactive Computer-Enhanced Remote Viewing

System (ICERVS) is a software tool for complex threedimensional (3-D) visualization and modeling. Its primary

purpose is to facilitate the use of robotic and telerobotic systems in remote and/or hazardous environments, where

spatial information is provided by 3-D mapping sensors.

ICERVS provides a robust, interactive system for viewing

sensor data in 3-D and combines this with interactive geometric modeling capabilities that allow an operator to

construct CAD models to match the remote environment.

Part I of this report traces the development of ICERVS

through three evolutionary phases: (1) development of firstgeneration software to render orthogonal view displays and

wireframe models; (2) expansion of this software to include

interactive viewpoint control, surface-shaded graphics, material (scalar and nonscalar) property data, cut/slice planes,

color and visibility mapping, and generalized object models;

(3) demonstration of ICERVS as a tool for the remediation of

underground storage tanks (USTs) and the dismantlement of

contaminated processing facilities. Part II of this report

details the software design of ICERVS, with particular emphasis on its object-oriented architecture and user interface.

209

(DOE/MC/29467–5670)

Decontamination systems information and research

programs. Quarterly report, July 1–August 31, 1996.

West Virginia Univ. Research Corp., Morgantown, WV

(United States). [1997]. 519p. Sponsored by USDOE Office

of Environmental Management, Washington, DC (United

States). DOE Contract FC21-92MC29467. Order Number

DE97052831. Source: OSTI; NTIS; GPO Dep.

The US contains numerous hazardous waste sites. Many

sites are on private land near operating units of various

companies. An effort is being made to determine the conditions under which such sites can be remediated voluntarily.

The objective of the project will be to first assess the interest

and willingness of industry in the Kanawha River Valley, WV

to participate in discussions that would lead toward voluntary cleanup activities. The second will be to implement the

activities agreed upon by the interested parties. The project

will first involve individual discussions with the industrial,

government, and other organized groups in the area. These

discussions will help determine the feasibility of organizing

voluntary efforts. If the discussions indicate that conditions

may be favorable for developing individual or group voluntary

cleanup projects, a working group will be convened to establish the environmental goals of the project as well as the

technical approach for achieving those goals. The projects

for the 1996 WVU Cooperative Agreement are categorized

into three task focus areas: Task 1.0 Contaminant Plume

Containment and Remediation, Task 2.0 Cross Cutting Innovative Technologies, and Task 3.0 Small Business Support

Program. Summaries of the accomplishments for the subtasks reporting under these categories during the third

quarter, 1 July 96 through 30 September 96, are presented.

210

(DOE/MC/30164–97/C0816)

Progress of electro-hydraulic scabbling technology for

concrete decontamination. Goldfarb, V.; Gannon, R. Textron, Inc., Wilmington, MA (United States). [1997]. 4p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC21-93MC30164. (CONF-9610231–14: Conference on industry partnerships to deploy environmental technology,

Morgantown, WV (United States), 22-24 Oct 1996). Order

Number DE97052256. Source: OSTI; NTIS; INIS; GPO Dep.

Concrete decontamination from organics, metals, and radionuclides requires removal of up to one inch of the

surface layer. The Electro- Hydraulic Scabbling (EHS) technique has been developed within a 3- phase program. A

prototype 8 kW EHS unit was designed and assembled in

Phase II. This system was tested initially by scabbling noncontaminated concrete, and later at the DOE Fernald site

where a concrete floor containing uranium was decontaminated. In the latter test, the unit operated without problems

and reduced the counts per minute by more than 90%. Currently in Phase III, a larger 30 kW unit has been assembled

and prepared for testing/demonstration.

211

(DOE/MC/30171–5710)

Recycle of contaminated scrap metal, comprehensive

executive summary. Final report, September 30, 1993–

March 31, 1996. Molten Metal Technology, Inc., Waltham,

MA (United States). [1997]. 81p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States). DOE Contract AC21-93MC30171. Order Number

DE97005431. Source: OSTI; NTIS; GPO Dep.

R&D activities have demonstrated Catalytic Extraction

Processing (CEP) to be a robust, one-step process process

that is relatively insensitive to wide variations in waste composition and is applicable to a broad spectrum of DOE

wastes. The feed size and composition compatible with CEP

have been increased in a short period of time, and additional R&D should lead to the ability to accept a drum (and

larger?) size feed of completely uncharacterized waste. Experiments have validated the CPU (Catalytic Processing

Unit). Two commercial facilities have been commissioned

and are currently processing mixed low level wastes. Expansion of CEP to transuranic and high level wastes should be

the next step in the development and deployment of CEP

for recycle, reuse, and disposal of materials from DOE decontamination and decommissioning activities.

212

(DOE/MC/30172–97/C0803)

Characterization of pipes, drain lines, and ducts using

the pipe explorer system. Cremer, C.D.; Kendrick, D.T.;

Cramer, E. Science and Engineering Associates, Inc., Albuquerque, NM (United States). [1997]. 17p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract AC21-93MC30172.

(CONF-9610231–3: Conference on industry partnerships to

deploy environmental technology, Morgantown, WV (United

States), 22-24 Oct 1996). Order Number DE97052243.

Source: OSTI; NTIS; INIS; GPO Dep.

As DOE dismantles its nuclear processing facilities, site

managers must employ the best means of disposing or remediating hundreds of miles of potentially contaminated

piping and duct work. Their interiors are difficult to access,

and in many cases even the exteriors are inaccessible.

Without adequate characterization, it must be assumed that

the piping is contaminated, and the disposal cost of buried

drain lines can be on the order of $1,200/ft and is often unnecessary as residual contamination levels often are below

free release criteria. This paper describes the program to

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

develop a solution to the problem of characterizing radioactive contamination in pipes. The technical approach and

results of using the Pipe Explorer  system are presented.

The heart of the system is SEA’s pressurized inverting

membrane adapted to transport radiation detectors and

other tools into pipes. It offers many benefits over other pipe

inspection approaches. It has video and beta/gamma detection capabilities, and the need for alpha detection has been

addressed through the development of the Alpha Explorer.

These systems have been used during various stages of decontamination and decommissioning of DOE sites, including

the ANL CP-5 reactor D&D. Future improvements and extensions of their capabilities are discussed.

213

(DOE/MC/30174–97/C0784)

Rapid surface sampling and archival record system

(RSSAR). Barren, E. (and others); Bracco, A.; Dorn, S.B.

General Electric Co., Schenectady, NY (United States). Corporate Research and Development Center. [1997]. 12p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC21-93MC30174. (CONF-970113–3: Field analytical methods for hazardous wastes and toxic chemicals conference,

Las Vegas, NV (United States), 29-31 Jan 1997). Order

Number DE97051970. Source: OSTI; NTIS; INIS; GPO Dep.

Purpose is to develop a rapid surface (concrete, steel)

contamination measurement system that will provide a

“quick-look” indication of contamination areas, an archival

record, and an automated analysis. A bulk sampling oven is

also being developed. The sampling device consists of a

sampling head, a quick look detector, and an archiving

system (sorbent tube). The head thermally desorbs semivolatiles, such as PCBs, oils, etc., from concrete and steel

surfaces; the volatilized materials are passed through a

quick-look detector. Sensitivity of the detector can be attenuated for various contaminant levels. Volatilized materials are

trapped in a tube filled with adsorbent. The tubes are housed

in a magazine which also archives information about sampling conditions. Analysis of the tubes can be done at a later

date. The concrete sampling head is fitted with a tungstenhalogen lamp; in laboratory experiments it has extracted

model contaminants by heating the top 4mm of the surface

to 250 C within 100-200 s. The steel sampling head has

been tested on different types of steels and has extracted

model contaminants within 30 s. A mathematical model of

heat and mass transport in concrete has been developed.

Rate of contaminant removal is at maximum when the moisture content is about 100 kg/m3. The system will be useful

during decontamination and decommissioning operations.

214

(DOE/MC/30174–5551)

Rapid Surface Sampling and Archival Record (RSSAR)

System. Topical report, October 1, 1993–December 31,

1994. General Electric Co., Schenectady, NY (United

States). Corporate Research and Development Center.

[1997]. 146p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract AC21-93MC30174. Order Number DE97002208.

Source: OSTI; NTIS; INIS; GPO Dep.

This report describes the results of Phase 1 efforts to develop a Rapid Surface Sampling and Archival Record

(RSSAR) System for the detection of semivolatile organic

contaminants on concrete, transite, and metal surfaces. The

characterization of equipment and building surfaces for the

presence of contaminants as part of building decontamination and decommissioning activities is an immensely large

tacks of concern to both government and industry. Contaminated and clean materials must be clearly identified and

segregated so that the clean materials can be recycled or

reused, if possible, or disposed of more cheaply as nonhazardous waste. Characterization of building and equipment

surfaces will be needed during initial investigations, during

cleanup operations, and during the final confirmatory process, increasing the total number of samples well beyond

that needed for initial characterization. This multiplicity of information places a premium on the ability to handle and

track data as efficiently as possible. Aware of the shortcomings of traditional surface characterization technology, GE,

with DOE support has undertaken a 12-month effort to complete Phase 1 of a proposed four-phase program to develop

the RSSAR system. The objectives of this work are to provide instrumentation to cost-effectively sample concrete and

steel surfaces, provide a quick-look indication for the presence or absence of contaminants, and collect samples for

later, more detailed analysis in a readily accessible and addressable form. The Rapid Surface Sampling and Archival

Record (RSSAR) System will be a modular instrument made

up of several components: (1) sampling heads for concrete

surfaces, steel surfaces, and bulk samples; (2) quick-look

detectors for photoionization and ultraviolet; (3) multisample

trapping module to trap and store vaporized contaminants in

a manner suitable for subsequent detailed lab-based analyses.

215

(DOE/MC/30175–5315)

Portable sensor for hazardous waste. Topical report,

October 1, 1993–September 30, 1994. Physical Sciences,

Inc., Andover, MA (United States). [1997]. 72p. Sponsored

by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract AC21-93MC30175.

Order Number DE97002063. Source: OSTI; NTIS; INIS;

GPO Dep.

The authors describe an innovative technique to detect

hazardous materials at sub part-per-billion levels. The approach exploits active nitrogen energy-transfer (ANET) to

excite atomic and molecular fluorescence characteristic of

various hazardous species. ANET excitation is very state

specific, generating simple spectra that are easily detected

with instrumentation of modest resolution. Typical spectral

features include 254 nm emission from Hg, 388 and 420 nm

emission from CN when organics are sampled, and 278 nm

emission from CCl when chlorinated organics are sampled.

They also observe several broadbands between 450 and

540 nm where uranium compounds are added to the D-B

discharge region. They attribute this spectrum to electronic

transitions of uranium oxide, probably UO. Additionally, they

have used ANET to detect a number of heavy metals such

as Cr, Se, Cd, Pb, and Cu. Dielectric-barrier (D-B) discharge

technology generates the active nitrogen. This approach

affords atmospheric-pressure operation, fluorescence excitation in gaseous, particulate, and aqueous sample matrices,

and is amenable to field operation because the discharge

and associated electronics are compact and can be powered by 12V batteries. This report details the results of the

first phase of a three and a half year program designed to

develop a portable monitor for sensitive hazardous waste

detection. The ultimate goal of the program is to develop the

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

concept to the prototype instrument level. In this first phase

they have demonstrated the applicability of the ANET

technology to a variety of hazardous species, and have determined detection sensitivity limits for Hg, Se, organics, and

chlorinated organics to be at part-per-billion levels or below.

216

(DOE/MC/30359–1)

Commercialization plan laser-based decoating systems.

Freiwald, J.; Freiwald, D.A. F2 Associates, Inc., Albuquerque, NM (United States). Jan 1998. 46p. Sponsored by

USDOE Assistant Secretary for Fossil Energy, Washington,

DC (United States);USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AR21-94MC30359. Order Number DE98054524. Source:

OSTI; NTIS; INIS; GPO Dep.

F2 Associates Inc. (F2) is a small, high-technology firm focused on developing and commercializing environmentally

friendly laser ablation systems for industrial-rate removal of

surface coatings from metals, concrete, and delicate substrates such as composites. F2 has a contract with the US

Department of Energy Federal Energy Technology Center

(FETC) to develop and test a laser-based technology for removing contaminated paint and other contaminants from

concrete and metal surfaces. Task 4.1 in Phase 2 of the

Statement of Work for this DOE contract requires that F2

“document its plans for commercializing and marketing the

stationary laser ablation system. This document shall include a discussion of prospects for commercial customers

and partners and may require periodic update to reflect

changing strategy. This document shall be submitted to the

DOE for review.” This report is being prepared and submitted in fulfillment of that requirement. This report describes

the laser-based technology for cleaning and coatings removal, the types of laser-based systems that have been

developed by F2 based on this technology, and the various

markets that are emerging for this technology. F2’s commercialization and marketing plans are described, including how

F2’s organization is structured to meet the needs of technology commercialization, F2’s strategy and marketing

approach, and the necessary steps to receive certification

for removing paint from aircraft and DOE certification for D

and D applications. The future use of the equipment built for

the DOE contract is also discussed.

217

(DOE/MC/31179–5309)

Environmental management technology leveraging initiative. Topical report, October 1994–September 1995.

Global Environment and Technology Foundation, Annandale, VA (United States). [1997]. 36p. Sponsored by USDOE

Office of Environmental Management, Washington, DC

(United States). DOE Contract FC21-94MC31179. Order

Number DE97002049. Source: OSTI; NTIS; GPO Dep.

The deployment of innovative DOE-EM technologies

could provide more cost-effective treatments than remediation technologies and methods currently in use. By building

partnerships between the public and private sectors, the

technological expertise of federal researchers and engineers

and the commercial incentive of industrialists and other nongovernment interests can combine to help move these

technologies “off the shelf’ and toward use at contaminated

sites. The GETE approach to achieving this end is: (1) to

develop a process which identifies and assesses DOEdeveloped technologies from the perspective of commercial

marketability; assists in bringing these technologies to the

attention of the private sector; and aids, if necessary, in

business planning and start-up activities, (2) to establish a

state-of-the-art electronic communications system, the

Global Network of Environment & Technology (GNET), to

disseminate information on DOE-developed technologies, as

well as information on capital and financing availability,

regulatory matters, and commercialization objectives to potential business partners and others, and (3) to undertake

public participation and outreach activities designed to address barrier reduction and public acceptance issues.

218

(DOE/MC/31185–5375)

Development of the integrated, in-situ remediation technology. Topical report for tasks No. 8 and No. 10

entitled: Laboratory and pilot scale experiments of

Lasagna process, September 26, 1994–May 25, 1996.

Ho, Sa V. (and others); Athmer, C.J.; Sheridan, P.W. Monsanto Co., St. Louis, MO (United States). [1997]. 71p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AR21-94MC31185. Order Number DE97002150. Source:

OSTI; NTIS; INIS; GPO Dep.

Contamination in low permeability soils poses a significant

technical challenge to in-situ remediation efforts. Poor accessibility to the contaminants and difficulty in delivery of

treatment reagents have rendered existing in-situ treatments

such as bioremediation, vapor extraction, pump and treat

rather ineffective when applied to low permeability soils

present at many contaminated sites. This technology is an

integrated in-situ treatment in which established geotechnical methods are used to install degradation zones directly in

the contaminated W and electro-osmosis is utilized to move

the contaminants back and forth through those zones until

the treatment is completed. This topical report summarizes

the results of the lab and pilot sized Lasagna experiments

conducted at Monsanto. Experiments were conducted with

kaofinite and an actual Paducah soil in units ranging from

bench-scale containing kg-quantity of soil to pilot-scale containing about half a ton of soil having various treatment zone

configurations. The obtained data support the feasibility of

scaling up this technology with respect to electrokinetic parameters as well as removal of organic contaminants. A

mathematical model was developed that was successful in

predicting the temperature rises in the soil. The information

and experience gained from these experiments along with

the modeling effort enabled us to successfully design and

operate a larger field experiment at a DOE TCEcontaminated clay site.

219

(DOE/MC/31185–5388)

Development of an integrated, in-situ remediation

technology. Topical report for task No. 6: lab-scale development of microbial degradation process, September

26, 1994–May 25, 1996. Odom, J.M. (DuPont Central Research & Development, Wilmington, DE (United States)).

Monsanto Co., St. Louis, MO (United States). [1997]. 21p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AR21-94MC31185. Order Number DE97002130. Source:

OSTI; NTIS; INIS; GPO Dep.

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

Contamination in low permeability soils poses a significant

technical challenge to in situ remediation efforts. Poor accessibility to the contaminants and difficulty in delivery of

treatment reagents have rendered existing in situ treatments

such as bioremediation, vapor extraction, and pump and

treat rather ineffective when applied to low permeability soils

present at many contaminated sites. The technology is an

integrated in situ treatment in which established geotechnical methods are used to install degradation zones directly in

the contaminated soil, and electro-osmosis is utilized to

move the contaminants back and forth through those zones

until the treatment is completed. The present Topical Report

for Task No. 6 summarizes the results of a study of the potential for stimulating microbial reductive dehalogenation as

part of the integrated in situ treatment process at the field

experiment test site at DOE’s Gaseous Diffusion Plant in

Paducah, Kentucky. A series of “microcosm bottle tests”

were performed on samples of contaminated soil and

groundwater taken from the Paducah site and spiked with

trichloroethene (TCE). A number of bottles were set up,

each spiked with a different carbon source in order to

enhance the growth of different microbial subpopulations already present within the indigenous population in the soil. In

addition, a series of bottle tests were completed with samples of the granular activated carbon (GAC) treatment zone

material retrieved from the test site during the Paducah field

experiment. In these tests, the GAC samples were used in

place of the soil. Results of the soil-groundwater microcosms yielded a negative indication of the presence of

dechlorinating bacteria at the site. However, charcoal (GAC)

samples from one location in the test plot exhibited marked

dechlorination with conversion of TCE to dichloroethene.

220

(DOE/MC/31185–5389)

Development of an integrated, in-situ remediation technology. Topical report for task No. 5: Cost analysis,

September 26, 1994–May 25, 1996. Quinton, G. (and others); Schultz, D.; Landis, R. Monsanto Co., St. Louis, MO

(United States). [1997]. 36p. Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract AR21-94MC31185. Order Number

DE97002134. Source: OSTI; NTIS; INIS; GPO Dep.

Contamination in low permeability soils poses a significant

technical challenge to in situ remediation efforts. Poor accessibility to the contaminants and difficulty in delivering

treatment reagents have rendered existing in situ treatments

such as bioremediation, vapor extraction, pump and treat

rather ineffective when applied to low permeability soils

present at many contaminated sites. The Lasagna technology is an integrated in situ treatment in which established

geotechnical methods are used to install degradation zones

directly into the contaminated soil and electro-osmosis if utilized to move the contaminants back and forth through

those zones until the treatment is completed. This topical report presents the results of an engineering evaluation and

cost analysis of the vertically configured treatment process

completed by the DuPont Company. The cost evaluation

was prepared by developing a cost optimization model of

the overall treatment process. This model considers various

input parameters such as soil properties, depth of contamination, cost for emplacing electrodes and treatment zones,

required purge water volume, time constraints to achieve

cleanup, and cost of power. Several example cases were

run using the cost model to provide representative cost

ranges for applying the technology to clean up

trichloroethene contamination in clay. These costs are estimated to range from $40 to $95 per cubic yard of soil for a

1-acre site, with cost depending on depth of contamination

(cost range valid from 15 to 45 ft), method of electrode/

treatment zone emplacement (cost range valid from 15 to 45

ft), method of electrode/treatment zone emplacement (cost

range valid for Lasagna Phase I emplacement and optimized emplacement techniques), and time available to

complete remediation (cost range valid for one- and threeyear timeframe).

221

(DOE/MC/31185–5390)

Development of an integrated in-situ remediation technology. Topical report for task No. 12 and 13 entitled:

Large scale field test of the Lasagna process, September 26, 1994–May 25, 1996. Athmer, C.J. (and others); Ho,

Sa V.; Hughes, B.M. Monsanto Co., St. Louis, MO (United

States). [1997]. 139p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States).

DOE Contract AR21-94MC31185. Order Number

DE97002156. Source: OSTI; NTIS; INIS; GPO Dep.

Contamination in low permeability soils poses a significant

technical challenge to in-situ remediation efforts. Poor accessibility to the contaminants and difficulty in delivery of

treatment reagents have rendered existing in-situ treatments

such as bioremediation, vapor extraction, pump and treat

rather ineffective when applied to low permeability soils

present at many contaminated sites. This technology is an

integrated in-situ treatment in which established geotechnical methods are used to instant degradation zones directly

in the contaminated soil and electroosmosis is utilized to

move the contaminants back and forth through those zones

until the treatment is completed. This topical report summarizes the results of the field experiment conducted at the

Paducah Gaseous Diffusion Plant in Paducah, KY. The test

site covered 15 feet wide by 10 feet across and 15 feet

deep with steel panels as electrodes and wickdrains containing granular activated carbon as treatment zone& The

electrodes and treatment zones were installed utilizing innovative adaptation of existing emplacement technologies. The

unit was operated for four months, flushing TCE by electroosmosis from the soil into the treatment zones where it

was trapped by the activated carbon. The scale up from laboratory units to this field scale was very successful with

respect to electrical parameters as weft as electroosmotic

flow. Soil samples taken throughout the site before and after

the test showed over 98% TCE removal, with most samples

showing greater than 99% removal.

222

(DOE/MC/31185–5391)

Development of an integrated, in-situ remediation technology: Task 2–4, electrokinetic modeling. Topical

report, September 26–May 25, 1996. Monsanto Co., St.

Louis, MO (United States). [1997]. 54p. Sponsored by USDOE Office of Environmental Management, Washington, DC

(United States). DOE Contract AR21-94MC31185. Order

Number DE97002135. Source: OSTI; NTIS; INIS; GPO Dep.

This report summarizes the work conducted in Tasks 2-4,

which together make up the Electrokinetic Modeling carried

out in this project. The modeling was divided into three main

sections: thermal analysis, chemical species transport, and

53
ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

electrode geometry and soil heterogeneity issues. The thermal modeling consisted of development of the governing

equations to incorporate Joule heating associated with

electro-osmosis, heat conduction and convection, and temperature dependencies of electrical conductivity and

electro-osmotic permeability. To model the transport of

chemical species in the LasagnaTM process, a onedimensional model was developed. This model is based on

previous models, but includes additional mechanism to account for charge transfer in the double layer, pH buffering of

the soil, and zeta potential dependency on pH and ionic

strength. The results of this model and the corroboration by

experimental measurement support some key assumptions

made in the thermal model. An analysis was also conducted

to compare the use of cylindrical electrodes to the plate geometry used in Phase I. In summary, cylindrical electrodes

may be appropriate for anodes, because the do not intercept the flow. If used as cathodes, a planar treatment zone

in their vicinity would probably be required. The cylindrical

electrodes can operate at reasonable current densities without boiling water. Because the hottest region is at the

electrode, cooling schemes could be used to operate at

higher current densities. If iron anodes are used, they will

have to be quite massive, and may not be economical compared to planar models. An example of soil heterogeneity

was investigated when it was discovered that a steel pt was

buried in the vicinity of the pilot test. There is some distortion of the field near the pit, but its effects on the test zone

between the electrodes are minimal.

223

(DOE/MC/31185–5392)

Development of an integrated, in-situ remediation technology. Topical report for task No. 9. Part I. TCE

degradation using nonbiological methods, September

26, 1994–May 25, 1996. Shapiro, A.P. (General Electric Research and Development, Schenectady, NY (United

States)); Sivavec, T.M.; Baghel, S.S. Monsanto Co., St.

Louis, MO (United States). [1997]. 35p. Sponsored by USDOE Office of Environmental Management, Washington, DC

(United States). DOE Contract AR21-94MC31185. Order

Number DE97002133. Source: OSTI; NTIS; INIS; GPO Dep.

Contamination in low-permeability soils poses a significant

technical challenge for in situ remediation efforts. Poor accessibility to the contaminants and difficulty in delivery of

treatment reagents have rendered existing in situ treatments

such as bioremediation, vapor extraction, pump and treat

rather ineffective when applied to low-permeability soils

present at many contaminated sites. The technology is an

integrated in situ treatment in which established geotechnical methods are used to install degradation zones directly in

the contaminated soil and electro-osmosis is used to move

the contaminants back and forth through those zones until

the treatment is completed. The present Draft Topical Report for Task No. 9 summarizes laboratory investigations into

TCE degradation using nonbiological methods. These studies were conducted by the General Electric Company. The

report concentrates on zero valent iron as the reducing

agent and presents data on TCE and daughter product

degradation rates in batch experiments, column studies, and

electroosmotic cells. It is shown that zero valent iron effectively degrades TCE in electroosmotic experiments.

Daughter product degradation and gas generation are

shown to be important factors in designing field scale treatment zones for the Lasagna process.

224

(DOE/MC/31185–5393)

Development of an integrated, in-situ remediation technology. Draft topical report for task No. 9. Part II.

Entitled: TCE degradation using non-biological methods, September 26, 1994–May 25, 1996. Orth, R.G.;

McKenzie, D.E. Monsanto Co., St. Louis, MO (United

States). [1997]. 24p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States).

DOE Contract AR21-94MC31185. Order Number

DE97002131. Source: OSTI; NTIS; INIS; GPO Dep.

Contamination in low permeability soils poses a significant

technical challenge to in-situ remediation efforts. Poor accessibility to the contaminants and difficulty in delivery of

treatment reagents have rendered existing in-situ treatments

such as bioremediation, vapor extraction, pump and treat

rather ineffective when applied to low permeability soils

present at many contaminated sites. The technology is an

integrated in-situ treatment in which established geotechnical methods are used to install degradation zones directly in

the contaminated soil and electro-osmosis is utilized to

move the contaminants back and forth through those zones

until the treatment is completed. The use of zero valence

iron for reductive dechlorination of aliphatic chlorinated hydrocarbons is currently under investigation by a number of

research groups as a potential method of in-situ treatment of

contaminated ground water. The reaction appears to involve

the transfer of electrons to chloro-aliphatic compounds by

the oxidation of zero valence iron to ferrous iron (Fe+2). Our

studies have indicated that this reaction is consistent with

those of corrosion, and as such, can be influenced or increased by the presence of small amounts of metals (5% by

weight) such as copper, tin, silver, gold and palladium

coated on the iron surface. Incomplete coverage of the iron

surface with a more electropositive metal results in an open

galvanic cell, which increases the oxidation of iron and facilitates and increases the concurrent reduction of

trichloroethylene and other chlorinated aliphatic compounds

to the corresponding alkenes and alkanes. Our results show

that plating more electropositive metals onto certain iron

surfaces results in approximately a factor of ten increase in

the dechlorination rate of small organochlorine compounds

such as TCE.

225

(DOE/MC/31185–5495)

Development of an integrated in-situ remediation

technology. Topical report for task No. 7 entitled: Development of degradation processes, September 26,

1994–May 25, 1996. Brackin, M.J. (and others); Heitkamp,

M.A.; Ho, Sa V. Monsanto Co., St. Louis, MO (United

States). [1997]. 53p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States).

DOE Contract AR21-94MC31185. Order Number

DE97002165. Source: OSTI; NTIS; INIS; GPO Dep.

Contamination in low permeability soils poses a significant

technical challenge to in-situ remediation efforts. Poor accessibility to the contaminants and difficulty in delivery of

treatment reagents have rendered existing in-situ treatments

such as bioremediation, vapor extraction, pump and treat

rather ineffective when applied to law permeability soils

present at many contaminated sites. The Lasagna technology is an integrated in-situ treatment in which established

geotechnical methods are used to install degradation zones

54
Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

directly in the contaminated soil and electro-osmosis is utilized to move the contaminants back and forth through

those zones until the treatment is completed. The general

concept of the technology is to use electrokinetics to move

contaminants from the soils into “treatment zones” where

the contaminants can be removed from the water by either

adsorption or degradation. The focus of technical task No. 7

was to optimize the conditions required for electro-osmotic

movement of contaminants and microbial degradation in the

treatment zones. This topical report summarizes the results

of aerobic microbial research performed to evaluate the feasibility of incorporating the chemical-degrading organisms

into biotreatment zones in laboratory-scale electro-osmosis

units and to demonstrate the combination of electrokinetics

and aerobic microbial degradation for the removal of contaminants from clay. Also included in this report are the

results of investigating microbial movement during electroosmosis and studies involving the optimization of the

microbial support matrix in the biozone. The Stanford study

was conducted in order to obtain a better understanding of

rates of anaerobic reductive dehalogenation of TCE to

ethylene and of factors affecting these rates in order to determine the potential for application of TCE biodegradation

as part of the Lasagna technology.

226

(DOE/MC/31185–5496)

Development of an integrated in-situ remediation

technology. Topical report for task No. 11 entitled: Evaluation of TCE contamination before and after the field

experiment, September 26, 1994–May 25, 1996. Hughes,

B.M. (and others); Athmer, C.J.; Sheridan, P.W. Monsanto

Co., St. Louis, MO (United States). [1997]. 214p. Sponsored

by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract AR21-94MC31185.

Order Number DE97002166. Source: OSTI; NTIS; INIS;

GPO Dep.

Contamination in low permeability soils poses a significant

technical challenge to in-situ remediation efforts. Poor accessibility to the contaminants and difficulty in delivery of

treatment reagents have rendered existing in-situ treatments

such as bioremediation, vapor extraction, pump and treat

rather ineffective when applied to low permeability soils

present at many contaminated sites. The technology is an

integrated in-situ treatment in which established geotechnical methods are used to install degradation zones directly in

the contaminated soil and electro-osmosis is utilized to

move the contaminants back and forth through those zones

until the treatment is completed. The present Topical Report

for Task No. 11 summarizes the results of TCE analysis in

soil and carbon before and after conducting the field experiment. In addition, a discussion of the TCE material balance

demonstrates that the Lasagna process is effective in

moving TCE from the contaminated soil into carbon treatment zones in the field experiment at DOE’s Gaseous

Diffusion Plant in Paducah, Kentucky.

227

(DOE/MC/31190–5547)

Base program interim phase test procedure - Coherent

Laser Vision System (CLVS). Final report, September 27,

1994–January 30, 1997. Coleman Research Corp., Springfield, VA (United States). [1997]. 44p. Sponsored by USDOE

Office of Environmental Management, Washington, DC

(United States). DOE Contract AR21-94MC31190. Order

Number DE97002207. Source: OSTI; NTIS; GPO Dep.

The purpose of the CLVS research project is to develop a

prototype fiber-optic based Coherent Laser Vision System

suitable for DOE’s EM Robotics program. The system provides three-dimensional (3D) vision for monitoring situations

in which it is necessary to update geometrics on the order of

once per second. The CLVS project plan required implementation in two phases of the contract, a Base Contract

and a continuance option. This is the Test Procedure and

test/demonstration results presenting a proof-of-concept for

a system providing three-dimensional (3D) vision with the

performance capability required to update geometrics on the

order of once per second.

228

(DOE/MC/31388–13-Pt.1)

Task 2 – Extraction and analysis of pollutant organics

from contaminated solids using off-line supercritical

fluid extraction (SFE) and on-line SFE-infrared spectroscopy. Semi-annual report, April 1–September 30,

1997. Hawthorne, S.B. Univ. of North Dakota, Energy and

Environmental Research Center, Grand Forks, ND (United

States). [1997]. 3p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States);USDOE Assistant Secretary for Fossil Energy,

Washington, DC (United States). DOE Contract FC21-

94MC31388. Order Number DE98054519. Source: OSTI;

NTIS; GPO Dep.

The work for this task was canceled as of February 1997.

At that time, Suprex Corporation, the commercial partner,

was purchased by a competitor (ISCO of Lincoln, Nebraska). ISCO had no plans to continue the development of

the interface which the EERC and Suprex were developing

since ISCO had recently developed a similar product based

on a window (rather than a fiber optic) interface. The EERC

is currently waiting for approval from the US Department of

Energy to close out this task.

229

(DOE/MC/31388–13-Pt.3)

Task 8 – Management and reporting. Semi-annual report, April 1–September 30, 1997. Daly, D.J.; Erickson,

T.A. Univ. of North Dakota, Energy and Environmental Research Center, Grand Forks, ND (United States). [1997]. 6p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States);USDOE Assistant

Secretary for Fossil Energy, Washington, DC (United

States). DOE Contract FC21-94MC31388. Order Number

DE98054521. Source: OSTI; NTIS; INIS; GPO Dep.

The task of addressing the environmental needs of nuclear defense complex sites under the US Department of

Energy (DOE) Environmental Management (EM) Program

requires the timely availability of appropriate cleanup

technologies. Fostering the commercialization of these technologies is the mission of EM-50, the EM Program Office of

Science and Technology. DOE’s Federal Energy Technology

Center (FETC) pursues activities integral to the EM-50 mission through its Cooperative Agreement with the EM Office

of Science and Technology (EMCA). The primary objective

of Task 8 is to ensure the effectiveness of the EMCA. This is

accomplished through (1) the coordination of internal EMCA

activities and coordination with the FETC contractor’s representative, (2) the coordination and expansion of the EMCA,

and (3) effective technical transfer.

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

230

(DOE/MC/31388–13-Pt.4)

Task 9 – Centrifugal membrane filtration. Semi-annual

report, April 1–September 30, 1997. Stepan, D.J.;

Grafsgaard, M.E. Univ. of North Dakota, Energy and Environmental Research Center, Grand Forks, ND (United

States). [1997]. 19p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States);USDOE Assistant Secretary for Fossil Energy,

Washington, DC (United States). DOE Contract FC21-

94MC31388. Order Number DE98054522. Source: OSTI;

NTIS; INIS; GPO Dep.

This project is designed to establish the utility of a novel

centrifugal membrane filtration technology for the remediation of liquid mixed waste streams at US Department of

Energy (DOE) facilities in support of the DOE Environmental

Management (EM) program. The Energy and Environmental

Research Center (EERC) has teamed with SpinTek Membrane Systems, Inc., a small business and owner of the

novel centrifugal membrane filtration technology, to

establish the applicability of the technology to DOE site remediation and the commercial viability of the technology for

liquid mixed waste stream remediation. The technology is a

uniquely configured process that makes use of ultrafiltration

and centrifugal force to separate suspended and dissolved

solids from liquid waste streams, producing a filtered water

stream and a low-volume contaminated concentrate stream.

This technology has the potential for effective and efficient

waste volume minimization, the treatment of liquid tank

wastes, the remediation of contaminated groundwater

plumes, and the treatment of secondary liquid waste

streams from other remediation processes, as well as the

liquid waste stream generated during decontamination and

decommissioning activities.

231

(DOE/MC/31388–13-Pt.5)

Task 10 – Technology development integration. Semiannual report, April 1–September 30, 1997. Erickson,

T.A.; Daly, D.J.; Jones, M.L. Univ. of North Dakota, Energy

and Environmental Research Center, Grand Forks, ND

(United States). [1997]. 20p. Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract FC21-94MC31388. Order Number

DE98054537. Source: OSTI; NTIS; GPO Dep.

Task 10 activities by the Energy and Environmental Research Center (EERC) have focused on the identification

and integration of new cleanup technologies for use in the

US Department of Energy (DOE) Environmental Management Program to address environmental issues within the

nuclear defense complex. Under Subtask 10A, activities focused on a review of technology needs compiled by the Site

Technology Coordination Groups as part of an ongoing

assessment of the relevance of the EM Cooperative Agreement Program activities to EM site needs. Work under this

subtask was completed August 31. Work under Task 10B

had as its goal assisting in the definition and development of

specific models to demonstrate several approaches to be

used by DOE to encourage the commercialization of environmental technologies. This activity included identification

and analysis of economic and regulatory factors affecting

feasibility of commercial development of two specific projects and two general models to serve as a mechanism for

the transfer of federally supported or developed environmental technologies to the private sector or for rapid

utilization in the federal government’s efforts to clean up the

weapons complex.

232

(DOE/MC/31388–13-Pt.6)

EM Task 12 – Laser cleaning of contaminated painted

surfaces. Semi-annual report, April 1–September 30,

1997. Grisanti, A.A.; Jenson, R.R.; Allan, S.E. Univ. of North

Dakota, Energy and Environmental Research Center, Grand

Forks, ND (United States). [1997]. [75p.] Sponsored by USDOE Office of Environmental Management, Washington, DC

(United States). DOE Contract FC21-94MC31388. Order

Number DE98054538. Source: OSTI; NTIS; INIS; GPO Dep.

Surface decontamination of concrete and steel surfaces in

nuclear facilities provides cost savings during decommissioning operations by allowing recycling or reuse of concrete

and steel structures. Separation of radionuclides and other

contamination from the concrete or steel substrates also allows reduction in volume of hazardous materials during the

D and D (decontamination and decommissioning) process,

resulting in further cost savings. Several techniques are

available or under development for surface decontamination

in nuclear facilities. Each technique has its merits; however,

none of them is universally the best choice for all surface

decontamination applications. Because of the multitude of

factors which influence the environmental and economic aspects of selecting a surface decontamination technique, it is

difficult to select the best method in a given situation; an

objective basis for comparing techniques is needed. The objective of this project is to develop a software tool for use by

personnel selecting a surface decontamination technique.

The software will incorporate performance data for available

surface decontamination techniques. The major activities in

the project are broken down as follows: Task 1–Complete

decision tree development; Task 2–Literature search for surface decontamination reports; Task 3–Compilation of

database from literature data; Task 4–Sensitivity analysis

and model design; Task 5–Design of model data structures;

and Task 6–PC software design and coding. Work during

this reporting period completed Tasks 1, 2, 3, 5, and 6. Task

4 activities resulted in a prototype of the model design; sensitivity analysis and model modifications are in progress at

the time of this report. Task 4 will be complete prior to the

end of December 1997. A working prototype of the software

implementation of the surface decontamination model and

technology database has been completed. (Abstract truncated)

233

(DOE/MC/31388–13-Pt.7)

EM Task 13 – Cone penetrometer for subsurface heavy

metals detection. Semi-annual report, April 1–

September 30, 1997. Grisanti, A.A.; Timpe, R.C.; Foster,

H.J.; Eylands, K.E.; Crocker, C.R. Univ. of North Dakota,

Energy and Environmental Research Center, Grand Forks,

ND (United States). [1997]. [100p.] Sponsored by USDOE

Office of Environmental Management, Washington, DC

(United States). DOE Contract FC21-94MC31388. Order

Number DE98054539. Source: OSTI; NTIS; GPO Dep.

Surface and subsurface contamination of soils by heavy

metals, including Pb, Cr, Cu, Zn, and Cd has become an

area of concern for many industrial and government organizations. Conventional sampling and analysis techniques for

soil provide a high degree of sensitivity and selectivity for individual analytes. However, obtaining a representative

56
Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

sampling and analysis from a particular site using conventional techniques is time-consuming and costly. Additionally,

conventional methods are difficult to implement in the field

for in situ and/or real-time applications. Therefore, there is a

need for characterization and monitoring techniques for

heavy metals in soils which allow cost-effective, rapid, in situ

measurements. Laser induced breakdown spectroscopy

(LIBS) has been used to successfully measure metals content in a variety of matrices including soil. Science and

Engineering Associates (SEA) is developing a subsurface

cone penetrometer (CPT) probe for heavy metal detection

that employs LIBS. The LIBS/CPT unit is to be applied to in

situ, real-time sampling and analysis of heavy metals in soil.

The overall objectives of this project are to evaluate potential calibration techniques for the LIBS/CPT instrument and

to provide a preliminary evaluation of the LIBS instrument

calibration using samples obtained from the field.

234

(DOE/MC/31388–13-Pt.8)

EM14 – Bubbleless gas transfer technology for the in

situ remediation of chlorinated hydrocarbons. Semiannual report, April 1–September 30, 1997. Gallagher,

J.R. Univ. of North Dakota, Energy and Environmental Research Center, Grand Forks, ND (United States). [1997]. 7p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States);USDOE Assistant

Secretary for Fossil Energy, Washington, DC (United

States). DOE Contract FC21-94MC31388. Order Number

DE98054533. Source: OSTI; NTIS; GPO Dep.

The primary objective of this project is to demonstrate the

ability of hydrogen to supply reducing equivalents for the reductive dehalogenation of PCE. This objective will be

accomplished by two types of activities. First, laboratory experiments will compare the kinetics of hydrogen-mediated

dehalogenation with natural routes of loss (hydrolysis and

natural attenuation). Secondly, bench-scale column experiments will be performed to demonstrate hydrogen-mediated

reductive dehalogenation in aquifer sediments.

235

(DOE/MC/31388–13-Pt.9)

Task 15 – Remediation of organically contaminated soil

using hot/liquid (subcritical) water. Semi-annual report,

April 1–September 30, 1997. Hawthorne, S.B. Univ. of

North Dakota, Energy and Environmental Research Center,

Grand Forks, ND (United States). [1997]. 7p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract FC21-94MC31388. Order

Number DE98054534. Source: OSTI; NTIS; GPO Dep.

This activity involves a pilot-scale demonstration of the

use of hot/liquid water for the removal of organic contaminants from soil at the pilot (20 to 40 kg) scale. Lab-scale

studies are being performed to determine the optimum temperature, contact time, and flow rates for removal of the

organic contaminants. Initial investigations into using carbon

sorbents to clean the extractant water for recycle use and to

concentrate the extracted contaminants in a small volume

for disposal are also being performed. Liquid water is normally considered to be too polar a solvent to be effective for

removal of organic contaminants from contaminated soils

and sludges. However, the Energy and Environmental Research Center (EERC) has demonstrated that the polarity of

liquid water can be changed from that of a very polar solvent at ambient conditions to that of an organic solvent

(e.g., ethanol or acetonitrile) by simply raising the temperature. The EERC has exploited this unique property of liquid

water to obtain highly selective extractions of polar (at lower

temperatures) to nonpolar (at 200 to 250 C) organics from

contaminated soils and sludges. Only moderate pressures

(a maximum of about 45 atm at 250 C and lower pressures

at lower temperatures) are required. With this procedure, all

detectable hazardous organics were removed from the

sludge, thus making the remaining material (about 99% of

the original mass) a nonhazardous material. The present

understanding of hot/liquid water extraction for the removal

of hazardous organics from contaminated soils and sludges

is being used to develop the engineering parameters

needed to perform a pilot-scale demonstration of the remediation technology. Progress during the report period is

summarized.

236

(DOE/MC/31388–5497)

Task 2: Extraction and analysis of pollutant organics

from contaminated solids using off-line Supercritical

Fluid Extraction (SFE) and on-line SFE-infrared spectroscopy. Semi-annual report, April 1, 1996–September

30, 1996. North Dakota Univ., Grand Forks, ND (United

States). Energy and Environmental Research Center.

[1997]. 12p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract FC21-94MC31388. Order Number DE97002176.

Source: OSTI; NTIS; GPO Dep.

This activity will result in a commercialized version of a

field-portable instrument for performing supercritical fluid extraction (SFE) with on-line Fourier transform infrared (FT-IR)

detection. The Energy & Environmental Research Center

(EERC) has developed an SFE field-portable method for

quantitatively extracting organic pollutants (e.g., polycyclic

aromatic hydrocarbons [PAHs], polychlorinated biphenyls

[PCBs], total petroleum hydrocarbons [TPHs]) from soils and

sludges under U.S. Environmental Protection Agency (EPA)

funding. FT-IR is a detector that can yield quantitative and

compound-class information for organic pollutants and is excellent for survey uses, since virtually all organic compound

classes can be monitored. A laboratory prototype SFE-FTIR instrument has been developed at the EERC and the

University of North Dakota (UND) Department of Chemistry.

The commercial instrument will be field-portable (requiring

only generator electricity) and able to extract and measure

organic pollutants from soils and sludges, identify the compound classes present, and provide quantitative or

semiquantitative results at detection limits relevant to regulatory needs (e.g., parts per million). The SFE-FT-IR approach

is particularly advantageous for very hazardous samples

(e.g., determination of organics in solids contaminated with

radioactive components), since SFE-FT-IR analysis generates no waste solvents. The instrument will also be

configured to allow collection of “positive” extracts for analysis by other confirmatory (e.g., gas chromatography-mass

spectroscopy [GC-MS]) methods.

237

(DOE/MC/31388–5498)

Task 3 - pyrolysis of plastic waste. Semi-annual report,

April 1–September 30, 1996. North Dakota Univ., Grand

Forks, ND (United States). Energy and Environmental Research Center. [1997]. 17p. Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

57
ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

States). DOE Contract FC21-94MC31388. Order Number

DE97002177. Source: OSTI; NTIS; GPO Dep.

This report briefly describes progress in the development

of a thermal decomposition process for volume reduction of

spent ion-exchange resin. During the reporting period, two

series of tests were performed. The mixed waste plastics

test investigated the effectiveness of the process in concentrating radionuclide surrogates in a solids residual while

yielding a surrogate-free condensate product. Preliminary

results indicated the occurrence of solids carryover. The ionexchange resin tests resulted in a cesium concentration in

the unfiltered condensate of about 4 to 20 micrograms/

gram, indicating that fine particulate material was passing

through the reactor cyclone. Future work includes the evaluation of an auger reactor in place of the fluidized bed reactor

to address the problem of reactor carryover. 2 figs., 7 tabs.

238

(DOE/MC/31388–5499)

Task 8 - management and reporting. Semi-annual report

April 1–September 30, 1996. North Dakota Univ., Grand

Forks, ND (United States). Energy and Environmental Research Center. [1997]. 16p. Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract FC21-94MC31388. Order Number

DE97002178. Source: OSTI; NTIS; INIS; GPO Dep.

The task of restoring nuclear defense complex sites under

the U.S. Department of Energy (DOE) Environmental Management (EM) program presents an unprecedented

challenge to the environmental restoration community. Effective and efficient cleanup requires the timely development

or modification of novel cleanup technologies applicable to

radioactive wastes. Fostering the commercialization of these

innovative technologies is the mission of EM-50, the EM

Program Office of Science and Technology. DOE’s Morgantown Energy Technology Center (METC) pursues activities

integral to the EM-50 mission through its Cooperative

Agreement with the EM Office of Science and Technology.

The advancement of innovative technologies is often arrested at the “valley of death,” the general term for barriers

to demonstration and commercialization. Alternatively, commercialization and deployment are impacted by a lack of

clear choices among competing technologies. The Energy &

Environmental Research Center (EERC), a not-for-profit,

contract-supported organization focused on research, development, demonstration, and commercialization (RDD&C) of

energy and environmental technologies, is in the second

year of a Cooperative Agreement with METC designed (1)

to deliver EM technologies into the commercial marketplace

through a unique combination of technical support, realworld demonstrations, and brokering; (2) to facilitate

decisions regarding deployment and support for commercialization by providing comparative performance data

through systems analysis; and (3) to support the integration

and deployment of “winner” technologies at EM sites. These

activities, along with program management, make up the

four program areas of the METC-EERC EM Cooperative

Agreement (EMCA): Technology Commercialization, Systems Engineering, Technology Integration, and Management

and Reporting.

239

(DOE/MC/31388–5500)

Task 9 - centrifugal membrane filtration. Semi-annual report April 1–September 30, 1996. Stepan, D.J.; Moe, T.A.;

Collings, M.E. North Dakota Univ., Grand Forks, ND (United

States). Energy and Environmental Research Center.

[1997]. 181p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract FC21-94MC31388. Order Number DE97002179.

Source: OSTI; NTIS; INIS; GPO Dep.

This report assesses a centrifugal membrane filtration

technology developed by SpinTek Membrane Systems, Inc.

The technology uses supported microporous membranes rotating at high rpm, under pressure, to separate suspended

and colloidal solids from liquid streams, yielding a solidsfree permeate stream and a highly concentrated solids

stream. The Tank Waste Focus Area was chosen for study.

Membrane-screening tests were performed with the STC-X4

static test cell filtration unit, using five ceramic membranes

with different pore size and composition. Based on permeate flux, a 0.25-m TiO2/Al2O3 membrane was selected for

detailed performance evaluation using the centrifugal membrane filtration unit with a surrogate tank waste solution. The

performance of the unit was evaluated with a statistical test

design that determined the effect of temperature, pressure,

membrane rotational speed, and solids loading on permeate

flux. All four variables were found to be statistically significant, with the magnitude of the effect in the order of

temperature, solids loading, rotor speed, and pressure. Temperature, rotor speed, and pressure had an increasing effect

on flux with increasing value, while increases in solids

loading showed a decrease in permeate flux. Significant interactions between rotor speed and solids loading and

pressure and solids loading were also observed. The regression equation derived from test data had a correlation

coefficient of 0.934, which represents a useful predictive capability for integrating the technology into DOE cleanup

efforts. An extended test run performed on surrogate waste

showed some deterioration in filtration performance, based

on flux, apparently due to the buildup of solids near the

inner portion of the membrane where relative membrane velocities were low. Continued testing of the system will focus

on modifications to the shear pattern across the entire membrane surface to affect improved long-term performance.

240

(DOE/MC/31388–5501)

Task 10 - technology development integration. Semiannual report, April 1–September 30, 1996. Hendrikson,

J.G.; Daly, D.J. North Dakota Univ., Grand Forks, ND

(United States). Energy and Environmental Research

Center. [1997]. 230p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States).

DOE Contract FC21-94MC31388. Order Number

DE97002180. Source: OSTI; NTIS; INIS; GPO Dep.

The Energy and Environmental Research Center (EERC),

in conjunction with the Waste Policy Institute (WPI), will

identify and integrate new technologies to meet site-specific

environmental management (EM) requirements at contaminated sites appropriate to U.S. Department of Energy (DOE)

interests. This paper briefly reports overall progress for three

activities: technology management, project management,

and technology integration. Work performed over the

reporting period has focused on providing logistical and administrative support. In addition, six monthly WPI reports to

the EERC are included as appendices. The WPI reports

contained detailed information for progress in each activity.

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

241

(DOE/MC/31388–5502)

Task 11: Technology development integration. Semiannual report, April 1, 1996–September 30, 1996. Musich,

M.A. North Dakota Univ., Grand Forks, ND (United States).

Energy and Environmental Research Center. [1997]. 12p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

FC21-94MC31388. Order Number DE97002181. Source:

OSTI; NTIS; INIS; GPO Dep.

A review was conducted of three systems analysis (SA)

studies performed by Lockheed Idaho Technologies Company (LITCO) on integrated thermal treatment systems

(ITTSs) and integrated nonthermal treatment systems

(INTSs) for the remediation of mixed low-level waste

(MLLW) stored throughout the U.S. Department of Energy

(DOE) weapons complex. The review was performed by an

independent team led by the Energy & Environmental

Research Center (EERC), including Science Applications International Corporation, the Waste Policy Institute (WPI),

and Virginia Tech. The three studies reviewed were as follows: (1) Integrated Thermal Treatment System Study,

Phase 1 - issued July 1994, (2) Integrated Thermal Treatment System Study, Phase 2 - issued February 1996, and

(3) Integrated Nonthermal Treatment System Study - drafted

March 1996. The three studies were commissioned by DOE

to be SA studies of environmental management (EM) systems. The purpose of LITCO’s engineering evaluation of the

MLLW treatment system alternatives was to help DOE in the

prioritization of research, development, and demonstration

activities for remediation technologies. The review of these

three studies was structured to further aid DOE in its current

and future decision-making processes. The methodology in

the studies was compared to a sound systems engineering

(SE) approach to help DOE determine which tasks still need

to be accomplished to complete a thorough design/review.

242

(DOE/MC/31388–5503)

Task 12: Laser cleaning of contaminated painted surfaces. Semi-annual report, April 1, 1996–September 30,

1996. Grisanti, A.A.; Hassett, D.J. North Dakota Univ.,

Grand Forks, ND (United States). Energy and Environmental

Research Center. [1997]. 22p. Sponsored by USDOE Office

of Environmental Management, Washington, DC (United

States). DOE Contract FC21-94MC31388. Order Number

DE97002182. Source: OSTI; NTIS; INIS; GPO Dep.

Paint contaminated with radionuclides and other hazardous materials is common in Department of Energy (DOE)

facilities. Facility decommissioning and decontamination requires the removal of contaminated paint. Paint removal

technologies include laser- and abrasive-based systems. F2

Associates are utilizing a pulsed-repetition CO2 laser that

produces a 2.5-cm x 2.5-cm beam which can be scanned

across a 30- x 100-cm raster and, when placed on a robot,

can be designed to clean any surface that the robot can be

programmed to follow. Causing little or no damage to the

substrate (concrete, steel, etc.), the laser ablates the material to be removed from a given surface. Ablated material is

then pulled into a filtration and collection (VAC-PAC) system

to prevent the hazardous substances from entering into the

atmosphere. The VAC-PAC system deposits the ablated material into waste drums which may be removed from the

system without compromising the integrity of the seal, allowing a new drum to be set up for collection without leakage of

the ablated material into the atmosphere.

243

(DOE/MC/31388–5772)

Task 15 - Remediation of Organically Contaminated Soil

Using Hot/Liquid (Subcritical) Water. Semiannual report,

November 1, 1996– March 31,1997. Hawthorne, Steven B.

North Dakota Univ., Grand Forks, ND (United States). 1997.

10p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

FC21-94MC31388. Order Number DE97005470. Source:

OSTI; NTIS; INIS; GPO Dep.

This activity will perform a pilot-scale demonstration of the

use of hot/liquid water for the removal of organic contaminants from soil at the pilot (20 to 40 kg) scale. Lab-scale

studies will be performed to determine the optimum temperature, contact time, and flow rates for removal of the organic

contaminants. Initial investigations into using carbon sorbents to clean the extractant water for recycle use and to

concentrate the extracted contaminants in a small volume

for disposal will also be performed.

244

(DOE/MC/31388–5773)

Task 14 - Bubbleless Gas Transfer Technology for the In

Situ Remediation of Chlorinated Hydrocarbons. Semiannual report, November 1, 1996–March 31, 1997.

Gallagher, J.R. North Dakota Univ. Grand Forks Energy And

Environmental Research Center (United States). 1997. 8p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

FC21-94MC31388 ; FC21-93MC30098. Order Number

DE97005471. Source: OSTI; NTIS; GPO Dep.

The primary objective of this project is to demonstrate the

ability of hydrogen to supply reducing equivalents for the reductive dehalogenation of PCE. This objective will be

accomplished by two types of activities. First, laboratory experiments will compare the kinetics of hydrogen-mediated

dehalogenation with natural routes of loss (hydrolysis and

natural attenuation). Secondly, bench-scale column experiments will be performed to demonstrate hydrogen-mediated

reductive dehalogenation in aquifer sediments.

245

(DOE/MC/31388–5774)

Task 10 - Technology Development Integration. Semiannual report, November 1, 1996–March 31, 1997. Erickson,

Thomas A.; Daly, Daniel J. Univ. of North Dakota Energy

and Environmental Research Center, Grand Forks (United

States). 1997. 59p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE

Contract FC21-94MC31388. Order Number DE97005472.

Source: OSTI; NTIS; GPO Dep.

The Energy and Environmental Research Center (EERC)

in conjunction with the Waste Policy Institute (WPI) will identify and integrate new technologies to meet site-specific

environmental management (EM) requirements at contaminated sites appropriate to U.S. Department of Energy (DOE)

interests. EM technologies offered by developers will be

evaluated to determine their complementary contribution to

new cleanup systems focused on particular characterization

and remediation problems at specific EM sites. The technology clusters identified will provide EM cleanup capabilities

59
ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

that are significantly faster, better, safer, and cheaper than

systems that are currently available. Work will be performed

under the DOE-EERC EM Cooperative Agreement (EMCA),

which includes provisions to develop, demonstrate, and

commercialize technologies that address environmental

management needs of contaminated sites together with

management activities which accelerate transfer of technologies. The effort began July 1, 1995.

246

(DOE/MC/31388–5775)

Task 9- Centrifugal Membrane Filtration. Semiannual report, November 1, 1996–March 31, 1997. Stephan, Daniel

J.; Grafsgaard, Michael E. North Dakota Univ. Grand Forks

Energy And Environmental Research Center (United

States). 1997. 13p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE

Contract FC21-94MC31388. Order Number DE97005473.

Source: OSTI; NTIS; GPO Dep.

The overall project consists of several integrated research

phases related to the applicability, continued development,

demonstration, and commercialization of the SpinTek centrifugal membrane filtration process. This phase of work is a

continuation of the Phase 1 evaluation of the SpinTek centrifugal membrane filtration technology. During Phase 1

testing conducted at the EERC using the SpinTek ST-IIL unit

operating on a surrogate tank waste, a solids cake developed on the membrane surface. Solids cake development

was observed where linear membrane velocities were less

than 17.5 feet per second and resulted in a reduction of unobstructed membrane surface area of up to 25%, reducing

overall filtration performance. The primary goal of the Phase

2 research effort is to enhance filtration performance through

the development and testing of alternative designs of the

turbulence promoters to generate a shear force across the

entire membrane surface that is sufficient to maintain a selfcleaning membrane capability and improve filtration

efficiency and long term performance. Specific Phase 2 research activities include the following: System modifications

to accommodate an 11-inch-diameter, two-disk rotating

membrane assembly. Development and fabrication of alternative designs to the existing turbulence promoters. *Testing

and evaluation of the existing and alternative turbulence

promoters under selected operating conditions using a statistically designed test matrix Data reduction and analysis.

247

(DOE/MC/31388–5777)

Task 3 - Pyrolysis of Plastic Waste. Semiannual report,

November 1, 1996–March 31, 1997. Ness, Robert O.;

Aulich, Ted R. North Dakota Univ., Grand Forks, ND (United

States). 1997. 11p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE

Contract FC21-94MC31388. Order Number DE97005475.

Source: OSTI; NTIS; INIS; GPO Dep.

Over the last 50 years, the U.S. Department of Energy

(DOE) has produced a wide variety of radioactive wastes

from activities associated with nuclear defense and nuclear

power generation. These wastes include low-level radioactive solid wastes, mixed wastes, and transuranic (TRU)

wastes. A portion of these wastes consists of high- organiccontent materials, such as resins, plastics, and other

polymers; synthetic and natural rubbers; cellulosic-based

materials; and oils, organic solvents, and chlorinated organic

solvents. Many of these wastes contain hazardous and/or

pyrophoric materials in addition to radioactive species.

Physical forms of the waste include ion-exchange resins

used to remove radioactive elements from nuclear reactor

cooling water, lab equipment and tools (e.g., measurement

and containment vessels, hoses, wrappings, equipment coverings and components, and countertops), oil products (e.g.,

vacuum pump and lubrication oils), bags and other storage

containers (for liquids, solids, and gases), solvents, gloves,

lab coats and anti-contamination clothing, and other items.

Major polymer and chemical groups found in high-organiccontent radioactive wastes include polyvinyl chloride (PVC),

low-density polyethylene (LDPE), polypropylene (PP),

Teflon(TM), polystyrene (PS), nylon, latex, polyethylene

terephthalate (PET), vinyl, high-density polyethylene

(HDPE), polycarbonate, nitriles, Tygon(R), butyl, and

Tyvec(R).

248

(DOE/MC/31388–5780)

Laser Cleaning of Contaminated Painted Surfaces.

Semiannual report, November 1, 1996–March 31, 1997.

Grisanti, Ames A.; Jensen, Robert R. North Dakota Univ.

Grand Forks Energy And Environmental Research Center

(United States). 1997. 23p. Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract FC21-94MC31388. Order Number

DE97005478. Source: OSTI; NTIS; INIS; GPO Dep.

The objective of this project is to develop a software tool

for use by personnel who must select a surface decontamination technique. The software will incorporate performance

data for available surface decontamination techniques. The

major activities in the project are broken down as follows:

Task 1 - Complete decision tree development. Task 2 - Literature search for surface decontamination reports. Task 3 -

Compilation of database from literature data. Task 4 - Sensitivity analysis and model design. Task 5 - Design of model

data structures. Task 6 - PC software design and coding

249

(DOE/MC/31388–5781)

Cone Penetrometer for Subsurface Heavy Metals Detection. Semiannual report, November 1, 1996–March 31,

1997. Grisanti, Ames A.; Timpe, Ronald C.; Foster, H.J.; Eylands, Kurt E.; Crocker, Charlene R. North Dakota Univ.

Grand Forks Energy And Environmental Research Center

(United States). 1997. 26p. Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract FC21-94MC31388. Order Number

DE97005479. Source: OSTI; NTIS; INIS; GPO Dep.

Surface and subsurface contamination of soils by heavy

metals, including Pb, Cr, Cu, Zn, and Cd, has become an

area of concern for many industrial and government organizations (1). Conventional sampling and analysis techniques

for soil provide a high degree of sensitivity and selectivity for

individual analytes. However, obtaining a representative

sampling and analysis from a particular site using conventional techniques is time consuming and costly (2).

Additionally, conventional methods are difficult to implement

in the field for in situ and/or real-time applications. Therefore,

there is a need for characterization and monitoring techniques for heavy metals in soils which allow cost-effective,

rapid, in situ measurements. Laser-induced breakdown

spectroscopy (LIBS) has been used to successfully measure

metals content in a variety of matrices (3-15) including soil

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

(16,17). Under the Department of Energy (DOE) Federal Energy Technology Center (FETC) Industry Program, Science

& Engineering Associates (SEA) is developing a subsurface

cone penetrometer (CPT) probe for heavy metals detection

that employs LIBS (18). The LIES-CPT unit is to be applied

to in situ, real-time sampling and analysis of heavy metals in

soil. As part of its contract with DOE FETC, SEA is scheduled to field test its LIBS-CPT system in September 1997.

250

(DOE/MC/32091–3)

Steam reforming of low-level mixed waste. Final report.

ThermoChem, Inc., Baltimore, MD (United States). Jun

1998. [400p.] Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract AR21-95MC32091. Order Number DE98058965.

Source: OSTI; NTIS; INIS; GPO Dep.

ThermoChem has successfully designed, fabricated and

operated a nominal 90 pound per hour Process Development Unit (PDU) on various low-level mixed waste

surrogates. The design, construction, and testing of the

PDU as well as performance and economic projections for a

300-lb/hr demonstration and commercial system are described. The overall system offers an environmentally safe,

non-incinerating, cost-effective, and publicly acceptable

method of processing LLMW. The steam-reforming technology was ranked the No. 1 non-incineration technology for

destruction of hazardous organic wastes in a study commissioned by the Mixed Waste Focus Area and published in

April 1997. The ThermoChem steam-reforming system has

been developed over the last 13 years culminating in this

successful test campaign on LLMW surrogates. Six surrogates were successfully tested including a 750-hour test on

material simulating a PCB- and Uranium-contaminated solid

waste found at the Portsmouth Gaseous Diffusion Plant.

The test results indicated essentially total (> 99.9999%)

destruction of RCRA and TSCA hazardous halogenated organics, significant levels of volume reduction (> 400 to 1),

and retention of radionuclides in the volume-reduced solids.

Economic evaluations have shown the steam-reforming system to be very cost competitive with more conventional and

other emerging technologies.

251

(DOE/MC/32110–5477)

Measurement of radionuclides using ion chromatography and flow-call scintillation counting with pulse shape

discrimination: Topical report, September 15, 1996–

October 3, 1996, Tasks 1.11, 1.12 and 1.13. South

Carolina Universities Research and Education Foundation,

Clemson, SC (United States). Strom Thurman Inst. [1997].

5p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AR21-95MC32110. Order Number DE97002144. Source:

OSTI; NTIS; INIS; GPO Dep.

Several flow-cell radiation detector systems are commercially available for quantification of aqueous radioactive

solutions. These systems do not use the technique of pulse

shape discrimination to identify the incident radiation and

therefore are limited in environmental characterization application when coupled to an ion chromatography system. The

advantages of the pulse shape discriminating flow-cell detector over the commercially available systems include: (1)

lower minimum detectable activity for alpha radiation, (2) reduced radiological interferences that may exist between

co-eluted alpha- and beta-emitting radionuclides, and (3)

possible isotopic information from the ion chromatography

system. For Tasks 1.1.1 and 1.1.2 of this project, several

scintillation materials were investigated for pulse shape (alpha and beta) discrimination capabilities and the best

candidate material was optimized. In addition, the following

detector properties were also optimized: scintillator particle

size, flow-cell tubing type, and electromagnetic as well as

optical crosstalk between the photomultiplier tubes.

252

(DOE/MC/32260–1)

PTC-6 vacuum system: WallWalker and Blastrac

shot blast cleaning system. Operating Engineers National

HAZMAT Program, Beaver, WV (United States). Feb 1998.

[150p.] Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

FC21-95MC32260. Order Number DE98058271. Source:

OSTI; NTIS; INIS; GPO Dep.

The LTC Americas, Inc. wall decontamination technology

consisted of two pneumatic hand-held tools: (1) a roto-peen

scaler that used star cutters and (2) a 3-piston hammer with

reciprocating bits. The hand-held tools were used in conjunction with the LTC PTC-6 vacuum system which captured

dust and debris as the wall decontamination took place.

Recommendations for improved worker safety and health

during use of the PTC-6 vacuum system with hand-held

tools include: (1) keeping all hoses and lines as orderly as

possible in compliance with good housekeeping requirements; (2) ergonomic training to include techniques in lifting,

bending, stooping, twisting, etc.; (3) use of a clamping system to hold hoses to the vacuum system; (4) a safety line

on the air line connections; (5) use of a mechanical lifting

system for waste drum removal; and (6) the use of ergonomically designed tools.

253

(DOE/MC/32260–3)

Pegasus International, Inc. coating removal systems.

Operating Engineers National HAZMAT Program, Beaver,

WV (United States). Feb 1998. [250p.] Sponsored by USDOE Office of Environmental Management, Washington, DC

(United States);USDOE Assistant Secretary for Fossil Energy, Washington, DC (United States). DOE Contract

FC21-95MC32260. Order Number DE98058272. Source:

OSTI; NTIS; GPO Dep.

The Pegasus Coating Removal System (PCRS) was

demonstrated at Florida International University (FIU) where

it was being evaluated for efficiency and cost. In conjunction

with the FIU testing demonstration, a human factors assessment was conducted to assess the hazards and associated

safety and health issues of concern for workers utilizing this

technology. The PCRS is a chemical paste that is applied to

the surface using a brush, roller, or airless sprayer. After the

type of PCRS, thickness, and dwell time have been determined, a laminated backed material is placed on top of the

chemical paste to slow down the drying process and to provide a mechanism to strip-off the chemical. After the dwell

time is reached, the chemical substrate can be removed.

Scrapers may be used to break-loose the layers as necessary or to break-loose the layers that are not removed when

the laminated paper is picked up. Residue may also be

cleaned off of the surface with a damp sponge with an agitating motion, absorbent sponges, or a vacuum, as needed.

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

The paint and removal agent is then placed in drums for disposal at a later time. During the assessment sampling was

conducted for organic vapors and general observational

techniques were conducted for ergonomics. Recommendations for improved worker safety and health during

application and removal of the PCRS include: (1) work practices that reflect avoidance of exposure or reducing the risk

of exposure; (2) assuring all PPE and equipment are compatible with the chemicals being used; (3) work practices

that reduce the worker’s need to walk on the slippery surface caused by the chemical or the use of special anti-slip

soles; (4) careful control of overspray (if a spray application

is used); and (5) the use of ergonomically designed longhandled tools to apply and remove the chemical (to alleviate

some of the ergonomic concerns).

254

(DOE/MC/32260–4)

A robotic inspection experimental system (ARIES) and

BOA. Operating Engineers National HAZMAT Program,

Beaver, WV (United States). Feb 1998. [250p.] Sponsored

by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract FC21-95MC32260.

Order Number DE98058273. Source: OSTI; NTIS; GPO

Dep.

ARIES consists of a 6-wheeled K3A mobile platform, a

compact subturret, a sonar imaging system, a laser-based

light detection and ranging (lidar) navigation beacon system,

and a camera positioning system. It has a sonar imaging

system used in navigation and collision avoidance and an

automatic docking/charging system. Drum-referencing

algorithms and camera-positioning algorithms have been included in the primitive instruction set for the robot. The

robot’s navigation is based on Synchro-Drive, a patented

design that utilizes concentric shafts to distribute drive and

steering power to the six wheels simultaneously. ARIES

uses a virtual path concept in which only a limited amount of

information needs to be provided to the control computer in

order to get the vehicle moving. The safety and health evaluation, during the human factors assessment, found several

areas of concern including ergonomics, laser hazards, tripping hazards, fall-from-above and struck-by hazards,

electrical hazards, and decontamination of the system. BOA

is a self-propelled automated mini-enclosure, able to remove

insulation from installed pipes, primarily of 4 inch nominal

outside diameter. The system is designed for two operators:

one oversees the abatement head operation from a distance

of 10 or 15 feet using a pendant control and the other bags

the debris at a cyclonic bagging station that is attached by a

vacuum hose to the cutting head. Since the abatement head

is its own enclosure, there may be no need for further enclosures to be built. The system wets and removes asbestos

insulation automatically, cutting the debris into consistent

chunks and moving the wave under a strong vacuum to a

bagging machine. Prior to reaching the bagging operation,

the material passes through a water separator which greatly

reduces the weight of the debris and allows recirculation of

water, after sufficient filtration. (Abstract truncated)

255

(DOE/NE/44139–83)

Integrated radwaste treatment system. Final report.

Baker, M.N.; Houston, H.M. West Valley Nuclear Services

Co., Inc., NY (United States). Oct 1997. 27p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract AC24-81NE44139. Order

Number DE98002842. Source: OSTI; NTIS; INIS; GPO Dep.

In May 1988, the West Valley Demonstration Project

(WVDP) began pretreating liquid high-level radioactive

waste (HLW). This HLW was produced during spent nuclear

fuel reprocessing operations that took place at the Western

New York Nuclear Service Center from 1966 to 1972. Original reprocessing operations used plutonium/uranium

extraction (PUREX) and thorium extraction (THOREX) processes to recover usable isotopes from spent nuclear fuel.

The PUREX process produced a nitric acid-based waste

stream, which was neutralized by adding sodium hydroxide

to it. About two million liters of alkaline liquid HLW produced

from PUREX neutralization were stored in an underground

carbon steel tank identified as Tank 8D-2. The THOREX

process, which was used to reprocess one core of mixed

uranium-thorium fuel, resulted in about 31,000 liters of

acidic waste. This acidic HLW was stored in an underground

stainless steel tank identified as Tank 8D-4. Pretreatment of

the HLW was carried out using the Integrated Radwaste

Treatment System (IRTS), from May 1988 until May 1995.

This system was designed to decontaminate the liquid HLW,

remove salts from it, and encapsulate the resulting waste

into a cement waste form that achieved US Nuclear Regulatory Commission (NRC) criteria for low-level waste (LLW)

storage and disposal. A thorough discussion of IRTS operations, including all systems, subsystems, and components,

is presented in US Department of Energy (DOE) Topical Report (DOE/NE/44139-68), Integrated Radwaste Treatment

System Lessons Learned from 2 1/2 Years of Operation.

This document also presents a detailed discussion of

lessons learned during the first 2 1/2 years of IRTS operation. This report provides a general discussion of all phases

of IRTS operation, and presents additional lessons learned

during seven years of IRTS operation.

256

(DOE/NV/11508–29)

Numerical evaluation of monofil and subtle-layered

evapotranspiration (ET) landfill caps. Wilson, G.V.; Henley, M.; Valceschini, R. Nevada Univ., Las Vegas, NV

(United States). Water Resources Center. Jan 1998. 65p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States);USDOE,

Washington, DC (United States). DOE Contract AC08-

95NV11508. (DRI–45159). Order Number DE98005553.

Source: OSTI; NTIS; INIS; GPO Dep.

The US Department of Energy/Nevada Operations Office

(DOE/NV) has identified the need to design a low-level

waste (LLW) closure cap for the arid conditions at the

Nevada Test Site (NTS). As a result of concerns for subsidence impacting the cover, DOE/NV redesigned the LLW

cover from one containing a ‘hard’ infiltration barrier that

would likely fail, to a ‘soft’ (ET) cover that is sufficiently deep

to accommodate the hydrologic problems of subsidence. An

ET cover is one that does not contain hydrologic barrier layers but relies on soil-water retention and sufficient thickness

to store water until evapotranspiration (ET) can remove the

moisture. Subtle layering within an ET cap using the native

soil could be environmentally beneficial and cost effective.

257

(DOE/NV/11508–34)

Hunter-gatherer adaptations and environmental change

in the southern Great Basin: The evidence from Pahute

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

and Rainier mesas. Pippin, L.C. University and Community

College System of Nevada, Desert Research Inst., Quaternary Sciences Center, Reno, NV (United States). Jun 1998.

159p. Sponsored by USDOE, Washington, DC (United

States);USDOE Office of Civilian Radioactive Waste Management, Washington, DC (United States);USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract AC08-95NV11508. Order Number

DE98002976. Source: OSTI; NTIS; GPO Dep.

Technical report number 92.

This paper reviews the evidence for fluctuations in past

environments in the southern Great Basin and examines

how these changes may have affected the strategies followed by past hunter and gatherers in their utilization of the

resources available on a highland in this region. The evidence used to reconstruct past environments for the region

include botanical remains from packrat middens, pollen

spectra from lake and spring deposits, faunal remains recovered from archaeological and geologic contexts, tree-ring

indices from trees located in sensitive (tree-line) environments, and eolian, alluvial and fluvial sediments deposited

in a variety of contexts. Interpretations of past hunter and

gatherer adaptive strategies are based on a sample of 1,311

archaeological sites recorded during preconstruction surveys on Pahute and Rainier mesas in advance of the US

Department of Energy’s nuclear weapons testing program.

Projectile point chronologies and available tree-ring, radiocarbon, thermoluminescence and obsidian hydration dates

were used to assign these archaeological sites to specific

periods of use.

258

(DOE/NV/11508–35)

Evaluation of groundwater flow and transport at the

Shoal underground nuclear test: An interim report.

Pohll, G.; Chapman, J.; Hassan, A.; Papelis, C.; Andricevic,

R.; Shirley, C. University and Community College System of

Nevada, Desert Research Inst., Las Vegas, NV (United

States). Jul 1998. [325p.] Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract AC08-95NV11508. Order Number

DE98007140. Source: OSTI; NTIS; INIS; GPO Dep.

Desert Research Institute publication number 45162.

Since 1962, all United States nuclear tests have been

conducted underground. A consequence of this testing has

been the deposition of large amounts of radioactive materials in the subsurface, sometimes in direct contact with

groundwater. The majority of this testing occurred on the

Nevada Test Site, but a limited number of experiments were

conducted in other locations. One of these is the subject of

this report, the Project Shoal Area (PSA), located about 50

km southeast of Fallon, Nevada. The Shoal test consisted of

a 12-kiloton-yield nuclear detonation which occurred on

October 26, 1963. Project Shoal was part of studies to enhance seismic detection of underground nuclear tests, in

particular, in active earthquake areas. Characterization of

groundwater contamination at the Project Shoal Area is being conducted by the US Department of Energy (DOE)

under the Federal Facility Agreement and Consent Order

(FFACO) with the State of Nevada Department of Environmental Protection and the US Department of Defense

(DOD). This order prescribes a Corrective Action Strategy

(Appendix VI), which, as applied to underground nuclear

tests, involves preparing a Corrective Action Investigation

Plan (CAIP), Corrective Action Decision Document (CADD),

Corrective Action Plan, and Closure Report. The scope of

the CAIP is flow and transport modeling to establish contaminant boundaries that are protective of human health and

the environment. This interim report describes the current

status of the flow and transport modeling for the PSA.

259

(DOE/NV/11718–182)

Establishment of a facility for intrusive characterization

of transuranic waste at the Nevada Test Site. Foster,

B.D. (Bechtel Nevada Corp., Las Vegas, NV (United

States)); Musick, R.G.; Pedalino, J.P.; Cowley, J.L.; Karney,

C.C.; Kremer, J.L. Bechtel Nevada Inc., Las Vegas, NV

(United States). Jan 1998. 16p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States). DOE Contract AC08-96NV11718. (CONF-980307–:

Waste management ’98, Tucson, AZ (United States), 1-5

Mar 1998). Order Number DE98052961. Source: OSTI;

NTIS; INIS; GPO Dep.

This paper describes design and construction, project

management, and testing results associated with the Waste

Examination Facility (WEF) recently constructed at the

Nevada Test Site (NTS). The WEF and associated systems

were designed, procured, and constructed on an extremely

tight budget and within a fast track schedule. Part 1 of this

paper focuses on design and construction activities, Part 2

discusses project management of WEF design and construction activities, and Part 3 describes the results of the

transuranic (TRU) waste examination pilot project conducted

at the WEF. In Part 1, the waste examination process is described within the context of Waste Isolation Pilot Plant

(WIPP) characterization requirements. Design criteria are

described from operational and radiological protection considerations. The WEF engineered systems are described.

These systems include isolation barriers using a glove box

and secondary containment structure, high efficiency particulate air (HEPA) filtration and ventilation systems, differential

pressure monitoring systems, and fire protection systems. In

Part 2, the project management techniques used for ensuring that stringent cost/schedule requirements were met are

described. The critical attributes of these management systems are described with an emphasis on team work. In Part

3, the results of a pilot project directed at performing intrusive characterization (i.e., examination) of TRU waste at the

WEF are described. Project activities included cold and hot

operations. Cold operations included operator training,

facility systems walk down, and operational procedures validation. Hot operations included working with plutonium

contaminated TRU waste and consisted of waste container

breaching, waste examination, waste segregation, data collection, and waste repackaging.

260

(DOE/NV/11718–196)

Remedial actions of nuclear safety shot sites: Double

Tracks and Clean Slates. Sanchez, M. (Dept. of Energy,

Las Vegas, NV (United States)); Shotton, M.; Lyons, C.

Bechtel Nevada Inc., Las Vegas, NV (United States). Mar

1998. 11p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE

Contract AC08-96NV11718. (CONF-980307–: Waste management ’98, Tucson, AZ (United States), 1-5 Mar 1998).

Order Number DE98052973. Source: OSTI; INIS; NTIS;

GPO Dep.

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

Remedial actions of plutonium (Pu)-contaminated soils

are in the preliminary stages of development at the Nevada

Test Site (NTS). Interim clean-up actions were completed at

the Double Tracks and Clean Slate 1 safety shot sites in

1996 and 1997, respectively. Soil at both sites, with a total

transuranic activity greater than 20 picoCuries per gram

(pCi/g), was excavated and shipped to the NTS for disposal.

Characterization and assessment efforts were initiated at

the Double Tracks site in 1995, and the clean-up of this site

as an interim action was completed in 1996. Clean-up of this

site consisted of taking site-specific data and applying rationale for dose and risk calculations in selecting parameter

values for the interim corrective action level. The remediation process included excavating and stockpiling the

contaminated soil and loading the soil into supersacks with

approximately 1,513 cubic meters (53,500 cubic feet) being

shipped to the NTS for disposal. In 1997, remediation began

on the Clean Slate 1 site on which characterization had

already been completed using a very similar approach; however, the site incorporated lessons learned, cost efficiencies,

and significant improvements to the process. This paper focuses on those factors and the progress that has been

made in cleaning up the sites. The application of a technically reasonable remediation method, as well as the cost

factors that supported transport and disposal of the low-level

waste in bulk are discussed.

261

(DOE/OR–01-1709&D1)

Removal action work plan for the YS-860 Firing Ranges,

Oak Ridge Y-12 Plant, Oak Ridge, Tennessee. Oak Ridge

National Lab., TN (United States);ENTECH, Inc., Oak

Ridge, TN (United States). Mar 1998. 28p. Sponsored by

USDOE, Washington, DC (United States);USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract AC05-84OR21400. Order Number

DE98004260. Source: OSTI; NTIS; INIS; GPO Dep.

The US Department of Energy is conducting environmental restoration activities at the Y-12 Plant in Oak Ridge,

Tennessee. As part of these efforts, a removal action is

planned for the former YS-860 Firing Ranges as described

in the Action Memorandum for the project. This removal action work plan (RmAWP) is focused on the former YS-860

Firing Ranges, located outside the primary fenceline at the

eastern end of the plant. This RmAWP defines the technical

approach, procedures, and requirements for the removal of

lead-contaminated soil and site restoration of the former

YS-860 Firing Ranges at the Y-12 Plant. This RmAWP describes excavation, verification/confirmatory sampling, and

reporting requirements for the project. Lower tier plans associated with the RmAWP, which are submitted as separate

stand-alone documents, include a field sampling and analysis plan, a health and safety plan, a quality assurance

project plan, a waste management plan, a data management implementation plan, and a best management

practices plan. A site evaluation of the YS-86O Firing

Ranges conducted in 1996 by Lockheed Martin Energy Systems, Inc., determined that elevated lead levels were

present in the Firing Ranges target berm soils. The results

of this sampling event form the basis for the removal action

recommendation as described in the Action Memorandum

for this project. This RmAWP contains a brief history and

description of the Former YS-860 Firing Ranges Project,

along with the current project schedule and milestones. This

RmAWP also provides an overview of the technical requirements of the project, including a summary of the approach

for the removal activities. Finally, the RmAWP identifies the

regulatory requirements and the appropriate removal action

responses to address applicable or relevant and appropriate

requirements to achieve the project goals of substantially reducing the risk to human health and the environment.

262

(DOE/OR–11-1729&D1)

Portsmouth annual environmental report for 1997. Bechtel Jacobs Co., Environmental Compliance Div., Piketon, OH

(United States). Sep 1998. [250p.] Sponsored by USDOE

Office of Environmental Management, Washington, DC

(United States). DOE Contract AC05-98OR22700. Order

Number DE99000914. Source: OSTI; NTIS; INIS; GPO Dep.

The Portsmouth plant is one of two US Department of

Energy (DOE)-owned, contractor-managed uranium enrichment facilities in operation. As of July 1, 1993, responsibility

for implementing environmental compliance at the facility

was split between DOE, as site owner, and the US Enrichment Corporation (USEC), a government-owned corporation

formed by the Energy Policy Act of 1992, to operate the nation’s uranium enrichment business. The management

contractor for DOE in 1997 was Lockheed Martin Energy

Systems, which was responsible for environmental restoration, waste management, removal of highly enriched

uranium, and operation of nonleased facilities at the

Portsmouth Gaseous Diffusion Plant (DOE/PORTS). A new

5 1/2-year management and integration contract was

awarded by DOE to Bechtel Jacobs Company LLC on

December 18, 1997. Bechtel Jacobs Company officially assumed management responsibilities on April 1, 1998, when

the Lockheed Martin Energy Systems contract expired.

Lockheed Martin Utility Services provides management

services for USEC. The Nuclear Regulatory Commission assumed direct oversight of USEC operations, formerly a DOE

function, in March 1997.

263

(DOE/OR/21492–T8)

Developing biological and chemical methods for environmental monitoring of DOE waste disposal and

storage facilities. Progress report, April 1, 1985–October

30, 1985. Oak Ridge Research Inst., TN (United States).

[1997]. 168p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract AC05-84OR21492. Order Number DE98000012.

Source: OSTI; NTIS; INIS; GPO Dep.

During the first year of this contract great efforts were

made to develop methods for (1) characterizing bacteria

from soil and sediment, (2) evaluating the ability of single

and mixed soil bacterial isolates to, (a) bioconcentrate, (b)

biodegrade and/or (c) precipitate inorganic and organic pollutants and (3) expanding current concepts for treating

waste in aqueous (i.e. biological waste treatment system)

and solid media (i.e. in situ soil (soil) treatment system). The

development of the above methods are in the final stages of

completion and we have as a result of these efforts isolated

from soil (1) a mixed culture which precipitate toxic metals

(i.e. mercury cadmium, lead etc.) and (2) single isolates

which bioconcentrate a variety of toxic metals. Methods for

screening soil bacterial isolates for their ability to concentrate, degrade and/or precipitate environmental pollutants

have been developed. The development of those methods

64
Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

will allow the staff at ORRI to quickly screen hundreds of

samples in our attempt to isolate bacteria capable of degrading, concentrating and/or precipitating inorganics and

organics in aqueous and solid waste. The results of these

studies are summarized below.

264

(DOE/OR/21492–T9)

Removal of dissolved heavy metals and radionuclides

by microbial spores. Revis, N.W. (and others); Hadden,

C.T.; Edenborn, H. Oak Ridge Research Inst., TN (United

States). [1997]. 14p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States).

DOE Contract AC05-84OR21492. Order Number

DE98000856. Source: OSTI; NTIS; INIS; GPO Dep.

Microbial systems have been shown to remove specific

heavy metals from contaminated aqueous waste to levels

acceptable to EPA for environmental release. However, systems capable of removing a variety of heavy metals from

aqueous waste to environmentally acceptable levels remain

to be reported. The present studies were performed to determine the specificity of spores of the bacterium Bacillus

megaterium for the adsorption of dissolved metals and radionuclides from aqueous waste. The spores effectively

adsorbed eight heavy metals from a prepared metal mix and

from a plating rinse waste to EPA acceptable levels for

waste water. These results suggest that spores have multiple binding sites for the adsorption of heavy metals. Spores

were also effective in adsorbing the radionuclides

85strontium and 197cesium. The presence of multiple sites in

spores for the adsorption of heavy metals and radionuclides

makes this biosorbent a good candidate for the treatment of

aqueous wastes associated with the plating and nuclear industries. 17 refs., 4 tabs.

265

(DOE/OR/22207–1)

Ground-water flow and ground- and surface-water interaction at the Weldon Spring quarry, St. Charles County,

Missouri. Imes, J.L.; Kleeschulte, M.J. Geological Survey,

Rolla, MO (United States). 1997. 76p. Sponsored by USDOE Office of Environmental Management, Washington, DC

(United States). DOE Contract AI05-94OR22207. (USGSWRI–96-4279). Order Number DE98002779. Source: OSTI;

NTIS; INIS; GPO Dep.

Ground-water-level measurements to support remedial

actions were made in 37 piezometers and 19 monitoring

wells during a 19-month period to assess the potential for

ground-water flow from an abandoned quarry to the nearby

St. Charles County well field, which withdraws water from

the base of the alluvial aquifer. From 1957 to 1966, lowlevel radioactive waste products from the Weldon Spring

chemical plant were placed in the quarry a few hundred feet

north of the Missouri River alluvial plain. Uranium-based

contaminants subsequently were detected in alluvial ground

water south of the quarry. During all but flood conditions, lateral ground-water flow in the bedrock from the quarry, as

interpreted from water-table maps, generally is southwest

toward Little Femme Osage Creek or south into the alluvial

aquifer. After entering the alluvial aquifer, the ground water

flows southeast to east toward a ground-water depression

presumably produced by pumping at the St. Charles County

well field. The depression position varies depending on the

Missouri River stage and probably the number and location

of active wells in the St. Charles County well field.

266

(DOE/OR/22459–T1)

Development of an integrated in-situ remediation technology. Topical report for Task #3.2 entitled, “Modeling

and iron dechlorination studies” (September 26, 1994–

August 31, 1997). Shapiro, A.P. (General Electric Research

and Development, Schenectady, NY (United States));

Sivavec, T.M.; Principe, J.M. Monsanto Co., St. Louis, MO

(United States). Nov 1997. 72p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States). DOE Contract AC05-96OR22459. Order Number

DE98006103. Source: OSTI; NTIS; GPO Dep.

Contamination in low-permeability soils poses a significant

technical challenge to in-situ remediation efforts. Poor accessibility to the contaminants and difficulty in delivery of

treatment reagents have rendered existing in-situ treatments

such as bioremediation, vapor extraction, and pump and

treat rather ineffective when applied to low-permeability soils

present at many contaminated sites. The technology is an

integrated in-situ treatment in which established geotechnical methods are used to install degradation zones directly in

the contaminated soil, and electro-osmosis is utilized to

move the contaminants back and forth through those zones

until the treatment is complete. The present Topical Report

for Task #3.2 summarizes the modeling and dechlorination

research conducted by General Electric Research and Development.

267

(DOE/OR/22459–T2)

Development of an integrated in-situ remediation technology. Draft topical report for Task #3.3 entitled, “Iron

dechlorination studies” (September 26, 1994–August 31,

1997). Orth, R.; Dauda, T.; McKenzie, D.E. Monsanto Co.,

St. Louis, MO (United States). Nov 1997. 27p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract AC05-96OR22459. Order

Number DE98006119. Source: OSTI; NTIS; GPO Dep.

Contamination in low-permeability soils poses a significant

technical challenge to in-situ remediation efforts. Poor accessibility to the contaminants and difficulty in delivery of

treatment reagents have rendered existing in-situ treatments

such as bioremediation, vapor extraction, and pump and

treat rather ineffective when applied to low permeability soils

present at many contaminated sites. The technology is an

integrated in-situ treatment in which established geotechnical methods are used to install degradation zones directly in

the contaminated soil and electro-osmosis is utilized to

move the contaminants back and forth through those zones

until the treatment is completed. The present Topical Report

for Task #3.3 summarizes the iron dechlorination research

conducted by Monsanto Company.

268

(DOE/OR/22459–T3)

Development of an integrated in-situ remediation technology. Draft topical report for Task #7.2 entitled “Field

scale test” (January 10, 1996–December 31, 1997). Athmer, C. (and others); Ho, S.V.; Hughes, B.M. Monsanto Co.,

St. Louis, MO (United States). Nov 1997. 53p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract AC05-96OR22459. Order

Number DE98006120. Source: OSTI; NTIS; GPO Dep.

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

Contamination in low-permeability soils poses a significant

technical challenge to in-situ remediation efforts. Poor accessibility to the contaminants and difficulty in delivery of

treatment reagents have rendered existing in-situ treatments

such as bioremediation, vapor extraction, and pump and

treat rather ineffective when applied to low permeability soils

present at many contaminated sites. The technology is an

integrated in-situ treatment in which established geotechnical methods are used to install degradation zones directly in

the contaminated soil and electro-osmosis is utilized to

move the contaminants back and forth through those zones

until the treatment is completed. The present Topical Report

for Task #7.2 summarizes the Field Scale Test conducted by

Monsanto Company, DuPont, and General Electric.

269

(DOE/OR/22520–T1)

Tennessee Department of Environment and Conservation Department of Energy Oversight Division - status

report to the public. Tennessee Dept. of Environment and

Conservation, Oak Ridge, TN (United States). Oct 1997.

64p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

FG05-96OR22520 ; FG05-96OR22521. Order Number

DE98004455. Source: OSTI; NTIS (US Sales Only); GPO

Dep.

The Oak Ridge Reservation, encompassing about 35,500

acres in Oak Ridge, Tennessee, is one of the largest US

Department of Energy (DOE) sites in the nation. The DOE

missions here employ more than 11,000 individuals at three

major facilities. The Manhattan Project and the Cold War left

a legacy of hazardous and radioactive waste around the

country at many sites, including Oak Ridge. The Cold War

has now come to an end, and the mission for DOE’s three

Oak Ridge plants is changing. With this change, environmental restoration has become a focal point for the State,

DOE and the community. Seeing the impacts DOE had on

the region, the State of Tennessee asserted its authority

over activities on the Oak Ridge Reservation. This authority

included enforcement of regulations, monitoring of the environment and oversight of cleanup on the ORR. The State’s

role has been enhanced by two major agreements that

govern the relationship between DOE and the State of Tennessee. This report outlines the State of Tennessee’s DOE

Oversight Division’s efforts to monitor residual contamination

and continuing releases to the air, water and land. It explains the complex issues surrounding DOE’s storage,

treatment and disposal of mixed and radioactive waste, and

its handling of contaminated sites and buildings. The report

also includes a list of further resources available to the interested reader.

270

(DOE/OSTI–3411/3)

The Office of Environmental Management technical reports: A bibliography. Dept. of Energy, Office of Scientific

and Technical Information, Oak Ridge, TN (United States).

Jul 1998. 260p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). Order

Number DE98005317. Source: OSTI; NTIS; GPO Dep.

The Office of Environmental Management’s (EM) technical reports bibliography is an annual publication that

contains information on scientific and technical reports sponsored by the Office of Environmental Management added to

the Energy Science and Technology Database from July 1,

1995–that were published from October 1, 1996–September

30, 1997. This information is divided into the following categories: Miscellaneous, Focus Areas and Crosscutting

Programs, Support Programs, Technology Integration and

International Technology Exchange, are now included in the

Miscellaneous category. The Office of Environmental

Management within the Department of Energy (DOE) is responsible for environmental restoration, waste management,

technology development and facility transition and management. Subjects include: subsurface contaminants; mixed

waste characterization, treatment and disposal; radioactive

tank waste remediation; plutonium; deactivation and decommissioning; robotics; characterization, monitoring, and

sensor technology; and efficient separations. 880 refs.

271

(DOE/R2/08007–T1)

NICE-3. Technical progress report, March 1, 1995–

October 31, 1995. New Jersey Public Utilities Board,

Newark, NJ (United States). [1997]. 4p. Sponsored by USDOE Office of Environmental Management, Washington, DC

(United States). DOE Contract FG43-92R208007. Order

Number DE98000954. Source: OSTI; NTIS; INIS; GPO Dep.

This is the final report on a project to demonstrate the application of ultrasonic cleaning technology to the task of tank

cleaning. The major activities in this period were the presentation of three technology sharing seminars to describe the

results achieved in this program.

272

(DOE/RL–91-50-Rev.2)

Environmental Monitoring Plan United States Department of Energy Richland Operations Office. Revision 2.

Pacific Northwest National Lab., Richland, WA (United

States); Fluor Daniel Hanford, Inc., Richland, WA (United

States); Waste Management Federal Services of Hanford,

Inc., Richland, WA (United States); Bechtel Hanford, Inc.,

Richland, WA (United States). 10 Nov 1997. [250p.] Sponsored by USDOE Office of Environmental Management,

Washington, DC (United States). DOE Contract AC06-

76RL01830. Order Number DE98050554. Source: OSTI;

NTIS; INIS; GPO Dep.

This Environmental Monitoring Plan was prepared for the

US Department of Energy’s (DOE’s) Richland Operations

Office (RL) to implement the requirements of DOE Order

5400.1. According to the Order, each DOE site, facility, or

activity that uses, generates, releases, or manages significant pollutants or hazardous materials shall prepare a

written environmental monitoring plan covering two major

activities: (1) effluent monitoring and (2) environmental

surveillance. The plan is to contain information discussing

the rationale and design criteria for the monitoring programs, sampling locations and schedules, quality assurance

requirements, program implementation procedures, analytical procedures, and reporting requirements. The plan’s

purpose is to assist DOE in the management of environmental activities at the Hanford Site and to help ensure that

operations on the site are conducted in an environmentally

safe and sound manner.

273

(DOE/RL–96-66)

RCRA corrective measure study for the 200-PO-1 operable unit. Bechtel Hanford, Inc., Richland, WA (United

States). Dec 1997. 107p. Sponsored by USDOE Office of

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

Environmental Management, Washington, DC (United

States). DOE Contract AC06-93RL12367. Order Number

DE97051699. Source: OSTI; NTIS; INIS; GPO Dep.

This Resource Conservation and Recovery Act of 1976

(RCRA) corrective measures study (CMS) report supports

the RCRA Facility Investigation process for the 200-PO-1

Groundwater Operable Unit in the 200 East Area of the

Hanford Site, located in Richland, Washington. This CMS

evaluates the need for interim actions and potential corrective measure that could be used should interim actions be

necessary. An evaluation of final actions would be coordinated with evaluations of actions at the source operable

unit. This CMS identifies, screens, and develops potential

corrective measures alternatives for three major contaminant plumes associated with a single RCRA treatment,

storage, or disposal unit and not with the remainder of the

operable unit evaluated.

274

(DOE/RL–97-75)

Sampling and Analysis Plan for the REDOX Plutonium

Loadout Hood. Encke, D.B. Bechtel Hanford, Inc., Richland, WA (United States). Mar 1998. 49p. Sponsored by

USDOE, Washington, DC (United States);USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract AC06-93RL12367. Order Number

DE98054159. Source: OSTI; NTIS; INIS; GPO Dep.

This sampling and analysis plan presents the rationale

and strategy for the sampling and analysis activities proposed in support of decontaminating and removing the

Plutonium Loadout Hood from the Reduction Oxidation

(REDOX) process canyon building. The results of this investigation will be used to estimate the types of radiological and

chemical contaminants and for initial waste designations for

the component vessels, pipes, loadout hood frame and plexiglass, decontamination materials, and debris, as well as for

development of future safety analysis documentation for

eventual removal of the Plutonium Loadout Hood.

275

(DOE/RL–98-031)

300 Area Process Trenches Postclosure Plan. Badden,

J.W. Bechtel Hanford, Inc., Richland, WA (United States).

May 1998. 32p. Sponsored by USDOE, Washington, DC

(United States);USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

W-7405-ENG-48. DE-AC06-93RL-12367. Order Number

DE98057348. Source: OSTI; INIS; NTIS; GPO Dep.

The 300 Area Process Trenches (300 APT) certified closure under a modified closure option and in compliance with

Condition II.K.3 oft he Hartford Facility Dangerous Waste

Permit (Penit) (Ecology 1994). Modified closure has been

determined to be the appropriate closure option for this unit

due to groundwater that remains contaminated from past

operations at the 300 APT. Corrective actions required for

dangerous waste constituents remaining in groundwater will

occur pursuant to the 300 APT Resource Conservation and

Recovery Act (RCRA) Final Status Facility Ground Water

Monitoring Plan, the Hanford Site Wide Dangerous Waste

Permit, and in conjunction with the Comprehensive Environmental Response, Compensation, and Liability Act

(CERCLA) remedial actions at the 300-FF-5 Groundwater

Operable Unit (OU) pursuant to the Record of Decision

(ROD) (EPA 1996). This postclosure plan identifies the modified closure actions required at the unit under postclosure

care. It contains a description of the unit, past closure

actions, and postclosure care requirements subject to compliance under the Permit (condition II.K.3).

276

(DOE/RL–98-035)

Surveillance and Maintenance Plan for the Plutonium

Uranium Extraction (PUREX) Facility. Woods, P.J. Bechtel Hanford, Inc., Richland, WA (United States). May 1998.

81p. Sponsored by USDOE, Washington, DC (United

States);USDOE Office of Environmental Management,

Washington, DC (United States). DOE Contract W-7405-

ENG-48. DE-AC06-93RL-12367. Order Number

DE98057349. Source: OSTI; INIS; NTIS; GPO Dep.

This document provides a plan for implementing surveillance and maintenance (S&M) activities to ensure the

Plutonium Uranium Extraction (PUREX) Facility is maintained in a safe, environmentally secure, and cost-effective

manner until subsequent closure during the final disposition

phase of decommissioning. This plan has been prepared in

accordance with the guidelines provided in the U.S.

Department of Energy (DOE), Office of Environmental Management (EM) Decommissioning Resource Manual (DOE/

EM-0246) (DOE 1995), and Section 8.6 of TPA change form

P-08-97-01 to the Hanford Federal Facility Agreement and

Consent Order (Tri-Party Agreement) (Ecology, et al. 1996).

Specific objectives of the S&M program are: Ensure adequate containment of remaining radioactive and hazardous

material. Provide security control for access into the facility

and physical safety to surveillance personnel. Maintain the

facility in a manner that will minimize potential hazards to

the public, the environment, and surveillance personnel.

Provide a plan for the identification and compliance with applicable environmental, safety, health, safeguards, and

security requirements.

277

(DOE/RL–98-043)

105-F and DR Phase 1 Sampling and Analysis Plan.

Curry, L.R. Bechtel Hanford, Inc., Richland, WA (United

States). Jun 1998. 122p. Sponsored by USDOE, Washington, DC (United States);USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract W-7405-ENG-48. DE-AC06-93RL-12367. Order

Number DE98057512. Source: OSTI; INIS; NTIS; GPO Dep.

This SAP presents the rationale and strategy for characterization of specific rooms within the 105-F and 105-DR

reactor buildings. Figures 1-1 and 1-2 identify the rooms that

are the subject of this SAP. These rooms are to be decontaminated and demolished as an initial step (Phase 1 ) in

the Interim Safe Storage process for these reactors. Section

1.0 presents the background and sites history for the reactor

buildings and summarizes the data quality objective process,

which provides the logical basis for this SAP. Preliminary

surveys indicate that little radiochemical contamination is

present. Section 2.0 presents the quality assurance project

plan, which includes a project management structure, sampling methods and quality control, and oversight of the

sampling process. Section 2.2.1 summarizes the sampling

methods, reflecting the radiological and chemical sampling

designs presented in Tables 1-17 and 1-18. Section 3.0

presents the Field Sampling Plan for Phase 1. The sampling

design is broken into two stages. Stage 1 will verify the list

of radioactive constituents of concern and generate the isotopic distribution. The objectives of Stage 2 are to estimate

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

the radionuclide inventories of room debris, quantify chemical contamination, and survey room contents for potential

salvage or recycle. Table 3-1 presents the sampling activities

to be performed in Stage 1. Tables 1-17 and 1-18 identify

samples to be collected in Stage 2. Stage 2 will consist

primarily of survey data collection, with fixed laboratory samples to be collected in areas showing visible stains. Quality

control sampling requirements are presented in Table 3-2.

278

(DOE/RW–0006-Rev.13)

Integrated data base report–1996: US spent nuclear fuel

and radioactive waste inventories, projections, and

characteristics. Oak Ridge National Lab., TN (United

States). Dec 1997. 263p. Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract AC05-96OR22464. Order Number

DE98003259. Source: OSTI; NTIS; INIS; GPO Dep.

The Integrated Data Base Program has compiled historic

data on inventories and characteristics of both commercial

and U.S. Department of Energy (DOE) spent nuclear fuel

(SNF) and commercial and U.S. government-owned radioactive wastes. Inventories of most of these materials are

reported as of the end of fiscal year (FY) 1996, which is

September 30, 1996. Commercial SNF and commercial

uranium mill tailings inventories are reported on an end-ofcalendar year (CY) basis. All SNF and radioactive waste

data reported are based on the most reliable information

available from government sources, the open literature,

technical reports, and direct contacts. The information forecasted is consistent with the latest DOE/Energy Information

Administration (EIA) projections of U.S. commercial nuclear

power growth and the expected DOE-related and private industrial and institutional activities. The radioactive materials

considered, on a chapter-by-chapter basis, are SNF, highlevel waste, transuranic waste, low-level waste, uranium mill

tailings, DOE Environmental Restoration Program contaminated environmental media, naturally occurring and

accelerator-produced radioactive material, and mixed (hazardous and radioactive) low-level waste. For most of these

categories, current and projected inventories are given

through FY 2030, and the radioactivity and thermal power

are calculated based on reported or estimated isotopic compositions.

279

(DOE/SF/20686–T2)

Final annual site environmental report, calendar year

1997, for the Laboratory for Energy-Related Health

Research (LEHR), University of California at Davis, California. Weiss Associates, Emeryville, CA (United States).

Sep 1998. [200p.] Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE

Contract AC03-96SF20686. Order Number DE99000732.

Source: OSTI; NTIS; INIS; GPO Dep.

This Annual Site Environmental Report (ASER) describes

DOE activities for the Environmental Restoration/Waste

Management (ER/WM) Project at the Laboratory for EnergyRelated Health Research (LEHR) site at UC Davis

California. The report provides information about the Site

and its environmental monitoring operation throughout calendar year 1997 for both radiological and non-radiological

parameters. This report also describes activities conducted

during 1997 in support of the Site environmental restoration

efforts, and information about the impact of these activities

on the public and the environment.

280

(DOE/SF/21375–T1)

Tribal Colleges Initiative project. Quarterly report, April

1–June 30, 1998. Crownpoint Inst. of Tech., NM (United

States);Dine Coll., Tsaile, AZ (United States);Southwestern

Indian Polytechnic Inst., Albuquerque, NM (United States).

Jul 1998. 16p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE

Contract FG03-97SF21375. Order Number DE98007291.

Source: OSTI; NTIS; GPO Dep.

The Tribal Colleges Initiative (TCI) grant is in the second

year of funding from the US Department of Energy Environmental Management program. This quarterly report includes

activities for the first three months (April 1–June 30, 1998) of

the Year 2 funding period. The TCI program office requested

each Tribal College to write a quarterly report of activities at

their respective institutions. These reports are attached.

These institutions are Southwestern Indian Polytechnic Institute (SIPI), Crownpoint Institute of Technology (CIT) and the

Dine’ College (DC, formerly Navajo Community College).

The purpose of this program is to offer educational opportunities to Native Americans in the environmental field.

281

(DOE/SF/21375–T2)

Tribal Colleges Initiative project. Quarterly report, April

1–June 30, 1998. Southwestern Indian Polytechnic Inst., Albuquerque, NM (United States);Tribal College Initiative

Program Office (United States);Crownpoint Inst. of Tech.

(United States);Dine’ Coll., Tsaile, AZ (United States). Jul

1998. [50p.] Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract FG03-97SF21375. Order Number DE99000074.

Source: OSTI; NTIS; GPO Dep.

The Tribal Colleges Initiative (TCI) grant is in the second

year of funding from the US Department of Energy Environmental Management Program. The project period has been

determined to be 7.5 months, April 1 to November 14, 1998

in order to align with the federal fiscal year. This quarterly

report includes activities for the first three months (April

1–June 30, 1998) of the Year 2 funding period. The TCI Program office requested each Tribal College to write a

quarterly report of activities at their respective institutions.

These reported are attached. These institutions are Southwestern Indian Polytechnic Institute (SIPI), Crownpoint

Institute of Technology (CIT) and the Dine’ College (DC, formerly Navajo Community College).

282

(DOE/SNF/REP–011-Vol.1)

Preliminary design specification for Department of Energy standardized spent nuclear fuel canisters. Volume

1: Design specification. Lockheed Martin Idaho Technologies Co., Idaho National Engineering and Environmental

Lab., Idaho Falls, ID (United States). 19 Aug 1998. 27p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC07-94ID13223. Order Number DE98058451. Source:

OSTI; NTIS; INIS; GPO Dep.

This document (Volume 1) is the preliminary design specification for the canisters to be used during the handling,

68
Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

storage, transportation, and repository disposal of Department of Energy (DOE) spent nuclear fuel (SNF). This

document contains no procurement information, such as the

number of canisters to be fabricated, explicit timeframes for

deliverables, etc. A companion document (Volume 2) provides background information and design philosophy in

order to help engineers better understand the established

design requirements for these DOE SNF canisters.

283

(DOE/SNF/REP–011-Vol.2)

Preliminary design specification for Department of Energy standardized spent nuclear fuel canisters. Volume

2: Rationale document. Lockheed Martin Idaho Technologies Co., Idaho National Engineering and Environmental

Lab., Idaho Falls, ID (United States). 19 Aug 1998. 41p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC07-94ID13223. Order Number DE98007434. Source:

OSTI; NTIS; INIS; GPO Dep.

This document (Volume 2) is a companion document to a

preliminary design specification for the design of canisters to

be used during the handling, storage, transportation, and

repository disposal of Department of Energy (DOE) spent

nuclear fuel (SNF). This document contains no procurement

information, such as the number of canisters to be fabricated, explicit timeframes for deliverables, etc. However,

this rationale document does provide background information and design philosophy in order to help engineers better

understand the established design criteria (contained in Volume 1 respectively) necessary to correctly design and

fabricate these DOE SNF canisters.

284

(DOE/SNF/REP–014)

Deployment evaluation methodology for the electrometallurgical treatment of DOE-EM spent nuclear fuel. Dahl,

C.A.; Adams, J.P.; Ramer, R.J. Dept. of Energy, Office of

Spent Fuel Management and Special Projects, Washington,

DC (United States). Jul 1998. 66p. Sponsored by USDOE

Office of Environmental Management, Washington, DC

(United States). DOE Contract AC07-94ID13223. Order

Number DE98058450. Source: OSTI; NTIS; INIS; GPO Dep.

Part of the Department of Energy (DOE) spent nuclear fuel

(SNF) inventory may require some type of treatment to meet

acceptance criteria at various disposition sites. The current

focus for much of this spent nuclear fuel is the electrometallurgical treatment process under development at Argonne

National Laboratory. Potential flowsheets for this treatment

process are presented. Deployment of the process for the

treatment of the spent nuclear fuel requires evaluation to determine the spent nuclear fuel program need for treatment

and compatibility of the spent nuclear fuel with the process.

The evaluation of need includes considerations of cost,

technical feasibility, process material disposition, and schedule to treat a proposed fuel. A siting evaluation methodology

has been developed to account for these variables. A work

breakdown structure is proposed to gather life-cycle cost information to allow evaluation of alternative siting strategies

on a similar basis. The evaluation methodology, while created specifically for the electrometallurgical evaluation, has

been written such that it could be applied to any potential

treatment process that is a disposition option for spent nuclear fuel. Future work to complete the evaluation of the

process for electrometallurgical treatment is discussed.

285

(DOE/SR/18445–T5)

Infrastructure support for a waste management

institute. Final project report, September 12, 1994–

September 11, 1997. North Carolina Agricultural and

Technical State Univ., Greensboro, NC (United States).

[1997]. 152p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract FG09-94SR18445. Order Number DE98001110.

Source: OSTI; NTIS; GPO Dep.

North Carolina A and T State University has completed

the development of an infrastructure for the interdisciplinary

Waste Management Institute (WMI). The Interdisciplinary

Waste Management Institute (WMI) was approved in June,

1994 by the General Administration of the University of

North Carolina as an academic support unit with research

and public service functions. The mission of the WMI is to

enhance awareness and understanding of waste management issues and to provide instructional support including

research and outreach. The goals of WMI are as follows: increase the number of minority professionals who will work in

waste management fields; develop cooperative and exchange programs involving faculty, students, government,

and industry; serve as institutional sponsor of public

awareness workshops and lecture series; and support interdisciplinary research programs. The vision of the WMI is to

provide continued state-of-the art environmental educational

programs, research, and outreach.

286

(EEG–65)

Probability of failure of the waste hoist brake system at

the Waste Isolation Pilot Plant (WIPP). Greenfield, M.A.

(Univ. of California, Los Angeles, CA (United States)); Sargent, T.J. Environmental Evaluation Group, Albuquerque,

NM (United States). Jan 1998. 30p. Sponsored by USDOE

Office of Environmental Management, Washington, DC

(United States). DOE Contract AC04-89AL58309. Order

Number DE98004011. Source: OSTI; NTIS; INIS; GPO Dep.

In its most recent report on the annual probability of failure of the waste hoist brake system at the Waste Isolation

Pilot Plant (WIPP), the annual failure rate is calculated to be

1.3E(7)(1/yr), rounded off from 1.32E(7). A calculation by

the Environmental Evaluation Group (EEG) produces a result that is about 4% higher, namely 1.37E(7)(1/yr). The

difference is due to a minor error in the US Department of

Energy (DOE) calculations in the Westinghouse 1996 report.

WIPP’s hoist safety relies on a braking system consisting of

a number of components including two crucial valves. The

failure rate of the system needs to be recalculated periodically to accommodate new information on component

failure, changes in maintenance and inspection schedules,

occasional incidents such as a hoist traveling out-of-control,

either up or down, and changes in the design of the brake

system. This report examines DOE’s last two reports on the

redesigned waste hoist system. In its calculations, the DOE

has accepted one EEG recommendation and is using more

current information about the component failures rates, the

Nonelectronic Parts Reliability Data (NPRD). However, the

DOE calculations fail to include the data uncertainties which

are described in detail in the NPRD reports. The US Nuclear

Regulatory Commission recommended that a system evaluation include mean estimates of component failure rates and

take into account the potential uncertainties that exist so

that an estimate can be made on the confidence level to be

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

ascribed to the quantitative results. EEG has made this suggestion previously and the DOE has indicated why it does

not accept the NRC recommendation. Hence, this EEG report illustrates the importance of including data uncertainty

using a simple statistical example.

287

(EEG–71)

Mine stability evaluation of panel 1 during waste emplacement operations at WIPP. Maleki, H. (Maleki

Technologies Inc., Spokane, WA (United States)). Environmental Evaluation Group, Albuquerque, NM (United

States);Environmental Evaluation Group, Carlsbad, NM

(United States). Jul 1998. [100p.] Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States). DOE Contract AC04-89AL58309. Order Number

DE98007031. Source: OSTI; NTIS; INIS; GPO Dep.

The specific objectives of the work were defined by the

Environmental Evaluation Group (EEG) as follows: (1) assess the stability of panel 1 during the proposed operation

of waste emplacement; (2) estimate the amount of time before room closure would be expected to transfer rock loads

to the waste packages. The work consisted of (1) an analysis of geotechnical data and a review of the Department of

Energy’s (DOE) plans for waste emplacement in panel 1, (2)

an evaluation of ground conditions based on data analysis

and observations of changes in ground conditions since the

first evaluation in 1993 (USBM 1993), and (3) preparation of

a report and presentation of the results to EEG staff. Excluded from this study are radiological safety issues and

policies. The study is based on data provided by DOE and

Westinghouse Electric Corporation (operator of the site) and

conversations with DOE and Westinghouse personnel. MTI

cannot independently verify the accuracy of the data within

the scope of this study and recommends independent evaluations of data gathering, quality assurance procedures, and

structural designs. The operator has the ultimate responsibility for structural designs and has expressed a strong

commitment to ensuring worker safety.

288

(EML–590)

ISD97, a computer program to analyze data from a series of in situ measurements on a grid and identify

potential localized areas of elevated activity. Reginatto,

M.; Shebell, P.; Miller, K.M. Dept. of Energy, Environmental

Measurements Lab., New York, NY (United States). Oct

1997. 82p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). Order Number DE98007054. Source: OSTI; NTIS; INIS; GPO Dep.

A computer program, ISD97, was developed to analyze

data from a series of in situ measurements on a grid and

identify potential localized areas of elevated activity. The

ISD97 code operates using a two-step process. A deconvolution of the data is carried out using the maximum entropy

method, and a map of activity on the ground that fits the

data within experimental error is generated. This maximum

entropy map is then analyzed to determine the locations and

magnitudes of potential areas of elevated activity that are

consistent with the data. New deconvolutions are then carried out for each potential area of elevated activity identified

by the code. Properties of the algorithm are demonstrated

using data from actual field measurements.

289

(EML–592)

Preparation and validation of gross alpha/beta samples

used in EML’s quality assessment program. Scarpitta,

S.C. Dept. of Energy, Environmental Measurements Lab.,

New York, NY (United States). Oct 1997. 29p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). Order Number DE98007063. Source:

OSTI; NTIS; INIS; GPO Dep.

A set of water and filter samples have been incorporated

into the existing Environmental Measurements Laboratory’s

(EML) Quality Assessment Program (QAP) for gross alpha/

beta determinations by participating DOE laboratories. The

participating laboratories are evaluated by comparing their

results with the EML value. The preferred EML method for

measuring water and filter samples, described in this report,

uses gas flow proportional counters with 2 in. detectors.

Procedures for sample preparation, quality control and instrument calibration are presented. Liquid scintillation (LS)

counting is an alternative technique that is suitable for quantifying both the alpha (241Am, 230Th and 238Pu) and beta

(

90Sr/90Y) activity concentrations in the solutions used to

prepare the QAP water and air filter samples. Three LS

counting techniques (Cerenkov, dual dpm and full spectrum

analysis) are compared. These techniques may be used to

validate the activity concentrations of each component in the

alpha/beta solution before the QAP samples are actually

prepared.

290

(EML–593)

A portable battery-powered continuous airborne 222Rn

sampler. Scarpitta, S.; Kadnar, M. Dept. of Energy, Environmental Measurements Lab., New York, NY (United States).

Apr 1998. 28p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). Order

Number DE98007064. Source: OSTI; NTIS; INIS; GPO Dep.

The Polyport, designed at the Environmental Measurements Laboratory (EML) for deployment in atmospheric

balloons or remote areas, was laboratory and field tested to

determine its effectiveness in collecting 222Rn gas in dry and

humid air. Twelve 6-cm long tubes containing 0.4 g of

Carboxen-564 a hydrophobic beaded carbon molecular

sieve (BCMS) material efficiently adsorbs airborne 222Rn under dynamic sampling conditions of 1–2 hr duration. The

exposed sorbent is later weighed for water uptake, transferred and counted in a low background liquid scintillation

(LS) counter that can detect alpha and beta emitting 222Rn

progeny with a maximum counting efficiency of 5 cpm per

dpm. Each sorbent tube can be gamma counted if it contains sufficient adsorbed 214Pb and 214Bi activity. The

variables tested were sampling flow rate, temperature, sampling time and relative humidity (RH).

291

(EML–594)

Semi-annual report of the Department of Energy, Office

of Environmental Management, Quality Assessment

Program. Greenlaw, P.D. Dept. of Energy, Environmental

Measurements Laboratory, New York, NY (United States).

Jan 1998. 324p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States).

Order Number DE98007065. Source: OSTI; NTIS; INIS;

GPO Dep.

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

This Quality Assessment Program (QAP) is designed to

test the quality of the environmental measurements being reported to the Department of Energy by its contractors. Since

1976, real or synthetic environmental samples that have

been prepared and thoroughly analyzed at the Environmental Measurements Laboratory (EML) have been distributed

at first quarterly and then semi-annually to these contractors.

Their results, which are returned to EML within 90 days, are

compiled with EML’s results and are reported back to the

participating contractors 30 days later. A summary of the reported results is available to the participants 4 days after the

reporting deadline via the Internet at www.eml.doe.gov. This

report presents the results from the analysis of the 47th set

of environmental quality assessment samples (QAP XLVII)

that were received on or before December 1, 1997.

292

(EML–595)

MAXED, a computer code for the deconvolution of multisphere neutron spectrometer data using the maximum

entropy method. Reginatto, M.; Goldhagen, P. Dept. of Energy, Environmental Measurements Lab., New York, NY

(United States). Jun 1998. 37p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States). Order Number DE98007067. Source: OSTI; NTIS;

INIS; GPO Dep.

The problem of analyzing data from a multisphere neutron

spectrometer to infer the energy spectrum of the incident

neutrons is discussed. The main features of the code

MAXED, a computer program developed to apply the maximum entropy principle to the deconvolution (unfolding) of

multisphere neutron spectrometer data, are described, and

the use of the code is illustrated with an example. A user’s

guide for the code MAXED is included in an appendix. The

code is available from the authors upon request.

293

(EML–596)

Semi-annual report of the Department of Energy, Office

of Environmental Management, Quality Assessment

Program. Greenlaw, P.D.; Minick, S.K. Dept. of Energy, Environmental Measurement Lab., New York, NY (United

States). 1 Jul 1998. 327p. Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

States). Order Number DE99000898. Source: OSTI; NTIS;

INIS; GPO Dep.

This Quality Assessment Program (QAP) is designed to

test the quality of the environmental measurements being

reported to the Department of Energy by its contractors.

Since 1976, real or synthetic environmental samples that

have been prepared and thoroughly analyzed at the Environmental Measurements Laboratory (EML) have been

distributed at first quarterly and then semi-annually to these

contractors. Their results, which are returned to EML within

90 days, are compiled with EML’s results and are reported

back to the participating contractors 30 days later. This report presents the results from the analysis of the 48th set of

environmental quality assessment samples (QAP XLVIII)

that were received on or before June 1, 1998.

294

(ESRF–025)

Landowner and permit-holder perceptions of wildlife

damage around the Idaho National Engineering and Environmental Laboratory. A survey of INEEL neighbors

about elk, mule deer, pronghorn antelope, and depredation. Roush, D.E. Jr. (Environmental Science and Research

Foundation, Inc., Idaho Falls, ID (United States)); Beaver,

D.E. Environmental Science and Research Foundation Inc.,

Idaho Falls, ID (United States). Jun 1998. 37p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract AC07-94ID13268. Order

Number DE98005880. Source: OSTI; NTIS; GPO Dep.

Property-owners (N = 220) around the Idaho National Engineering and Environmental Laboratory (INEEL) in

southeastern Idaho were surveyed about depredation, control methods and economic issues related to use of the area

by elk (Cervus elaphus), mule deer (Odocoileus hemionus),

and pronghorn antelope (Antilocapra americana). Depredation was defined as damage to privately-owned crops,

forage, and fences and irrigation equipment by these animals. The focus on the three ungulate species was

prompted by concerns that elk, which had recolonized the

INEEL since 1984, were responsible for an inordinate

amount of unprecedented damage to agricultural operations.

As the INEEL is a US Department of Energy (DOE) reserve

with little public hunting access, there have been calls for removal of elk from this land. This study’s objective was to

quantify the wildlife damage occurring on agricultural operations adjacent to the INEEL and to characterize the damage

attributed to each big game species. Responses from 70.2%

of the target population indicate an evenness of opinion, by

which the authors mean that various opinions were represented equitably, toward these animals and wildlife damage

Total estimated wildlife damage in 1996 was between

$140,000 and $180,000 It was attributed foremost to elk,

although pronghorn antelope were viewed nearly as damaging. Respondents placed high values in big game animals

and wished to see them continue to inhabit these lands. For

managing depredation, adjusting hunting seasons was preferred.

295

(ESRF–027)

Environmental Science and Research Foundation, Inc.

annual technical report: Calendar year 1997. Reynolds,

R.D.; Warren, R.W. (eds.). Environmental Science and Research Foundation, Inc., Idaho Falls, ID (United States).

May 1998. 109p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE

Contract AC07-94ID13268. Order Number DE98003890.

Source: OSTI; NTIS; INIS; GPO Dep.

This Annual Technical Report describes work conducted

for the Department of Energy, Idaho Operations Office

(DOE-ID), by the Environmental Science and Research

Foundation (Foundation). The Foundation’s mission to DOEID provides support in several key areas. The Foundation

conducts an environmental monitoring and surveillance program over an area covering much of the upper Snake River

Plain, and provides environmental education and support

services related to Idaho National Engineering and Environmental Laboratory (INEEL) natural resource issues. Also,

the Foundation, with its University Affiliates, conducts ecological and radioecological research on the Idaho National

Environmental Research Park. This research benefits major

DOE-ID programs including Waste Management, Environmental Restoration, Spent Nuclear Fuels, and Land

Management Issues. Summaries are included of the individual research projects.

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

296

(FEMP–2535)

Presidential Rapid Commercialization Initiative for

mixed waste solvent extraction. Honigford, L. (Fluor

Daniel Fernald, Inc., Cincinnati, OH (United States). Fernald

Environmental Management Project); Dilday, D.; Cook, D.;

Sattler, J. Fluor Daniel Fernald, Inc., Cincinnati, OH (United

States). [1997]. 8p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE

Contract AC24-92OR21972. (CONF-970335–32: Waste

Management ‘97, Tucson, AZ (United States), 2-7 Mar

1997). Order Number DE97004117. Source: OSTI; NTIS;

INIS; GPO Dep.

Recently, the Fernald Environmental Management Project

(FEMP) has made some major steps in mixed waste treatment which have taken it closer to meeting final remediation

goals. However, one major hurdle remains for the FEMP

mixed waste treatment program, and that hurdle is tri-mixed

waste. Tri-mixed is a term coined to describe low-level

waste containing RCRA hazardous constituents along with

polychlorinated biphenyls (PCB). The prescribed method for

disposal of PCBs is incineration. In mixed waste treatment

plans developed by the FEMP with public input, the FEMP

committed to pursue non-thermal treatment methods and

avoid the use of incineration. Through the SITE Program,

the FEMP identified a non-thermal treatment technology

which uses solvents to extract PCBs. The technology belongs to a small company called Terra-Kleen Response

Group, Inc. A question arose as to how can this new and innovative technology be implemented by a small company at

a Department of Energy (DOE) facility. The answer came in

the form of the Rapid Commercialization Initiative (RCI) and

the Mixed Waste Focus Area (MWFA). RCI is a program

sponsored by the Department of commerce (DOC), DOE,

Department of Defense (DOD), US EPA and various state

agencies to aid companies to market new and innovative

technologies.

297

(HLW-OVP–98-0037)

High Level Waste System Plan Revision 9. Davis, N.R.;

Wells, M.N.; Choi, A.S.; Paul, P.; Wise, F.E. Westinghouse

Savannah River Company, Aiken, SC (United States). Apr

1998. 100p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract AC09-96SR18500. Order Number DE98058909.

Source: OSTI; NTIS; INIS; GPO Dep.

Revision 9 of the High Level Waste System Plan documents the current operating strategy of the HLW System at

SRS to receive, store, treat, and dispose of high-level waste.

298

(INEEL–95/0109-Rev.2)

Position for determining gas-phase volatile organic

compound concentrations in transuranic waste containers. Revision 2. Connolly, M.J. (Lockheed Martin Idaho

Technologies Co., Idaho Falls, ID (United States). Idaho National Engineering and Environmental Lab.); Liekhus, K.J.;

Djordjevic, S.M.; Loehr, C.A.; Spangler, L.R. Lockheed Martin Idaho Technologies, Idaho National Engineering and

Environmental Lab., Idaho Falls, ID (United States). Jun

1998. 79p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract AC07-94ID13223. Order Number DE98057352.

Source: OSTI; NTIS; INIS; GPO Dep.

In the conditional no-migration determination (NMD) for

the test phase of the Waste Isolation Pilot Plant (WIPP), the

US Environmental Protection Agency (EPA) imposed certain

conditions on the US Department of Energy (DOE)

regarding gas phase volatile organic compound (VOC) concentrations in the void space of transuranic (TRU) waste

containers. Specifically, the EPA required the DOE to ensure that each waste container has no layer of confinement

that contains flammable mixtures of gases or mixtures of

gases that could become flammable when mixed with air.

The EPA also required that sampling of the headspace of

waste containers outside inner layers of confinement be representative of the entire void space of the container. The

EPA stated that all layers of confinement in a container

would have to be sampled until DOE can demonstrate to the

EPA that sampling of all layers is either unnecessary or can

be safely reduced. A test program was conducted at the

Idaho National Engineering and Environmental Laboratory

(INEEL) to demonstrate that the gas phase VOC concentration in the void space of each layer of confinement in vented

drums can be estimated from measured drum headspace

using a theoretical transport model and that sampling of

each layer of confinement is unnecessary. This report summarizes the studies performed in the INEEL test program

and extends them for the purpose of developing a methodology for determining gas phase VOC concentrations in both

vented and unvented TRU waste containers. The methodology specifies conditions under which waste drum

headspace gases can be said to be representative of drum

gases as a whole and describes a method for predicting

drum concentrations in situations where the headspace

concentration is not representative. The methodology addresses the approach for determining the drum VOC gas

content for two purposes: operational period drum handling

and operational period no-migration calculations.

299

(INEEL/CON–97-00119)

Degradation of hazardous chemicals in liquid radioactive wastes from biomedical research using a mixed

microbial population. Wolfram, J.H. (Lockheed Martin

Idaho Technology Co., Idaho Falls, ID (United States). Idaho

National Engineering and Environmental Lab.); Radtke, M.;

Wey, J.E.; Rogers, R.D.; Rau, E.H. Lockheed Martin Idaho

Technologies Co., Idaho National Engineering and Environmental Lab., Idaho Falls, ID (United States). Oct 1997. 29p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC07-94ID13223. (CONF-970857–: 4. biennial ASME

mixed waste symposium, Baltimore, MD (United States), 17-

21 Aug 1997). Order Number DE98050320. Source: OSTI;

NTIS; INIS; GPO Dep.

As the costs associated with treatment of mixed wastes

by conventional methods increase, new technologies will be

investigated as alternatives. This study examines the potential of using a selected mixed population of microorganisms

to treat hazardous chemical compounds in liquid low level

radioactive wastes from biomedical research procedures. Microorganisms were isolated from various waste samples and

enriched against compounds known to occur in the wastes.

Individual isolates were tested for their ability to degrade

methanol, ethanol, phenol, toluene, phthalates, acetonitrile,

chloroform, and trichloroacetic acid. Following these tests,

the organisms were combined in a media with a mixture of

the different compounds. Three compounds: methanol,

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

acetonitrile, and pseudocumene, were combined at 500 microliter/liter each. Degradation of each compound was

shown to occur (75% or greater) under batch conditions with

the mixed population. Actual wastes were tested by adding

an aliquot to the media, determining the biomass increase,

and monitoring the disappearance of the compounds. The

compounds in actual waste were degraded, but at different

rates than the batch cultures that did not have waste added.

The potential of using bioprocessing methods for treating

mixed wastes from biomedical research is discussed.

300

(INEEL/CON–97-00284)

Applying programmatic risk assessment to nuclear materials stabilization R and D planning. Kenley, C.R.

(Lockheed Idaho Technologies Co., Idaho Falls, ID (United

States)); Brown-van Hoozer, S.A. Lockheed Idaho Technologies Co., Idaho Falls, ID (United States). [1997]. 7p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC07-94ID13223. (CONF-970803–: 7. international conference on creep and fracture of engineering materials and

structure, Los Angeles, CA (United States), 3-14 Aug 1997).

Order Number DE98050323. Source: OSTI; NTIS; INIS;

GPO Dep.

A systems engineering approach to programmatic risk assessment, derived from the aerospace industry, was applied

to various stabilization technologies to assess their relative

maturity and availability for use in stabilizing nuclear materials. The assessment provided valuable information for

trading off available technologies and identified the at-risk

technologies that will require close tracking by the Department of Energy (DOE) to mitigate programmatic risks.

301

(INEEL/CON–97-00285)

Department of Energy environmental management

complex-wide integration using systems engineering.

Fairbourn, P. Lockheed Idaho Technologies Co., Idaho

Falls, ID (United States). [1997]. 9p. Sponsored by USDOE

Office of Environmental Management, Washington, DC

(United States). DOE Contract AC07-94ID13223. (CONF970803–: 7. international conference on creep and fracture

of engineering materials and structure, Los Angeles, CA

(United States), 3-14 Aug 1997). Order Number

DE98050284. Source: OSTI; NTIS; INIS; GPO Dep.

A systems engineering approach was successfully used

to recommend changes to environmental management

activities across the DOE Complex. A team of technical experts and systems engineers developed alternatives that

could save tax payers billions of dollars if the barriers are removed to allow complete implementation. The alternatives

are technically-based and defensible, and are being worked

through the stakeholder review process. The integration process and implementing project structure are both discussed.

302

(INEEL/CON–97-00286)

Development of the environmental management integrated baseline at the Idaho National Engineering

Laboratory using systems engineering. Murphy, J.A.;

Caliva, R.M.; Wixson, J.R. Lockheed Idaho Technologies

Co., Idaho Falls, ID (United States). [1997]. 8p. Sponsored

by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract AC07-94ID13223.

(CONF-970803–: 7. international conference on creep and

fracture of engineering materials and structure, Los Angeles,

CA (United States), 3-14 Aug 1997). Order Number

DE98050285. Source: OSTI; NTIS; INIS; GPO Dep.

The Idaho National Engineering Laboratory (INEL) is one

of many Department of Energy (DOE) national laboratories

that has been performing environmental cleanup and stabilization, which was accelerated upon the end of the cold

war. In fact, the INEL currently receives two-thirds of its

scope to perform these functions. However, the cleanup is a

highly interactive system that creates an opportunity for systems engineering methodology to be employed. At the INEL,

a group called EM (Environmental Management) Integration

has been given this charter along with a small core of systems engineers. This paper discusses the progress to date

of converting the INEL legacy system into one that uses the

systems engineering discipline as the method to ensure that

external requirements are met.

303

(INEEL/CON–97-00880)

Characterization of environmental samples using ion

trap-secondary ion mass spectrometry. Groenewold,

G.S.; Appelhans, A.D.; Ingram, J.C. Lockheed Martin Idaho

Technologies Co., Idaho National Engineering and Environmental Lab., Idaho Falls, ID (United States). Feb 1998. 9p.

Sponsored by USDOE, Washington, DC (United

States);USDOE Office of Environmental Management,

Washington, DC (United States). DOE Contract AC07-

94ID13223. (CONF-971163–: 1997 U.S. Army Edgewood

Research, Development and Engineering Center scientific

conference on chemical and biological defense research,

Aberdeen Proving Ground, MD (United States), 18-21 Nov

1997). Order Number DE98052225. Source: OSTI; NTIS;

GPO Dep.

The detection of chemical warfare agent residues on

environmental surfaces is an important analytical activity because of the potential for proliferation of these weapons,

and for environmental monitoring in areas where they are

stored. Historically, one of the most widely used agents has

been bis(2-chloroethyl) sulfide, also known as mustard gas

and HD. It was initially used in combat in 1917; by the end

of the First World War, more than 16% of all casualties were

due to chemicals, in most cases mustard. Manufacture of

mustard is continuing to this day; consequently, there are

ongoing opportunities for exposure. 2-Chloroethyl ethyl sulfide (CEES) is used as a simulant for mustard (HD) in a

study to develop secondary ion mass spectrometry (SIMS)

for rapid, semi-quantitative detection of mustard on soil. Using SIMS with single stage mass spectrometry, a signature

for CEES can be unequivocally observed only at the highest

concentrations (0.1 monolayer and above). Selectivity and

sensitivity are markedly improved employing multiple-stage

mass spectrometry using an ion trap. C2H5SC2H4

+ from

CEES eliminates C2H4 and H2S, which are highly diagnostic. CEES was detected at 0.0012 monolayer on soil. A

single analysis could be conducted in under 5 minutes.

304

(INEEL/CON–97-00895)

Development of a techno-economic model to optimization DOE spent nuclear fuel disposition. Ramer, R.J.;

Plum, M.M.; Adams, J.P.; Dahl, C.A. Lockheed Martin Idaho

Technologies Co., Idaho National Engineering Lab., Idaho

73
ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

Falls, ID (United States). Nov 1997. 11p. Sponsored by USDOE Office of Environmental Management, Washington, DC

(United States). DOE Contract AC07-94ID13223. (CONF980307–: Waste management ’98, Tucson, AZ (United

States), 1-5 Mar 1998). Order Number DE98050590.

Source: OSTI; NTIS; INIS; GPO Dep.

The purpose of the National Spent Nuclear Fuel (NSNF)

Program conducted by Lockheed Martin Idaho Technology

Co. (LMITCO) at the Idaho National Engineering and Environmental Laboratory (INEEL) is to evaluate what to do with

the spent nuclear fuel (SNF) in the Department of Energy

(DOE) complex. Final disposition of the SNF may require

that the fuel be treated to minimize material concerns. The

treatments may range from electrometallurgical treatment

and chemical dissolution to engineering controls. Treatment

options and treatment locations will depend on the fuel type

and the current locations of the fuel. One of the first steps

associated with selecting one or more sites for treating the

SNF in the DOE complex is to determine the cost of each

option. An economic analysis will assist in determining

which fuel treatment alternative attains the optimum disposition of SNF at the lowest possible cost to the government

and the public. For this study, a set of questions was developed for the electrometallurgical treatment process for fuels

at several locations. The set of questions addresses all issues associated with the design, construction, and operation

of a production facility. A matrix table was developed to

determine questions applicable to various fuel treatment options. A work breakdown structure (WBS) was developed to

identify a treatment process and costs from initial design to

shipment of treatment products to final disposition. Costs

will be applied to determine the life-cycle cost of each option. This technique can also be applied to other treatment

techniques for treating spent nuclear fuel.

305

(INEEL/CON–97-00898)

High-level waste program integration within the DOE

complex. Valentine, J.H. (Lockheed Martin Idaho Technologies Co., Idaho Falls, ID (United States). Idaho National

Engineering and Environmental Lab.); Davis, N.R.; Malone,

K.; Schaus, P.S. Lockheed Martin Idaho Technologies Co.,

Idaho National Engineering and Environmental Lab., Idaho

Falls, ID (United States). Mar 1998. 14p. Sponsored by USDOE Office of Environmental Management, Washington, DC

(United States). DOE Contract AC07-94ID13223. (CONF980307–: Waste management ’98, Tucson, AZ (United

States), 1-5 Mar 1998). Order Number DE98052245.

Source: OSTI; NTIS; INIS; GPO Dep.

Eleven major Department of Energy (DOE) site contractors were chartered by the Assistant Secretary to use a

systems engineering approach to develop and evaluate

technically defensible cost savings opportunities across the

complex. Known as the complex-wide Environmental Management Integration (EMI), this process evaluated all the

major DOE waste streams including high level waste (HLW).

Across the DOE complex, this waste stream has the highest

life cycle cost and is scheduled to take until at least 2035

before all HLW is processed for disposal. Technical contract

experts from the four DOE sites that manage high level

waste participated in the integration analysis: Hanford, Savannah River Site (SRS), Idaho National Engineering and

Environmental Laboratory (INEEL), and West Valley Demonstration Project (WVDP). In addition, subject matter experts

from the Yucca Mountain Project and the Tanks Focus Area

participated in the analysis. Also, departmental representatives from the US Department of Energy Headquarters

(DOE-HQ) monitored the analysis and results. Workouts

were held throughout the year to develop recommendations

to achieve a complex-wide integrated program. From this effort, the HLW Environmental Management (EM) Team

identified a set of programmatic and technical opportunities

that could result in potential cost savings and avoidance in

excess of $18 billion and an accelerated completion of the

HLW mission by seven years. The cost savings, schedule

improvements, and volume reduction are attributed to a multifaceted HLW treatment disposal strategy which involves

waste pretreatment, standardized waste matrices, riskbased retrieval, early development and deployment of a

shipping system for glass canisters, and reasonable, low

cost tank closure.

306

(INEEL/CON–97-00930)

Integrated process analysis of treatment systems for

mixed low level waste. Cooley, C.R. (Dept. of Energy,

Washington, DC (United States)); Schwinkendorf, W.E.;

Bechtold, T.E. Lockheed Martin Idaho Technologies Co.,

Idaho National Engineering and Environmental Lab., Idaho

Falls, ID (United States). Oct 1997. 35p. Sponsored by USDOE Office of Environmental Management, Washington, DC

(United States). DOE Contract AC07-94ID13223. (CONF970857–: 4. biennial ASME mixed waste symposium,

Baltimore, MD (United States), 17-21 Aug 1997). Order

Number DE98050322. Source: OSTI; NTIS; INIS; GPO Dep.

Selection of technologies to be developed for treatment of

DOE’s mixed low level waste (MLLW) requires knowledge

and understanding of the expected costs, schedules, risks,

performance, and reliability of the total engineered systems

that use these technologies. Thus, an integrated process

analysis program was undertaken to identify the characteristics and needs of several thermal and nonthermal systems.

For purposes of comparison, all systems were conceptually

designed for a single facility processing the same amount of

waste at the same rate. Thirty treatment systems were evaluated ranging from standard incineration to innovative

thermal systems and innovative nonthermal chemical treatment. Treating 236 million pounds of waste in 20 years

through a central treatment was found to be the least costly

option with total life cycle cost ranging from $2.1 billion for a

metal melting system to $3.9 billion for a nonthermal acid

digestion system. Little cost difference exists among nonthermal systems or among thermal systems. Significant cost

savings could be achieved by working towards maximum on

line treatment time per year; vitrifying the final waste

residue; decreasing front end characterization segregation

and sizing requirements; using contaminated soil as the vitrifying agent; and delisting the final vitrified waste form from

Resource Conservation and Recovery Act (RCRA) Land

Disposal Restriction (LDR) requirements.

307

(INEEL/CON–97-00940)

Development of a comprehensive source term model for

the Subsurface Disposal Area at the Idaho National Engineering and Environmental Laboratory. Lockheed

Martin Idaho Technologies Co., Idaho National Engineering

and Environmental Laboratory, Idaho Falls, ID (United

States). [1997]. 6p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

Contract AC07-94ID13223. (CONF-980307–: Waste management ’98, Tucson, AZ (United States), 1-5 Mar 1998).

Order Number DE98054117. Source: OSTI; NTIS; INIS;

GPO Dep.

The first detailed comprehensive simulation study to

evaluate fate and transport of wastes disposed in the Subsurface Disposal Area (SDA), at the Radioactive Waste

Management Complex (RWMC), Idaho National Engineering

and Environmental Laboratory (INEEL) has recently been

conducted. One of the most crucial parts of this modeling

was the source term or release model. The current study

used information collected over the last five years defining

contaminant specific information including: the amount disposed, the waste form (physical and chemical properties)

and the type of container used for each contaminant disposed. This information was used to simulate the release of

contaminants disposed in the shallow subsurface at the

SDA. The DUST-MS model was used to simulate the release. Modifications were made to allow the yearly disposal

information to be incorporated. The modeling includes

unique container and release rate information for each of

the 42 years of disposal. The results from this simulation effort are used for both a groundwater and a biotic uptake

evaluation. As part of this modeling exercise, inadequacies

in the available data relating to the release of contaminants

have been identified. The results from this modeling study

have been used to guide additional data collection activities

at the SDA for purposes of increasing confidence in the appropriateness of model predictions.

308

(INEEL/CON–97-00953)

Pinhole corrosion of CH-TRU waste containers by

volatile organic compounds. Zeek, D.P. Lockheed Martin

Idaho Technologies Co., Idaho National Engineering and Environmental Lab., Idaho Falls, ID (United States). Mar 1998.

11p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC07-94ID13223. (CONF-980307–: Waste management

’98, Tucson, AZ (United States), 1-5 Mar 1998). Order Number DE98052756. Source: OSTI; NTIS; INIS; GPO Dep.

In the spring of 1996 at the Idaho National Engineering

and Environmental Laboratory Radioactive Waste Management Complex, an epidemic of corroded CH-TRU waste

drums was encountered. The observed corrosion was in the

form of rusty brown streaks that emanated from pinholes in

about the upper one-third of the 55 gal drums. Wet streaks

were tested as highly acidic by litmus paper. The liquid that

emanated from the pinholes was found to be hydrochloric

(HCl) acid. An investigation concluded that the pinholes

were localized pitting corrosion caused by HCl acid formed

in the drum headspace from reactions involving chlorinated

volatile organic compounds (VOCs) in the waste and the unlined steel of the internal drum wall. The pinholes occurred

in the upper parts of the drums because this corresponds to

the internal headspace region above the rigid liner. Affected

drums had a few to hundreds of pinholes with no detectable

release of radioactivity. This was due to the internal packaging of waste in heavy polyethylene and/or polyvinyl chloride

waste bags inside a rigid high-density polyethylene liner.

The corrective action taken was to overpack pinhole corrosion drums into polyethylene-lined 83-gal drums and to test

hundreds of drums with drum filters, but without pinhole

corrosion, for the presence of HCl acid in the headspace

gas with colorimetric tubes fitted to the drum filters. These

colorimetric tubes contain a substance that changes color in

reaction to HCl acid when headspace gas is drawn by a

hand pump. Only drums that had a significant probability for

the presence of HCl acid in the headspace were segregated

in storage to allow ready inspection and efficient handling, if

needed. It is recommended that any facility involved in the

long-term storage of waste or other contents, that include

chlorinated VOCs in unlined steel containers, be wary for

the possible development of pinhole corrosion.

309

(INEEL/CON–97-00964)

Incineration of DOE offsite mixed waste at the Idaho National Engineering and Environmental Laboratory.

Harris, J.D. (Lockheed Martin Idaho Technologies Co., Idaho

Falls, ID (United States)); Harvego, L.A.; Jacobs, A.M.; Willcox, M.V. Lockheed Martin Idaho Technologies Co., Idaho

National Engineering and Environmental Lab., Idaho Falls,

ID (United States). Jan 1998. 32p. Sponsored by USDOE

Office of Environmental Management, Washington, DC

(United States). DOE Contract AC07-94ID13223. (CONF980307–: Waste management ’98, Tucson, AZ (United

States), 1-5 Mar 1998). Order Number DE98052244.

Source: OSTI; NTIS; INIS; GPO Dep.

The Waste Experimental Reduction Facility (WERF) incinerator at the Idaho National Engineering and Environmental

Laboratory (INEEL) is one of three incinerators in the US

Department of Energy (DOE) Complex capable of incinerating mixed low-level waste (MLLW). WERF has received

MLLW from offsite generators and is scheduled to receive

more. The State of Idaho supports receipt of offsite MLLW

waste at the WERF incinerator within the requirements established in the (INEEL) Site Treatment Plan (STP). The

incinerator is operating as a Resource Conservation and

Recovery Act (RCRA) Interim Status Facility, with a RCRA

Part B permit application currently being reviewed by the

State of Idaho. Offsite MLLW received from other DOE facilities are currently being incinerated at WERF at no charge to

the generator. Residues associated with the incineration of

offsite MLLW waste that meet the Envirocare of Utah waste

acceptance criteria are sent to that facility for treatment and/

or disposal. WERF is contributing to the treatment and reduction of MLLW in the DOE Complex.

310

(INEEL/CON–97-00968)

Evaluation of engineered barriers at the Idaho National

Engineering and Environmental Laboratory. Bhatt, R.N.;

Porro, I. Lockheed Martin Idaho Technologies Co., Idaho

National Engineering and Environmental Lab., Idaho Falls,

ID (United States). Feb 1998. 13p. Sponsored by USDOE

Office of Environmental Management, Washington, DC

(United States). DOE Contract AC07-94ID13223. (CONF980307–: Waste management ’98, Tucson, AZ (United

States), 1-5 Mar 1998). Order Number DE98052224.

Source: OSTI; NTIS; INIS; GPO Dep.

Subsurface Disposal (SDA) of the Radioactive Waste

Management Complex serves as the low level waste burial

ground at the Idaho National Engineering and Environmental Laboratory (INEEL). The low level wastes are buried in

trenches, pits, and soil vaults in surficial sediments. A closure/post-closure plan must be written prior to closure of the

SDA. The closure plan for the facility must include a design

for an engineered barrier closure cover that will meet all applicable regulatory requirements. This paper describes the

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

approach being followed at the INEEL to choose an appropriate cover design for the SDA closure. Regulatory

requirements and performance objectives potentially applicable to closure of the SDA were identified. Technical issues

related to SDA closure were identified from a literature

search of previous arid site engineered barrier studies and

from previous SDA closure cover evaluations. Five engineered barrier conceptual design alternatives were

identified: (1) a bio/capillary barrier cover, (2) a thin soil

cover, (3) a thick soil cover, (4) a Resource Conservation

and Recovery Act cover, and (5) a concrete sealed surface

cover. Two of these designs were chosen for in situ hydraulic testing, rather than all five, in order to maximize the

amount of information generated relative to projected project

costs. Testing of these two cover designs provides data to

quantify hydrologic model input parameters and for verification of site specific hydrologic models for long term closure

cover performance evaluation and detailed analysis of closure cover alternatives. The specific objectives of the field

tests are to determine the water balance for the two covers

over several years and to determine cover soil physical and

hydraulic properties.

311

(INEEL/CON–97-00993)

Cask crush pad analysis using detailed and simplified

analysis methods. Uldrich, E.D.; Hawkes, B.D. Lockheed

Idaho Technologies Co., Idaho Falls, ID (United States).

[1997]. 5p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract AC07-94ID13223. (CONF-980426–: American power

conference, Chicago, IL (United States), 14-16 Apr 1998).

Order Number DE98052578. Source: OSTI; NTIS; INIS;

GPO Dep.

A crush pad has been designed and analyzed to absorb

the kinetic energy of a hypothetically dropped spent nuclear

fuel shipping cask into a 44-ft. deep cask unloading pool at

the Fluorinel and Storage Facility (FAST). This facility, located at the Idaho Chemical Processing Plant (ICPP) at the

Idaho national Engineering and Environmental Laboratory

(INEEL), is a US Department of Energy site. The basis for

this study is an analysis by Uldrich and Hawkes. The purpose of this analysis was to evaluate various hypothetical

cask drop orientations to ensure that the crush pad design

was adequate and the cask deceleration at impact was less

than 100 g. It is demonstrated herein that a large spent fuel

shipping cask, when dropped onto a foam crush pad, can

be analyzed by either hand methods or by sophisticated dynamic finite element analysis using computer codes such as

ABAQUS. Results from the two methods are compared to

evaluate accuracy of the simplified hand analysis approach.

312

(INEEL/CON–97-01042)

Demonstration of the TRUEX process for the treatment

of actual high activity tank waste at the INEEL using

centrifugal contactors. Law, J.D.; Brewer, K.N.; Todd,

T.A.; Olson, L.G. Idaho National Engineering Lab., Idaho

Falls, ID (United States). 1997. 10p. Sponsored by USDOE

Office of Environmental Management, Washington, DC

(United States). DOE Contract AC07-94ID13223. (CONF970962–: 214. American Chemical Society meeting, Las

Vegas, NV (United States), 7-13 Sep 1997). Order Number

DE98050366. Source: OSTI; NTIS; INIS; GPO Dep.

The Idaho Chemical Processing Plant (ICPP), located at

the Idaho National Engineering and Environmental Laboratory (INEEL), formerly reprocessed spent nuclear fuel to

recover fissionable uranium. The radioactive raffinates from

the solvent extraction uranium recovery processes were

converted to granular solids (calcine) in a high temperature

fluidized bed. A secondary liquid waste stream was generated during the course of reprocessing, primarily from

equipment decontamination between campaigns and solvent

wash activities. This acidic tank waste cannot be directly

calcined due to the high sodium content and has historically

been blended with reprocessing raffinates or non-radioactive

aluminum nitrate prior to calcination. Fuel reprocessing activities are no longer being performed at the ICPP, thereby

eliminating the option of waste blending to deplete the waste

inventory. Currently, approximately 5.7 million liters of highactivity waste are temporarily stored at the ICPP in large

underground stainless-steel tanks. The United States Environmental Protection Agency and the Idaho Department of

Health and Welfare filed a Notice of Noncompliance in 1992

contending some of the underground waste storage tanks

do not meet secondary containment. As part of a 1995

agreement between the State of Idaho, the Department of

Energy, and the Department of Navy, the waste must be removed from the tanks by 2012. Treatment of the tank waste

inventories by partitioning the radionuclides and immobilizing the resulting high-activity and low-activity waste streams

is currently under evaluation. A recent peer review identified

the most promising radionuclide separation technologies for

evaluation. The Transuranic Extraction-(TRUEX) process

was identified as a primary candidate for separation of the

actinides from ICPP tank waste.

313

(INEEL/CON–97-01064)

Analysis of a hypothetical dropped spent nuclear fuel

shipping cask impacting a floor mounted crush pad.

Hawkes, B.D.; Uldrich, E.D. Lockheed Martin Idaho Technologies Co., Idaho National Engineering and Environmental

Lab., Idaho Falls, ID (United States). Mar 1998. 9p. Sponsored by USDOE Office of Environmental Management,

Washington, DC (United States). DOE Contract AC07-

94ID13223. (CONF-960708–: IMACS international

conference on computational engineering in systems applications, Lille (France), 8-10 Jul 1996). Order Number

DE98052574. Source: OSTI; NTIS; INIS; GPO Dep.

A crush pad has been designed and analyzed to absorb

the kinetic energy of a hypothetically dropped spent nuclear

fuel shipping cask into a 44-ft. deep cask unloading pool at

the Idaho Chemical Processing Plant. The 110-ton Large

Cell Cask was assumed to be accidentally dropped onto the

parapet of the unloading pool, causing the cask to tumble

through the pool water and impact the floor mounted crush

pad with the cask’s top corner. The crush pad contains rigid

polyurethane foam, which was modeled in a separate computer analysis to simulate the manufacturer’s testing of the

foam and to determine the foam’s stress and strain characteristics. This computer analysis verified that the foam was

accurately represented in the analysis to follow. A detailed

non-linear, dynamic finite element analysis was then performed on the crush pad and adjacent pool structure to

assure that a drop of this massive cask does not result in

unacceptable damage to the storage facility. Additionally,

verification was made that the crush pad adequately protects the cask from severe impact loading. At impact, the

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

cask has significant vertical, horizontal and rotational velocities. The crush pad absorbs much of the energy of the cask

through plastic deformation during primary and secondary

impacts. After the primary impact with the crush pad, the

cask still has sufficient energy to rebound and rotate until it

impacts the pool wall. An assessment is made of the damage to the crush pad and pool wall and of the impact

loading on the cask.

314

(INEEL/CON–97-01171)

Design and operational considerations of United States

commercial near-surface low-level radioactive waste

disposal facilities. Birk, S.M. Lockheed Idaho Technologies

Co., Idaho Falls, ID (United States). Oct 1997. 17p. Sponsored by USDOE Office of Environmental Management,

Washington, DC (United States). DOE Contract AC07-

94ID13223. (CONF-9710133–: Korean Institute of Nuclear

Safety Workshop, Taejon (Korea, Republic of), 19-24 Oct

1997). Order Number DE98050596. Source: OSTI; NTIS;

INIS; GPO Dep.

In accordance with the Low-Level Radioactive Waste Policy Amendments Act of 1985, states are responsible for

providing for disposal of commercially generated low-level

radioactive waste (LLW) within their borders. LLW in the US

is defined as all radioactive waste that is not classified as

spent nuclear fuel, high-level radioactive waste, transuranic

waste, or by-product material resulting from the extraction of

uranium from ore. Commercial waste includes LLW generated by hospitals, universities, industry, pharmaceutical

companies, and power utilities. LLW generated by the country’s defense operations is the responsibility of the Federal

government and its agency, the Department of Energy. The

commercial LLRW disposal sites discussed in this report are

located near: Sheffield, Illinois (closed); Maxey Flats, Kentucky (closed); Beatty, Nevada (closed); West Valley, New

York (closed); Barnwell, South Carolina (operating); Richland, Washington (operating); Ward Valley, California,

(proposed); Sierra Blanca, Texas (proposed); Wake County,

North Carolina (proposed); and Boyd County, Nebraska

(proposed). While some comparisons between the sites described in this report are appropriate, this must be done with

caution. In addition to differences in climate and geology between sites, LLW facilities in the past were not designed and

operated to today’s standards. This report summarizes each

site’s design and operational considerations for near-surface

disposal of low-level radioactive waste. The report includes:

a description of waste characteristics; design and operational features; post closure measures and plans; cost and

duration of site characterization, construction, and operation;

recent related R and D activities for LLW treatment and disposal; and the status of the LLW system in the US.

315

(INEEL/CON–97-01172)

Security preparation for receipt of SNF from the FRR to

the INEEL. Dahlquist, R.L. Lockheed Martin Idaho Technologies Co., Idaho National Engineering and Environmental

Lab., Idaho Falls, ID (United States). 9 Oct 1997. 7p. Sponsored by USDOE Office of Environmental Management,

Washington, DC (United States). DOE Contract AC07-

94ID13223. (CONF-9710102–: 1997 international meeting

on reduced enrichment for research and test reactors, Jackson Hole, WY (United States), 5-10 Oct 1997). Order

Number DE98050355. Source: OSTI; NTIS; INIS; GPO Dep.

This paper reports the key security related activities associated with the FRR shipment. Starting with transportation of

the SNF in the country of origin to the final destination at the

INEEL. Methodology for compliance will be addressed. The

graded approach and a three step system will be explained.

This paper will be used as part of the planning to support

the FRR Project for returning the Asia and European SNF

back to the US.

316

(INEEL/CON–97-01173)

Status of the TRIGA shipments to the INEEL from Europe. Mustin, T. (Dept. of Energy, Washington, DC (United

States)); Stump, R.C.; Tyacke, M.J. Lockheed Martin Idaho

Technologies Co., Idaho National Engineering and Environmental Lab., Idaho Falls, ID (United States). 9 Oct 1997.

11p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC07-94ID13223. (CONF-9710102–: 1997 international

meeting on reduced enrichment for research and test reactors, Jackson Hole, WY (United States), 5-10 Oct 1997).

Order Number DE98002873. Source: OSTI; NTIS; INIS;

GPO Dep.

This paper reports the activities underway by the US Department of Energy (DOE) for returning Training, Research,

Isotope, General Atomics (TRIGA) spent nuclear fuel (SNF)

from foreign research reactors (FRR) in four European

countries to the Idaho National Engineering and Environmental Laboratory (INEEL). Those countries are Germany,

Italy, Romania, and Slovenia. This is part of the “Nuclear

Weapons Nonproliferation Policy” of returning research reactor SNF containing uranium enriched in the US. This

paper describes the results of a pre-assessment trip in

September, 1997, to these countries, including: history of

the reactors and research being performed; inventory of

TRIGA SNF; fuel types (stainless steel, aluminum, or

Incoloy) and enrichments; and each country’s plans for returning their TRIGA SNF to the INEEL.

317

(INEEL/CON–97-01174)

Assessment results of the South Korea TRIGA SNF to

be shipped to INEEL. Cole, C.M. (Lockheed Martin Idaho

Technologies Co., Idaho Falls, ID (United States)); Dirk,

W.J.; Cottam, R.E.; Paik, S.T. Lockheed Martin Idaho Technologies Co., Idaho National Engineering and Environmental

Lab., Idaho Falls, ID (United States). 9 Oct 1997. 15p. Sponsored by USDOE Office of Environmental Management,

Washington, DC (United States). DOE Contract AC07-

94ID13223. (CONF-9710102–: 1997 international meeting

on reduced enrichment for research and test reactors, Jackson Hole, WY (United States), 5-10 Oct 1997). Order

Number DE98050356. Source: OSTI; NTIS; INIS; GPO Dep.

This paper describes the Training, Research, Isotope,

General Atomics (TRIGA) spent nuclear fuel (SNF) examination at the Seoul and the Taejon Research Reactor Facilities

in South Korea. The examination was required before the

SNF would be accepted for transportation and storage at

the INEEL. The results of the aluminum and stainless steel

clad TRIGA fuel examination have been summarized. A description of the examination team training, the examination

work plan and examination equipment is also included. This

paper also explains the technical basis for the examination

and physical condition criteria used to determine what, if

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

any, additional packaging would be required for transportation and for the receipt and storage of the fuel at the INEEL.

This paper delineates the preparation activities prior to the

fuel examinations and includes (1) collecting spent fuel data;

(2) preparatory work by the Korean Atomic Energy

Research Institute (KAERI) for fuel examination: (3) preparation of a radionuclide report, Radionuclide Mass Inventory,

Activity, Decay Heat, and Dose Rate Parametric Data for

TRIGA Spent Nuclear Fuels needed to provide input data

for transportation and fuel acceptance at the Idaho National

Engineering and Environmental Laboratory (INEEL); (4)

gathering FRR Facility data; and (5) coordination between

the INEEL and KAERI. Included, are the unanticipated conditions encountered in the unloading of fuel from the dry

storage casks in Taejon in preparation for examination, a

description of the damaged condition of the fuel removed

from the casks, and the apparent cause of the damages.

Lessons learned from all the activities are also addressed. A

brief description of the preparatory work for the shipment of

the spent fuel from Korea to INEEL is included.

318

(INEEL/CON–97-01175)

Status of the TRIGA shipments to the INEEL from Asia.

Tyacke, M. (Lockheed Martin Idaho Technology Co., Idaho

Falls, ID (United States)); George, W.; Petrasek, A.; Stump,

R.C.; Patterson, J. Lockheed Martin Idaho Technologies

Co., Idaho National Engineering and Environmental Lab.,

Idaho Falls, ID (United States). 9 Oct 1997. 11p. Sponsored

by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract AC07-94ID13223.

(CONF-9710102–: 1997 international meeting on reduced

enrichment for research and test reactors, Jackson Hole,

WY (United States), 5-10 Oct 1997). Order Number

DE98050357. Source: OSTI; NTIS; INIS; GPO Dep.

This paper will report on preparations being made for returning Training, Research, Isotope, General Atomics

(TRIGA) foreign research reactor (FRR) spent fuel from

South Korea and Indonesia to the Idaho National Engineering and Environmental Laboratory (INEEL). The roles of US

Department of Energy, INEEL, and NAC International in

implementing a safe shipment are provided. Special preparations necessitated by making a shipment through a west

coast port of the US to the INEEL will be explained. The institutional planning and actions needed to meet the unique

political and operational environment for making a shipment

from Asia to INEEL will be discussed. Facility preparation at

both the INEEL and the FRRs is discussed. Cask analysis

needed to properly characterize the various TRIGA configurations, compositions, and enrichments is discussed.

Shipping preparations will include an explanation of the integrated team of spent fuel transportation specialists, and

shipping resources needed to retrieve the fuel from foreign

research reactor sites and deliver it to the INEEL.

319

(INEEL/CON–97-01176)

Assessment results of the Indonesian TRIGA SNF to be

shipped to INEEL. Jefimoff, J. (Lockheed Martin Idaho

Technologies Co., Idaho Falls, ID (United States)); Robb,

A.K.; Wendt, K.M.; Syarip, I.; Alfa, T. Lockheed Martin Idaho

Technologies Co., Idaho National Engineering and Environmental Lab., Idaho Falls, ID (United States). 9 Oct 1997.

15p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC07-94ID13223. (CONF-9710102–: 1997 international

meeting on reduced enrichment for research and test reactors, Jackson Hole, WY (United States), 5-10 Oct 1997).

Order Number DE98050358. Source: OSTI; NTIS; INIS;

GPO Dep.

This paper describes the Training, Research, Isotope,

General Atomics (TRIGA) spent nuclear fuel (SNF) examination performed by technical personnel from the Idaho

National Engineering and Environmental Laboratory (INEEL)

at the Bandung and Yogyakarta research reactor facilities in

Indonesia. The examination was required before the SNF

would be accepted for transportation to and storage at the

INEEL. This paper delineates the Initial Preparations prior to

the Indonesian foreign research reactor (FRR) fuel examination. The technical basis for the examination, the TRIGA

SNF Acceptance Criteria, and the physical condition required for transportation, receipt and storage of the TRIGA

SNF at the INEEL is explained. In addition to the initial

preparations, preparation descriptions of the Work Plan For

TRIGA Fuel Examination, the Underwater Examination

Equipment used, and personnel Examination Team Training

are included. Finally, the Fuel Examination and Results of

the aluminum and stainless steel clad TRIGA fuel examination have been summarized. Lessons learned from all the

activities completed to date is provided in an addendum.

The initial preparations included: (1) coordination between

the INEEL, FRR or Badan Tenaga Atom Nasional (BATAN),

DOE-HQ, and the US State Department and Embassy; (2)

incorporating Savannah River Site (SRS) FRR experience

and lessons learned; (3) collecting both FRR facility and

spent fuel data, and issuing a radionuclide report (Radionuclide Mass Inventory, Activity, Decay Heat, and Dose Rate

Parametric Data for TRIGA Spent Nuclear Fuels) needed for

transportation and fuel acceptance at the INEEL; and (4)

preexamination work at the research reactor for the fuel examination.

320

(INEEL/CON–97-01181)

Performance assessment and licensing issues for

United States commercial near-surface low-level radioactive waste disposal facilities. Birk, S.M. Lockheed

Idaho Technologies Co., Idaho Falls, ID (United States). Oct

1997. 18p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract AC07-94ID13223. (CONF-9710133–: Korean Institute

of Nuclear Safety Workshop, Taejon (Korea, Republic of),

19-24 Oct 1997). Order Number DE98050597. Source:

OSTI; NTIS; INIS; GPO Dep.

The final objective of performance assessment for a nearsurface LLW disposal facility is to demonstrate that potential

radiological impacts for each of the human exposure pathways will not violate applicable standards. This involves

determining potential pathways and specific receptor locations for human exposure to radionuclides; developing

appropriate scenarios for each of the institutional phases of

a disposal facility; and maintaining quality assurance and

control of all data, computer codes, and documentation. The

results of a performance assessment should be used to

demonstrate that the expected impacts are expected to be

less than the applicable standards. The results should not

be used to try to predict the actual impact. This is an important distinction that results from the uncertainties inherent in

performance assessment calculations. The paper discusses

performance objectives; performance assessment phases;

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

scenario selection; mathematical modeling and computer

programs; final results of performance assessments submitted for license application; institutional control period;

licensing issues; and related research and development activities.

321

(INEEL/CON–97-01187)

Developmental assessment of the SCDAP/RELAP5

code. Harvego, E.A. (and others); Slefken, L.J.; Coryell,

E.W. Idaho National Engineering Lab., Idaho Falls, ID

(United States). 1997. 12p. Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

States);Nuclear Regulatory Commission, Washington, DC

(United States). DOE Contract AC07-94ID13223. (CONF9705246–: 6. international conference on nuclear energy

(ICONE-6), San Diego, CA (United States), 10-15 May

1997). Order Number DE98052571. Source: OSTI; NTIS;

INIS; GPO Dep.

The development and assessment of the late-phase damage progression models in the current version (designated

MOD3.2) of the SCDAP/RELAP5 code are described. The

SCDAP/RELAP5 code is being developed at the Idaho National Engineering and Environmental Laboratory under the

primary sponsorship of the US Nuclear Regulatory Commission (NRC) to provide best-estimate transient simulations of

light water reactor coolant systems (RCS) during severe accident conditions. Recent modeling improvements made to

the MOD3.2 version of the code include (1) molten pool formation and heat up, including the transient start-up of

natural circulation heat transfer, (2) in-core molten pool

thermal-mechanical crust failure, (3) the melting and relocation of upper plenum structures, and (4) improvements in the

modeling of lower plenum debris behavior and the potential

for failure of the lower head. Finally, to eliminate abrupt transitions between core damage states and provide more

realistic predictions of late phase accident progression phenomena, a transition smoothing methodology was developed

and implemented that results in the calculation of a gradual

transition from an intact core geometry through the different

core damage states leading to molten pool formation. A

wide range of experiments and modeling tools were used to

assess the capabilities of MOD3.2. The results of the SCDAP/RELAP5/MOD3.2 assessment indicate that modeling

improvements have significantly enhanced the code capabilities and performance in several areas compared to the

earlier code version. New models for transition smoothing

between core damage states, and modeling improvements/

additions for cladding oxide failure, molten pool behavior,

and molten pool crust failure have significantly improved the

code usability for a wide range of applications and have significantly improved the prediction of hydrogen production,

molten pool melt mass and core melt relocation time.

322

(INEEL/CON–97-01225)

Mercury emissions control technologies for mixed

waste thermal treatment. Chambers, A. (Lockheed Martin

Idaho Technologies Co., Idaho Falls, ID (United States).

Idaho National Engineering and Environmental Lab.);

Knecht, M.; Soelberg, N.; Eaton, D.; Roberts, D.; Broderick,

T. Lockheed Martin Idaho Technologies Co., Idaho National

Engineering and Environmental Lab., Idaho Falls, ID (United

States). [1997]. 12p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States).

DOE Contract AC07-94ID13223. (CONF-980472–: 1998 international conference on incineration and thermal treatment

technologies, Salt Lake City, UT (United States), 17-20 Apr

1998). Order Number DE98056074. Source: OSTI; NTIS;

INIS; GPO Dep.

EPA has identified wet scrubbing at low mercury feedrates, as well as carbon adsorption via carbon injection into

the offgas or via flow through fixed carbon beds, as control

technologies that can be used to meet the proposed Maximum Achievable Control Technology (MACT) rule limit for

mercury emissions from hazardous waste incinerators. DOE

is currently funding demonstrations of gold amalgamation

that may also control mercury to the desired levels. Performance data from a variety of sources was reviewed to

determine ranges of achievable mercury control. Preliminary

costs were estimated for using these technologies to control

mercury emissions from mixed waste incineration. Mercury

emissions control for mixed waste incineration may need to

be more efficient than for incineration of other hazardous

wastes because of higher mercury concentrations in some

mixed waste streams. However, mercury control performance data for wet scrubbing and carbon adsorption is

highly variable. More information is needed to demonstrate

control efficiencies that are achievable under various design

and operating conditions for wet scrubbing, carbon adsorption, and gold amalgamation technologies. Given certain

assumptions made in this study, capital costs, operating

costs, and lifecycle costs for carbon injection, carbon beds,

and gold amalgamation generally vary for different assumed

mercury feedrates and for different offgas flowrates. Assuming that these technologies can in fact provide the

necessary mercury control performance, each of these technologies may be less costly than the others for certain

mercury feedrates and the offgas flowrates.

323

(INEEL/CON–97-01241)

Volatilization of heavy metals and radionuclides from

soil heated in an induction “cold” crucible melter. Aloy,

A.S. (Khlopin Radium Inst., St. Petersburg (Russian Federation)); Belov, V.Z.; Trofimenko, A.S.; Dmitriev, S.A.;

Stefanovsky, S.V.; Gombert, D.; Knecht, D.A. Lockheed

Martin Idaho Technologies Co., Idaho National Engineering

and Environmental Lab., Idaho Falls, ID (United States).

[1997]. 10p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract AC07-94ID13223. (CONF-980513–: International

conference on incineration and thermal treatment technologies, Salt Lake City, UT (United States), 11-15 May 1998).

Order Number DE98054118. Source: OSTI; NTIS; INIS;

GPO Dep.

The behavior of heavy metals and radionuclides during

high-temperature treatment is very important for the design

and operational capabilities of the off-gas treatment system,

as well as for a better understanding of the nature and

forms of the secondary waste. In Russia, a process for hightemperature melting in an induction heated cold crucible

system is being studied for vitrification of Low Level Waste

(LLW) flyash and SYNROC production with simulated high

level waste (HLW). This work was done as part of a Department of Energy (DOE) funded research project for thermal

treatment of mixed low level waste (LLW). Soil spiked with

heavy metals (Cd, Pb) and radionuclides (Cs-137, U-239,

Pu-239) was used as a waste surrogate. The soil was

melted in an experimental lab-scale system that consisted of

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

a high-frequency generator (1.76 MHz, 60 kW), a cold crucible melter (300 mm high and 90 mm in diameter), a shield

box, and an off-gas system. The process temperature was

1,350–1,400 C. Graphite and silicon carbide were used as

sacrificial conductive materials to start heating and initial

melting of the soil batch. The off-gas system was designed

in such a manner that after each experiment, it can be disconnected to collect and analyze all deposits to determine

the mass balance. The off-gases were also sampled during

an experiment to analyze for hydrogen, NOx, carbon dioxide, carbon monoxide and chlorine formation. This paper

describes distribution and mass balance of metals and radionuclides in various parts of the off-gas system. The leach

rate of the solidified blocks identified by the PCT method is

also reported.

324

(INEEL/CON–97-01271)

Corrosion Resistance of Various High Chromium Alloys

in Simulated Chemical Processing Nuclear Plant Waste

Solutions. Anderson, P.A. (Lockheed Martin Idaho Technologies Co., Idaho Falls, ID (United States)); Agarwal, D.C.

Lockheed Martin Idaho Technologies Co., Idaho Falls, ID

(United States). [1997]. 13p. Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract AC07-94ID13223. (CONF-980316–:

Corrosion ’98, San Diego, CA (United States), 22-27 Mar

1998). Order Number DE98051454. Source: OSTI; NTIS;

GPO Dep.

Prepared in cooperation with Krupp VDM.

High chromium nickel alloys were tested at the Idaho

Chemical Processing Plant (ICPP) to determine their corrosion performance in the high temperature aggressive

chemical environments of liquid waste evaporators used in

the chemical reprocessing of irradiated nuclear fuels. The

results of these tests, which included a variety of base metal

alloys I weld filler material combinations, are presented and

discussed.

325

(INEEL/CON–97-01313)

Spreadsheet application to classify radioactive material

for shipment. Brown, A.N. Lockheed Martin Idaho Technologies Co., Idaho National Engineering and Environmental

Lab., Idaho Falls, ID (United States). Dec 1997. 9p. Sponsored by USDOE Office of Environmental Management,

Washington, DC (United States). DOE Contract AC07-

94ID13223. (CONF-980307–: Waste management ’98,

Tucson, AZ (United States), 1-5 Mar 1998). Order Number

DE98051451. Source: OSTI; NTIS; INIS; GPO Dep.

A spreadsheet application has been developed at the

Idaho National Engineering and Environmental Laboratory

to aid the shipper when classifying nuclide mixtures of normal form, radioactive materials. The results generated by

this spreadsheet are used to confirm the proper US Department of Transportation (DOT) classification when offering

radioactive material packages for transport. The user must

input to the spreadsheet the mass of the material being

classified, the physical form (liquid or not), and the activity of

each regulated nuclide. The spreadsheet uses these inputs

to calculate two general values: (1) the specific activity of

the material, and (2) a summation calculation of the nuclide

content. The specific activity is used to determine if the material exceeds the DOT minimal threshold for a radioactive

material (Yes or No). If the material is calculated to be radioactive, the specific activity is also used to determine if the

material meets the activity requirement for one of the three

Low Specific Activity designations (LSA-I, LSA-II, LSA-III, or

Not LSA). Again, if the material is calculated to be radioactive, the summation calculation is then used to determine

which activity category the material will meet (Limited Quantity, Type A, Type B, or Highway Route Controlled Quantity).

326

(INEEL/CON–97-01339)

Overview of the United States spent nuclear fuel program. Hurt, W.L. Lockheed Martin Idaho Technologies Co.,

National Spent Nuclear Fuel Program, Idaho Falls, ID

(United States). Dec 1997. 11p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States). DOE Contract AC07-94ID13223. (CONF-971225–:

International Atomic Energy Agency (IAEA) meeting on

procedures and techniques for the management of experimental and exotic fuels from research and test reactors,

Vienna (Austria), 1-7 Dec 1997). Order Number

DE98052633. Source: OSTI; NTIS; INIS; GPO Dep.

As a result of the end of the Cold War, the mission of the

US Department of Energy (DOE) has shifted from an emphasis on nuclear weapons development and production to

an emphasis on the safe management and disposal of excess nuclear materials including spent nuclear fuel from

both production and research reactors. Within the US, there

are two groups managing spent nuclear fuel. Commercial

nuclear power plants are managing their spent nuclear fuel

at the individual reactor sites until the planned repository is

opened. All other spent nuclear fuel, including research

reactors, university reactors, naval reactors, and legacy material from the Cold War is managed by DOE. DOE’s

mission is to safely and efficiently manage its spent nuclear

fuel and prepare it for disposal. This mission involves correcting existing vulnerabilities in spent fuel storage; moving

spent fuel from wet basins to dry storage; processing at-risk

spent fuel; and preparing spent fuel in road-ready condition

for repository disposal. Most of DOE’s spent nuclear fuel is

stored in underwater basins (wet storage). Many of these

basins are outdated, and spent fuel is to be removed and

transferred to more modern basins or to new dry storage

facilities. In 1995, DOE completed a complex-wide environmental impact analysis that resulted in spent fuel being sent

to one of three principal DOE sites for interim storage (up to

40 years) prior to shipment to a repository. This regionalization by fuel type will allow for economies of scale yet

minimize unnecessary transportation. This paper discusses

the national SNF program, ultimate disposition of SNF, and

the technical challenges that have yet to be resolved,

namely, release rate testing, non-destructive assay, alternative treatments, drying, and chemical reactivity.

327

(INEEL/CON–97-01359)

Predicting flammability of gas mixtures containing

volatile organic compounds. Liekhus, K. (Lockheed Martin

Idaho Technologies Co., Idaho Falls, ID (United States).

Idaho National Engineering and Environmental Lab.); Zlochower, I.; Djordjevic, S.; Loehr, C. Lockheed Martin Idaho

Technologies Co., Idaho National Engineering and Environmental Lab., Idaho Falls, ID (United States). [1997]. 17p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

AC07-94ID13223. (CONF-980972–: International symposium on hazards, prevention, and mitigation of industrial

explosions, Schaumberg, IL (United States), 21-25 Sep

1998). Order Number DE98058489. Source: OSTI; NTIS;

INIS; GPO Dep.

One requirement regarding the transportation of transuranic (TRU) radioactive waste containers currently limits the

total concentration of potentially flammable volatile organic

compounds (VOCs) and flammable gases in the headspace

of the waste container. Typical VOCs observed in the drums

include aromatic hydrocarbons, ketones, alcohols, cyclohexane, as well as chlorinated hydrocarbons (alkanes and

alkenes). Flammable gases, such as hydrogen and

methane, may be generated in the containers by radiationinduced decomposition (radiolysis) of water and

hydrocarbon waste forms. An experimental program was

initiated to identify an accurate means for predicting flammability for gas mixtures containing one or more of the

following species: hydrogen, carbon tetrachloride, 1,2-

dichloroethane, toluene, or 2-butanone. The lower

flammability limits (LFL) of gas mixtures containing equimolar quantity for each species were determined in a 19-liter

laboratory flammability chamber using a strong spark ignition source. The group factor contribution method was

determined to be more accurate than the LeChatelier

method for estimating the LFL for these gas mixtures.

328

(INEEL/CON–97-01431)

Removal of strontium-90 from calcined wastes with the

SREX process. Wood, D.J.; Mann, N.R.; Tillotson, R.; Tullock, P.A.; Todd, T.A. Lockheed Martin Idaho Technologies,

Inc., Idaho National Engineering and Environmental Lab.,

Idaho Falls, ID (United States). [1997]. 5p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract AC07-94ID13223.

(CONF-980905–: SPECTRUM ’98: nuclear and hazardous

waste management international topical meeting, Denver,

CO (United States), 13-18 Sep 1998). Order Number

DE98056070. Source: OSTI; NTIS; INIS; GPO Dep.

Experiments have been performed to formulate chemical

procedures for the processing of radioactive dissolved calcine wastes for the removal of 90Sr with the SREX (Strontium

Extraction) solvent. Batch contact solvent extraction experiments have been performed to yield a processing scheme

which is highly efficient for the extraction of Sr, while remaining free from insoluble precipitate formation and third phase

formation. The effect of various scrubbing and stripping

techniques and elevated temperature have been evaluated.

The results of the batch contact experimentation has formed

the basis for a proposed processing flowsheet which is

scheduled soon for demonstration in centrifugal contactors.

329

(INEEL/CON–97-01433)

Treatment of acidic INEEL waste using a countercurrent

cobalt dicarbollide-based universal solvent extraction

process. Todd, T.A. (Lockheed Martin Idaho Technologies,

Inc., Idaho Falls, ID (United States). Idaho National Engineering and Environmental Lab.); Law, J.D.; Herbst, R.S.;

Brewer, K.N.; Romanovskiy, V.N.; Esimantovskiy, V.M.;

Smirnov, I.V.; Babain, V.A.; Zaitsev,.Lockheed Martin Idaho

Technologies, Inc., Idaho National Engineering and Environmental Lab., Idaho Falls, ID (United States). [1997]. 5p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC07-94ID13223. (CONF-980905–: SPECTRUM ’98: nuclear and hazardous waste management international

topical meeting, Denver, CO (United States), 13-18 Sep

1998). Order Number DE98056071. Source: OSTI; NTIS;

INIS; GPO Dep.

A tertiary solvent containing chlorinated cobalt dicarbollide,

diphenylcarbamoylmethylphosphine oxide and polyethylene

glycol in different diluents was evaluated for the separation

of cesium, strontium, actinides and rare earth elements from

acidic liquid radioactive waste in countercurrent solvent extraction processes. This universal solvent extraction process

has been demonstrated in 24-stage centrifugal contactor pilot plants, using simulated acidic tank waste, at the Khlopin

Radium Institute (KRI), St. Petersburg, Russia, and at the

Idaho National Engineering and Environmental Laboratory

(INEEL). Demonstration of the universal extraction process

with actual tank waste is scheduled at the INEEL in 1998.

330

(INEEL/CON–97-01434)

Developing a dependable approach for evaluating waste

treatment data. Gering, K.L. Lockheed Martin Idaho Technologies Co., Idaho National Engineering and Environmental

Lab., Idaho Falls, ID (United States). [1997]. 16p. Sponsored by USDOE Office of Environmental Management,

Washington, DC (United States). DOE Contract AC07-

94ID13223. (CONF-980307–: Waste management ’98,

Tucson, AZ (United States), 1-5 Mar 1998). Order Number

DE98058490. Source: OSTI; NTIS; INIS; GPO Dep.

Decision makers involved with hazardous waste treatment

issues are faced with the challenge of making objective

evaluations concerning treatment formulations. This work

utilizes an effectiveness factor (denoted as ) as the basis

for waste treatment evaluations, which was recently developed for application to mixed waste treatability studies

involving solidification and stabilization at the Idaho National

Engineering and Environmental Laboratory. The effectiveness factor incorporates an arbitrary treatment criterion Φ,

which in practice could be the Toxicity Characteristic Leaching Procedure, Unconfined Compressive Strength,

Leachability Index, or any other criterion used to judge treatment performance. Three values for Φ are utilized when

assessing a given treatment formulation: before treatment,

after treatment, and a reference value (typically a treatment

standard). The expression for  also incorporates the waste

loading as the prime experimental parameter, and accounts

for the contribution that each hazard has upon the overall

treatment performance. Also discussed are general guidelines for numerical boundaries and statistical interpretations

of treatment data. Case studies are presented that demonstrate the usefulness of the effectiveness factor and related

numerical methods, where the typical hazards encountered

are toxic metals within mixed waste.

331

(INEEL/CON–98-00055)

An alternative test for verifying electronic balance linearity. Thomas, I.R. Lockheed Martin Idaho Technologies

Co., Idaho National Engineering and Environmental Lab.,

Idaho Falls, ID (United States). Feb 1998. 16p. Sponsored

by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract AC07-94ID13223.

(CONF-980230–: 1998 measurement science conference

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

symposium, Pasadena, CA (United States), 5-6 Feb 1998).

Order Number DE98052757. Source: OSTI; NTIS; INIS;

GPO Dep.

This paper presents an alternative method for verifying

electronic balance linearity and accuracy. This method is

being developed for safeguards weighings (weighings for

the control and accountability of nuclear material) at the

Idaho National Engineering and Environmental Laboratory

(INEEL). With regard to balance linearity and accuracy,

DOE Order 5633.3B, Control and Accountability of Nuclear

Materials, Paragraph 2, 4, e, (1), (a) Scales and Balances

Program, states: “All scales and balances used for accountability purposes shall be maintained in good working

condition, recalibrated according to an established schedule,

and checked for accuracy and linearity on each day that the

scale or balance is used for accountability purposes.” Various tests have been proposed for testing accuracy and

linearity. In the 1991 Measurement Science Conference, Dr.

Walter E. Kupper presented a paper entitled: “Validation of

High Accuracy Weighing Equipment.” Dr. Kupper emphasized that tolerance checks for calibrated, state-of-the-art

electronic equipment need not be complicated, and he presented four easy steps for verifying that a calibrated balance

is operating correctly. These tests evaluate the standard deviation of successive weighings (of the same load), the

off-center error, the calibration error, and the error due to

nonlinearity. This method of balance validation is undoubtedly an authoritative means of ensuring balance operability,

yet it could have two drawbacks: one, the test for linearity is

not intuitively obvious, especially from a statistical viewpoint;

and two, there is an absence of definitively defined testing

limits. Hence, this paper describes an alternative means of

verifying electronic balance linearity and accuracy that is being developed for safeguards measurements at the INEEL.

332

(INEEL/EXT–97-00609)

Development, calibration, and predictive results of a

simulator for subsurface pathway fate and transport of

aqueous- and gaseous-phase contaminants in the Subsurface Disposal Area at the Idaho National Engineering

and Environmental Laboratory. Magnuson, S.O.; Sondrup,

A.J. Lockheed Martin Idaho Technologies Co., Idaho National Engineering and Environmental Lab., Idaho Falls, ID

(United States). Jul 1998. [250p.] Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States). DOE Contract AC07-94ID13223. Order Number

DE98058438. Source: OSTI; NTIS; INIS; GPO Dep.

This document presents the development, calibration, and

predictive results of a simulation study of fate and transport

of waste buried in the Subsurface Disposal Area (SDA)

(which is hereafter referred to as the SDA simulation study).

This report builds on incorporates a previous report that

dealt only with the calibration of a flow model for simulation

of water movement beneath the SDA (Magnuson and Sondrup 1996). The primary purpose of the SDA simulation

study was to perform fate and transport calculations to support the IRA. A secondary purpose of the SDA simulation

study was to be able to use the model to evaluate possible

remediation strategies and their effects on flow and transport in the OU 7-13/14 feasibility study.

333

(INEEL/EXT–97-00654)

Alternative calcination development status report.

Boardman, R.D. Lockheed Martin Idaho Technologies Co.,

Inc., Idaho National Engineering and Environmental Lab.,

Idaho Falls, ID (United States). Dec 1997. [200p.] Sponsored by USDOE Office of Environmental Management,

Washington, DC (United States). DOE Contract AC07-

94ID13223. Order Number DE98058432. Source: OSTI;

NTIS; INIS; GPO Dep.

The Programmatic Spent Nuclear Fuel and (INEEL) Environmental Restoration and Waste Management Programs

Environmental Impact Statement Record of Decision, dated

June 1, 1995, specifies that high-level waste stored in the

underground tanks at the ICPP continue to be calcined

while other options to treat the waste are studied. Therefore,

the High-Level Waste Program has funded a program to

develop new flowsheets to increase the liquid waste processing rate. Simultaneously, a radionuclide separation

process, as well as other options, are also being developed,

which will be compared to the calcination treatment option.

Two alternatives emerged as viable candidates; (1) elevated

temperature calcination (also referred to as high temperature calcination), and (2) sugar-additive calcination. Both

alternatives were determined to be viable through testing

performed in a lab-scale calcination mockup. Subsequently,

10-cm Calciner Pilot Plant scoping tests were successfully

completed for both flowsheets. The results were compared

to the standard 500 C, high-ANN flow sheet (baseline flowsheet). The product and effluent streams were characterized

to help elucidate the process chemistry and to investigate

potential environmental permitting issues. Several

supplementary tests were conducted to gain a better understanding of fine-particles generation, calcine hydration,

scrub foaming, feed makeup procedures, sugar/organic

elimination, and safety-related issues. Many of the experiments are only considered to be scoping tests, and

follow-up experiments will be required to establish a more

definitive understanding of the flowsheets. However, the

combined results support the general conclusion that flowsheet improvements for the NWCF are technically viable.

334

(INEEL/EXT–97-00831)

Development of the SREX process for the treatment of

ICPP liquid wastes. Wood, D.J.; Law, J.D.; Garn, T.G.;

Tillotson, R.D.; Tullock, P.A.; Todd, T.A. Lockheed Idaho

Technologies Co., Idaho Falls, ID (United States). Dec 1997.

44p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC07-94ID13223. Order Number DE98052247. Source:

OSTI; NTIS; INIS; GPO Dep.

The removal of 90Sr from actual and simulated wastes at

the Idaho Chemical Processing Plant (ICPP) at the Idaho

National Engineering and Environmental Laboratory (INEEL)

has been demonstrated with the SREX process. This solvent extraction process employs the extractant 40

,40(50)

di-(t-butylcyclohexano)-18-crown-6 in 1-octanol or a mixture

of tributyl phosphate and a hydrocarbon diluent called Isopar

L. Process flowsheets have been designed for testing in

countercurrent experiments with centrifugal contractors. The

flowsheets have been designed using batch contract solvent

extraction methods. The extraction of Sr as well as other interfering ions has been studied. The effect of various

parameters including nitric acid dependence, extractant concentration dependence, hydronium ion concentration, and

interferent concentrations upon the extraction efficiency of

the process has been evaluated. The radiolysis of the SREX

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

solvent has also been investigated as a function of absorbed gamma radiation. The extraction efficiency of the

solvent has been shown to be only slightly dependent upon

absorbed dose in the range 0–1,000 kGy. The decontamination of actual sodium-bearing waste and dissolved calcine

solutions has been accomplished in batch contact flowsheets. Decontamination factors as high as 10E3 have been

obtained with sequential batch contacts. Flowsheets have

been developed to accomplish decontamination of the liquid

wastes with respect to 90Sr as well as the removal of Pb and

Hg. Pb may be partitioned from the Sr fraction in a separate

stripping procedure using ammonium citrate. This work has

led to the formulation of countercurrent flowsheets which

have been tested in centrifugal contractors with actual waste

and reported in the document INEEL/EXT-97-00832.

335

(INEEL/EXT–97-00837)

TRUEX flowsheet testing for the removal of the actinides from dissolved ICPP zirconium calcine using

centrifugal contactors. Herbst, R.S.; Law, J.D.; Brewer,

K.N.; Todd, T.A. Lockheed Idaho Technologies Co., Idaho

Falls, ID (United States). Dec 1997. 26p. Sponsored by USDOE Office of Environmental Management, Washington, DC

(United States). DOE Contract AC07-94ID13223. Order

Number DE98052249. Source: OSTI; NTIS; INIS; GPO Dep.

Solid calcine is one of the wastes under evaluation for

TRU removal by the TRUEX process. The calcine must first

be dissolved in nitric acid prior to the removal of TRUs and

fission products. Zirconium type calcine (generated from zirconium fuel reprocessing raffinates) comprises the majority

of the calcine currently stored at the ICPP. The zirconium

calcines average 18.3 wt% ZrO2 and are anticipated to be

the most challenging to treat with regards to TRU removal

because of the large zirconium content. This paper reports

the results from a countercurrent flowsheet test performed

with a dissolved calcine simulant in a 2-cm centrifugal contractor pilot plant. The simulant was spiked with radioactive

241Am and 95Zr to facilitate analysis and evaluate the behavior of the actinides. Flooding and precipitate formation were

observed in the strip section during the flowsheet testing. It

is postulated that the flooding occurred as a result of precipitate formation. The precipitate was determined to be ZrPO4

and was likely formed due the excessive amount of Zr carried into the strip section with the organic phase. Roughly

65% of the Zr in the feed was extracted. Of the extracted Zr,

15.6% reported to the strip product and 15.1% ended up in

the organic effluent, indicating the strip section was ineffective at re-extracting Zr. The poor strip section performance

was probably due to the precipitation and concomitant flooding problems encountered in the test, resulting in the strip

section never achieving steady state operating conditions.

Despite the obvious problems encountered during the test,

> 99.18% of the americium was removed from the feed in

the extraction section. This may be slightly lower than the

anticipated 99.9% Am removal efficiency necessary to insure the < 10 nCi/g TRU content in the LLW raffinate.

336

(INEEL/EXT–97-01032)

Buried waste containment system materials. Final

Report. Weidner, J.R.; Shaw, P.G. Lockheed Idaho Technologies Co., Idaho Falls, ID (United States). Oct 1997. 58p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC07-94ID13223. Order Number DE98051444. Source:

OSTI; NTIS; INIS; GPO Dep.

This report describes the results of a test program to validate the application of a latex-modified cement formulation

for use with the Buried Waste Containment System (BWCS)

process during a proof of principle (POP) demonstration.

The test program included three objectives. One objective

was to validate the barrier material mix formulation to be

used with the BWCS equipment. A basic mix formula for initial trials was supplied by the cement and latex vendors. The

suitability of the material for BWCS application was verified

by laboratory testing at the Idaho National Engineering and

Environmental Laboratory (INEEL). A second objective was

to determine if the POP BWCS material emplacement process adversely affected the barrier material properties. This

objective was met by measuring and comparing properties

of material prepared in the INEEL Materials Testing Laboratory (MTL) with identical properties of material produced by

the BWCS field tests. These measurements included hydraulic conductivity to determine if the material met the US

Environmental Protection Agency (EPA) requirements for

barriers used for hazardous waste sites, petrographic analysis to allow an assessment of barrier material separation

and segregation during emplacement, and a set of mechanical property tests typical of concrete characterization. The

third objective was to measure the hydraulic properties of

barrier material containing a stop-start joint to determine if

such a feature would meet the EPA requirements for hazardous waste site barriers.

337

(INEEL/EXT–97-01069)

An engineering and economic analysis: Inductively

coupled plasma mobile treatment of hazardous waste.

Detering, B.A.; McLlwain, M.E. Idaho National Engineering

Lab., Idaho Falls, ID (United States). Oct 1997. 42p. Sponsored by USDOE Office of Environmental Management,

Washington, DC (United States). DOE Contract AC07-

94ID13223. Order Number DE98050425. Source: OSTI;

NTIS; INIS; GPO Dep.

This analysis considers the engineering and economic

viability of an rf-plasma, mobile treatment process for remediation of hazardous waste located at remote sites in

Alaska. A simple engineering process flowsheet is used to

define the elements associated with the process and to

identify major pieces of equipment. The proposed flowsheet

and equipment are used to estimate capital and operational

costs for four separate processing cases. These cases explore various operational situations, including moving

equipment to a remote site, transporting wastes to a base

site, and varying operational periods. Some cases consider

variations in fuel costs known to exist across Alaska. Operational costs, capital equipment costs, and revenues are

used to calculate pro-forma income statements. These income statements are used to predict economic viability.

Based on the economic viability, the analysis suggests that

processing of hydrocarbon-contaminated soils is more profitable when performed at remote sites as compared to at a

home base. Processing of poly-chloro-biphenyl (PCB)-

contaminated oil at a stationary site is more profitable as

compared to remote treatment due to the cost of transporting the equipment. Over the range of fuel prices considered,

higher fuel costs increase the per unit treatment price by ten

percent. Based on the results of this analysis, an rf-plasma

based process appears to be economically viable for remote

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treatment of hydrocarbon-contaminated soil, but less viable

for treatment of PCB-contaminated oil.

338

(INEEL/EXT–97-01072)

Evaluation of emplacement sensors for detecting radiation and volatile organic compounds and for long-term

monitoring access tubes for the BWCS. Lord, D.L.; Averill, R.H. Idaho National Engineering Lab., Idaho Falls, ID

(United States). Oct 1997. 21p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States). DOE Contract AC07-94ID13223. Order Number

DE98050621. Source: OSTI; NTIS; INIS; GPO Dep.

This document evaluates sensors for detecting contaminants in the excavated waste generated by the Buried

Waste Containment System (BWCS). The Barrier Placement Machine (BPM) removes spoils from under a landfill or

plume and places it on a conveyor belt on the left and right

sides of the BPM. The spoils will travel down the conveyor

belts past assay monitors and be deposited on top of the

site being worked. The belts are 5 ft wide and transport approximately 15 ft3 /minute of spoils. This corresponds to a

10 ft per hour BPM advance rate. With a 2 in. spoils height

the belt speed would be 3.6 in. per second. The spoils being

removed are expected to be “clean” (no radiation or volatile

organics above background levels). To ensure that the

equipment is not digging through a contaminated area, assay equipment will monitor the spoils for mg radiation and

volatile organic compounds (VOCs). The radiation monitors

will check for gross radiation indication. Upon detection of

radiation levels above a predetermined setpoint, further

evaluation will be performed to determine the isotopes

present and their quantity. This will require hand held monitors and a remote monitoring station. Simultaneously, VOC

monitors will monitor for predetermined volatile/semi-volatile

organic compounds. A Fourier-Transform Infrared Spectrometer (FTIR) monitor is recommended for this operation.

Specific site requirements and regulations will determine

setpoints and operation scenarios. If VOCs are detected,

the data will be collected and recorded. A flat panel display

will be mounted in the BPM operator’s cab showing the

radio nuclide and VOC monitoring data. As the BPM advances, a 3-in. diameter PVC tube will be placed on the

bottom of the barrier slot in front of the 12 to 16-in. containment barrier being emplaced.

339

(INEEL/EXT–97-01113)

Radioactive waste management complex low-level

waste radiological composite analysis. McCarthy, J.M.;

Becker, B.H.; Magnuson, S.O.; Keck, K.N.; Honeycutt, T.K.

Lockheed Martin Idaho Technologies Co., Idaho National

Engineering and Environmental Lab., Idaho Falls, ID (United

States). May 1998. 110p. Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract AC07-94ID13223. Order Number

DE98056049. Source: OSTI; NTIS; INIS; GPO Dep.

The composite analysis estimates the projected cumulative impacts to future members of the public from the

disposal of low-level radioactive waste (LLW) at the Idaho

National Engineering and Environmental Laboratory (INEEL)

Radioactive Waste Management Complex (RWMC) and all

other sources of radioactive contamination at the INEEL that

could interact with the LLW disposal facility to affect the

radiological dose. Based upon the composite analysis evaluation, waste buried in the Subsurface Disposal Area (SDA)

at the RWMC is the only source at the INEEL that will significantly interact with the LLW facility. The source term used

in the composite analysis consists of all historical SDA subsurface disposals of radionuclides as well as the authorized

LLW subsurface disposal inventory and projected LLW subsurface disposal inventory. Exposure scenarios evaluated in

the composite analysis include all the all-pathways and

groundwater protection scenarios. The projected dose of 58

mrem/yr exceeds the composite analysis guidance dose

constraint of 30 mrem/yr; therefore, an options analysis was

conducted to determine the feasibility of reducing the projected annual dose. Three options for creating such a

reduction were considered: (1) lowering infiltration of precipitation through the waste by providing a better cover, (2)

maintaining control over the RWMC and portions of the INEEL indefinitely, and (3) extending the period of institutional

control beyond the 100 years assumed in the composite

analysis. Of the three options investigated, maintaining control over the RWMC and a small part of the present INEEL

appears to be feasible and cost effective.

340

(INEEL/EXT–97-01138)

High performance APCS conceptual design and evaluation scoping study. Soelberg, N.; Liekhus, K.; Chambers,

A.; Anderson, G. EG and G Idaho, Inc., Idaho Falls, ID

(United States). Feb 1998. 147p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States). DOE Contract AC07-94ID13223. Order Number

DE98054111. Source: OSTI; NTIS; INIS; GPO Dep.

This Air Pollution Control System (APCS) Conceptual Design and Evaluation study was conducted to evaluate a

high-performance (APC) system for minimizing air emissions

from mixed waste thermal treatment systems. Seven

variations of high-performance APCS designs were conceptualized using several design objectives. One of the system

designs was selected for detailed process simulation using

ASPEN PLUS to determine material and energy balances

and evaluate performance. Installed system capital costs

were also estimated. Sensitivity studies were conducted to

evaluate the incremental cost and benefit of added carbon

adsorber beds for mercury control, specific catalytic reduction for NOx control, and offgas retention tanks for holding

the offgas until sample analysis is conducted to verify that

the offgas meets emission limits. Results show that the

high-performance dry-wet APCS can easily meet all expected emission limits except for possibly mercury. The

capability to achieve high levels of mercury control (potentially necessary for thermally treating some DOE mixed

streams) could not be validated using current performance

data for mercury control technologies. The engineering approach and ASPEN PLUS modeling tool developed and

used in this study identified APC equipment and system

performance, size, cost, and other issues that are not yet resolved. These issues need to be addressed in feasibility

studies and conceptual designs for new facilities or for determining how to modify existing facilities to meet expected

emission limits. The ASPEN PLUS process simulation with

current and refined input assumptions and calculations can

be used to provide system performance information for

decision-making, identifying best options, estimating costs,

reducing the potential for emission violations, providing information needed for waste flow analysis, incorporating new

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

APCS technologies in existing designs, or performing facility

design and permitting activities.

341

(INEEL/EXT–97-01142)

Low-level radioactive waste form qualification testing.

Sohal, M.S.; Akers, D.W. Lockheed Martin Idaho Technologies Co., Idaho National Engineering and Environmental

Lab., Idaho Falls, ID (United States). Jun 1998. 78p. Sponsored by USDOE Office of Environmental Management,

Washington, DC (United States). DOE Contract AC07-

94ID13223. Order Number DE98058441. Source: OSTI;

NTIS; INIS; GPO Dep.

This report summarizes activities that have already been

completed as well as yet to be performed by the Idaho National Engineering and Environmental Laboratory (INEEL) to

develop a plan to quantify the behavior of radioactive lowlevel waste forms. It briefly describes the status of various

tasks, including DOE approval of the proposed work, several regulatory and environmental related documents, tests

to qualify the waste form, preliminary schedule, and approximate cost. It is anticipated that INEEL and Brookhaven

National Laboratory will perform the majority of the tests.

For some tests, services of other testing organizations may

be used. It should take approximately nine months to provide the final report on the results of tests on a waste form

prepared for qualification. It is anticipated that the overall

cost of the waste quantifying service is approximately

$150,000. The following tests are planned: compression,

thermal cycling, irradiation, biodegradation, leaching, immersion, free-standing liquid tests, and full-scale testing.

342

(INEEL/EXT–97-01145-Vol.1)

Waste disposal options report. Volume 1. Russell, N.E.;

McDonald, T.G.; Banaee, J.; Barnes, C.M.; Fish, L.W.;

Losinski, S.J.; Peterson, H.K.; Sterbentz, J.W.; Wenzel,

D.R. Lockheed Idaho Technologies Co., Idaho Falls, ID

(United States). Feb 1998. 53p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States). DOE Contract AC07-94ID13223. Order Number

DE98052238. Source: OSTI; NTIS; INIS; GPO Dep.

This report summarizes the potential options for the

processing and disposal of mixed waste generated by reprocessing spent nuclear fuel at the Idaho Chemical

Processing Plant. It compares the proposed wasteimmobilization processes, quantifies and characterizes the

resulting waste forms, identifies potential disposal sites and

their primary acceptance criteria, and addresses disposal issues for hazardous waste.

343

(INEEL/EXT–97-01145-Vol.2)

Waste disposal options report. Volume 2. Russell, N.E.;

McDonald, T.G.; Banaee, J.; Barnes, C.M.; Fish, L.W.;

Losinski, S.J.; Peterson, H.K.; Sterbentz, J.W.; Wenzel, D.R.

Lockheed Idaho Technologies Co., Idaho Falls, ID (United

States). Feb 1998. [300p.] Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract AC07-94ID13223. Order Number

DE98002911. Source: OSTI; NTIS; INIS; GPO Dep.

Includes INEEL/EXT–97-01147-Rev.1.

Volume 2 contains the following topical sections: estimates of feed and waste volumes, compositions, and

properties; evaluation of radionuclide inventory for Zr calcine; evaluation of radionuclide inventory for Al calcine;

determination of keff for high level waste canisters in various

configurations; review of ceramic silicone foam for radioactive waste disposal; epoxides for low-level radioactive waste

disposal; evaluation of several neutralization cases in processing calcine and sodium-bearing waste; background

information for EFEs, dose rates, watts/canister, and PEcuries; waste disposal options assumptions; update of

radiation field definition and thermal generation rates for calcine process packages of various geometries-HKP-26-97;

and standard criteria of candidate repositories and environmental regulations for the treatment and disposal of ICPP

radioactive mixed wastes.

344

(INEEL/EXT–97-01164)

Performance test results of noninvasive characterization of RCRA surrogate waste by prompt gamma

neutron activation analysis. Gehrke, R.J.; Propp, W.A.

Lockheed Martin Idaho Technologies Co., Idaho National

Engineering and Environmental Lab., Idaho Falls, ID (United

States). Nov 1997. 13p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States).

DOE Contract AC07-94ID13223. Order Number

DE98056053. Source: OSTI; NTIS; INIS; GPO Dep.

A performance evaluation to determine the feasibility of

using prompt gamma neutron activation analysis (PGNAA)

for noninvasive, quantitative assay of mixed waste containers was sponsored by DOE’s Office of Technology

Development (OTD), the Mixed Waste Focus Area (MWFA),

and the Idaho National Engineering and Environmental Laboratory (INEEL). The evaluation was conducted using a

surrogate waste, based on Portland cement, that was

spiked with three RCRA metals, mercury, cadmium, and

lead. The results indicate that PGNAA has potential as a

process monitor. However, further development is required

to improve its sensitivity to meet regulatory requirements for

determination of these RCRA metals.

345

(INEEL/EXT–97-01204-Vol.1)

ICPP tank farm closure study. Volume 1. Spaulding, B.C.

(and others); Gavalya, R.A.; Dahlmeir, M.M. Lockheed

Idaho Technologies Co., Idaho Falls, ID (United States). Feb

1998. [500p.] Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract AC07-94ID13223. Order Number DE98052226.

Source: OSTI; NTIS; INIS; GPO Dep.

The disposition of INEEL radioactive wastes is now under

a Settlement Agreement between the DOE and the State of

Idaho. The Settlement Agreement requires that existing liquid sodium bearing waste (SBW), and other liquid waste

inventories be treated by December 31, 2012. This agreement also requires that all HLW, including calcined waste,

be disposed or made road ready to ship from the INEEL by

2035. Sodium bearing waste (SBW) is produced from decontamination operations and HLW from reprocessing of

SNF. SBW and HLW are radioactive and hazardous mixed

waste; the radioactive constituents are regulated by DOE

and the hazardous constituents are regulated by the Resource Conservation and Recovery Act (RCRA). Calcined

waste, a dry granular material, is produced in the New

Waste Calcining Facility (NWCF). Two primary waste tank

storage locations exist at the ICPP: Tank Farm Facility (TFF)

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

and the Calcined Solids Storage Facility (CSSF). The TFF

has the following underground storage tanks: four 18,400-

gallon tanks (WM 100-102, WL 101); four 30,000-gallon

tanks (WM 103-106); and eleven 300,000+ gallon tanks.

This includes nine 300,000-gallon tanks (WM 182-190) and

two 318,000 gallon tanks (WM 180-181). This study analyzes the closure and subsequent use of the eleven

300,000+ gallon tanks. The 18,400 and 30,000-gallon tanks

were not included in the work scope and will be closed as a

separate activity. This study was conducted to support the

HLW Environmental Impact Statement (EIS) waste separations options and addresses closure of the 300,000-gallon

liquid waste storage tanks and subsequent tank void uses.

A figure provides a diagram estimating how the TFF could

be used as part of the separations options. Other possible

TFF uses are also discussed in this study.

346

(INEEL/EXT–97-01204-Vol.2)

ICPP tank farm closure study. Volume 2: Engineering

design files. Lockheed Idaho Technologies Co., Idaho

Falls, ID (United States). Feb 1998. [500p.] Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract AC07-94ID13223. Order

Number DE98002909. Source: OSTI; NTIS; INIS; GPO Dep.

Volume 2 contains the following topical sections: Tank

farm heel flushing/pH adjustment; Grouting experiments for

immobilization of tank farm heel; Savannah River high level

waste tank 20 closure; Tank farm closure information; Clean

closure of tank farm; Remediation issues; Remote demolition techniques; Decision concerning EIS for debris

treatment facility; CERCLA/RCRA issues; Area of contamination determination; Containment building of debris

treatment facility; Double containment issues; Characterization costs; Packaging and disposal options for the waste

resulting from the total removal of the tank farm; Take-off

calculations for the total removal of soils and structures at

the tank farm; Vessel off-gas systems; Jet-grouted polymer

and subsurface walls; Exposure calculations for total removal of tank farm; Recommended instrumentation during

retrieval operations; High level waste tank concrete encasement evaluation; Recommended heavy equipment and

sizing equipment for total removal activities; Tank buoyancy

constraints; Grout and concrete formulas for tank heel solidification; Tank heel pH requirements; Tank cooling water;

Evaluation of conservatism of vehicle loading on vaults; Typical vault dimensions and approximately tank and vault void

volumes; Radiological concerns for temporary vessel off-gas

system; Flushing calculations for tank heels; Grout lift depth

analysis; Decontamination solution for waste transfer piping;

Grout lift determination for filling tank and vault voids;

sprung structure vendor data; Grout flow properties through

a 2–4 inch pipe; Tank farm load limitations; NRC low level

waste grout; Project data sheet calculations; Dose rates for

tank farm closure tasks; Exposure and shielding calculations

for grout lines; TFF radionuclide release rates; Documentation of the clean closure of a system with listed waste

discharge; and Documentation of the ORNL method of radionuclide concentrations in tanks.

347

(INEEL/EXT–97-01204-Vol.3)

ICPP tank farm closure study. Volume 3: Cost estimates, planning schedules, yearly cost flowcharts, and

life-cycle cost estimates. Lockheed Idaho Technologies

Co., Idaho Falls, ID (United States). Feb 1998. [500p.]

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC07-94ID13223. Order Number DE98002910. Source:

OSTI; NTIS; INIS; GPO Dep.

This volume contains information on cost estimates, planning schedules, yearly cost flowcharts, and life-cycle costs

for the six options described in Volume 1, Section 2: Option

1 – Total removal clean closure; No subsequent use; Option

2 – Risk-based clean closure; LLW fill; Option 3 – Riskbased clean closure; CERCLA fill; Option 4 – Close to RCRA

landfill standards; LLW fill; Option 5 – Close to RCRA landfill

standards; CERCLA fill; and Option 6 – Close to RCRA

landfill standards; Clean fill. This volume is divided into two

portions. The first portion contains the cost and planning

schedule estimates while the second portion contains lifecycle costs and yearly cash flow information for each option.

348

(INEEL/EXT–97-01251)

DPC loading feasibility study report. Dafoe, R.E.; Lopez,

D.A.; Williams, K.L. Lockheed Martin Idaho Technologies

Co., Idaho National Engineering and Environmental Lab.,

Idaho Falls, ID (United States). Nov 1997. 341p. Sponsored

by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract AC07-94ID13223.

Order Number DE98051441. Source: OSTI; NTIS; INIS;

GPO Dep.

Disposal of radioactive wastes now stored at the Idaho

Chemical Processing Plant at the Idaho National Engineering and Environmental Laboratory is mandated under a

“Settlement Agreement” between the Department of Energy

and the State of Idaho. This study investigates the feasibility

of using the Dry Transfer Cell facility to package waste into

Dual Purpose Canisters for interim storage at the adjacent

Dry Storage System comprised of an interim storage pad

with NUHOMS storage modules. The wastes would then

be road-ready for eventual disposal in a permanent repository. The operating period for these activities is expected to

be from 2015 to 2035.

349

(INEEL/EXT–97-01253)

Human health risk comparisons for environmental management baseline program and integration opportunities

(discussion draft). Eide, S.A.; Jones, J.L.; Wierman, T.E.

Lockheed Martin Idaho Technologies Co., Idaho National

Engineering and Environmental Lab., Idaho Falls, ID (United

States). Feb 1998. [150p.] Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract AC07-94ID13223. Order Number

DE98058439. Source: OSTI; NTIS; INIS; GPO Dep.

This report documents the process and results of human

health risk assessments of the US Department of Energy

(DOE) complex-wide programs for high-level waste, transuranic waste, low-level waste, mixed low-level waste, and

spent nuclear fuel. The DOE baseline programs and alternatives for these five material types were characterized by

disposition maps (system flow diagrams) and supporting information in the May 1997 report A Contractor Report to the

Department of Energy on Environmental Baseline Programs

and Integration Opportunities (Discussion Draft). Risk analyses were performed using the Simplified Risk Model (SRM),

developed to support DOE Environmental Management

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

(EM) integration studies. The SRM risk analyses consistently and comprehensively cover the entire programs for

the five material types, from initial storage through final disposition. Risk results are presented at several levels: DOE

complex-wide, material type program, individual DOE sites,

and DOE site activities.

350

(INEEL/EXT–97-01273)

SWEPP PAN assay system uncertainty analysis: Active

mode measurements of solidified aqueous sludge

waste. Blackwood, L.G.; Harker, Y.D.; Meachum, T.R.

Lockheed Idaho Technologies Co., Idaho Falls, ID (United

States). Dec 1997. 35p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States).

DOE Contract AC07-94ID13223. Order Number

DE98052237. Source: OSTI; NTIS; INIS; GPO Dep.

The Idaho National Engineering and Environmental Laboratory is being used as a temporary storage facility for

transuranic waste generated by the US Nuclear Weapons

program at the Rocky Flats Plant (RFP) in Golden, Colorado. Currently, there is a large effort in progress to

prepare to ship this waste to the Waste Isolation Pilot Plant

(WIPP) in Carlsbad, New Mexico. In order to meet the TRU

Waste Characterization Quality Assurance Program Plan

nondestructive assay compliance requirements and quality

assurance objectives, it is necessary to determine the total

uncertainty of the radioassay results produced by the Stored

Waste Examination Pilot Plant (SWEPP) Passive Active

Neutron (PAN) radioassay system. This paper is one of a

series of reports quantifying the results of the uncertainty

analysis of the PAN system measurements for specific

waste types and measurement modes. In particular this report covers active mode measurements of weapons grade

plutonium-contaminated aqueous sludge waste contained in

208 liter drums (item description codes 1, 2, 7, 800, 803,

and 807). Results of the uncertainty analysis for PAN active

mode measurements of aqueous sludge indicate that a bias

correction multiplier of 1.55 should be applied to the PAN

aqueous sludge measurements. With the bias correction,

the uncertainty bounds on the expected bias are 0  27%.

These bounds meet the Quality Assurance Program Plan

requirements for radioassay systems.

351

(INEEL/EXT–97-01300)

FY-97 operations of the pilot-scale glass melter to vitrify

simulated ICPP high activity sodium-bearing waste. Musick, C.A. Lockheed Idaho Technologies Co., Idaho Falls, ID

(United States). Nov 1997. 56p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States). DOE Contract AC07-94ID13223. Order Number

DE98051445. Source: OSTI; NTIS; INIS; GPO Dep.

A 3.5 liter refractory-lined joule-heated glass melter was

built to test the applicability of electric melting to vitrify simulated high activity waste (HAW). The HAW streams result

from dissolution and separation of Idaho Chemical Processing Plant (ICPP) calcines and/or radioactive liquid waste.

Pilot scale melter operations will establish selection criteria

needed to evaluate the application of joule heating to immobilize ICPP high activity waste streams. The melter was

fabricated with K-3 refractory walls and Inconel 690 electrodes. It is designed to be continuously operated at 1,150 C

with a maximum glass output rate of 10 lbs/hr. The first set

of tests were completed using surrogate HAW-sodium bearing waste (SBW). The melter operated for 57 hours and was

shut down due to excessive melt temperatures resulting in

low glass viscosity (< 30 Poise). Due to the high melt temperature and low viscosity the molten glass breached the

melt chamber. The melter has been dismantled and examined to identify required process improvement areas and

successes of the first melter run. The melter has been redesigned and is currently being fabricated for the second

run, which is scheduled to begin in December 1997.

352

(INEEL/EXT–97-01325)

Assessment of the RELAP5 multi-dimensional component model using data from LOFT test L2-5. Davis, C.B.

Idaho National Engineering Lab., Idaho Falls, ID (United

States). Jan 1998. 50p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States).

DOE Contract AC07-94ID13223. Order Number

DE98052253. Source: OSTI; NTIS; INIS; GPO Dep.

The capability of the RELAP5-3D computer code to perform multi-dimensional analysis of a pressurized water

reactor (PWR) was assessed using data from the LOFT L2-

5 experiment. The LOFT facility was a 50 MW PWR that

was designed to simulate the response of a commercial

PWR during a loss-of-coolant accident. Test L2-5 simulated

a 200% double-ended cold leg break with an immediate primary coolant pump trip. A three-dimensional model of the

LOFT reactor vessel was developed. Calculations of the

LOFT L2-5 experiment were performed using the RELAP5-

3D Version BF02 computer code. The calculated

thermal-hydraulic responses of the LOFT primary and secondary coolant systems were generally in reasonable

agreement with the test. The calculated results were also

generally as good as or better than those obtained previously with RELAP/MOD3.

353

(INEEL/EXT–97-01337)

Complex-Wide Waste Flow Analysis V1.0 verification

and validation report. Hsu, K.M.; Lundeen, A.S.; Oswald,

K.B.; Shropshire, D.E.; Robinson, J.M.; West, W.H. Lockheed Martin Idaho Technologies Co., Idaho National

Engineering and Environmental Lab., Idaho Falls, ID (United

States). 21 Nov 1997. 228p. Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract AC07-94ID13223. Order Number

DE98051446. Source: OSTI; NTIS; INIS; GPO Dep.

The complex-wide waste flow analysis model (CWWFA)

was developed to assist the Department of Energy (DOE)

Environmental Management (EM) Office of Science and

Technology (EM-50) to evaluate waste management scenarios with emphasis on identifying and prioritizing technology

development opportunities to reduce waste flows and public

risk. In addition, the model was intended to support the

needs of the Complex-Wide Environmental Integration (EMI)

team supporting the DOE’s Accelerating Cleanup: 2006

Plan. CWWFA represents an integrated environmental modeling system that covers the life cycle of waste management

activities including waste generation, interim process

storage, retrieval, characterization and sorting, waste preparation and processing, packaging, final interim storage,

transport, and disposal at a final repository. The CWWFA

shows waste flows through actual site-specific and facilityspecific conditions. The system requirements for CWWFA

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

are documented in the Technical Requirements Document

(TRD). The TRD is intended to be a living document that will

be modified over the course of the execution of CWWFA development. Thus, it is anticipated that CWWFA will continue

to evolve as new requirements are identified (i.e., transportation, small sites, new streams, etc.). This report

provides a documented basis for system verification of

CWWFA requirements. System verification is accomplished

through formal testing and evaluation to ensure that all performance requirements as specified in the TRD have been

satisfied. A Requirement Verification Matrix (RVM) was used

to map the technical requirements to the test procedures.

The RVM is attached as Appendix A. Since February of

1997, substantial progress has been made toward development of the CWWFA to meet the system requirements. This

system verification activity provides a baseline on system

compliance to requirements and also an opportunity to

reevaluate what requirements need to be satisfied in FY-98.

354

(INEEL/EXT–97-01389)

Vitrified waste option study report. Lopez, D.A.; Kimmitt,

R.R. Idaho National Engineering Lab., Idaho Falls, ID

(United States). Feb 1998. 451p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States). DOE Contract AC07-94ID13223. Order Number

DE98052230. Source: OSTI; NTIS; INIS; GPO Dep.

A “Settlement Agreement” between the Department of Energy and the State of Idaho mandates that all radioactive

high-level waste (HLW) now stored at the Idaho Chemical

Processing Plant (ICPP) will be treated so that it is ready to

be moved out of Idaho for disposal by a target date of 2035.

This report investigates vitrification treatment of all ICPP calcine, including the existing and future HLW calcine resulting

from calcining liquid Sodium-Bearing Waste (SBW). Currently, the SBW is stored in the tank farm at the ICPP.

Vitrification of these wastes is an acceptable treatment

method for complying with the Settlement Agreement. This

method involves vitrifying the calcined waste and casting the

vitrified mass into stainless steel canisters that will be ready

to be moved out of the Idaho for disposal by 2035. These

canisters will be stored at the Idaho National Engineering

and Environmental Laboratory (INEEL) until they are sent to

a HLW national repository. The operating period for vitrification treatment will be from 2013 through 2032; all HLW will

be treated and in storage by the end of 2032.

355

(INEEL/EXT–97-01392)

Hot isostatic press waste option study report. Russell,

N.E.; Taylor, D.D. Lockheed Idaho Technologies Co., Idaho

Falls, ID (United States). Feb 1998. [400p.] Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract AC07-94ID13223. Order

Number DE98052233. Source: OSTI; NTIS; INIS; GPO Dep.

A Settlement Agreement between the Department of Energy and the State of Idaho mandates that all high-level

radioactive waste now stored at the Idaho Chemical Processing Plant be treated so that it is ready to move out of

Idaho for disposal by the target date of 2035. This study

investigates the immobilization of all Idaho Chemical Processing Plant calcine, including calcined sodium bearing

waste, via the process known as hot isostatic press, which

produces compact solid waste forms by means of high temperature and pressure (1,050 C and 20,000 psi), as the

treatment method for complying with the settlement agreement. The final waste product would be contained in

stainless-steel canisters, the same type used at the Savannah River Site for vitrified waste, and stored at the Idaho

National Engineering and Environmental Laboratory until a

national geological repository becomes available for its disposal. The waste processing period is from 2013 through

2032, and disposal at the High Level Waste repository will

probably begin sometime after 2065.

356

(INEEL/EXT–97-01393)

Interim storage study report. Rawlins, J.K. Lockheed

Idaho Technologies Co., Idaho Falls, ID (United States). Feb

1998. [400p.] Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract AC07-94ID13223. Order Number DE98052240.

Source: OSTI; NTIS; INIS; GPO Dep.

High-level radioactive waste (HLW) stored at the Idaho

Chemical Processing Plant (ICPP) in the form of calcine and

liquid and liquid sodium-bearing waste (SBW) will be processed to provide a stable waste form and prepare the

waste to be transported to a permanent repository. Because

a permanent repository will not be available when the waste

is processed, the waste must be stored at ICPP in an

Interim Storage Facility (ISF). This report documents consideration of an ISF for each of the waste processing options

under consideration.

357

(INEEL/EXT–97-01396-Vol.1)

Calcined solids storage facility closure study. Dahlmeir,

M.M. (and others); Tuott, L.C.; Spaulding, B.C. Idaho National Engineering Lab., Idaho Falls, ID (United States). Feb

1998. 310p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract AC07-94ID13223. Order Number DE98052234.

Source: OSTI; NTIS; INIS; GPO Dep.

The disposal of radioactive wastes now stored at the

Idaho National Engineering and Environmental Laboratory is

currently mandated under a “Settlement Agreement” (or

“Batt Agreement”) between the Department of Energy and

the State of Idaho. Under this agreement, all high-level

waste must be treated as necessary to meet the disposal

criteria and disposed of or made road ready to ship from the

INEEL by 2035. In order to comply with this agreement, all

calcined waste produced in the New Waste Calcining Facility and stored in the Calcined Solids Facility must be treated

and disposed of by 2035. Several treatment options for the

calcined waste have been studied in support of the HighLevel Waste Environmental Impact Statement. Two

treatment methods studied, referred to as the TRU Waste

Separations Options, involve the separation of the high-level

waste (calcine) into TRU waste and low-level waste (Class

A or Class C). Following treatment, the TRU waste would be

sent to the Waste Isolation Pilot Plant (WIPP) for final storage. It has been proposed that the low-level waste be

disposed of in the Tank Farm Facility and/or the Calcined

Solids Storage Facility following Resource Conservation and

Recovery Act closure. In order to use the seven Bin Sets

making up the Calcined Solids Storage Facility as a

low-level waste landfill, the facility must first be closed to Resource Conservation and Recovery Act (RCRA) standards.

This study identifies and discusses two basic methods available to close the Calcined Solids Storage Facility under the

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

RCRA - Risk-Based Clean Closure and Closure to Landfill

Standards. In addition to the closure methods, the regulatory

requirements and issues associated with turning the Calcined Solids Storage Facility into an NRC low-level waste

landfill or filling the bin voids with clean grout are discussed.

358

(INEEL/EXT–97-01396-Vol.2)

ICPP calcined solids storage facility closure study. Volume II: Cost estimates, planning schedules, yearly cost

flowcharts, and life-cycle cost estimates. Idaho National

Engineering Lab., Idaho Falls, ID (United States). Feb 1998.

339p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC07-94ID13223. Order Number DE98002912. Source:

OSTI; NTIS; INIS; GPO Dep.

This document contains Volume II of the Closure Study

for the Idaho Chemical Processing Plant Calcined Solids

Storage Facility. This volume contains draft information on

cost estimates, planning schedules, yearly cost flowcharts,

and life-cycle costs for the four options described in Volume

I: (1) Risk-Based Clean Closure; NRC Class C fill, (2) RiskBased Clean Closure; Clean fill, (3) Closure to landfill

Standards; NRC Class C fill, and (4) Closure to Landfill

Standards; Clean fill.

359

(INEEL/EXT–97-01396-Vol.3)

ICPP calcined solids storage facility closure study.

Volume III: Engineering design files. Idaho National Engineering Lab., Idaho Falls, ID (United States). Feb 1998.

481p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC07-94ID13223. Order Number DE98002913. Source:

OSTI; NTIS; INIS; GPO Dep.

Includes WINCO–1180 and INEL/EXT–97-00117.

The following information was calculated to support cost

estimates and radiation exposure calculations for closure

activities at the Calcined Solids Storage Facility (CSSF).

Within the estimate, volumes were calculated to determine

the required amount of grout to be used during closure activities. The remaining calcine on the bin walls, supports,

piping, and floor was also calculated to approximate the remaining residual calcine volumes at different stages of the

removal process. The estimates for remaining calcine and

vault void volume are higher than what would actually be

experienced in the field, but are necessary for bounding purposes. The residual calcine in the bins may be higher than

was is experienced in the field as it was assumed that the

entire bin volume is full of calcine before removal activities

commence. The vault void volumes are higher as the vault

roof beam volumes were neglected. The estimations that

follow should be considered rough order of magnitude, due

to the time constraints as dictated by the project’s scope of

work. Should more accurate numbers be required, a new

analysis would be necessary.

360

(INEEL/EXT–97-01399)

Direct cementitious waste option study report. Dafoe,

R.E.; Losinski, S.J. Idaho National Engineering Lab., Idaho

Falls, ID (United States). Feb 1998. 500p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract AC07-94ID13223. Order

Number DE98052242. Source: OSTI; NTIS; INIS; GPO Dep.

A settlement agreement between the Department of Energy (DOE) and the State of Idaho mandates that all

high-level radioactive waste (HLW) now stored at the Idaho

Chemical Processing Plant (ICPP) will be treated so that it is

ready to be moved out of Idaho for disposal by a target data

of 2035. This study investigates the direct grouting of all

ICPP calcine (including the HLW dry calcine and those resulting from calcining sodium-bearing liquid waste currently

residing in the ICPP storage tanks) as the treatment method

to comply with the settlement agreement. This method involves grouting the calcined waste and casting the resulting

hydroceramic grout into stainless steel canisters. These

canisters will be stored at the Idaho National Engineering

and Environmental Laboratory (INEEL) until they are sent to

a national geologic repository. The operating period for

grouting treatment will be from 2013 through 2032, and all

the HLW will be treated and in interim storage by the end of

2032.

361

(INEEL/EXT–97-01400)

Cementitious waste option scoping study report. Lee,

A.E.; Taylor, D.D. Lockheed Idaho Technologies Co., Idaho

Falls, ID (United States). Feb 1998. [400p.] Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract AC07-94ID13223. Order

Number DE98052239. Source: OSTI; NTIS; INIS; GPO Dep.

A Settlement Agreement between the Department of Energy (DOE) and the State of Idaho mandates that all

high-level radioactive waste (HLW) now stored at the Idaho

Chemical Processing Plant (ICPP) on the Idaho National

Engineering and Environmental Laboratory (INEEL) will be

treated so that it is ready to be moved out of Idaho for disposal by a target date of 2035. This study investigates the

nonseparations Cementitious Waste Option (CWO) as a

means to achieve this goal. Under this option all liquid

sodium-bearing waste (SBW) and existing HLW calcine

would be recalcined with sucrose, grouted, canisterized, and

interim stored as a mixed-HLW for eventual preparation and

shipment off-Site for disposal. The CWO waste would be

transported to a Greater Confinement Disposal Facility

(GCDF) located in the southwestern desert of the US on the

Nevada Test Site (NTS). All transport preparation, shipment,

and disposal facility activities are beyond the scope of this

study. CWO waste processing, packaging, and interim storage would occur over a 5-year period between 2013 and

2017. Waste transport and disposal would occur during the

same time period.

362

(INEEL/EXT–97-01414)

Evaluation of SAFT America, Inc. electrochemical capacitors. Wright, R.B.; Murphy, T.C. Lockheed Idaho

Technologies Co., Idaho Falls, ID (United States). Dec 1997.

70p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC07-94ID13223. Order Number DE98052255. Source:

OSTI; NTIS; GPO Dep.

The electrochemical capacitor devices described in this

report were deliverables from Lawrence Berkeley National

Laboratory (LBNL), Contract No. 4606510 with SAFT America, Inc., as part of LBNL’s exploratory research program.

Dr. Kimio Kinoshita is the Program Manager at LBNL. The

contract was in support of the US Department of Energy’s

(DOE) exploratory electrochemical energy storage program

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

which includes development projects for a wide variety of

advanced high-energy/high-power energy storage systems

for electric and hybrid vehicle programs. The DOE is currently developing various electrochemical capacitors as

candidate power assist devices for the Partnership for a

New Generation of Vehicles (PNGV) fast-response engine

requirements. The LBNL contract with SAFT America, Inc.,

was intended to evaluate various activated carbon-based

electrode formulations and develop an electrical model of

the double-layer capacitor. The goal is to design and deliver

prototypes meeting the DOE requirement of > 1,000 W/kg,

16 Wh/kg. Deliverables were sent to the INEEL EST laboratory for independent testing and evaluation. The following

report describes performance testing on ten devices received September 2, 1996. Due to the initial performance of

these early devices, life-cycle testing was not conducted.

Additional devices, with improved performance, are expected to be tested. Future results will be reported in a

follow-on report.

363

(INEEL/EXT–97-01461)

Fusion safety program annual report fiscal year 1997.

Longhurst, G.R. (and others); Anderl, R.A.; Cadwallader,

L.C. Lockheed Idaho Technologies Co., Idaho Falls, ID

(United States). Jan 1998. 68p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States). DOE Contract AC07-94ID13223. Order Number

DE98052227. Source: OSTI; NTIS; INIS; GPO Dep.

This report summarizes the major activities of the Fusion

Safety Program in FY 1997. The Idaho National Engineering

and Environmental Laboratory (INEEL) is the designated

lead laboratory, and Lockheed Martin Idaho Technologies

Company is the prime contractor for this program. The Fusion Safety Program was initiated in FY 1979 to perform

research and develop data needed to ensure safety in fusion facilities. Activities include experiments, analysis, code

development and application, and other forms of research.

These activities are conducted at the INEEL, different DOE

laboratories, and other institutions. The technical areas covered in this report include chemical reactions and activation

product release, tritium safety, risk assessment failure rate

database development, and safety code development and

application to fusion safety issues. Most of this work has

been done in support of the International Thermonuclear Experimental Reactor (ITER) project. Work done for ITER this

year has focused on developing the needed information for

the Non-site Specific Safety Report (NSSR-2).

364

(INEEL/EXT–98-00004)

Demonstration of an optimized TRUEX flowsheet for

partitioning of actinides from actual ICPP sodiumbearing waste using centrifugal contactors in a shielded

cell facility. Law, J.D.; Brewer, K.N.; Herbst, R.S.; Todd,

T.A.; Olson, L.G. Lockheed Idaho Technologies Co., Idaho

Falls, ID (United States). Jan 1998. 30p. Sponsored by USDOE Office of Environmental Management, Washington, DC

(United States). DOE Contract AC07-94ID13223. Order

Number DE98052248. Source: OSTI; NTIS; INIS; GPO Dep.

The TRUEX process is being evaluated at the Idaho

Chemical Processing Plant (ICPP) for the separation of the

actinides from acidic radioactive wastes stored at the ICPP.

These efforts have culminated in recent demonstrations of

the TRUEX process with actual tank waste. The first demonstration was performed in 1996 using 24 stages of 2-cm

diameter centrifugal contactors and waste from tank WM183. Based on the results of this flowsheet demonstration,

the flowsheet was optimized and a second flowsheet

demonstration was performed. This test also was performed

using 2-cm diameter centrifugal contactors and waste from

tank WM-183. However, the total number of contactor

stages was reduced from 24 to 20. Also, the concentration

of HEDPA in the strip solution was reduced from 0.04 M to

0.01 M in order to minimize the amount of phosphate in the

HLW fraction, which would be immobilized into a glass

waste form. This flowsheet demonstration was performed

using centrifugal contactors installed in the shielded hot cell

at the ICPP Remote Analytical Laboratory. The flowsheet

tested consisted of six extraction stages, four scrub stages,

six strip stages, two solvent was stages, and two acid rinse

stages. An overall removal efficiency of 99.79% was

obtained for the actinides. As a result, the activity of the actinides was reduced from 540 nCi/g in the feed to 0.90 nCi/g

in the aqueous raffinate, which is well below the NRC Class

A LLW requirement of 10 nCi/g for non-TRU waste. Removal efficiencies of 99.84%, 99.97%, 99.97%, 99.85%, and

99.76% were obtained for 241Am, 238Pu, 239Pu, 235U, and 238U, respectively.

365

(INEEL/EXT–98-00062)

Mapping of contamination at Savannah River Site FBWU

by INEEL trolley. Carpenter, M.V.; Gehrke, R.J.; Helmer,

R.G.; Josten, N. Lockheed Idaho Technologies Co., Idaho

Falls, ID (United States). Jan 1998. [50p.] Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract AC07-94ID13223. Order

Number DE98052241. Source: OSTI; NTIS; INIS; GPO Dep.

The Ford Building Waste Unit (FBWU) 643-11G is a Resource Conservation and Recovery Act/Comprehensive

Environmental Response Compensation and Liability Act

(RCRA/CERCLA) designated site at the Savannah River

Site (SRS) in Aiken, South Carolina. Pre-Work Plan

Characterization at the FBWU in May 1996 indicated that radiological contamination was present in surface and near

surface soils and identified cesium-137, 137Cs, the unit specific contaminant, as being primarily in the top 15 cm of soil.

The Idaho National Engineering and Environmental Laboratory (INEEL) sent the dig-face trolley system to SRS where

it demonstrated its capability over a 6.1-m (20 ft.) x 9.6-m

(30 ft.) area to rapidly map the contamination on-line with its

large area plastic scintillation detector. Also, an extendedrange (10 keV to 3 MeV) Ge detector was used at selected

locations to identify and quantify the 137Cs contamination.

The coordinate locations of each measurement acquired in

either the scanning or fixed position mode was obtained with

a survey system based on radial encoders. Topography

measurements were also made during measurements to

permit correction of field of view and activity concentrations

for changes in the ground to detector distance.

366

(INEEL/EXT–98-00100)

Evaluation and testing of HUMASORB-CS for the removal of radionuclides from groundwater. Mann, N.R.;

Todd, T.A.; Wood, D.J. Lockheed Idaho Technologies Co.,

Idaho Falls, ID (United States). Jan 1998. 29p. Sponsored

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by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract AC07-94ID13223.

Order Number DE98052236. Source: OSTI; NTIS; INIS;

GPO Dep.

An independent experiment to demonstrate the combined

removal of the radionuclides, 85Sr and 137Cs from groundwater has been conducted with the sorbent, HUMASORB-CS.

Arctech, Inc. manufactures this humic acid-based sorbent

material. This sorbent material is reported to have potential

for remediation of contaminated groundwater present at

DOE sites. The purpose of this work was to evaluate the

removal efficiency and the capacity of the sorbent. Two ionexchange columns were assembled at the Idaho Chemical

Processing Plant (ICPP) to evaluate the sorbent technology.

Initial 137Cs breakthrough in both columns was observed after 22.0 and 30.2 bed volumes, respectively. Strontium-85

removal was slightly more efficient than 137Cs removal. Initial 85Sr breakthrough in both columns was observed after

29.4 and 22.7 bed volumes, respectively. Calcium, which is

of concern, is the major constituent within the feed solution.

Calcium is attributed to loading interference in addition to

other alkaline and alkaline earth metals such as stable Sr,

Mg, Na, K, and Ba. Interfering ions fill exchange sites that

greatly reduce the sorbents efficiency to sorb targeted ions

such as radioactive Cs and Sr. Despite high concentrations

of Ca in the feed solution, Ca was not sorbed by

HUMASORB-CS. Results indicate HUMASORB-CS does

not sorb sodium or potassium. Sodium and potassium

concentrations were consistently observed at 100% breakthrough throughout the test.

367

(INEEL/EXT–98-00101)

High level waste facilities – Continuing operation or orderly shutdown. Decker, L.A. Lockheed Martin Idaho

Technologies Co., Idaho National Engineering and Environmental Lab., Idaho Falls, ID (United States). Apr 1998. 41p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC07-94ID13223. Order Number DE98054113. Source:

OSTI; NTIS; INIS; GPO Dep.

Two options for Environmental Impact Statement No action alternatives describe operation of the radioactive liquid

waste facilities at the Idaho Chemical Processing Plant at

the Idaho National Engineering and Environmental Laboratory. The first alternative describes continued operation of all

facilities as planned and budgeted through 2020. Institutional

control for 100 years would follow shutdown of operational

facilities. Alternatively, the facilities would be shut down in

an orderly fashion without completing planned activities. The

facilities and associated operations are described. Remaining sodium bearing liquid waste will be converted to solid

calcine in the New Waste Calcining Facility (NWCF) or will

be left in the waste tanks. The calcine solids will be stored in

the existing Calcine Solids Storage Facilities (CSSF). Regulatory and cost impacts are discussed.

368

(INEEL/EXT–98-00116)

Idaho Chemical Processing Plant low-activity waste

grout stabilization development program FY-97 status

report. Herbst, A.K.; Marshall, D.W.; McCray, J.A. Lockheed Idaho Technologies Co., Idaho National Engineering

and Environmental Lab., Idaho Falls, ID (United States).

Feb 1998. 29p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE

Contract AC07-94ID13223. Order Number DE98052563.

Source: OSTI; NTIS; INIS; GPO Dep.

The general purpose of the Grout Development Program

is to solidify and stabilize the liquid low-activity wastes

(LAW) generated at the Idaho Chemical Processing Plant

(ICPP). It is anticipated that LAW will be produced from the

following: (1) chemical separation of the tank farm highactivity sodium-bearing waste, (2) retrieval, dissolution, and

chemical separation of the aluminum, zirconium, and

sodium calcines, (3) facility decontamination processes, and

(4) process equipment waste. Grout formulation studies for

sodium-bearing LAW, including decontamination and process equipment waste, continued this fiscal year. A second

task was to develop a grout formulation to solidify potential

process residual heels in the tank farm vessels when the

vessels are closed.

369

(INEEL/EXT–98-00157)

Legacy sample disposition project. Volume 2: Final report. Gurley, R.N.; Shifty, K.L. Lockheed Martin Idaho

Technologies Co., Idaho National Engineering and Environmental Lab., Idaho Falls, ID (United States). Feb 1998. 77p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC07-94ID13223. Order Number DE98052565. Source:

OSTI; NTIS; INIS; GPO Dep.

This report describes the legacy sample disposition

project at the Idaho Engineering and Environmental Laboratory (INEEL), which assessed Site-wide facilities/areas to

locate legacy samples and owner organizations and then

characterized and dispositioned these samples. This project

resulted from an Idaho Department of Environmental Quality

inspection of selected areas of the INEEL in January 1996,

which identified some samples at the Test Reactor Area and

Idaho Chemical Processing Plant that had not been

characterized and dispositioned according to Resource Conservation and Recovery Act (RCRA) requirements. The

objective of the project was to manage legacy samples in

accordance with all applicable environmental and safety requirements. A systems engineering approach was used

throughout the project, which included collecting the legacy

sample information and developing a system for amending

and retrieving the information. All legacy samples were dispositioned by the end of 1997. Closure of the legacy sample

issue was achieved through these actions.

370

(INEEL/EXT–98-00221)

Workshop proceedings: Developing the scientific basis

for long-term land management of the Idaho National

Engineering and Environmental Laboratory. Sperber,

T.D. (Environmental Science and Research Foundation,

Inc., Idaho Falls, ID (United States)); Reynolds, T.D. (eds.);

Breckenridge, R.P. (ed.). Lockheed Martin Idaho Technologies Co., Idaho National Engineering and Environmental

Lab., Idaho Falls, ID (United States). Mar 1998. [150p.]

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC07-94ID13223. (ESRF–023; CONF-9709210–Summ.:

Workshop on developing the scientific basis for long-term

land management of the Idaho National Engineering and

Environmental Laboratory, Idaho Falls, ID (United States),

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

9-10 Sep 1997). Order Number DE98052560. Source:

OSTI; NTIS; INIS; GPO Dep.

Responses to a survey on the INEEL Comprehensive Facility and Land Use Plan (US DOE 1996a) indicated the

need for additional discussion on environmental resources,

disturbance, and land use issues on the Idaho National Engineering and Environmental Laboratory (INEEL). As a

result, in September 1997, a workshop evaluated the existing scientific basis and determined future data needs for

long-term land management on the INEEL. This INEEL

Long-Term Land Management Workshop examined existing

data on biotic, abiotic, and heritage resources and how

these resources have been impacted by disturbance activities of the INEEL. Information gained from this workshop will

help guide land and facility use decisions, identify data

gaps, and focus future research efforts. This report summarizes background information on the INEEL and its

long-term land use planning efforts, presentations and discussions at the workshop, and the existing data available at

the INEEL. In this document, recommendations for future

INEEL land use planning, research efforts, and future workshops are presented. The authors emphasize these are not

policy statements, but comments and suggestions made by

scientists and others participating in the workshop. Several

appendices covering land use disturbance, legal drivers,

land use assumptions and workshop participant comments,

workshop participants and contributors, and the workshop

agenda are also included.

371

(INEEL/EXT–98-00284)

National Low-Level Waste Management Program final

summary report of key activities and accomplishments

for fiscal year 1997. Rittenberg, R.B. Lockheed Idaho

Technologies Co., Idaho National Engineering and Environmental Lab., Idaho Falls, ID (United States). Mar 1998. 22p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC07-94ID13223. Order Number DE98052579. Source:

OSTI; NTIS; INIS; GPO Dep.

The US Department of Energy (DOE) has responsibilities

under the Low-Level Radioactive Waste Policy Amendments

Act of 1985 to assist states and compacts in their siting and

licensing efforts for low-level radioactive waste disposal

facilities. The National Low-Level Waste Management Program (NLLWMP) is the element of the DOE that performs

the key support activities under the Act. The NLLWMP’s activities are driven by the needs of the states and compacts

as they prepare to manage their low-level waste under the

Act. Other work is added during the fiscal year as necessary

to accommodate new requests brought on by status

changes in states’ and compacts’ siting and licensing efforts.

This report summarizes the activities and accomplishments

of the NLLWMP during FY 1997.

372

(INEEL/EXT–98-00301)

Waste generator services implementation plan.

Mousseau, J.; Magleby, M.; Litus, M. Lockheed Martin Idaho

Technologies Co., Idaho National Engineering and Environmental Lab., Idaho Falls, ID (United States). Apr 1998.

109p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC07-94ID13223. Order Number DE98056054. Source:

OSTI; NTIS; INIS; GPO Dep.

Recurring waste management noncompliance problems

have spurred a fundamental site-wide process revision to

characterize and disposition wastes at the Idaho National

Engineering and Environmental Laboratory. The reengineered method, termed Waste Generator Services, will

streamline the waste acceptance process and provide waste

generators comprehensive waste management services

through a single, accountable organization to manage and

disposition wastes in a timely, cost-effective, and compliant

manner. This report outlines the strategy for implementing

Waste Generator Services across the INEEL. It documents

the culmination of efforts worked by the LMITCO Environmental Management Compliance Reengineering project

team since October 1997. These efforts have included defining problems associated with the INEEL waste management

process; identifying commercial best management practices;

completing a review of DOE Complex-wide waste management training requirements; and involving others through an

Integrated Process Team approach to provide recommendations on process flow, funding/charging mechanisms, and

WGS organization. The report defines the work that will be

performed by Waste Generator Services, the organization

and resources, the waste acceptance process flow, the

funding approach, methods for measuring performance, and

the implementation schedule and approach. Field deployment will occur first at the Idaho Chemical Processing Plant

in June 1998. Beginning in Fiscal Year 1999, Waste Generator Services will be deployed at the other major INEEL

facilities in a phased approach, with implementation completed by March 1999.

373

(INEEL/EXT–98-00303)

Corral Monitoring System assessment results. Filby,

E.E.; Haskel, K.J. Lockheed Martin Idaho Technologies Co.,

Idaho National Engineering and Environmental Lab., Idaho

Falls, ID (United States). Mar 1998. 60p. Sponsored by USDOE Office of Environmental Management, Washington, DC

(United States). DOE Contract AC07-94ID13223. Order

Number DE98054112. Source: OSTI; NTIS; INIS; GPO Dep.

This report describes the results of a functional and operational assessment of the Corral Monitoring Systems

(CMS), which was designed to detect and document accountable items entering or leaving a monitored site. Its

development was motivated by the possibility that multiple

sites in the nuclear weapons states of the former Soviet

Union might be opened to such monitoring under the provisions of the Strategic Arms Reduction Treaty. The

assessment was performed at three levels. One level evaluated how well the planned approach addressed the target

application, and which involved tracking sensitive items

moving into and around a site being monitored as part of an

international treaty or other agreement. The second level

examined the overall design and development approach,

while the third focused on individual subsystems within the

total package. Unfortunately, the system was delivered as

disassembled parts and pieces, with very poor documentation. Thus, the assessment was based on fragmentary

operating data coupled with an analysis of what documents

were provided with the system. The system design seemed

to be a reasonable match to the requirements of the target

application; however, important questions about site manning and top level administrative control were left

unanswered. Four weaknesses in the overall design and development approach were detected: (1) poor configuration

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

control and management, (2) inadequate adherence to a

well defined architectural standard, (3) no apparent provision for improving top level error tolerance, and (4)

weaknesses in the object oriented programming approach.

The individual subsystems were found to offer few features

or capabilities that were new or unique, even at the conceptual level. The CMS might possibly have offered a unique

combination of features, but this level of integration was

never realized, and it had no unique capabilities that could

be readily extracted for use in another system.

374

(INEEL/EXT–98-00339)

ICPP Tank Farm planning through 2012. Palmer, W.B.;

Millet, C.B.; Staiger, M.D.; Ward, F.S. Lockheed Martin

Idaho Technologies Co., Idaho National Engineering and

Environmental Lab., Idaho Falls, ID (United States). 1 Apr

1998. [75p.] Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract AC07-94ID13223. Order Number DE98056057.

Source: OSTI; NTIS; INIS; GPO Dep.

Historically, liquid high-level waste (HLW) generated at

the Idaho Chemical Processing Plant has been stored in the

Tank Farm after which it is calcined with the calcine being

stored in stainless steel bins. Following the curtailment of

spent nuclear fuel reprocessing in 1992, the HLW treatment

methods were re-evaluated to establish a path forward for

producing a final waste form from the liquid sodium bearing

wastes (SBW) and the HLW calcine. Projections for significant improvements in waste generation, waste blending and

evaporation, and calcination were incorporated into the Tank

Farm modeling. This optimized modeling shows that all of

the SBW can be calcined by the end of 2012 as required by

the Idaho Settlement Agreement. This Tank Farm plan discusses the use of each of the eleven HLW tanks and shows

that two tanks can be emptied, allowing them to be Resource Conservation and Recovery Act closed by 2006. In

addition, it describes the construction of each tank and

vault, gives the chemical concentrations of the contents of

each tank, based on historical input and some sampling,

and discusses the regulatory drivers important to Tank Farm

operation. It also discusses new waste generation, the computer model used for the Tank Farm planning, the operating

schedule for each tank, and the schedule for when each

tank will be empty and closed.

375

(INEEL/EXT–98-00446)

Idaho Nuclear Technology and Engineering Center

(INTEC) (formerly ICPP) ash reutilization study. Langenwalter, T.; Pettet, M.; Ochoa, R.; Jensen, S. Lockheed

Martin Idaho Technologies Co., Idaho National Engineering

and Environmental Lab., Idaho Falls, ID (United States).

May 1998. [200p.] Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE

Contract AC07-94ID13223. Order Number DE98056082.

Source: OSTI; NTIS; INIS; GPO Dep.

Since 1984, the coal-fired plant at the Idaho Nuclear

Technology and Engineering Center (INTEC, formerly Idaho

Chemical Processing Plant) has been generating fly ash at

a rate of approximately 1,000 tons per year. This ash is hydrated and placed in an ash bury pit near the coal-fired

plant. The existing ash bury pit will be full in less than 1 year

at its present rate of use. A conceptual design to build a

new ash bury pit was completed, and the new pit is

estimated to cost $1.7 million. This report evaluates ash reutilization alternatives that propose to eliminate this waste

stream and save the $1.7 million required to build a new pit.

The alternatives include using ash for landfill day cover,

concrete admixture, flowable fill, soil stabilization, waste remediation, and carbon recovery technology. Both physical

and chemical testing, under the guidance of the American

Society for Testing and Materials, have been performed on

ash from the existing pit and from different steps within the

facility’s processes. The test results have been evaluated,

compared to commercial ash, and are discussed as they relate to reutilization alternatives. This study recommends that

the ash be used in flowable fill concrete for Deactivation and

Demolition work at the Idaho National Engineering and Environmental Laboratory.

376

(INEEL/EXT–98-00666)

Parameter selection for Department of Energy spent nuclear fuel to be used in the Yucca Mountain Viability

Assessment. Fillmore, D.L. Lockheed Martin Idaho Technologies Co., Idaho National Engineering and Environmental

Lab., Idaho Falls, ID (United States). Jun 1998. 31p. Sponsored by USDOE Office of Environmental Management,

Washington, DC (United States). DOE Contract AC07-

94ID13223. Order Number DE98057353. Source: OSTI;

NTIS; INIS; GPO Dep.

This report contains the chemical, physical, and radiological parameters that were chosen to represent the

Department of Energy spent nuclear fuel in the Yucca

Mountain Viability Assessment. It also contains the selected

packaging requirements for the various fuel types and the

criticality controls that were used. The data is reported for

representative fuels in groups of fuels that were selected for

the analysis. The justification for the selection of each parameter is given. The data reported was not generated

under any Q.A. Program.

377

(INEEL/EXT–98-00702)

Preliminary design report for SCDAP/RELAP5 lower

core plate model. Coryell, E.W. (Lockheed Martin Idaho

Technologies Co., Idaho Falls, ID (United States). Idaho National Engineering and Environmental Lab.); Griffin, F.P.

Lockheed Martin Idaho Technologies Co., Idaho National

Engineering and Environmental Lab., Idaho Falls, ID (United

States). Jul 1998. 47p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States).

DOE Contract AC07-94ID13223. Order Number

DE98058446. Source: OSTI; NTIS; INIS; GPO Dep.

The SCDAP/RELAP5 computer code is a best-estimate

analysis tool for performing nuclear reactor severe accident

simulations. Under primary sponsorship of the US Nuclear

Regulatory Commission (NRC), Idaho National Engineering

and Environmental Laboratory (INEEL) is responsible for

overall maintenance of this code and for improvements for

pressurized water reactor (PWR) applications. Since 1991,

Oak Ridge National Laboratory (ORNL) has been improving

SCDAP/RELAP5 for boiling water reactor (BWR) applications. The RELAP5 portion of the code performs the

thermal-hydraulic calculations for both normal and severe

accident conditions. The structures within the reactor vessel

and coolant system can be represented with either RELAP5

heat structures or SCDAP/RELAP5 severe accident structures. The RELAP5 heat structures are limited to normal

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

operating conditions (i.e., no structural oxidation, melting, or

relocation), while the SCDAP portion of the code is capable

of representing structural degradation and core damage progression that can occur under severe accident conditions.

DCDAP/RELAP5 currently assumes that molten material

which leaves the core region falls into the lower vessel head

without interaction with structural materials. The objective of

this design report is to describe the modifications required

for SCDAP/RELAP5 to treat the thermal response of the

structures in the core plate region as molten material relocates downward from the core, through the core plate

region, and into the lower plenum. This has been a joint task

between INEEL and ORNL, with INEEL focusing on PWRspecific design, and ORNL focusing upon the BWR-specific

aspects. Chapter 2 describes the structures in the core plate

region that must be represented by the proposed model.

Chapter 3 presents the available information about the damage progression that is anticipated to occur in the core plate

region during a severe accident, including typical SCDAP/

RELAP5 simulation results. (Abstract truncated)

378

(INEEL/EXT–98-00780)

An evaluation of the cost/benefits of concrete biodecontamination. Gorschboth, F.F.; Hamilton, M.A. Lockheed

Martin Idaho Technologies Co., Idaho National Engineering

and Environmental Lab., Idaho Falls, ID (United States).

Aug 1998. 42p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE

Contract AC07-94ID13223. Order Number DE98058435.

Source: OSTI; NTIS; INIS; GPO Dep.

Two candidate technologies for decontamination of extensive areas of radioactively contaminated concrete, a

biological technology and electro-hydraulic scabbling, that

had been rated as highly useful in an earlier study were assessed more precisely. These technologies were compared

to a base technology, scarification. The evaluation method

was an adaptation of the Multi-Attribute Utility Technique

(MAUT), a formal quantitative approach for analyzing decisions with regard to multiple objectives. The advantages of

the biodecontamination technology were confirmed by this

more precise quantitative analysis.

379

(INEL–96/00279)

Where has the public gone and will communications

technology bring them back?. Hutterman, L.; Smith, R.

Idaho National Engineering Lab., Idaho Falls, ID (United

States). 1997. 8p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE

Contract AC07-94ID13223. (CONF-970335–54: Waste Management ‘97, Tucson, AZ (United States), 2-7 Mar 1997).

Order Number DE97052129. Source: OSTI; NTIS; INIS;

GPO Dep.

This paper addresses the decreasing number of persons

interested and participating in the Comprehensive Environmental Response, Compensation, and Liability Act

(CERCLA) or “Superfund” process. It also looks at communications technology to bring people back into participation in

the Superfund process. The material studied and the technologies evaluated involve the Environmental Restoration

Program at the Idaho National Engineering and Environmental Laboratory. The conclusions are probably valid for

most DOE Superfund activities. Where has the public gone?

The public has taken an interest in issues that they perceive

have greater impact on their quality of life and that have an

adverse impact on the environment, such as the shipment

and storage of spent nuclear fuel. Will communications technology bring them back? Technology can do many things: it

can reduce cost; it can allow quicker access to and from the

public; it can offer more information; and it can increase interest because of its novelty for short periods of time, but it

will not, in and of its own, create public involvement.

380

(INEL–96/0280-Rev.2)

Acceptable knowledge document for INEEL stored

transuranic waste – Rocky Flats Plant waste. Revision

2. WASTREN, Inc., Westminster, CO (United States). 23

Jan 1998. [300p.] Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE

Contract AC07-94ID13223. Order Number DE98058388.

Source: OSTI; NTIS; INIS; GPO Dep.

This document and supporting documentation provide a

consistent, defensible, and auditable record of acceptable

knowledge for waste generated at the Rocky Flats Plant

which is currently in the accessible storage inventory at the

Idaho National Engineering and Environmental Laboratory.

The inventory consists of transuranic (TRU) waste generated from 1972 through 1989. Regulations authorize waste

generators and treatment, storage, and disposal facilities to

use acceptable knowledge in appropriate circumstances to

make hazardous waste determinations. Acceptable knowledge includes information relating to plant history, process

operations, and waste management, in addition to wastespecific data generated prior to the effective date of the

RCRA regulations. This document is organized to provide

the reader a comprehensive presentation of the TRU waste

inventory ranging from descriptions of the historical plant operations that generated and managed the waste to specific

information about the composition of each waste group.

Section 2 lists the requirements that dictate and direct TRU

waste characterization and authorize the use of the acceptable knowledge approach. In addition to defining the TRU

waste inventory, Section 3 summarizes the historical operations, waste management, characterization, and certification

activities associated with the inventory. Sections 5.0 through

26.0 describe the waste groups in the inventory including

waste generation, waste packaging, and waste characterization. This document includes an expanded discussion for

each waste group of potential radionuclide contaminants, in

addition to other physical properties and interferences that

could potentially impact radioassay systems.

381

(INEL–96/00343)

Results from five years of treatability studies using hydraulic binders to stabilize low-level mixed waste at the

INEL. Gering, K.L.; Schwendiman, G.L. Idaho National Engineering Lab., Idaho Falls, ID (United States). 1997. 19p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC07-94ID13223. (CONF-970335–48: Waste Management

‘97, Tucson, AZ (United States), 2-7 Mar 1997). Order Number DE97052976. Source: OSTI; NTIS; INIS; GPO Dep.

This paper summarizes work involving bench-scale solidification of nonincinerable, land disposal restricted low-level

mixed waste. Waste forms included liquids, sludges, and

solids; treatment techniques included hydraulic systems

(Portland cement with and without additives), proprietary

94
Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

commercial formulations, and sulphur polymer cement. Solidification was performed to immobilize hazardous heavy

metals (including mercury, lead, chromium, and cadmium),

and volatile and semivolatile organic compounds. Pretreatment options for mixed wastes are discussed, using a

decision tree based on the form of mixed waste and the

type of hazardous constituents. Hundreds of small concrete

monoliths were formed for a variety of waste types. The experimental parameters used for the hydraulic concrete

systems include the ratio of waste to dry binder (Portland

cement, proprietary materials, etc.), the total percentage of

water in concrete, and the amount of concrete additives. The

only parameter that was used for the sulfur polymer-based

monoliths is ratio of waste to binder. Optimum concrete formulations or “recipes” for a given type of waste were derived

through this study, as based on results from the Toxicity

Characteristic Leaching Procedure analyses and a free liquids test. Overall results indicate that high waste loadings in

the concrete can be achieved while the monolithic mass

maintains excellent resistance to leaching of heavy metals.

In our study the waste loadings in the concrete generally fell

within the range of 0.5 to 2.0 kg mixed waste per kg dry

binder. Likewise, the most favorable amount of water in

concrete, which is highly dependent upon the concrete constituents, was determined to be generally within the range of

300 to 330 g/kg (30-33% by weight). The results of this

bench-scale study will find applicability at facilities where

mixed or hazardous waste solidification is a planned or ongoing activity. 19 refs., 1 fig., 5 tabs.

382

(INEL–96/00351)

Gamma-ray pulse height spectrum analysis on systems

with multiple Ge detectors using a spectrum summing.

Killian, E.W. Idaho National Engineering Lab., Idaho Falls,

ID (United States). 1997. 8p. Sponsored by USDOE Office

of Environmental Management, Washington, DC (United

States). DOE Contract AC07-94ID13223. (CONF-970126–

15: 5. nondestructive assay/nondestructive examination

waste characterization conference, Salt Lake City, UT

(United States), 14-16 Jan 1997). Order Number

DE97052138. Source: OSTI; NTIS; INIS; GPO Dep.

A technique has been developed at the Idaho National

Engineering Laboratory to sum high resolution gamma-ray

pulse spectra from systems with multiple Ge detectors.

Lockheed Martin Idaho Technologies Company operates a

multi-detector spectrometer configuration at the Stored

Waste Examination Pilot Plant facility which is used to characterize the radio nuclide contents in waste drums destined

for shipment to Waste Isolation Pilot Plant. This summing

technique was developed to increase the sensitivity of the

system, reduce the count times required to properly quantify

the radionuclides and provide a more consistent methodology for combining data collected from multiple detectors. In

spectrometer systems with multiple detectors looking at non

homogenous waste forms it is often difficult to combine individual spectrum analysis results from each detector to

obtain a meaningful result for the total waste container. This

is particularly true when the counting statistics in each individual spectrum are poor. The spectrum summing technique

adds the spectra collected by each detector into a single

spectrum which has better counting statistics than each individual spectrum. A normal spectral analysis program can

then be used to analyze the sum spectrum to obtain radio

nuclide values which have smaller errors and do not have to

be further manipulated to obtain results for the total waste

container.

383

(INEL–96/00357)

Passive active neutron radioassay measurement uncertainty for combustible and glass waste matrices.

Blackwood, L.G.; Harker, Y.D.; Meachum, T.R.; Yoon, Woo

Y. Lockheed Martin Idaho Technologies Co., Idaho Falls, ID

(United States). [1997]. 31p. Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract AC07-94ID13223. (CONF-970126–4:

5. nondestructive assay/nondestructive examination waste

characterization conference, Salt Lake City, UT (United

States), 14-16 Jan 1997). Order Number DE97051090.

Source: OSTI; NTIS; INIS; GPO Dep.

Using a modified statistical sampling and verification approach, total uncertainty of INEL’s Passive Active Neutron

(PAN) radioassay system was evaluated for combustible

and glass content codes. Waste structure and content of

100 randomly selected drums in each the waste categories

were computer modeled based on review of real-time radiography video tapes. Specific quantities of Pu were added to

the drum models according to an experimental design.

These drum models were then submitted to the Monte Carlo

Neutron Photon code processing and subsequent calculations to produce simulated PAN system measurements. The

reported Pu masses from the simulation runs were compared with the corresponding input masses. Analysis of the

measurement errors produced uncertainty estimates. This

paper presents results of the uncertainty calculations and

compares them to previous reported results obtained for

graphite waste.

384

(INEL–96/00358)

Sampling and verification methods for the uncertainty

analysis of NDA and NDE waste characterization systems. Blackwood, L.G. Lockheed Martin Idaho Technologies

Co., Idaho Falls, ID (United States). [1997]. 20p. Sponsored

by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract AC07-94ID13223.

(CONF-970126–3: 5. nondestructive assay/nondestructive

examination waste characterization conference, Salt Lake

City, UT (United States), 14-16 Jan 1997). Order Number

DE97051091. Source: OSTI; NTIS; INIS; GPO Dep.

Use of nondestructive assay (NDA) and evaluation (NDE)

systems in critical waste characterization requires a realistic

assessment of the uncertainty in the measurements. The

stated uncertainty must include potential effects of a variety

of complicating external factors on the expected bias and

precision. These factors include material heterogeneity (matrix effects), fluctuating background levels, and other

variable operating conditions. Uncertainty figures from application of error propagation methods to data from controlled

laboratory experiments using standard test materials can

grossly underestimate the expected error. This paper reviews the standard error propagation method of uncertainty

analysis, discusses some of its limitations, and presents an

alternative approach based on sampling and verification. Examples of application of sampling and verification methods

to measurement systems at INEL are described.

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

385

(INEL–96/00366)

SWEPP assay system software: An update. East, L.V.

Lockheed Martin Idaho Technologies Co., Idaho Falls, ID

(United States). [1997]. 12p. Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract AC07-94ID13223. (CONF-970126–5:

5. nondestructive assay/nondestructive examination waste

characterization conference, Salt Lake City, UT (United

States), 14-16 Jan 1997). Order Number DE97051089.

Source: OSTI; NTIS; INIS; GPO Dep.

The development of a new software package to control

data acquisition and perform data analysis for a Passive/

Active Neutron Assay system was reported at this conference in 1994. The software has undergone additional

development including improvements to the user interface,

additional data integrity checks and support for a shift register coincidence analyzer. An overview of this additional work

is presented in this report.

386

(INEL/CON–97-00008)

The development of a new edition of the gamma-ray

spectrum catalogues designed for presentation in electronic format. Heath, R.L. Idaho National Engineering Lab.,

Idaho Falls, ID (United States). 1997. 10p. Sponsored by

USDOE Office of Energy Research, Washington, DC

(United States). DOE Contract AC07-94ID13223. (CONF970126–14: 5. nondestructive assay/nondestructive

examination waste characterization conference, Salt Lake

City, UT (United States), 14-16 Jan 1997). Order Number

DE97052141. Source: OSTI; NTIS; INIS; GPO Dep.

New editions of the original Gamma-ray Spectrum Catalogues are being prepared for publication in electronic

format. The objective of this program is to produce versions

of the Catalogues in CD-ROM format and as an Internet resource. Additions to the original content of the Catalogues

will include integrated decay scheme drawings, tables of related decay data, and updated text on the techniques of

gamma-ray spectrometry. Related decay data from the Evaluated Nuclear Structure Data File (ENSDF) are then added,

and all data converted to the Adobe Acrobat (PDF) format

for CD-ROM production and availability on the Internet. At a

later date the catalogues will be expanded to include spectra representing the response of large-volume Ge detectors,

alpha-particle spectra, prompt neutron capture and inelastic

scattering gamma-ray spectra, and gross fission product

spectra characteristic of fuel cycle waste materials. Characterization of radioactivity in materials is a requirement in

many phases of radioactive waste management. Movement,

shipping, treatment, all activities which involve handling of

mixed waste or TRU categories of waste at all DOE sites

will require that measurements and assessment documentation utilize basic nuclear data which are tracable to

internationally accepted standard values. This program will

involve the identification of data needs unique to the development and application of specialized detector systems for

radioactive waste characterization.

387

(INEL/CON–97-00085)

Field screening of soils contaminated with explosives

using ion mobility spectrometry. Atkinson, D.A. (Lockheed Idaho Technologies Co., Idaho Falls, ID (United

States)); Crockett, A.B.; Jenkins, T.F. Lockheed Idaho Technologies Co., Idaho Falls, ID (United States). [1997]. 9p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC07-94ID13223. (CONF-970113–5: Field analytical methods for hazardous wastes and toxic chemicals conference,

Las Vegas, NV (United States), 29-31 Jan 1997). Order

Number DE97052137. Source: OSTI; NTIS; GPO Dep.

This study involved the comparison of IMS screening with

EPA’s standard method for explosives, Method 8330. The

US Army Corps of Engineers provided a large number of

soil samples that had been collected from three locations at

each of three explosive contaminated installations. The

samples had been dried, ground, homogenized and analyzed in duplicate by Method 8330. Duplicate two gram

aliquots of these samples were extracted with 10 mL of acetone by shaking for three minutes, allowed to settle, then

analyzed by IMS for Method 8330 compounds. Half of the

extracts from one location have also been analyzed in duplicate by IMS for TNT. Results from TNT contaminated soils

look extremely promising. Correlation between IMS and EPA

Method 8330 results was very high (r = 0.99). Based on

these results, the intention is to further develop and evaluate

IMS for simultaneously quantifying multiple analytes. IMS

throughput and cost per sample makes it an attractive

technique. The ultimate objective is to provide adequate validation data to EPA for inclusion of the method as a

screening procedure in SW-846.

388

(INEL/CON–97-00102)

Public participation in a DOE national program: The

mixed waste focus area’s approach. Idaho National Engineering Lab., Idaho Falls, ID (United States). 1997. 11p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC07-94ID13223. (CONF-970335–49: Waste Management

‘97, Tucson, AZ (United States), 2-7 Mar 1997). Order Number DE97052936. Source: OSTI; NTIS; INIS; GPO Dep.

The authors describe the Mixed Waste Focus Area’s approach to involving interested Tribal and public members in

the mixed waste technology development process. Evidence

is provided to support the thesis that the Focus Area’s systems engineering process, which provides visible and

documented requirements and decision criteria, facilitates

effective Tribal and public participation. Also described is a

status of Tribal and public involvement at three levels of Focus Area activities.

389

(INEL/CON–97-00103)

The proposed combustion standards and DOE thermal

treatment systems. McFee, J. (IT Corp. (United States));

Hinman, M.B.; Eaton, D.; NcNeel, K. Lockheed Idaho Technologies Co., Idaho Falls, ID (United States). [1997]. 9p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC07-94ID13223. (CONF-970335–: Waste Management

‘97, Tucson, AZ (United States), 2-7 Mar 1997). Order Number DE97053003. Source: OSTI; NTIS; INIS; GPO Dep.

Under the provisions of the Clean Air Act (CAA) concerning emission of hazardous air pollutants (HAPs), the

Environmental Protection Agency (EPA) published the proposed Revised Standards for Hazardous Waste Combustors

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

on April 19, 1996 (EPA, 1996). These standards would apply to the existing Department of Energy (DOE) radioactive

and mixed waste incinerators, and may be applied to several developing alternatives to incineration. The DOE has

reviewed the basis for these regulations and prepared extensive comments to present concerns about the bases and

implications of the standards. DOE is now discussing compliance options with the EPA for regulation of radioactive

and mixed waste thermal treatment systems.

390

(INEL/CON–97-00104)

The Mixed Waste Focus Area: Status and accomplishments. Conner, J.E. (Dept. of Energy, Idaho Falls, ID

(United States). Idaho Operations Office); Williams, R.E.

Lockheed Idaho Technologies Co., Idaho Falls, ID (United

States). [1997]. 7p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE

Contract AC07-94ID13223. (CONF-970335–: Waste Management ‘97, Tucson, AZ (United States), 2-7 Mar 1997).

Order Number DE97053004. Source: OSTI; NTIS; INIS;

GPO Dep.

The Mixed Waste Focus Area began operations in

February of 1995. Its mission is to provide acceptable technologies that enable implementation of mixed waste

treatment systems developed in partnership with end-users,

stakeholders, tribal governments, and regulators. The

MWFA will develop, demonstrate, and deliver implementable

technologies for treatment of mixed waste within the DOE

complex. Treatment refers to all post waste-generation activities including sampling and analysis, characterization,

storage, processing, packaging, transportation, and disposal. The MWFA’s mission arises from the Resources

Conservation and Recovery Act (RCRA) as amended by the

Federal Facility Compliance Act. Each DOE site facility that

generates or stores mixed waste prepared a plan, the Site

Treatment Plan, for developing treatment capacities and

treating that waste. Agreements for each site were concluded with state regulators, resulting in Consent Orders

providing enforceable milestones for achieving treatment of

the waste. The paper discusses the implementation of the

program, its status, accomplishments and goals for FY1996,

and plans for 1997.

391

(INEL/CON–97-00182)

Construction safety: Can management prevent all accidents or are workers responsible for their own actions?.

Cotten, G.B.; Jenkins, S.L. Parsons Infrastructure and Technology Group, Inc., Idaho Falls, ID (United States). 1997.

5p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC07-94ID13223. (CONF-970952–: Decontamination,

decommissioning and reutilization of commercial and government facilities, Knoxville, TN (United States), 7-12 Sep

1997). Order Number DE98050308. Source: OSTI; NTIS;

INIS; GPO Dep.

The construction industry has struggled for many years

with the answer to the question posed in the title: Can Management Prevent All Accidents or Are Workers Responsible

for Their Own Actions? In the litigious society that we live, it

has become more important to find someone “at fault” for an

accident than it is to find out how we can prevent it from

ever happening again. Most successful companies subscribe to the theme that “all accidents can be prevented.”

They institute training and qualification programs, safe performance incentives, and culture-change-driven directorates

such as the Voluntary Protection Program (VPP); yet we still

see construction accidents that result in lost time, and occasionally death, which is extremely costly in the shortsighted

measure of money and, in real terms, impact to the worker’s

family. Workers need to be properly trained in safety and

health protection before they are assigned to a job that may

expose them to safety and health hazards. A management

committed to improving worker safety and health will bring

about significant results in terms of financial savings,

improved employee morale, enhanced communities, and increased production. But how can this happen, you say?

Reduction in injury and lost workdays are the rewards. A decline in reduction of injuries and lost workdays results in

lower workers’ compensation premiums and insurance

rates. In 1991, United States workplace injuries and

illnesses cost public and private sector employers an estimated $62 billion in workers’ compensation expenditures.

392

(INEL/CON–97-00184)

Design and operation of the Rover vacuum system.

Wagner, E.P. Jr. (LMITCO, Idaho Falls, ID (United States));

Griffith, D.L.; Rivera, J.M. Idaho National Engineering Lab.,

Idaho Falls, ID (United States). 1997. 9p. Sponsored by USDOE Office of Environmental Management, Washington, DC

(United States). DOE Contract AC07-94ID13223. (CONF970952–: Decontamination, decommissioning and

reutilization of commercial and government facilities,

Knoxville, TN (United States), 7-12 Sep 1997). Order Number DE97053245. Source: OSTI; NTIS; INIS; GPO Dep.

The Rover process for recovering unused uranium from

graphite fuels was operated during 1983 and 1984, and then

shut down in 1984. The first steps of the process used fluidized alumina beds to burn away the graphite and produce

a uranium bearing ash. The ash was then transferred to a

different process cell for acid dissolution. At the time of shutdown, a significant, but unmeasureable, quantity of highly

enriched uranium was left in the process vessels. Normal

decontamination procedures could not be used due to

plugged process lines and the exclusion of moderator materials (water or finely divided organic substances) for

criticality safety. The presence of highly enriched uranium in

poorly defined quantity and configuration led to concerns for

criticality safety, nuclear materials accountability, and physical security. A project was established to eliminate these

concerns by cleaning and/or removing the process vessels,

piping, and cells and sending the recovered Uranium Bearing Material (UBM) to secure storage. A key element of this

project was the design of a system for collecting and transporting dry solids to a location where they could be loaded

into critically favorable storage cans.

393

(INEL/CON–97-00185)

A graded approach to safety analysis for Rover Processing Facility deactivation. Henrikson, D.J. Idaho

National Engineering Lab., Idaho Falls, ID (United States).

1997. 4p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract AC07-94ID13223. (CONF-970952–: Decontamination,

decommissioning and reutilization of commercial and government facilities, Knoxville, TN (United States), 7-12 Sep

97
ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

1997). Order Number DE97053242. Source: OSTI; NTIS;

INIS; GPO Dep.

The Rover Fuels Processing Facility operated in the early

1980’s, recovering uranium from graphite fuels. In 1996

clean-out began of uranium bearing material remaining in

the Rover cells where combustion processes had occurred.

Success of the Rover Deactivation Project depends on the

safe, timely, and cost-effective repackaging and removal of

the uranium bearing material. Due to a number of issues

which could not be resolved prior to clean-out, and consideration of cost and schedule objectives, a graded approach

was taken to projected design and criticality safety analysis.

The safety authorization basis was upgraded primarily by a

specific Deactivation addendum, instead of being completely

rewritten to current format and content standards. In place of

having all design activities completed prior to the start of the

Deactivation, the project design and accompanying safety

documentation evolved as the project progressed. The Unreviewed Safety Question determination process was used

to ensure that new project activities were within the safety

envelope. This graded approach allowed operational flexibility while maintaining a critically safe work environment.

394

(INEL/CON–97-00260)

High resolution gamma spectroscopy well logging system. Giles, J.R.; Dooley, K.J. Idaho National Engineering

Lab., Idaho Falls, ID (United States). 1997. 17p. Sponsored

by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract AC07-94ID13223.

(CONF-970424–8: 4. international conference on methods

and applications of radioanalytical chemistry, Kona, HI

(United States), 6-11 Apr 1997). Order Number

DE97052973. Source: OSTI; NTIS; INIS; GPO Dep.

A Gamma Spectroscopy Logging System (GSLS) has

been developed to study sub-surface radionuclide contamination. The absolute counting efficiencies of the GSLS

detectors were determined using cylindrical reference

sources. More complex borehole geometries were modeled

using commercially available shielding software and correction factors were developed based on relative gamma-ray

fluence rates. Examination of varying porosity and moisture

content showed that as porosity increases, and as the

formation saturation ratio decreases, relative gamma-ray fluence rates increase linearly for all energies. Correction

factors for iron and water cylindrical shields were found to

agree well with correction factors determined during previous studies allowing for the development of correction

factors for type-304 stainless steel and low-carbon steel

casings. Regression analyses of correction factor data

produced equations for determining correction factors applicable to spectral gamma-ray well logs acquired under

non-standard borehole conditions.

395

(INEL/CON–97-00292)

Gravity gradiometry difference measurement as a tool

for monitoring pumping and injection; forward modeling

results. Creed, R. (Department of Energy, Idaho Falls, ID

(United States)); Edwards, A. Idaho National Engineering

Lab., Idaho Falls, ID (United States). 1997. 14p. Sponsored

by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract AC07-94ID13223.

(CONF-9703120–: 32. annual symposium on engineering

geology and geotechnical engineering, Boise, ID (United

States), 26-28 Mar 1997). Order Number DE97053250.

Source: OSTI; NTIS; INIS; GPO Dep.

Gravity gradiometry forward models have been developed

at the Idaho National Engineering and Environmental laboratory (INEEL) that can characterize gravity gradient changes

with the development of a cone of depression or injection

mound in water table aquifers. Difference measurements at

long time intervals reduce delayed drainage effects and

eliminate the need for determining an initial density structure. Qualitative or semi-quantitative analysis of the gradient

signal to determine changes in groundwater distribution with

injection or pumping may be possible, particularly if the time

varying nature of the signal is of interest. Gravity gradiometer instruments (such as the Gravity Gradient Survey

System) have progressed to the point where the complete

second order gravity gradient tensor can be measured with

an instrument noise level of less than 1 Eotvos (0.1 microgals/meter). Modeling indicates direct gravity measurements

for the injection mound perched aquifier case could produce

similar signal to noise ratios. However gravity gradients provide 5 independent measurements and due to the common

mode nature of the instruments are less susceptible to other

effects (tide, latitude, elevation, etc.). The gradients also

provide a sharper image of the edge of the anomaly. The

systematic identification and removal of specific retention,

rainfall and subsidence or uplift effects may be required to

make gradiometry difference imaging practical for field use.

396

(INEL/CON–97-00331)

Clean-up criteria for remediation of contaminated soils.

Nguyen, H.D. (Lockheed Martin Idaho Technologies Co.,

Idaho Falls, ID (United States). Idaho National Engineering

and Environmental Lab.); Wilson, J.R.; Sato, Chikashi.

Idaho National Engineering Lab., Idaho Falls, ID (United

States). 1997. 14p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE

Contract AC07-94ID13223. (CONF-9704167–: 1997 conference on hazardous wastes and materials, Pocatello, ID

(United States), 8-9 Apr 1997). Order Number DE97053006.

Source: OSTI; NTIS; INIS; GPO Dep.

“How clean is clean?” is a question commonly raised in

the remediation of contaminated soils. To help with the

answer, criteria are proposed to serve as guidelines for remedial actions and to define a clean-up level such that the

remaining contaminant residuals in the soil will not violate

the Drinking Water Standards (DWS). The equations for

computing those criteria are developed from the principle of

conservation of mass and are functions of the maximum

concentration level in the water (MCL) and the sorption coefficient. A multiplier, ranging from 10 to 1000, is also factored

into the soil standard equation to reflect the effectiveness of

various remediation techniques. Maximum allowable concentration in the soil (MSCL) is presented for several

contaminants which are being regulated at the present time.

Future modifications are recommended for better estimates

of the MSCLs as additional transport mechanisms are incorporated to account for other potentially dominant effects.

397

(INEL/CON–97-00334)

Optimization of hydraulic cement admixture waste

forms for sodium-bearing, high aluminum, and high zirconium wastes. Herbst, A.K. Idaho National Engineering

Lab., Idaho Falls, ID (United States). 1997. 9p. Sponsored

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract AC07-94ID13223.

(CONF-970537–: 18. annual DOE low-level radioactive

waste management conference, Salt Lake City, UT (United

States), 20-22 May 1997). Order Number DE97053243.

Source: OSTI; NTIS; INIS; GPO Dep.

A three-way blend of portland cement, blast furnace slag,

and fly ash was successfully tested on simulated acidic high

sodium, aluminum, and zirconium low-level wastes (LLW).

Grout cubes were prepared at various waste loadings to

maximize loading while meeting compressive strength and

leach resistance requirements. For sodium LLW, a 21%

waste loading achieves a volume reduction of 3.3 and a

compressive strength of 2750 pounds per square inch while

meeting leach, mix, and flow requirements. It was found that

the sulfur in the slag reduces the chromium leach rate below

regulatory limits. For aluminum LLW, a 10% waste loading

achieves a volume reduction of 8.5 and a compressive

strength of 4.50 pounds per square inch while meeting leach

requirements. Likewise for zirconium LLW, a 21% waste

loading achieves a volume reduction of 8.3 and a compressive strength of 3570 pounds per square inch.

398

(INEL/CON–97-00455)

The VirtualwindoW for nuclear applications. Anderson,

M.O.; McKay, M.D.; Willis, W.D. Idaho National Engineering

Lab., Idaho Falls, ID (United States). 1997. 8p. Sponsored

by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract AC07-94ID13223.

(CONF-970464–: 7. American Nuclear Society topical meeting on robotics and remote systems, Augusta, GA (United

States), 27 Apr - 1 May 1997). Order Number DE97053248.

Source: OSTI; NTIS; INIS; GPO Dep.

Throughout the Department of Energy (DOE) complex

there are numerous facilities which were constructed to research and develop nuclear materials during the cold war

era. As a result, there are now many facilities such as

reactors which require dismantlement and clean up. Technological advances over the past 10 years have significantly

increased the state of computers, electronics and automated

machinery. Because of this rapid growth, the technology of

robotics has played a key role in clean up and remote operations. While robotic systems which perform hazardous

tasks are being advanced, the human interface has not.

Only within the past few years has the human/machine interface been addressed. A growing concern with the rapid

advances in technology is that the robotic systems will become so complex that operators will be overwhelmed by the

complexity and number of controls. Thus there is an on going effort within the remote and teleoperated robotic field to

develop better man-machine interfaces. The Department of

Energy’s Idaho National Engineering Laboratory (INEL) has

been researching methods to simplify this interface including

telepresence techniques which are applicable to nuclear environments. Initial telepresence research conducted at the

INEL developed a concept called the VirtualwindoW. This

system minimizes the complexity of remote stereo viewing

controls and provides the operator the ‘feel’ of viewing the

environment in a natural setting. The VirtualwindoW has

shown that the man-machine interface can be simplified

while increasing operator performance. This paper deals

with the continuing research and development of the VirtualwindoW system to provide a standard camera interface. An

application of the VirtualwindoW in the dismantlement of the

Chicago Pile-Five (CP-5) reactor at Argonne National

Laboratory-East is discussed.

399

(INEL/CON–97-00507)

Thermal denitration and mineralization of waste constituents. Nenni, J.A.; Boardman, R.D. Idaho National

Engineering Lab., Idaho Falls, ID (United States). 1997.

14p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC07-94ID13223. (CONF-970537–: 18. annual DOE lowlevel radioactive waste management conference, Salt Lake

City, UT (United States), 20-22 May 1997). Order Number

DE97053244. Source: OSTI; NTIS; INIS; GPO Dep.

In order to produce a quality grout from LLW using

hydraulic cements, proper conditioning of the waste is essential for complete cement curing. Several technologies

were investigated as options for conditions. Since the LLW

is dilute, removal of all, or most, of the water will significantly

reduce the final waste volume. Neutralization of the LLW is

also desirable since acidic liquids to not allow cement to

cure properly. The nitrate compounds are very soluble and

easily leached from solid waste forms; therefore, denitration

is desirable. Thermal and chemical denitration technologies

have the advantages of water removal, neutralization, and

denitration. The inclusion of additives during thermal treatment were investigated as a method of forming insoluable

waste conditions.

400

(INEL/CON–97-00533)

Systems engineering identification and control of mixed

waste technology development. Beitel, G.A. Lockheed

Idaho Technologies Co., Idaho Falls, ID (United States).

[1997]. 19p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract AC07-94ID13223. (CONF-970857–: 4. biennial ASME

mixed waste symposium, Baltimore, MD (United States), 17-

21 Aug 1997). Order Number DE97053252. Source: OSTI;

NTIS; INIS; GPO Dep.

The Department of Energy (DOE) established the Mixed

Waste Characterization, Treatment, and Disposal Focus

Area (MWFA) to develop technologies required to meet the

Department’s commitments for treatment of mixed low-level

and transuranic wastes. Waste treatment includes all necessary steps from generation through disposal. Systems

engineering was employed to reduce programmatic risk, that

is, risk of failure to meet technical commitments within cost

and schedule. Customer needs (technology deficiencies) are

identified from Site Treatment Plans, Consent Orders, ten

year plans, Site Technical Coordinating Groups, Stakeholders, and Site Visits. The Technical Baseline, a prioritized list

of technology deficiencies, forms the basis for determining

which technology development activities will be supported

by the MWFA. Technology Development Requirements Documents are prepared for each technology selected for

development. After technologies have been successfully developed and demonstrated, they are documented in a

Technology Performance Report. The Technology Performance Reports are available to any of the customers or

potential users of the technology, thus closing the loop between problem identification and product development. This

systematic approach to technology development and its effectiveness after 3 years is discussed in this paper.

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

401

(INEL/CON–97-00644)

To retrieve or not to retrieve: These are the issues.

Hyde, R.A.; Dahlmeir, M.M.; Nickelson, D.F.; Swanson, S.P.

Lockheed Martin Idaho Technologies Co., Idaho National

Engineering and Environmental Lab., Idaho Falls, ID (United

States). Oct 1997. 20p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States).

DOE Contract AC07-94ID13223. (CONF-970857–: 4. biennial ASME mixed waste symposium, Baltimore, MD (United

States), 17-21 Aug 1997). Order Number DE98050469.

Source: OSTI; NTIS; INIS; GPO Dep.

There are many factors that must be evaluated when

determining whether a buried mixed waste site should be retrieved and subsequently stored, treated, and/or disposed of

or if some other action is more appropriate. The criteria developed for the evaluation of remedial actions at mixed

waste sites under Comprehensive Environmental Response,

Compensation, and Liability Act (CERCLA) regulation EPA,

provide an excellent methodology for deciding upon a

preferred action even if the site is not under CERCLA regulation. Each topic for evaluation in the criteria is not mutually

exclusive, and many tradeoffs must be reviewed. The criteria have been broken down into a number of categories:

overall protection of human health and the environment;

compliance with Applicable or Relevant and Appropriate

Requirements (ARARs); long-term effectiveness and permanence; reduction of toxicity, mobility, and volume; short-term

effectiveness; implementability; cost; state acceptance; and

community acceptance. Once the data is gathered, a Hazards Analysis must be performed to understand the risks of

the site to workers, the public, and the environment. The

Hazard Analysis is critical in helping personnel understand

the associated issues so that an effective evaluation can

take place. The intent of this paper is not to focus on a particular site, but to provide information that is useful for many

problem holders to better understand the issues associated

with buried mixed waste retrieval. Ultimately, these issues

affect the final decision of whether or not retrieval is a feasible alternative.

402

(INEL/CON–97-00705)

Actinide partitioning from actual Idaho chemical processing plant acidic tank waste using centrifugal

contactors. Law, J.D.; Brewer, K.N.; Todd, T.A. Idaho National Engineering Lab., Idaho Falls, ID (United States).

1997. 6p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract AC07-94ID13223. (CONF-971004–: GLOBAL ’97:

international conference on future nuclear systems, Yokohama (Japan), 5-10 Oct 1997). Order Number DE98050471.

Source: OSTI; NTIS; INIS; GPO Dep.

The TRUEX process is being evaluated at the Idaho

Chemical Processing Plant (ICPP) for the separation of the

actinides from acidic radioactive wastes stored at the ICPP.

These efforts have culminated in a recent demonstration of

the TRUEX process with actual tank waste. This demonstration was performed using 24 stages of 2-cm diameter

centrifugal contactors installed in a shielded hot cell at the

ICPP Remote Analytical Laboratory. An overall removal efficiency of 99.97% was obtained for the actinides. As a result,

the activity of the actinides was reduced from 457 nCi/g in

the feed to 0.12 nCi/g in the aqueous raffinate, which is well

below the U.S. NRC Class A LLW requirement of 10 nCi/g

for non-TRU waste. Iron was partially extracted by the

TRUEX solvent, resulting in 23% of the Fe exiting in the

strip product. Mercury was also extracted by the TRUEX

solvent (76%) and stripped from the solvent in the 0.25 M

Na2CO3 wash section.

403

(INEL/CON–97-00706)

Demonstration of the SREX process for the removal of

90Sr from actual highly radioactive solutions in centrifugal contactors. Law, J.D.; Wood, D.J.; Todd, T.A.; Olson,

L.G. Idaho National Engineering Lab., Idaho Falls, ID

(United States). 1997. 6p. Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract AC07-94ID13223. (CONF-971004–:

GLOBAL ’97: international conference on future nuclear

systems, Yokohama (Japan), 5-10 Oct 1997). Order Number

DE98050470. Source: OSTI; NTIS; INIS; GPO Dep.

The SREX process is being evaluated at the Idaho Chemical Processing Plant (ICPP) for the separation of 90Sr from

acidic radioactive wastes stored at the ICPP. These efforts

have culminated in a recent demonstration of the SREX process with actual tank waste. This demonstration was

performed using 24 stages of 2-cm diameter centrifugal contactors installed in a shielded hot cell at the ICPP Remote

Analytical Laboratory. An overall removal efficiency of

99.995% was obtained for 90Sr. As a result, the activity of 90Sr was reduced from 201 Ci/m3 in the feed solution of

0.0089 Ci/m3 in the aqueous raffinate, which is below the

U.S. NRC Class A LLW limit of 0.04 Ci/m3 for 90Sr. Lead

was extracted by the SREX solvent and successfully partitioned from the 90Sr using an ammonium citrate strip

solution. Additionally, 94% of the total alpha activity, 1.9% of

the 241Am, 99.94% of the 238Pu, 99.97% of the 239Pu, 36.4%

of the K, 64% of the Ba, and >83% of the Zr were extracted

by the SREX solvent. Cs, B, Cd, Ca, Cr, Fe, Mn, Ni, and Na

were essentially inextractable. 10 refs., 2 figs., 3 tabs.

404

(INEL/CON–97-00707)

Tribal and stakeholder involvement in systems analysis.

McClure, L. (Lockheed Martin Idaho Technologies Company, Idaho Falls, ID (United States)); Swartz, G.; Cooley,

C. Idaho National Engineering Lab., Idaho Falls, ID (United

States). 1997. 6p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE

Contract AC07-94ID13223. (CONF-971004–: GLOBAL ’97:

international conference on future nuclear systems, Yokohama (Japan), 5-10 Oct 1997). Order Number DE98050310.

Source: OSTI; NTIS; INIS; GPO Dep.

Beginning in early 1995, U.S. Department of Energy

began an experiment to link tribal and stakeholder representatives into technology assessment activities related to an

Integrated Nonthermal Treatment System (INTS) study. The

INTS study moved outside the framework of after-the-fact

public involvement by providing the opportunity for technical

and non-technical stakeholders alike to work together in the

early predecision stages of the criteria development and assessment of options for innovative mixed waste treatment.

The stakeholders gained an appreciation of the intense level

of effort required to complete such an analysis. The engineers and scientists conducting the systems analyses had

the opportunity (some for the first time) to learn more about

tribal and stakeholder issues and how they might apply to

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

the technical tasks related to technology assessment and

selection.

405

(INEL/CON–97-00711)

System for decision analysis support on complex waste

management issues. Shropshire, D.E. Idaho National Engineering Lab., Idaho Falls, ID (United States). 1997. 8p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC07-94ID13223. (CONF-971040–: ICEM ‘97: 6. international conference on radioactive waste management and

environmental remediation, Singapore (Singapore), 12-16

Oct 1997). Order Number DE98050311. Source: OSTI;

NTIS; INIS; GPO Dep.

A software system called the Waste Flow Analysis has

been developed and applied to complex environmental management processes for the United States Department of

Energy (US DOE). The system can evaluate proposed

methods of waste retrieval, treatment, storage, transportation, and disposal. Analysts can evaluate various scenarios

to see the impacts to waste slows and schedules, costs,

and health and safety risks. Decision analysis capabilities

have been integrated into the system to help identify preferred alternatives based on a specific objectives may be to

maximize the waste moved to final disposition during a

given time period, minimize health risks, minimize costs, or

combinations of objectives. The decision analysis capabilities can support evaluation of large and complex problems

rapidly, and under conditions of variable uncertainty. The

system is being used to evaluate environmental management strategies to safely disposition wastes in the next ten

years and reduce the environmental legacy resulting from

nuclear material production over the past forty years.

406

(INEL/CON–97-01062)

Integration of project management and systems

engineering: Tools for a total-cycle environmental management system. Blacker, P.B.; Winston, R. Lockheed

Idaho Technologies Co., Idaho Falls, ID (United States).

[1997]. 4p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE

Contract AC07-94ID13223. (CONF-9709185–: Project Management Institute ’97, Chicago, IL (United States), 29 Sep

1997). Order Number DE98050367. Source: OSTI; NTIS;

INIS; GPO Dep.

An expedited environmental management process has

been developed at the Idaho National Engineering and Environmental Laboratory (INEEL). This process is one result of

the Lockheed Martin commitment to the US Department of

Energy to incorporate proven systems engineering practices

with project management and program controls practices at

the INEEL. Lockheed Martin uses a graded approach of its

management, operations, and systems activities to tailor the

level of control to the needs of the individual projects. The

Lockheed Martin definition of systems engineering is: “Systems Engineering is a proven discipline that defines and

manages program requirements, controls risk, ensures program efficiency, supports informed decision making, and

verifies that products and services meet customer needs.”

This paper discusses: the need for an expedited environmental management process; how the system was

developed; what the system is; what the system does; and

an overview of key components of the process.

407

(IS–5128)

Performance testing of multi-metal continuous emissions monitors. Haas, W.J. (Ames Lab., IA (United

States)); French, N.B.; Brown, C.H.; Burns, D.B.; Lemieux,

P.M.; Ryan, J.V.; Priebe, S.J.; Waterland, L.R. Ames Lab.,

IA (United States). 17 Nov 1997. [70p.] Sponsored by USDOE Office of Environmental Management, Washington, DC

(United States);Environmental Protection Agency, Washington, DC (United States). DOE Contract W-7405-ENG-82.

Order Number DE98004610. Source: OSTI; NTIS; GPO

Dep.

Three prototype multi-metals continuous emissions monitors (CEMs) were tested in April 1996 at the Rotary Kiln

Incinerator Simulator facility at the US Environmental Protection Agency (EPA) National Risk Management Research

Laboratory, Research Triangle Park, North Carolina. The

CEM instruments were: Inductively Coupled Plasma-Atomic

Emission Spectrometry (ICP-AES); Laser Induced Breakdown Spectrometry-Atomic Emission Spectroscopy (LIBS);

and Laser Spark Spectrometry, another LIBS instrument.

The three CEMs were tested simultaneously during test periods in which low, medium, and high concentration levels of

seven toxic metals – antimony, arsenic, beryllium, cadmium,

chromium, lead, and mercury – were maintained under

carefully controlled conditions. Two methods were used to

introduce the test metals into the flue gas: (1) solution atomization, introducing metal-containing aerosol directly into the

secondary combustion burner, and (2) injection of fly ash

particulates. The testing addressed four measures of CEM

performance: relative accuracy (RA), calibration drift, zero

drift, and response time. These were accomplished by comparing the toxic metal analyte concentrations reported by

the CEMs to the concentrations measured using the EPA

reference method (RM) for the same analytes. Overall, the

test results showed the prototype nature of the test CEMs

and the clear need for further development. None of the

CEMs tested consistently achieved RA values of 20% or

less as required by the EPA draft performance specification.

Instrument size reduction and automation will also likely

need additional attention before multi-metal CEMs systems

become commercially available for service as envisioned by

regulators and citizens.

408

(IS–5128-App.-Vol.1)

Performance testing of multi-metal continuous emissions monitors. Appendix Volume 1. Haas, W.J. Jr.

(Ames Lab., IA (United States)); French, N.B.; Brown, C.H.;

Burns, D.B.; Lemieux, P.M.; Ryan, J.V.; Priebe, S.J. Ames

Lab., IA (United States). 17 Nov 1997. [100p.] Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States);Environmental Protection Agency, Washington, DC (United States). DOE Contract W-7405-ENG-82.

Order Number DE98004611. Source: OSTI; NTIS; GPO

Dep.

This report contains appendices to the study of three prototype multi-metal continuous emission monitors (CEMs).

The appendices are: Final report of the Diagnostic Instrumentation and Analytical Laboratory (DIAL) CEM developer

team; Final report of Navy/Thermo Jarrell Ash Corp. CEM

developer team; Final report of Sandia National Laboratories

CEM developer team; Developer team comments; and

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

Performance specification 10 – Specifications and test procedures for multi-metals continuous monitoring systems in

stationary sources.

409

(IS–5128-App.-Vol.2)

Performance testing of multi-metal continuous emissions monitors. Appendix Volume 2. Haas, W.J. Jr.

(Ames Lab., IA (United States)); French, N.B.; Brown, C.H.;

Burns, D.B.; Lemieux, P.M.; Ryan, J.V.; Priebe, S.J. Ames

Lab., IA (United States). 17 Nov 1997. [250p.] Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States);Environmental Protection Agency, Washington, DC (United States). DOE Contract W-7405-ENG-82.

Order Number DE98004612. Source: OSTI; NTIS; GPO

Dep.

This report contains appendices to the study of three prototype multi-metals continuous emission monitors (CEMs).

The appendices are: Diagnostic Instrumentation and Analytical Laboratory daily logbook pages and CEM data; Navy/

Thermo Jarrell Ash Corp. daily logbook pages and CEM

data; Sandia National Laboratories daily logbook pages and

CEM data; Measurement data from Insitec particle counter,

sizers, velocimeter.

410

(JIEE–97008398)

DOE-EM privatization and the 2006 Plan: Principles for

procurement policies and risk management. Bjornstad,

D.J.; Jones, D.W.; Duemmer, C.L. Joint Inst. for Energy and

Environment, Knoxville, TN (United States). [1997]. 22p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). Order Number

DE97008398. Source: OSTI; NTIS; INIS; GPO Dep.

The Department of Energy’s Office of Environmental Remediation and Waste Management (EM) has recently set in

place programs to restructure the strategic planning mechanism that will drive its clean-up schedule, The 2006 Plan,

and to create a new set of business relationships with private contractors that will reduce costs–privatization. Taken

together, the 2006 Plan and privatization will challenge EM

to create new business practices to recast its risk management policies to support these initiatives while ensuring that

its responsibilities toward the environment, human health,

and worker safety (ES and H) are maintained. This paper

argues that the 2006 Plan has transformed EM’s traditional,

bottoms-up approach based on technical dictates to a

top-down approach based on management goals–a transformation from an engineering problem to an economic

problem. The 2006 Plan evolved from EM’s Ten-Year Plan,

and seeks to convert the largely open-ended planning approach previously undertaken by EM to a plan bounded by

time and dollars. The plan emphasizes making tradeoffs and

choosing activities that deliver the most clean-up for the dollar. It also recognizes that each major player–stakeholders,

DOE, OMB and Congress–has distinct interests that must

be resolved if the process is to succeed. This, in turn, has

created the need for a corresponding transformation in risk

management practices from compliance-driven to benefit/

cost-driven.

411

(K/WM–177)

Review of organic nitrile incineration at the Toxic Substances Control Act Incinerator. Lockheed Martin Energy

Systems, Inc., Toxic Substances Control Act/Health Issues

Team, Oak Ridge, TN (United States). Oct 1997. 30p. Sponsored by USDOE Office of Environmental Management,

Washington, DC (United States). DOE Contract AC05-

84OR21400. Order Number DE98003664. Source: OSTI;

NTIS; INIS; GPO Dep.

Lockheed Martin Energy Systems, Inc. (LMES) operates

the East Tennessee Technology Park (ETTP), formerly

called the Oak Ridge K-25 Site, where uranium was enriched under contract with the US Department of Energy

(DOE). Currently, ETTP missions include environmental

management, waste management (WM), and the development of new technologies. As part of its WM mission, ETTP

operates the TSCA (Toxic Substances Control Act) Incinerator (TSCAI) for treatment of hazardous waste and

polychlorinated biphenyls (PCBs) contaminated with

low-level radioactivity. Beginning in the autumn of 1995, employees from diverse ETTP buildings and departments

reported experiencing headaches, fatigue, depression, muscle aches, sleeplessness, and muscle tremors. These

symptoms were judged by a physician in the ETTP Health

Services Department to be consistent with chronic exposures to hydrogen cyanide (HCN). The National Institute for

Occupational Safety and Health (NIOSH) was called in to

perform a health hazard evaluation to ascertain whether the

employees’ illnesses were in fact caused by occupational

exposure to HCN. The NIOSH evaluation found no patterns

for employees’ reported symptoms with respect to work

location or department. NIOSH also conducted a comprehensive air sampling study, which did not detect airborne

cyanides at the ETTP. Employees, however, expressed concerns that the burning of nitrile-bearing wastes at the TSCAI

might have produced HCN as a combustion product. Therefore, LMES and DOE established a multidisciplinary team

(TSCAI Technical Review Team) to make a more detailed

review of the possibility that combustion of nitrile-bearing

wastes at the TSCAI might have either released nitriles or

created HCN as a product of incomplete combustion (PIC).

412

(KY/EM–206)

Paducah site annual environmental for 1996. Belcher, G.

(ed.). Paducah Gaseous Diffusion Plant, KY (United States).

Dec 1997. 166p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE

Contract AC05-84OR21400. Order Number DE98004010.

Source: OSTI; NTIS; INIS; GPO Dep.

The Paducah Gaseous Diffusion Plant, located in McCracken County, Kentucky, has been producing enriched

uranium since 1952. In July 1993, the US Department of

Energy (DOE) leased the production areas of the site to the

United States Enrichment Corporation (USEC). A subsidiary

of Lockheed Martin Corporation, Lockheed Martin Utility

Services, manages the leased facilities for USEC. The DOE

maintains responsibility for the environmental restoration,

waste management, and depleted uranium hexafluoride

cylinder program activities at the plant through its management contractor, Lockheed Martin Energy Systems. The

purpose of this document is to summarize calendar year

1996 environmental monitoring activities for DOE activities

at the Paducah Site. The DOE requires all of its facilities to

conduct and document such activities annually. This report

does not include USEC environmental activities.

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

413

(LA–13329)

Measurement of surface emission flux rates for volatile

organic compounds at Technical Area 54. Trujillo, V. (Los

Alamos National Lab., NM (United States)); Morgenstern,

M.; Krier, D.; Gilkeson, R. Los Alamos National Lab., NM

(United States). Jun 1998. 84p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States). DOE Contract W-7405-ENG-36. Order Number

DE98007277. Source: OSTI; NTIS; INIS; GPO Dep.

The survey described in this report was conducted to estimate the mass of volatile organic compounds venting to the

atmosphere from active and inactive waste disposal sites at

Technical Area 54. A large number of nonintrusive passive

sample collection devices were placed on the ground surface for 72 hours to characterize an area of approximately

150 acres. Results provided an indication of the boundary

location of the known volatile organic plume, plume constituents, and isolated high concentration areas. The data

from this survey enhanced existing data from a limited number of monitor wells currently used for plume surveillance.

Results indicate that the estimated mass emission to the

atmosphere is orders of magnitude lower than what is considered a small flux rate at a spill site or a Resource

Conservation and Recovery Act landfill and is far below the

threshold limit established by the State of New Mexico as an

air quality concern.

414

(LA–13350)

Old-field plant succession on the Pajarito Plateau. Foxx,

T. (Los Alamos National Lab., NM (United States)); Mullen,

M.; Salisbury, M.; Tierney, G. Los Alamos National Lab., NM

(United States). Oct 1997. 109p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States). DOE Contract W-7405-ENG-36. Order Number

DE98001722. Source: OSTI; NTIS; INIS; GPO Dep.

Eight fallow historic fields of the ponderosa pine and

pinon-juniper cover types were surveyed to determine

species composition and distribution. The purpose of the

study was to understand plant succession on old fields as

related to mechanically manipulated sites such as material

disposal areas (MDAs). Additionally, the authors wanted a

listing of species on disturbed lands of the Pajarito Plateau

to aide in the reclamation planning of MDAs using native

species. They also wanted to determine if any species could

be used as an indicator of disturbance. The eight historic

fields were all within Los Alamos County, New Mexico, and

had been abandoned in 1943. Two sites were within the

boundaries of Los Alamos National Laboratory and were

studied both in 1982 and 1993. The study provides a description of each of the field sites, historic information about

the homesteads from patent applications, a photographic

record of some of the sites, and a listing of species found

within each field. The study showed that there were 78 different plant species found on disturbed sites. Of these 78

species, 23 were found to be dominant on one or more of

the MDAs or old fields. Although, the disturbance history of

each site is imperfectly known, the study does provide an indication of successional processes within disturbed sites of

the Pajarito Plateau. Additionally, it provides a listing of

species that will invade disturbed sites, species that may be

used in site reclamation.

415

(LA–13372-MS)

An analysis of background noise in selected canyons of

Los Alamos County. Huchton, K.; Koch, S.W.; Robinson,

R. Los Alamos National Lab., NM (United States). Oct 1997.

26p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

W-7405-ENG-36. Order Number DE98000768. Source:

OSTI; NTIS; GPO Dep.

The authors recorded background noise levels in six

canyons within Los Alamos County in order to establish a

baseline for future comparisons and to discover what noises

animals are exposed to. Noise level measurements were

taken within each canyon, beginning at an established starting point and at one-mile intervals up to four miles. The

primary source of noise above 55 dBA was vehicular traffic.

One clap of thunder provided the highest recorded noise

level (76 dBA). In general, the level of noise, once away

from highways and parking lots, was well below 60 dBA.

416

(LA–13374)

Correction to the MCNP perturbation feature for crosssection dependent tallies. Densmore, J.D.; McKinney,

G.W.; Hendricks, J.S. Los Alamos National Lab., NM

(United States). Oct 1997. 39p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States). DOE Contract W-7405-ENG-36. Order Number

DE98001724. Source: OSTI; NTIS; INIS; GPO Dep.

The differential operator perturbation technique is a new

feature of the Monte Carlo N-Particle Transport Code MCNP

version 4B that will allow users to calculate the effects of

cross-section data perturbations on tallies. The implementation of the differential operator perturbation technique in

MCNP assumes that the tally is independent of any perturbed cross-section data, an assumption that may not be

valid for some tallies. The authors provide derivations of

both the first- and second-order corrected perturbations. In

addition, the appropriate perturbation corrections are

demonstrated so users may accurately calculate perturbation effects for any cross-section dependent tally. Finally,

corrected perturbations from six example problems are compared to actual MCNP results.

417

(LA–13380-MS)

A Standard Analysis Method (SAM) for the automated

analysis of polychlorinated biphenyls (PCBs) in soils

using the chemical analysis automation (CAA)

paradigm: Validation and performance. Rzeszutko, C.

(Los Alamos National Lab., NM (United States)); Johnson,

C.R.; Monagle, M.; Klatt, L.N. Los Alamos National Lab.,

NM (United States). Nov 1997. 15p. Sponsored by USDOE

Office of Environmental Management, Washington, DC

(United States). DOE Contract W-7405-ENG-36. Order

Number DE98001727. Source: OSTI; NTIS; GPO Dep.

The Chemical Analysis Automation (CAA) program is developing a standardized modular automation strategy for

chemical analysis. In this automation concept, analytical

chemistry is performed with modular building blocks that

correspond to individual elements of the steps in the analytical process. With a standardized set of behaviors and

interactions, these blocks can be assembled in a plug-andplay manner into a complete analysis system. These

building blocks, which are referred to as Standard laboratory

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

Modules (SLM), interface to a host control system that orchestrates the entire analytical process, from sample

preparation through data interpretation. The integrated system is called a Standard Analysis Method (SAM). A SAM for

the automated determination of polychlorinated biphenyls

(PCBs) in soils, assembled in a mobile laboratory, is undergoing extensive testing and validation. The SAM consists of

the following SLMs: a four-channel Soxhlet extractor, a

high-volume concentration, a column clean-up, a gas chromatography, a PCB data-interpretation module, a robot, and

a human-computer interface. The SAM is configured to

meet the requirements specified in the US Environmental

Protection Agency’s (EPA) SW-846 methods 3541/3620A/

8082 for the analysis of PCBs in soils. The PCB SAM will be

described along with the developmental test plan. Performance data obtained during developmental testing will also

be discussed.

418

(LA–13407-MS)

HEPA filter jointer. Hill, D.; Martinez, H.E. Los Alamos National Lab., NM (United States). Feb 1998. 38p. Sponsored

by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract W-7405-ENG-36.

Order Number DE98004420. Source: OSTI; NTIS; GPO

Dep.

A HEPA filter jointer system was created to remove nitrate

contaminated wood from the wooden frames of HEPA filters

that are stored at the Rocky Flats Plant. A commercial jointer was chosen to remove the nitrated wood. The chips from

the wood removal process are in the right form for caustic

washing. The jointer was automated for safety and ease of

operation. The HEPA filters are prepared for jointing by

countersinking the nails with a modified air hammer. The

equipment, computer program, and tests are described in

this report.

419

(LA–13419-PR)

Laboratory and field studies related to radionuclide

migration at the Nevada Test Site. Progress report, October 1, 1996–September 30, 1997. Thompson, J.L. (ed.).

Los Alamos National Lab., NM (United States). Feb 1998.

38p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). Order Number

DE98002777. Source: OSTI; NTIS; INIS; GPO Dep.

In this report the authors describe the work done at Los

Alamos National Laboratory in FY 1997 for the Hydrologic

Resources Management Program funded by the Nevada

Operations Office of the US Department of Energy. A major

part of their work is the study of the movement underground

of radioactive material from nuclear tests at the Nevada Test

Site. This year water samples from near the nuclear tests

BULLION, BILBY, DALHART, CHESHIRE, and TYBO were

analyzed for radionuclides. Data from the first four sites

were consistent with expectations based on previous measurements; however, the water from TYBO contained

unexpected amounts of plutonium. This plutonium was subsequently found to originate from the BENHAM test which

was located 1.3 km distant. The low concentration of plutonium was associated with natural groundwater colloids and

could be largely removed by filtration. The authors are attempting to identify the physical and chemical form of the

plutonium and to assess the mechanism(s) of its movement

over the observed distance. They report the successful testing of small diameter pumps in tandem to extract water form

tubing too small to accommodate other means of pumping.

And finally, they review this year’s consultative and educational activities and list their publications.

420

(LA–13475)

Recovery of 241Am/Be neutron sources, Wooster, Ohio.

Tompkins, J.A.; Wannigman, D.; Hatler, V. Los Alamos National Lab., NM (United States). Jul 1998. [50p.] Sponsored

by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract W-7405-ENG-36.

Order Number DE98007274. Source: OSTI; NTIS; INIS;

GPO Dep.

In August 1997, the Nuclear Regulatory Commission

(NRC) submitted to the US Department of Energy (DOE) a

partial list of licensed radioactive sealed sources to be recovered under a pilot project initiating Radioactive Source

Recovery Program (RSRP) operations. The first of the pilot

project recoveries was scheduled for September 1997 at

Eastern Well Surveys in Wooster, Ohio, a company with five

unwanted sealed sources on the NRC list. The sources were

neutron emitters, each containing 241Am/Be with activities

ranging from 2.49 to 3.0 Ci. A prior radiological survey had

established that one of these sources, a Gulf Nuclear Model

71-1 containing 3 Ci of 241Am, was contaminated with 241Am

and might be leaking. The other four sources were obsolete

and could no longer be used by Eastern Well Surveys for

their intended application in well-logging applications due to

NRC decertification of these sources. All of the sources exceeded the limits established for Class C waste under 10

CFR 61.55 and, as a result, are the ultimate responsibility of

the DOE under the provisions of PL 99-240. This report describes the cooperative effort between the DOE and NRC to

recover the sources and transport them to Los Alamos National Laboratory (LANL) for deactivation under the RSRP.

This operation alleviated any potential risk to the public

health and safety from the site which might result from the

leaking neutron sources or the potential mismanagement of

unwanted sources. The on-site recovery occurred on

September 23, 1997, and was performed by personnel from

LANL and its contractor and was observed by staff from the

Region III office of the NRC. All aspects of the recovery

were successfully accomplished, and the sources were received at LANL on September 29, 1997. Experience gained

during this operation will be used to formulate operational

poilicies and procedures which will contribute to the eventual routine recovery operations of a full-scale RSRP.

421

(LA–13480-PR)

Radionuclide concentrations in honey bees from Area G

at TA-54 during 1997. Progress report. Haarmann, T.K.;

Fresquez, P.R. Los Alamos National Lab., NM (United

States). Jul 1998. 31p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States).

DOE Contract W-7405-ENG-36. Order Number

DE98007278. Source: OSTI; NTIS; INIS; GPO Dep.

Honey bees were collected from two colonies located at

Los Alamos National Laboratory’s Area G, Technical Area

54, and from one control (background) colony located near

Jamez Springs, NM. Samples were analyzed for the following: cesium (137Cs), americium (241Am), plutonium (238Pu

and 239;240Pu), tritium (3H), total uranium, and gross gamma

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

activity. Area G sample results from both colonies were

higher than the upper (95%) level background concentration

for 238Pu and 3H.

422

(LA-SUB–93-260)

241-SY-101 strain concentration factor development via

nonlinear analysis. Volume 1 of 1. Los Alamos National

Lab., NM (United States); Advent Engineering Services,

Inc., San Ramon, CA (United States). [1997]. 133p. Sponsored by USDOE Office of Environmental Management,

Washington, DC (United States). DOE Contract W-7405-

ENG-36. Order Number DE97003572. Source: OSTI; NTIS;

INIS; GPO Dep.

The 241-SY-101 waste storage tank at the Hanford-Site

has been known to accumulate and release significant

quantities of hydrogen gas. An analysis was performed to

assess the tank’s structural integrity when subjected to postulated hydrogen deflagration loads. The analysis addressed

many nonlinearities and appealed to a strain-based failure

criteria. The model used to predict the global response of

the tank was not refined enough to confidently predict local

peak strains. Strain concentration factors were applied at

structural discontinuities that were based on steel-lined

reinforced-concrete containment studies. The discontinuities

included large penetrations, small penetrations, springline

geometries, stud/liner connections, and the 1

2 inch to 3/8

inch liner thickness transition. The only tank specific strain

concentration factor applied in the evaluation was for the 1

2

inch to 3/8 inch liner thickness change in the dome. Review

of the tank drawings reveals the possibility that a 4 inches

Sch. 40 pipe penetrates the dome thickness transition

region. It is not obvious how to combine the strain concentration factors for a small penetration with that of a thickness

transition to arrive at a composite strain concentration factor.

It is the goal of this effort to make an approximate determination of the relative significance of the 4 inch penetration

and the 1

2 inch to 3/8 inch thickness transition in the 241-SY101 dome geometry. This is accomplished by performing a

parametric study with three general finite-element models.

The first represents the thickness transition only, the second

represents a 4 inch penetration only, and the third combines

the thickness transition with a penetration model.

423

(LA-SUB–95-87)

Prediction of heat capacities of solid inorganic salts

from group contributions. Mostafa, A.T.M.G. (New Mexico

State Univ., Las Cruces, NM (United States). Dept. of

Chemical Engineering); Eakman, J.M.; Yarbro, S.L. Los

Alamos National Lab., NM (United States); New Mexico

State Univ., Las Cruces, NM (United States). Dept. of

Chemical Engineering. [1997]. 46p. Sponsored by USDOE

Office of Environmental Management, Washington, DC

(United States). DOE Contract W-7405-ENG-36. Order

Number DE97002570. Source: OSTI; NTIS; GPO Dep.

A group contribution technique is proposed to predict the

coefficients in the heat capacity correlation, Cp = a + bT + c/

T2 + dT2, for solid inorganic salts. The results from this work

are compared with fits to experimental data from the literature. It is shown to give good predictions for both simple and

complex solid inorganic salts. Literature heat capacities for a

large number (664) of solid inorganic salts covering a broad

range of cations (129), anions (17) and ligands (2) have

been used in regressions to obtain group contributions for

the parameters in the heat capacity temperature function. A

mean error of 3.18% is found when predicted values are

compared with literature values for heat capacity at 298 K.

Estimates of the error standard deviation from the regression for each additivity constant are also determined.

424

(LA-SUB–95-165)

Chemical gel barriers as low-cost alternative to containment and in situ cleanup of hazardous wastes to protect

groundwater. Los Alamos National Lab., NM (United

States). [1997]. 57p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States).

DOE Contract W-7405-ENG-36. Order Number

DE97002592. Source: OSTI; NTIS; INIS; GPO Dep.

Chemical gel barriers are being considered as a low-cost

alternative for containment and in situ cleanup of hazardous

wastes to protect groundwater. Most of the available gels in

petroleum application are non-reactive and relative impermeable, providing a physical barriers for all fluids and

contaminants. However, other potential systems can be envisioned. These systems could include gels that are

chemically reactive and impermeable such that most phase

are captured by the barriers but the contaminants could diffuse through the barriers. Another system that is chemically

reactive and permeable could have potential applications in

selectivity capturing contaminants while allowing water to

pass through the barriers. This study focused on chemically

reactive and permeable gel barriers. The gels used in experiment are DuPont LUDOX SM colloidal silica gel and Pfizer

FLOPAAM 1330S hydrolyzed polyacrylamide (HPAM) gel.

425

(LA-SUB–98-37)

Treatability study Number PDC-1-O-T. Final report. Los

Alamos National Lab., NM (United States);Perma-Fix Environmental Services, Gainesville, FL (United States). 22 Apr

1998. [50p.] Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract W-7405-ENG-36. Order Number DE99001032. Source:

OSTI; NTIS; INIS; GPO Dep.

Los Alamos National Laboratory provided treatability

study samples from four waste streams, designated Stream

#1, Stream #3, Stream #6, and Stream #7. Stream #1 consisted of one 55-gallon drum of personal protective

equipment (PPE), rags, and neutralizing agent (bicarbonate)

generated during the cleanup of a sodium dichromate solution spill. Stream #3 was one 55-gallon drum of paper, rags,

lab utensils, tools, and tape from the decontamination of a

glovebox. The sample of Stream #6 was packaged in three

30-gallon drums and a 100 ft3 wooden box. It consisted of

plastic sheeting, PPE, and paper generated from the

cleanup of mock explosive (barium nitrate) from depleted

uranium parts. Stream #7 was scrap metal (copper, stainless and carbon steel joined with silver solder) from the

disassembly of gas manifolds. The objective of the treatability study is to determine: (1) whether the Perma-Fix

stabilization/solidification process can treat the waste sample to meet Land Disposal Restrictions and the Waste

Acceptance Criteria for LANL Technical Area 54, Area G,

and (2) optimum loading and resulting weight and volume of

finished waste form. The stabilized waste was mixed into

grout that had been poured into a lined drum. After each

original container of waste was processed, the liner was

closed and a new liner was placed in the same drum on top

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

of the previous closed liner. This allowed an overall reduction in waste volume but kept waste segregated to minimize

the amount of rework in case analytical results indicated any

batch did not meet treatment standards. Samples of treated

waste from each waste stream were analyzed by Perma-Fix

Analytical Services to get a preliminary approximation of

TCLP metals. Splits of these samples were sent to American Environmental Network’s mixed waste analytical lab in

Cary, NC for confirmation analysis. (Abstract truncated)

426

(LA-UR–96-3983)

Real-time alpha emitter assay of large volumes. Kerr,

P.L.; Koster, J.E.; Macy, K.; Cook, J. Los Alamos National

Lab., NM (United States). [1997]. 11p. Sponsored by USDOE Office of Environmental Management, Washington, DC

(United States). DOE Contract W-7405-ENG-36. (CONF970335–7: Waste Management ‘97, Tucson, AZ (United

States), 2-7 Mar 1997). Order Number DE97001674.

Source: OSTI; NTIS; INIS; GPO Dep.

In this paper we discuss the design and behavior of a

High Airflow Monitor (HAFM) based on Long-Range Alpha

Detector (LRAD) technology [1]. The low air resistance construction of the HAFM enables the high airflow crucial for

assay of rooms, vaults, or cargo vehicles. This is accomplished by orienting plates parallel to the airflow rather than

perpendicular, as are the grids in other LRADS. As will be

shown in this paper, the advantages of an LRAD-based volume monitor are its inexpensive simplicity, ruggedness, and

its ability to detect contamination that is hidden from traditional alpha detection methods such as Geiger-Muller, gas

cell, or solid-state detectors.

427

(LA-UR–96-4071)

Low-level radioactive waste disposal operations at Los

Alamos National Laboratory. Stanford, A.R. Los Alamos

National Lab., NM (United States). [1997]. 5p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract W-7405-ENG-36.

(CONF-970335–19: Waste Management ‘97, Tucson, AZ

(United States), 2-7 Mar 1997). Order Number

DE97003125. Source: OSTI; NTIS; INIS; GPO Dep.

Los Alamos National Laboratory (LANL) generates LowLevel Radioactive Waste (LLW) from various activities:

research and development, sampling and storage of TRU

wastes, decommissioning and decontamination of facilities,

and from LANL’s major role in stockpile stewardship. The

Laboratory has its own active LLW disposal facility located

at Technical Area 54, Area G. This paper will identify the

current operations of the facility and the issues pertaining to

operating a disposal facility in today’s compliance and costeffective environment.

428

(LA-UR–96-4434)

Key regulatory drivers affecting shipments of mixed

transuranic waste from Los Alamos National Laboratory

to the Waste Isolation Pilot Plant. Schumann, P.B. (and

others); Bacigalupa, G.A.; Kosiewicz, S.T.; Sinkule, B.J. Los

Alamos National Lab., NM (United States). 1997. 12p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

W-7405-ENG-36. (CONF-970335–16: Waste Management

‘97, Tucson, AZ (United States), 2-7 Mar 1997). Order Number DE97003132. Source: OSTI; NTIS; INIS; GPO Dep.

A number of key regulatory drivers affect the nature,

scope, and timing of Los Alamos National Laboratory’s

(LANL’s) plans for mixed transuranic (MTRU) waste shipments to the Waste Isolation Pilot Plant (WIPP), which are

planned to commence as soon as possible following WIPP’s

currently anticipated November, 1997 opening date. This

paper provides an overview of some of the key drivers at

LANL, particularly emphasizing those associated with the

hazardous waste component of LANL’s MTRU waste

(MTRU, like any mixed waste, contains both a radioactive

and a hazardous waste component). The key drivers discussed here derive from the federal Resource Conservation

and Recovery Act (RCRA) and its amendments, including

the Federal Facility Compliance Act (FFCAU), and from the

New Mexico Hazardous Waste Act (NMHWA). These

statutory provisions are enforced through three major mechanisms: facility RCRA permits; the New Mexico Hazardous

Waste Management Regulations, set forth in the New Mexico Administrative Code, Title 20, Chapter 4, Part 1: and

compliance orders issued to enforce these requirements.

General requirements in all three categories will apply to

MTRU waste management and characterization activities at

both WIPP and LANL. In addition, LANL is subject to facilityspecific requirements in its RCRA hazardous waste facility

permit, permit conditions as currently proposed in RCRA

Part B permit applications presently being reviewed by the

New Mexico Environment Department (NNED), and facilityspecific compliance orders related to MTRU waste

management. Likewise, permitting and compliance-related

requirements specific to WIPP indirectly affect LANL’s characterization, packaging, record-keeping, and transportation

requirements for MTRU waste. LANL must comply with this

evolving set of regulatory requirements to begin shipments

of MTRU waste to WIPP in a timely fashion.

429

(LA-UR–96-4722)

Los Alamos National Laboratory’s Mobile Real Time Radiography System. Vigil, J.; Taggart, D.; Betts, S.; Mendez,

J.; Rael, C.; Martinez, F. Los Alamos National Lab., NM

(United States). [1997]. 9p. Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract W-7405-ENG-36. (CONF-970126–1:

5. nondestructive assay/nondestructive examination waste

characterization conference, Salt Lake City, UT (United

States), 14-16 Jan 1997). Order Number DE97001667.

Source: OSTI; NTIS; INIS; GPO Dep.

A 450-KeV Mobile Real Time Radiography (RTR) System

was delivered to Los Alamos National Laboratory (LANL) in

January 1996. It was purchased to inspect containers of radioactive waste produced at (LANL). Since its delivery it has

been used to radiograph greater than 600 drums of radioactive waste at various LANL sites. It has the capability of

inspecting waste containers of various sizes. It has three independent X-Ray acquisition formats. The primary system

used is a 12 in. image intensifier, the second is a 36 in. linear diode array (LDA) and the last is an open system. It is

fully self contained with on board generator, HVAC and a

fire suppression system. It is on a 53 ft long X 8 ft. wide X

14 ft. high trailer that can be moved over any highway requiring only a easily obtainable overweight permit because it

weighs approximately 38 tons. It was built to conform to

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

industry standards for a cabinet system which does not require an exclusion zone. The fact that this unit is mobile has

allowed us to operate where the waste is stored, rather than

having to move the waste to a fixed facility.

430

(LA-UR–96-4723)

Experience operating LANL’s passive/active neutron

(PAN) assay system. Taggart, D.P.; Betts, S.E.; Martinez,

E.F.; Mendez, J.L.; Rael, C.D.; Vigil, J.J. Los Alamos National Lab., NM (United States). [1997]. 13p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract W-7405-ENG-36.

(CONF-970126–2: 5. nondestructive assay/nondestructive

examination waste characterization conference, Salt Lake

City, UT (United States), 14-16 Jan 1997). Order Number

DE97001668. Source: OSTI; NTIS; INIS; GPO Dep.

We present a summary of our operating experience with

LANL’s mobile PAN assay system, which was acquired from

the Carlsbad Area Office in 1994, refurbished, calibrated,

and fielded for the first time on LANL’s TRU waste in the

winter of 1996. It is functionally identical to other PAN systems throughout the DOE complex and its software is the

same as at INEL. Since Jan. 1996, it has passed the first

round of the Performance Demonstration Program and has

been used to assay several hundred drums of LANL’s TRU

waste. Difficulties in assaying homogeneous wastes with

high (,n) neutron fluxes and experience in assaying debris

waste in both active and passive PAN modes are reported

on.

431

(LA-UR–96-4870)

Atmospheric transport in complex terrain at Los

Alamos, Area G. Vold, E.L. Los Alamos National Lab., NM

(United States). [1997]. 21p. Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract W-7405-ENG-36. Order Number

DE97004254. Source: OSTI; NTIS; GPO Dep.

This report documents the atmospheric dispersion used in

the Area G Performance Assessment for off-site airborne

dose calculations. Potential airborne contaminants from the

mesa top disposal facility disperse in the complex terrain

dominated by narrow mesas in parallel to narrow canyons.

The dispersion is characterized by site-specific values of X/

Q [(Ci/m3)/(Ci/s)] at each of two designated receptor locations, a ‘maximum off-site dose’ location and a nearby

population center (White Rock, NM). The values of X/Q in

each of the sixteen wind sectors are first estimated with the

CAP-88 computer code using 1992 annual meteorologic

data from Area G and assuming an area source for release.

This data captures the dominant wind direction on the mesa

tops from the SSW. These dispersion parameters are assumed to apply to open, flat terrain and must be corrected

for the complex mesa and canyon terrain terrain surrounding the Area G site. Additional meteorologic data has been

collected over two years from six remote temporary meteorological stations operated on the mesas and in the canyons

immediately around Area G. These data indicate that the

wind flow in the canyons is exclusively bimodel, flowing up

canyon during the day and down canyon at night. It is conservatively assumed that all ground level releases from Area

G which blow out across an adjacent canyon become entrained in the canyon flow. This effectively combines the

contaminant release for several sectors into a single canyon

flow which is upstream during the day or downstream at

night. This canyon channeling mechanism is implemented in

the model by summing the wind sector dispersion factors

over those sectors appropriate to the geometry for a release

from Area G toward either adjacent canyon.

432

(LA-UR–96-4871)

A model for the effective diffusion of gas or the vapor

phase in a fractured media unsaturated zone driven by

periodic atmospheric pressure fluctuations. Vold, E.L.

Los Alamos National Lab., NM (United States). [1997]. 40p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

W-7405-ENG-36. Order Number DE97004255. Source:

OSTI; NTIS; GPO Dep.

There is evidence for migration of tritiated water vapor

through the tuff in the unsaturated zone from the buried disposal shafts located on a narrow mesa top at Area G, Los

Alamos, NM. Field data are consistent with an effective insitu vapor phase diffusion coefficient of 1.5x103 ms

/s, or a

factor of 60 greater than the binary diffusion coefficient for

water vapor in air. A model is derived to explain this observation of anomolously large diffusion, which relates an

effective vapor or gas phase diffusion coefficient in the

fractured porous media to the subsurface propagation of atmospheric pressure fluctuations (barometric pumping). The

near surface (unattenuated) diffusion coefficient is independent of mode period under the simplified assumptions of a

complete ‘mixing mechanism’ for the effective diffusion process. The unattenuated effective diffusion driven by this

barometric pumping is proportional to an average media

permeability times the sum of the square of pressure mode

amplitudes, while the attenuation length is proportional to

the squarer root of the product of permeability times mode

period. There is evidence that the permeability needed to

evaluate the pressure attenuation length is the in-situ value,

approximately that of the matrix. The diffusion which results

using Area G parameter values is negligible in the matrix but

becomes large at the effective permeability of the fractured

tuff matrix. The effective diffusion coefficient predicted by this

model, due to pressure fluctuations and the observed fracture characteristics, is in good agreement with the observed

in-situ diffusion coefficient for tritium field measurements. It

is concluded that barometric pumping in combination with

the enhanced permeability of the fractured media is a likely

candidate to account for the observed in-field migration of

vapor in the near surface unsaturated zone at Area G.

433

(LA-UR–97-210)

Visualizing data for environmental analysis. Benson, J.

Los Alamos National Lab., NM (United States). [1997]. 11p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

W-7405-ENG-36. (CONF-970493–1: American Society for

Photogrammetry and Remote Sensing/American Congress

on Surveying and Mapping (ASPRS/ACSM), Seattle, WA

(United States), 10 Apr 1997). Order Number DE97004758.

Source: OSTI; NTIS; INIS; GPO Dep.

The Environmental Restoration Project at Los Alamos

National Laboratory (LANL) has over 11,000 sampling locations in a 44 square mile area. The sample analyses contain

raw analytical chemistry values for over 2,300 analytes and

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

compounds used to define and remediate contaminated areas at LANL. The data consist of 2.5 million records in an

oracle database. Maps are often used to visualize the data.

Problems arise when a client specifies a particular kind of

map without fully understanding the limitations of the data or

the map. The ability of maps to convey information is dependent on many factors, though all maps are data dependent.

The quantity, spatial distribution, and numerical range of the

data can limit use with certain kinds of maps. To address

these issues and educate the clients, several types of statistical maps (e.g., choropleth, isarithm, and graduated symbol

such as bubble and spike) used for environmental analysis

were chosen to show the advantages, disadvantages, and

data limitations of each. By examining both the complexity

of the analytical data and the limitations of the map type, it

is possible to consider how reality has been transformed

through the map, and if that transformation accurately conveys the information present.

434

(LA-UR–97-1144)

CID-based ICP-AES instrumentation for continuous online analysis of aqueous industrial waste streams.

Federici, C. (Los Alamos National Lab., NM (United States));

Doorn, S.; Villanueva, D.; Arrington, T. Los Alamos National

Lab., NM (United States). 1997. 16p. Sponsored by USDOE

Office of Environmental Management, Washington, DC

(United States). DOE Contract W-7405-ENG-36. (CONF970503–36: 17. IEEE particle accelerator conference,

Vancouver (Canada), 12-16 May 1997). Order Number

DE97007474. Source: OSTI; NTIS; INIS; GPO Dep.

A CID detection based ICP-AES instrument has been incorporated into an on-line continuous process monitoring

system for analysis of aqueous industrial waste streams.

Total wavelength coverage afforded by the CID detection allows increased confidence in the analytical results through

use of multiple wavelengths for analysis of each element.

Total wavelength coverage also allows quick detection of interferences present in the varying waste stream that may

cause false positives. Several internal standards have been

evaluated to correct for expected variations in the waste

stream matrix, and results have been incorporated in the analytical method. The system has been tested on a surrogate

waste stream and results are compared to those obtained

through conventional ICP-AES analysis of waste stream

grab samples.

435

(LA-UR–97-1170)

New spectroscopic studies of plutonium (IV) nitrate

complex formation in solution. Berg, J.M. (and others);

Veirs, D.K.; Vaughn, R.B. Los Alamos National Lab., NM

(United States). 1997. 10p. Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract W-7405-ENG-36. (CONF-970424–7:

4. international conference on methods and applications of

radioanalytical chemistry, Kona, HI (United States), 6-11 Apr

1997). Order Number DE97007579. Source: OSTI; NTIS;

INIS; GPO Dep.

Spectrophotometric titrations of Pu(IV) with HNO3 were

conducted in a series of aqueous HClO4 solutions ranging

ionic strength from 2 to 19 mol/kg on the molality scale. The

Pu f-f absorption spectra in the visible and near IR range

were deconvoluted into spectra of Pu4+(aq), Pu(NO3)

3+ and

Pu(NO3)2

2+ complexes and their formation constants as

functions of ionic strength. When corrected for the incomplete dissociation of nitric acid, these formation constants

exhibit smooth increases with ionic strength from 5 to 19

mol/kg.

436

(LA-UR–97-1263)

A new waste minimization method for the determination

of total nonhalogenated volatile organic compounds in

TRU wastes. Sandoval, W. (and others); Quintana, B.D.;

Ortega, L. Los Alamos National Lab., NM (United States).

1997. 13p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract W-7405-ENG-36. (CONF-970424–15: 4. international

conference on methods and applications of radioanalytical

chemistry, Kona, HI (United States), 6-11 Apr 1997). Order

Number DE97007186. Source: OSTI; NTIS; INIS; GPO Dep.

As part of the technical support CST-12 provides for a

wide variety of defense and nondefense programs within

Los Alamos National Laboratory (LANL) and the Department

of Energy (DOE) complex, new waste minimization technique is under development for radiological volatile organic

analysis (Hot VOA). Currently all HOT VOA must be run in a

glovebox. Several types of sample contain TRU radiological

waste in the form of particulates. By prefiltering the samples

through a 1.2 micron syringe and counting the radioactivity,

it has been found that many of the samples can be analyzed

outside a glovebox. In the present investigation, the types of

Hot VOA samples that can take advantage of this new technique, the volume and types of waste reduced and the

experimental parameters will be discussed. Overall, the radioactive waste generated is minimized.

437

(LA-UR–97-1279)

New bifunctional anion-exchange resins for nuclear

waste treatment: Part 2. Marsh, S.F. (Los Alamos National

Lab., NM (United States)); Jarvinen, G.D.; Barr, M.E.;

Bartsch, R.A. Los Alamos National Lab., NM (United States).

[1997]. 11p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract W-7405-ENG-36. (CONF-970424–6: 4. international

conference on methods and applications of radioanalytical

chemistry, Kona, HI (United States), 6-11 Apr 1997). Order

Number DE97007417. Source: OSTI; NTIS; INIS; GPO Dep.

Additional bifunctional anion-exchange resins have been

designed, synthesized and evaluated for their ability to take

up Pu(IV) from nitric acid solutions. Bifunctionality is

achieved by adding a second anion-exchange site to the

pyridine nitrogen (also an anion-exchange site) of the base

poly(4-vinylpyridine) resin. Previous work focused on the effect of varying the chemical properties of the added site

along with the length of an alkylene spacer between the two

sites. Here the authors examine four new 3- and 4-picolyl

derivatives which maintain more rigidly defined geometries

between the two nitrogen cationic sites. These materials,

which have the two anion-exchange sites separated by

three and four carbons, respectively, exhibit lower overall

Pu(IV) distribution coefficients than the corresponding Nalkylenepyridium derivatives with more flexible spacers.

Methylation of the second pyridium site results in a ca. 20%

increase in the Pu(IV) distribution coefficients.

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

438

(LA-UR–97-2003)

Plutonium (IV) complexation by nitrate in acid solutions

of ionic strengths from 2 to 19 molal. Berg, J.M. (Los

Alamos National Lab., NM (United States). Nuclear Materials Technology Div.); Veirs, D.K.; Vaughn, R.B.; Cisneros,

M.A.; Smith, C.A. Los Alamos National Lab., NM (United

States). [1997]. 12p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States).

DOE Contract W-7405-ENG-36. (CONF-9706138–2: Workshop on long-lived radionuclide chemistry in nuclear waste

treatment, Avignon (France), 18-20 Jun 1997). Order Number DE97008755. Source: OSTI; NTIS; INIS; GPO Dep.

Titrations of Pu(IV) with HNO3 in a series of aqueous

HClO4 solutions ranging in ionic strength from 2 to 19 molal

were followed using absorption spectrophotometry. The Pu

5f-5f spectra in the visible and near IR range change with

complex formation. At each ionic strength, a series of spectra were obtained by varying nitrate concentration. Each

series was deconvoluted into spectra f Pu4+(aq), Pu(NO3)

3+

and Pu(NO3)2

2+ complexes, and simultaneously their formation constants were determined. When corrected for the

incomplete dissociation of nitric acid, the ionic strength dependence of each formation constant can be described by

two parameters, 0 and ∆" using the formulae of specific ion

interaction theory. The difficulties with extending this analysis to higher nitrate coordination numbers are discussed.

439

(LA-UR–97-2414)

Speciation and surface interactions of actinides on

aged ion-exchange resins. Morris, D.E. (and others);

Buscher, C.T.; Donohoe, R.J. Los Alamos National Lab.,

NM (United States). 1997. 5p. Sponsored by USDOE Office

of Environmental Management, Washington, DC (United

States). DOE Contract W-7405-ENG-36. (CONF-970844–:

Plutonium futures: the science, Santa Fe, NM (United

States), 25-27 Aug 1997). Order Number DE97008970.

Source: OSTI; NTIS; INIS; GPO Dep.

The United States Department of Energy is presently

faced with the stabilization and safe disposition of hundreds

of metric tons of residue materials resulting from 50+ years

of nuclear weapons production activities. These residues

encompass a broad range of substrates and radionuclides

and include both solid and liquid materials. Combustible

residues constitute a significant fraction of the total residue

inventory, and an important constituent within the combustible category is spent anion ion-exchange resins. These

resins are typically utilized for the separation of plutonium

from other radionuclides under strongly acidic nitric or hydrochloric acid solution conditions which favor the formation

and partitioning of anionic Pu(IV) nitrato or chloride species.

The spent resins are usually rinsed prior to storage as

residues to reduce both acid and radionuclide concentrations, but significant radionuclide concentrations remain in

these resins, and the long-term effects of concentrated acid

and radiolysis on the resin integrity are relatively unexplored. Thus, new research is needed to assess the stability

of these resin residues and address the need for further

treatment to ensure stability prior to long-term disposal.

440

(LA-UR–97-2592)

Oxidation kinetics of plutonium in air: Consequences

for environmental dispersal. Haschke, J.M.; Allen, T.H.;

Martz, J.C. Los Alamos National Lab., NM (United States).

1997. 16p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract W-7405-ENG-36. (CONF-970907–: Actinides ’97:

international conference on actinides, Baden-Baden (Germany), 21-26 Sep 1997). Order Number DE97008884.

Source: OSTI; NTIS; INIS; GPO Dep.

Kinetic studies show that plutonium corrosion in air is catalyzed by plutonium hydride on the metal surface and

suggest that the process has caused storage containers to

fail. The catalyzed reaction initiates at 25C, indiscriminately

consumes both O2 and N2, and transforms metal into a dispersible product at a 107-1010 faster rate (0.6  0.1 g Pu/

cm2 min) than normal air oxidation. The catalyzed Pu+O2

reaction advances into the metal at a linear rate of 2.9 m/h.

Rate equations and particle size data, which are presented

for catalyzed and atmospheric corrosion at temperatures up

to 3500C, provide a technical basis for more accurately assessing the dispersal hazard posed by plutonium metal.

441

(LA-UR–97-2741)

Performance of NDA techniques on a vitrified waste

form. Hurd, J.R.; Veazey, G.W.; Prettyman, T.H.; Mercer,

D.J.; Ricketts, T.E.; Nakaoka, R.K. Los Alamos National

Lab., NM (United States). [1997]. 9p. Sponsored by USDOE

Office of Environmental Management, Washington, DC

(United States). DOE Contract W-7405-ENG-36. (CONF970744–: 38. annual meeting of the Institute of Nuclear

Materials management, Phoenix, AZ (United States), 20-24

Jul 1997). Order Number DE98001014. Source: OSTI;

NTIS; INIS; GPO Dep.

Rocky Flats Environmental Technology Site (RFETS) is

currently considering the use of vitrified transuranic (TRU)-

waste forms for the final disposition of several waste

materials. To date, however, little nondestructive assay

(NDA) data have been acquired in the general NDA community to assist in this endeavor. This paper describes the

efforts to determine constraints and operating parameters

for using NDA instrumentation on vitrified waste. The

present study was conducted on a sample composed of a

plutonium-contaminated ash, similar to that found in the

RFETS inventory, and a borosilicate-based glass. The vitrified waste item was fabricated at Los Alamos National

Laboratory (LANL) using methods and equipment similar to

those being proposed by RFETS to treat their ash material.

The focus of this study centered on the segmented gamma

scanner (SGS) with 1/2-inch collimation, a technique that is

presently available at RFETS. The accuracy and precision

of SGS technology was evaluated, with particular attention

to bias issues involving matrix geometry, homogeneity, and

attenuation. Tomographic gamma scanning was utilized in

the determination of the waste form homogeneity. A thermal

neutron technique was also investigated and comparisons

made with the gamma results.

442

(LA-UR–97-2810)

Comparison of silver(II), cobalt(III), and cerium(IV) as

electron transfer mediators in the MEO mixed waste

treatment process. Smith, W.H.; Purdy, G.M.; McKee, S.D.

Los Alamos National Lab., NM (United States). [1997]. 8p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

W-7405-ENG-36. (CONF-9709118–: I&EC symposium,

109
ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

Pittsburgh, PA (United States), 15-17 Sep 1997). Order

Number DE98000805. Source: OSTI; NTIS; INIS; GPO Dep.

Mediated electrochemical oxidation (MEO) has been developed as a method to treat mixed hazardous waste. The

technology has for the most part been targeted toward

wastes generated by the nuclear industry, consisting of a

hazardous or non-hazardous organic material contaminated

by a radioactive substance. The MEO process consists of

the electrochemical generation of a powerful oxidizing

agent, which serves as an electron transfer mediator to

bring about the oxidation of the organic component. Numerous studies on a variety of organic substrates have

demonstrated complete oxidation to carbon dioxide can be

realized under the proper reaction conditions, with water

serving as the source of oxygen. The radioactive component, usually an actinide element or heavy metal isotope,

can then be recovered from the resulting organic free aqueous solution by standard methods such as ion exchange or

solvent extraction. In addition to the variety of organic compounds tested, investigators have also looked at a number

of process parameters including choice of mediator, temperature, concentration of mediator, current density, anode

material, acid concentration, and cell separator material.

From these studies it would appear that for a given organic

substrate, the two most important process parameters are

choice of mediator and temperature. The purpose of this

work is to evaluate these two parameters for a given organic

material, holding all other parameters constant. The organic

material chosen for this study is the industry standard sulfonated styrene-divinyl benzene based cation exchange

resin. This material is ubiquitous throughout the nuclear

complex as a process residue, and is very resistant to

chemical attack making it an ideal substrate to evaluate

MEO capability. A high acid concentration is necessary to

solubilize the mediator in its higher oxidation state, 6 M nitric

acid was chosen since it is compatible with existing subsequent actinide element recovery processes.

443

(LA-UR–97-2934)

TRU waste transportation – The flammable gas generation problem. Connolly, M.J. (Lockheed Idaho Technologies

Co., Idaho Falls, ID (United States)); Kosiewicz, S.T. Los

Alamos National Lab., NM (United States). [1997]. 11p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

W-7405-ENG-36. (CONF-970857–: 4. biennial ASME mixed

waste symposium, Baltimore, MD (United States), 17-21

Aug 1997). Order Number DE98000995. Source: OSTI;

NTIS; INIS; GPO Dep.

The Nuclear Regulatory Commission (NRC) has imposed

a flammable gas (i.e., hydrogen) concentration limit of 5%

by volume on transuranic (TRU) waste containers to be

shipped using the TRUPACT-II transporter. This concentration is the lower explosive limit (LEL) in air. This was done

to minimize the potential for loss of containment during a

hypothetical 60 day period. The amount of transuranic radionuclide that is permissible for shipment in TRU waste

containers has been tabulated in the TRUPACT-II Safety

Analysis Report for Packaging (SARP, 1) to conservatively

prevent accumulation of hydrogen above this 5% limit.

Based on the SARP limitations, approximately 35% of the

TRU waste stored at the Idaho National Engineering and

Environmental Lab (INEEL), Los Alamos National Lab

(LANL), and Rocky Flats Environmental Technology Site

(RFETS) cannot be shipped in the TRUPACT-II. An even

larger percentage of the TRU waste drums at the Savannah

River Site (SRS) cannot be shipped because of the much

higher wattage loadings of TRU waste drums in that site’s

inventory. This paper presents an overview of an integrated,

experimental program that has been initiated to increase the

shippable portion of the Department of Energy (DOE) TRU

waste inventory. In addition, the authors will estimate the

anticipated expansion of the shippable portion of the inventory and associated cost savings. Such projection should

provide the TRU waste generating sites a basis for developing their TRU waste workoff strategies within their Ten Year

Plan budget horizons.

444

(LA-UR–97-2935)

Hazardous waste systems analysis at Los Alamos National Laboratory. Urioste, J. Los Alamos National Lab.,

NM (United States). [1997]. 11p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States). DOE Contract W-7405-ENG-36. (CONF-970854–:

13. pollution prevention conference, Atlanta, GA (United

States), 26-28 Aug 1997). Order Number DE98000985.

Source: OSTI; NTIS; INIS; GPO Dep.

Los Alamos National Laboratory produces routine and

non-routine hazardous waste as a by-product of mission operations. Hazardous waste commonly generated at the

Laboratory includes many types of laboratory research

chemicals, solvents, acids, bases, carcinogens, compressed

gases, metals, and other solid waste contaminated with hazardous waste. The Los Alamos National Laboratory

Environmental Stewardship Office has established a Hazardous Waste Minimization Coordinator to specifically focus

on routine and non-routine RCRA, TSCA, and other administratively controlled wastes. In this process, the Waste

Minimization Coordinator has developed and implemented a

systems approach to define waste streams, estimate waste

management costs and develop plans to implement avoidance practices, and develop projects to reduce or eliminate

the waste streams at the Laboratory. The paper describes

this systems approach.

445

(LA-UR–97-2997)

Metal recycling experience at Los Alamos National Laboratory. Reuse, release, and recycle of metals from

radiological control areas”. Gogol, S. Los Alamos National Lab., NM (United States). [1997]. 8p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract W-7405-ENG-36.

(CONF-970854–: 13. pollution prevention conference, Atlanta, GA (United States), 26-28 Aug 1997). Order Number

DE98000986. Source: OSTI; NTIS; INIS; GPO Dep.

Approximately 15% of the Low-Level Waste (LLW) produced at Los Alamos consists of scrap metal equipment and

materials. The majority of this material is produced by decommissioning and the modification of existing facilities. To

reduce this waste stream, Department of Energy Headquarters, EM-77 Office, sponsored the Reuse, Recycle, and

Release of Metals from Radiological Control Areas High Return on Investment (ROI) Project to implement recycle,

reuse, and release of scrap metal at the laboratory. The

goal of this project was to develop cost effective alternatives

to LLW disposal of scrap metal and to avoid the disposal of

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

2,400 m3 of scrap metal. The ROI for this project was estimated at 948%. The ROI project was funded in March 1996

and is scheduled for completion by October 1997. At completion, a total of 2,400 m3 of LLW avoidance will have been

accomplished and a facility to continue recycling activities

will be operational. This paper will present the approach

used to develop effective alternatives for scrap metal at Los

Alamos and then discuss the tasks identified in the approach in detail. Current scrap metal inventory, waste

projections, alternatives to LLW disposal, regulatory guidance, and efforts to institutionalize the alternatives to LLW

disposal will be discussed in detail.

446

(LA-UR–97-3188)

A successful waste stream analysis on a large construction project in a radiologically controlled facility.

Kennicott, M. (n,p Energy, Inc. (United States)); Durrer, R.;

Richardson, D.; Starke, T.P. Los Alamos National Lab., NM

(United States). [1997]. 8p. Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract W-7405-ENG-36. (CONF-970854–:

13. pollution prevention conference, Atlanta, GA (United

States), 26-28 Aug 1997). Order Number DE98001340.

Source: OSTI; NTIS; INIS; GPO Dep.

The Los Alamos National Laboratory (the Laboratory)

Chemistry and Metallurgy Research (CMR) Facility, constructed in 1952, is currently under going a major, multi-year

demolition and construction project. Many of the operations

required under this project (i.e., design, demolition, decontamination, construction, and waste management) mimic the

processes required of a large scale decontamination and

decommissioning (D and D) job and are identical to the requirements of any of several upgrades projects anticipated

for the laboratory and other Department of Energy (DOE)

sites. For these reasons the CMR upgrades Project is seen

as an ideal model facility–to test the application and measure the success of waste minimization techniques which

could be implemented for any similar projects. The purpose

of this paper will be to discuss the successful completion of

a waste stream analysis. The analyses performed was to

measure the potential impact of waste generation, in terms

of volume and costs, for a reconfiguration option being considered to change the approach and execution of the

original project.

447

(LA-UR–97-4023)

Automating the analytical laboratory via the Chemical

Analysis Automation paradigm. Hollen, R.; Rzeszutko, C.

Los Alamos National Lab., NM (United States). Oct 1997.

15p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

W-7405-ENG-36. (CONF-9710163–: ISLAR ’97, Boston,

MA (United States), 19-22 Oct 1997). Order Number

DE98003082. Source: OSTI; NTIS; GPO Dep.

To address the need for standardization within the analytical chemistry laboratories of the nation, the Chemical

Analysis Automation (CAA) program within the US Department of Energy, Office of Science and Technology’s Robotic

Technology Development Program is developing laboratory

sample analysis systems that will automate the environmental chemical laboratories. The current laboratory automation

paradigm consists of islands-of-automation that do not integrate into a system architecture. Thus, today the chemist

must perform most aspects of environmental analysis

manually using instrumentation that generally cannot communicate with other devices in the laboratory. CAA is

working towards a standardized and modular approach to

laboratory automation based upon the Standard Analysis

Method (SAM) architecture. Each SAM system automates a

complete chemical method. The building block of a SAM is

known as the Standard Laboratory Module (SLM). The SLM,

either hardware or software, automates a subprotocol of an

analysis method and can operate as a standalone or as a

unit within a SAM. The CAA concept allows the chemist to

easily assemble an automated analysis system, from

sample extraction through data interpretation, using standardized SLMs without the worry of hardware or software

incompatibility or the necessity of generating complicated

control programs. A Task Sequence Controller (TSC) software program schedules and monitors the individual tasks

to be performed by each SLM configured within a SAM. The

chemist interfaces with the operation of the TSC through the

Human Computer Interface (HCI), a logical, icon-driven

graphical user interface. The CAA paradigm has successfully been applied in automating EPA SW-846 Methods

3541/3620/8081 for the analysis of PCBs in a soil matrix utilizing commercially available equipment in tandem with

SLMs constructed by CAA.

448

(LA-UR–97-4024)

A standard analysis method (SAM) for the automated

analysis of polychlorinated biphenyls (PCBs) in soils using the chemical analysis automation (CAA) paradigm:

validation and performance. Rzeszutko, C. (Los Alamos

National Lab., NM (United States)); Johnson, C.R.; Monagle, M.; Klatt, L.N. Los Alamos National Lab., NM (United

States). Oct 1997. 18p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States).

DOE Contract W-7405-ENG-36. (CONF-9710163–: ISLAR

’97, Boston, MA (United States), 19-22 Oct 1997). Order

Number DE98003081. Source: OSTI; NTIS; INIS; GPO Dep.

The Chemical Analysis Automation (CAA) program is developing a standardized modular automation strategy for

chemical analysis. In this automation concept, analytical

chemistry is performed with modular building blocks that

correspond to individual elements of the steps in the analytical process. With a standardized set of behaviors and

interactions, these blocks can be assembled in a ’plug and

play’ manner into a complete analysis system. These building blocks, which are referred to as Standard Laboratory

Modules (SLM), interface to a host control system that orchestrates the entire analytical process, from sample

preparation through data interpretation. The integrated system is called a Standard Analysis Method (SAME). A SAME

for the automated determination of Polychlorinated

Biphenyls (PCB) in soils, assembled in a mobile laboratory,

is undergoing extensive testing and validation. The SAME

consists of the following SLMs: a four channel Soxhlet extractor, a High Volume Concentrator, column clean up, a

gas chromatograph, a PCB data interpretation module, a

robot, and a human- computer interface. The SAME is

configured to meet the requirements specified in U.S. Environmental Protection Agency’s (EPA) SW-846 Methods

3541/3620A/8082 for the analysis of pcbs in soils. The PCB

SAME will be described along with the developmental test

plan. Performance data obtained during developmental testing will also be discussed.

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

449

(LA-UR–97-4102)

Report on the GC-MBS method for correcting NaI spectra for transmission loss in hand-held instruments.

Rawool-Sullivan, M. Los Alamos National Lab., NM (United

States). 8 Oct 1997. 32p. Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract W-7405-ENG-36. Order Number

DE98003094. Source: OSTI; NTIS; INIS; GPO Dep.

The goals of this project were (1) to develop a capability

to study the scattered components in the NaI spectra of attenuated sources and (2) to evaluate the effectiveness of

the gross count material basis set (GC-MBS) method in

quantifying transmission losses from the shapes of measured NaI spectra. These goals are related, as the GC-MBS

method involves a linear log-spectrum decomposition into

MBS component spectra, and scattered gamma rays represent a significant nonlinear interference. Eventually, the

authors hope to understand the effect of the scattered components on the MBS decomposition and to develop ways to

correct for inaccuracies. As of this writing the authors have

not reached that long-term objective, so the two halves of

this project are treated here as separate topics, with a separate section for each. They have substantially achieved both

of the project goals and are collecting additional data for two

publications at the upcoming IEEE conference in Albuquerque, NM–one paper about their work on scattering and

another on the GC-MBS method. This project report will

contain preliminary portions of those two papers.

450

(LA-UR–97-4439)

Effects on the long term storage container by thermal

cycling alpha plutonium. Flamm, B.F.; Prenger, F.C.;

Veirs, D.K.; Hill, D.D.; Isom, G.M. Los Alamos National Lab.,

NM (United States). Mar 1998. 21p. Sponsored by USDOE

Office of Environmental Management, Washington, DC

(United States). DOE Contract W-7405-ENG-36. (CONF971125–: 1997 American Nuclear Society (ANS) winter

meeting, Albuquerque, NM (United States), 16-20 Nov

1997). Order Number DE98003351. Source: OSTI; NTIS;

INIS; GPO Dep.

Experiments were conducted to determine the validity of

the steady state temperature limit of 100 C established by

the DOE-STD-3013-96 for storing alpha plutonium metal.

Studies with an alpha plutonium ingot combined with strain

gauge measurements indicate that the stainless steel storage container, yields very little (0.005 in.) to the expanding

plutonium metal as it undergoes alpha beta phase transformation at temperatures above 112 C. Another experiment

using an alpha plutonium rod for point loading of the

container wall showed no measured deformation of the container. The results of strain measurements for alpha beta

and beta alpha transformations for twenty five thermal

cycles are reported. Finite element modeling using the measured data predicts that the compressive yield strength is

3,500 psi versus the literature value of 13,000 psi.

451

(LA-UR–97-4616)

Hazards associated with retrieval and storage of legacy

waste at the Transuranic Waste Inspectable Storage

Project. Pannell, M.A.; Grogin, P.W.; Langford, R.R. Los

Alamos National Lab., NM (United States). Mar 1998. 12p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

W-7405-ENG-36. (CONF-980307–: Waste management ’98,

Tucson, AZ (United States), 1-5 Mar 1998). Order Number

DE98002928. Source: OSTI; NTIS; INIS; GPO Dep.

Approximately 17,000 containers of solid transuranic and

hazardous waste have been stored beneath earthen cover

for nearly twenty years at Technical Area 4 of the Los

Alamos National Laboratory. The mission of the Transuranic

Waste Inspectable Storage Project (TWISP) is to retrieve,

vent, and place these containers into an inspectable storage

configuration in compliance with the Resource Conservation

and Recovery Act, prior to final disposition at the Waste Isolation Pilot Plant. Significant hazards currently identified with

TWISP activities include: (1) the pressurization of drums; (2)

volatilization of organic compounds (VOCs) within the

drums; and (3) the generation of elevated hydrogen levels by

certain waste streams. Based on the retrieval of 15% of the

waste containers, the following preliminary conclusions are

presented to better protect personnel and the environment:

(1) the likelihood of unvented drums becoming pressurized

increases when environmental conditions change; (2) pressurized drums must be vented before they become bulging

drums; (3) vented drums present the potential for VOC

emissions and personnel exposure; (4) the vapor pressure

and boiling points of waste stream constituents may be an

indication of the likelihood of VOC emissions from stored

hazardous waste containers; (5) large numbers of colocated vented drums may present the potential of increased

hydrogen and VOC concentrations within unventilated storage domes; (6) monitoring and sampling vented drum

storage domes is necessary to ensure that the levels of risk

to drum handlers and inspection personnel are acceptable;

(7) identifying, tagging, and segregating special case drums

is necessary to prevent personnel overexposures and

preclude environmental contamination; (8) applying rust inhibitor prolongs the useful life of waste containers stored

under earthen cover; (9) acoustic drum pressure detection

may be a viable tool in assessing elevated drum pressures.

452

(LA-UR–97-4632)

Systematic evaluation of options to avoid generation of

noncertifiable transuranic (TRU) waste at Los Alamos

National Laboratory. Boak, J.M.; Kosiewicz, S.T.; Triay, I.;

Gruetzmacher, K.; Montoya, A. Los Alamos National Lab.,

NM (United States). Mar 1998. 13p. Sponsored by USDOE

Office of Environmental Management, Washington, DC

(United States). DOE Contract W-7405-ENG-36. (CONF980307–: Waste management ’98, Tucson, AZ (United

States), 1-5 Mar 1998). Order Number DE98002933.

Source: OSTI; NTIS; INIS; GPO Dep.

At present, >35% of the volume of newly generated

transuranic (TRU) waste at Los Alamos National Laboratory

is not certifiable for transport to the Waste Isolation Pilot

Plant (WIPP). Noncertifiable waste would constitute 900–

1,000 m3 of the 2,600 m3 of waste projected during the

period of the Environmental Management (EM) Accelerated

Cleanup: Focus on 2006 plan (DOE, 1997). Volume expansion of this waste to meet thermal limits would increase the

shipped volume to 5,400 m3. This paper presents the results of efforts to define which TRU waste streams are

noncertifiable at Los Alamos, and to prioritize site-specific

options to reduce the volume of certifiable waste over the

period of the EM Accelerated Cleanup Plan. A team of Los

112
Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

Alamos TRU waste generators and waste managers reviewed historic generation rates and thermal loads and

current practices to estimate the projected volume and thermal load of TRU waste streams for Fiscal Years 1999–2006.

These data defined four major problem TRU waste streams.

Estimates were also made of the volume expansion that

would be required to meet the permissible wattages for all

waste. The four waste streams defined were: (1) 238Pucontaminated combustible waste from production of

Radioactive Thermoelectric Generators (RTGs) with 238Pu

activity which exceeds allowable shipping limits by 10–100X.

(2) 241Am-contaminated cement waste from plutonium recovery processes (nitric and hydrochloric acid recovery) are

estimated to exceed thermal limits by 3X. (3) 239Pucontaminated combustible waste, mainly organic waste

materials contaminated with 239Pu and 241Am, is estimated

to exceed thermal load requirements by a factor of 2X. (4)

Oversized metal waste objects, (especially gloveboxes),

cannot be shipped as is to WIPP because they will not fit in

a standard waste box or drum.

453

(LA-UR–97-4976)

Quality management in environmental programs: Los

Alamos National Laboratory’s approach. Maassen, L.;

Day, J.L. Los Alamos National Lab., NM (United States).

Mar 1998. 5p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE

Contract W-7405-ENG-36. (CONF-980354–: National environmental and standards integration ’98, Las Vegas, NV

(United States), 3-6 Mar 1998). Order Number

DE98004366. Source: OSTI; NTIS; INIS; GPO Dep.

Since its inception in 1943, Los Alamos National Laboratory’s (LANL’s) primary mission has been nuclear weapons

research and development, which involved the use of hazardous and radioactive materials, some of which were

disposed of onsite. LANL has established an extensive Environmental Restoration Project (Project) to investigate and

remediate those hazardous and radioactive waste disposal

sites. This paper describes LANL’s identification and resolution of critical issues associated with the integration and

management of quality in the Project.

454

(LA-UR–97-5185)

Synopsis of hydrologic data collected by waste management for characterization of unsaturated transport at

Area G. Vold, E. Los Alamos National Lab., NM (United

States). Mar 1998. 34p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States).

DOE Contract W-7405-ENG-36. Order Number

DE98004335. Source: OSTI; NTIS; INIS; GPO Dep.

Data which have been collected by Los Alamos National

Laboratory waste management for the hydrologic characterization of the subsurface at the low level radioactive waste

disposal facility, Area G, are reported and discussed briefly.

The data includes Unsaturated Flow Apparatus measurements of the unsaturated conductivity in samples from

borehole G-5. Analysis compares these values to the predictions from van Genuchten estimates, and the implications

for transport and data matching are discussed, especially at

the location of the Vapor Phase Notch (VPN). There, evaporation drives a significant vapor flux and the liquid flux

cannot be measured accurately by the UFA device. Data

also include hydrologic characterization of samples from

borehole G-5, Area G surface soils, Los Alamos (Cerros de

Rio) basalt, Tsankawi and Cerro-Toledo layers, the Vapor

Phase Notch (VPN), and additional new samples from the

uppermost tuff layer at Area G. Hydraulic properties from

these sample groups can be used to supplement the existing data base. The data in this report can be used to

improve the accuracy and reduce the uncertainty in future

computational modeling of the unsaturated transport at Area

G. This report supports the maintenance plan for the Area G

Performance Assessment.

455

(LA-UR–97-5186)

Synopsis of moisture monitoring by neutron probe in

the unsaturated zone at Area G. Vold, E. Los Alamos National Lab., NM (United States). 1997. 51p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract W-7405-ENG-36. Order

Number DE98004337. Source: OSTI; NTIS; INIS; GPO Dep.

Moisture profiles from neutron probe data provide valuable information in site characterization and to supplement

ground water monitoring efforts. The neutron probe precision error (reproducibility) is found to be about 0.2 vol%

under in situ field conditions where the slope in moisture

content with depth is varying slowly. This error is about 2

times larger near moisture spikes (e.g., at the vapor phase

notch), due to the sensitivity of the probe response to vertical position errors on the order of 0.5 inches. Calibrations

were performed to correct the downhole probe response to

the volumetric moisture content determined on core samples. Calibration is sensitive to borehole diameter and

casing type, requiring 3 separate calibration relations for the

boreholes surveyed here. Power law fits were used for calibration in this study to assure moisture content results

greater than zero. Findings in the boreholes reported here

confirm the broad features seen previously in moisture profiles at Area G, a near-surface region with large moisture

variability, a very dry region at greater depths, and a moisture spike at the vapor phase notch (VPN). This feature is

located near the interface between the vitrified and vitrified

stratigraphic units and near the base of the mesa. This report describes the in-field calibration methods used for the

neutron moisture probe measurements and summarizes

preliminary results of the monitoring program in the in-situ

monitoring network at Area G. Reported results include

three main areas: calibration studies, profiles from each of

the vertical boreholes at Area G, and time-dependent variations in a select subset of boreholes. Results are reported

here for the vertical borehole network. Results from the horizontal borehole network will be described when available.

456

(LA-UR–97-5202)

Synopsis of recent moisture flux analyses relevant to

the unsaturated zone at Area G. Vold, E. Los Alamos National Lab., NM (United States). Mar 1998. 56p. Sponsored

by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract W-7405-ENG-36.

Order Number DE98004332. Source: OSTI; NTIS; INIS;

GPO Dep.

This report summarizes selected recent analyses relevant

to the assessment of the site performance for disposal facilities at Los Alamos (Area G) regarding unsaturated zone

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

transport of moisture in liquid and vapor phases and the surface water balance. Much of the analyses methods have

been reported previously but in several separate and detailed reports. These do not always reflect the overview

possible with hindsight. The present report is an attempt to

integrate the author’s previous results into a cohesive

whole. Due to project time constraints, this report is incomplete in some area. This report first reviews the basis for the

Darcy flux analyses and its inherent uncertainties, as detailed in previous reports. Results from the previous works

are then reviewed and discussed and in some cases, elaborated in an attempt for clarification. New results of the Darcy

Flux Analyses are presented and discussed for Area G

mesa top locations, nearby canyon locations and a second

mesa top location (TA46 west of Area G). Select evapotranspiration and precipitation data from TA6 are presented and

discussed. The conclusions section draws a picture of the

hydrology which unifies the study results reported here and

in previous reports for the undisturbed and disturbed site locations.

457

(LA-UR–98-26)

New probability table treatment in MCNP for unresolved

resonances. Carter, L.L. (Carter M.C. Analysis, Richland,

WA (United States)); Little, R.C.; Hendricks, J.S.; MacFarlane, R.E. Los Alamos National Lab., NM (United States).

Apr 1998. 10p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE

Contract W-7405-ENG-36. (CONF-980403–: Radiation protection and shielding topical meeting: technologies for the

new century, Nashville, TN (United States), 19-23 Apr

1998). Order Number DE98005277. Source: OSTI; NTIS;

INIS; GPO Dep.

An upgrade for MCNP has been implemented to sample

the neutron cross sections in the unresolved resonance

range using probability tables. These probability tables are

generated with the cross section processor code NJOY, by

using the evaluated statistical information about the resonances to calculate cumulative probability distribution

functions for the microscopic total cross section. The elastic,

fission, and radiative capture cross sections are also tabulated as the average values of each of these partials

conditional upon the value of the total. This paper summarizes how the probability tables are utilized in this MCNP

upgrade and compares this treatment with the approximate

smooth treatment for some example problems.

458

(LA-UR–98-433)

Test plan for hydrogen getters project. Mroz, G. (Los

Alamos National Lab., NM (United States)); Weinrach, J.

Los Alamos National Lab., NM (United States);Benchmark

Environmental Corp., Albuquerque, NM (United States). 1

Apr 1998. 17p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE

Contract W-7405-ENG-36. Order Number DE98005930.

Source: OSTI; NTIS; INIS; GPO Dep.

Hydrogen levels in many transuranic (TRU) waste drums

are above the compliance threshold, therefore deeming the

drums non-shippable to the Waste Isolation Pilot Plant

(WIPP). Hydrogen getters (alkynes and dialkynes) are

known to react irreversibly with hydrogen in the presence of

certain catalysts. The primary purpose of this investigation is

to ascertain the effectiveness of a hydrogen getter in an environment that contains gaseous compounds commonly

found in the headspace of drums containing TRU waste. It

is not known whether the volatile organic compounds

(VOCs) commonly found in the headspace of TRU waste

drums will inhibit (poison) the effectiveness of the hydrogen

getter. The results of this study will be used to assess the

feasibility of a hydrogen-getter system, which is capable of

removing hydrogen from the payload containers or the

Transuranic package Transporter-II (TRUPACT-II) inner containment vessel to increase the quantity of TRU waste that

can be shipped to the WIPP.

459

(LA-UR–98-845)

Use of data fusion to optimize contaminant transport

predictions. Eeckhout, E. van. Los Alamos National Lab.,

NM (United States). Oct 1997. 17p. Sponsored by USDOE

Office of Environmental Management, Washington, DC

(United States). DOE Contract W-7405-ENG-36. Order

Number DE98006333. Source: OSTI; NTIS; INIS; GPO Dep.

The original data fusion workstation, as envisioned by

Coleman Research Corp., was constructed under funding

from DOE (EM-50) in the early 1990s. The intent was to

demonstrate the viability of fusion and analysis of data from

various types of sensors for waste site characterization, but

primarily geophysical. This overall concept changed over

time and evolved more towards hydrogeological (groundwater) data fusion after some initial geophysical fusion work

focused at Coleman. This initial geophysical fusion platform

was tested at Hanford and Fernald, and the later hydrogeological fusion work has been demonstrated at Pantex,

Savannah River, the US Army Letterkenny Depot, a DoD

Massachusetts site and a DoD California site. The hydrogeologic data fusion package has been spun off to a company

named Fusion and Control Technology, Inc. This package is

called the Hydrological Fusion And Control Tool (HydroFACT) and is being sold as a product that links with the

software package, MS-VMS (MODFLOW-SURFACT Visual

Modeling System), sold by HydroGeoLogic, Inc. MODFLOW

is a USGS development, and is in the public domain. Since

the government paid for the data fusion development at

Coleman, the government and their contractors have access

to the data fusion technology in this hydrogeologic package

for certain computer platforms, but would probably have to

hire FACT (Fusion and Control Technology, Inc.,) and/or HydroGeoLogic for some level of software and services.

Further discussion in this report will concentrate on the

hydrogeologic fusion module that is being sold as HydroFACT, which can be linked with MS-VMS.

460

(LA-UR–98-898)

Test plan for headspace gas sampling of remotehandled transuranic waste containers at Los Alamos

National Laboratory. Field, L.R. (Los Alamos National

Lab., NM (United States)); Villarreal, R. Los Alamos National Lab., NM (United States);Benchmark Environmental

Corp., Albuquerque, NM (United States). 24 Feb 1998. 31p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

W-7405-ENG-36. Order Number DE98006332. Source:

OSTI; NTIS; INIS; GPO Dep.

Seventeen remote-handled (RH) transuranic (TRU) waste

canisters currently are stored in vertical, underground shafts

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

at Technical Area (TA)-54, Area G, at Los Alamos National

Laboratory (LANL). These 17 RH TRU waste canisters are

destined to be shipped to the Waste Isolation Pilot Plant

(WIPP) for permanent disposal in the geologic repository.

As the RH TRU canister is likely to be the final payload container prior to placement into the 72-B cask and shipment to

the WIPP, these waste canisters provide a unique

opportunity to ascertain representative flammable gas concentrations in packaged RH-TRU waste. Hydrogen, which is

produced by the radiolytic decomposition of hydrogenous

constituents in the waste matrix, is the primary flammable

gas of concern with RH TRU waste. The primary objectives

of the experiment that is described by this test plan are to

sample and analyze the waste canister headspace gases to

determine the concentration of hydrogen in the headspace

gas and to calculate the hydrogen gas generation rate for

comparison to the applicable maximum allowable hydrogen

generation rate (mole/sec) limits. It is a goal of this experiment to determine the headspace gas concentrations of

other gases (e.g., oxygen, nitrogen, carbon dioxide, carbon

monoxide, and volatile organic compounds (VOCs) with

molecular weights less than 60 g/mole) that are produced by

radiolysis or present when the waste was packaged. Additionally, the temperature, pressure, and flow rate of the

headspace gas will be measured.

461

(LA-UR–98-1450)

Draft test plan for hydrogen getters project. Mroz, G.

(Los Alamos National Lab., NM (United States)); Weinrach,

J. Los Alamos National Lab., NM (United

States);Benchmark Environmental Corp., Albuquerque, NM

(United States). 1 Apr 1998. 18p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States). DOE Contract W-7405-ENG-36. Order Number

DE99000861. Source: OSTI; NTIS; INIS; GPO Dep.

Hydrogen levels in many transuranic (TRU) waste drums

are above the compliance threshold, therefore deeming the

drums non-shippable to the Waste Isolation Pilot Plant

(WIPP). Hydrogen getters (alkynes and dialkynes) are

known to react irreversibly with hydrogen in the presence of

certain catalysts. The primary purpose of this investigation is

to ascertain the effectiveness of a hydrogen getter in an environment that contains gaseous compounds commonly

found in the headspace of drums containing TRU waste. It

is not known whether the volatile organic compounds

(VOCs) commonly found in the headspace of TRU waste

drums will inhibit (poison) the effectiveness of the hydrogen

getter. The results of this study will be used to assess the

feasibility of a hydrogen-getter system, which is capable of

removing hydrogen from the payload containers or the

Transuranic Package Transporter-II (TRUPACT-II) inner

containment vessel to increase the quantity of TRU waste

that can be shipped to the WIPP.

462

(LA-UR–98-1826)

Comparison of General Purpose Heat Source testing

with the ANSI N43.6-1977 (R1989) sealed source standard. Grigsby, C.O. Los Alamos National Lab., NM (United

States). 26 Mar 1998. [150p.] Sponsored by USDOE Office

of Environmental Management, Washington, DC (United

States). DOE Contract W-7405-ENG-36. Order Number

DE99001117. Source: OSTI; NTIS; INIS; GPO Dep.

This analysis provides a comparison of the testing of Radioisotope Thermoelectric Generators (RTGs) and RTG

components with the testing requirements of ANSI

N43.6-1977 (R1989) “Sealed Radioactive Sources, Categorization”. The purpose of this comparison is to demonstrate

that the RTGs meet or exceed the requirements of the ANSI

standard, and thus can be excluded from the radioactive inventory of the Chemistry and Metallurgy Research (CMR)

building in Los Alamos per Attachment 1 of DOE STD 1027-

92. The approach used in this analysis is as follows: (1)

describe the ANSI sealed source classification methodology;

(2) develop sealed source performance requirements for the

RTG and/or RTG components based on criteria from the accident analysis for CMR; (3) compare the existing RTG or

RTG component test data to the CMR requirements; and (4)

determine the appropriate ANSI classification for the RTG

and/or RTG components based on CMR performance requirements. The CMR requirements for treating RTGs as

sealed sources are derived from the radiotoxicity of the isotope (238P7) and amount (13 kg) of radioactive material

contained in the RTG. The accident analysis for the CMR

BIO identifies the bounding accidents as wing-wide fire, explosion and earthquake. These accident scenarios set the

requirements for RTGs or RTG components stored within

the CMR.

463

(LA-UR–98-2022)

Standard data report. 1997 annual report on waste generation and waste minimization progress. Wilburn, D. Los

Alamos National Lab., NM (United States). 7 Apr 1998. 25p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

W-7405-ENG-36. Order Number DE99000806. Source:

OSTI; NTIS; INIS; GPO Dep.

The Laboratory’s central mission of Reducing the Global

Nuclear Danger supports core competencies that enable the

Laboratory to contribute to defense, civilian, and industrial

needs. In turn, the intellectual challenges of civilian and industrial problems strengthen and help support the core

competencies required for the national security mission. The

ability to do great science underpins all of the applied work.

There are five core competencies which support this mission: (1) Stockpile Stewardship ensures the US has safe,

secure and reliable nuclear weapons; (2) Stockpile Management provides capabilities ranging from dismantling to

remanufacturing of the enduring stockpile; (3) Nuclear

Materials Management ensures the availability and safe disposition of plutonium, highly enriched uranium, and tritium;

(4) Nonproliferation and Counterproliferation help to deter,

detect, and respond to the proliferation of weapons of mass

destruction; and (5) Environmental Stewardship provides for

the remediation and reduction of wastes from the nuclear

weapons complex. This report contains data on volumes of

waste generated as part of routine and cleanup/stabilization

activities of the lab.

464

(LA-UR–98-2130)

Gas generation matrix depletion quality assurance

project plan. Los Alamos National Lab., NM (United

States). 1 May 1998. 27p. Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract W-7405-ENG-36. Order Number

DE99000811. Source: OSTI; NTIS; INIS; GPO Dep.

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

The Los Alamos National Laboratory (LANL) is to provide

the necessary expertise, experience, equipment and instrumentation, and management structure to: Conduct the

matrix depletion experiments using simulated waste for

quantifying matrix depletion effects; and Conduct experiments on 60 cylinders containing simulated TRU waste to

determine the effects of matrix depletion on gas generation

for transportation. All work for the Gas Generation Matrix

Depletion (GGMD) experiment is performed according to the

quality objectives established in the test plan and under this

Quality Assurance Project Plan (QAPjP).

465

(LBL–38024)

Susceptibility of polysiloxane and colloidal silica to

degradation by soil microorganisms. Lundy, D.Z.

(Lawrence Berkeley National Lab., CA (United States).

Earth Sciences Div.); Hunter-Cevera, J.C.; Moridis, G.J.

Lawrence Berkeley National Lab., CA (United States). Nov

1997. 68p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract AC03-76SF00098. Order Number DE98051514.

Source: OSTI; NTIS; GPO Dep.

This report is a description of the laboratory study undertaken to determine the biodegradability of Colloidal Silica

(CS) and PolySiloXane (PSX), a new generation of barrier

liquids employed by the Viscous Liquid Barrier (VLB) technology in the containment of subsurface contaminants.

Susceptibility of either material to microbial degradation

would suggest that the effectiveness of a barrier in the subsurface may deteriorate over time. Degradation may result

from several different biological events. Organisms may

consume the material as a carbon and/or energy source,

organisms may chemically change the material as a detoxification mechanism, or organisms may erode the material by

their physical penetration of the material during growth. To

determine if degradation occurs, physical interactions

between soil microbes and the barrier materials were analyzed, and the metabolic activity of individual organisms in

the presence of CS and PSX was measured.

466

(LBNL–40939)

Literature search on the use of resins for treatment of

radioactive wastes. AlMahamid, I.; Smith, B.M. Lawrence

Berkeley National Lab., CA (United States). Oct 1997. 14p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC03-76SF00098. Order Number DE98052314. Source:

OSTI; NTIS; INIS; GPO Dep.

Over 100 commercial providers with mixed-waste treatability capabilities exist in the US. The maturity level of these

technologies varies from a bench scale to a pilot or a commercial scale. The techniques include deactivation, chemical

oxidation, recovery of metals, stabilization, vitrification, incineration, biodegradation, and chemical extraction. This report

focuses on the use of resins to remove actinides and heavy

metals from aqueous waste streams. Only the literature that

described resins with high removing efficiency are presented

here. The majority of the literature reviewed are proceedings

and national or international reports ordered through the

Berkeley Lab Library. Some of the reports that the authors

requested have not yet arrived. Only a few papers were

found in the open literature (journals or magazines). Although this report does not include all existing references, it

provides an accurate assessment of efficient resins to be

considered for waste minimization procedures. 70 refs.

467

(LBNL–41192)

Environmental Management Science Program awards.

Fiscal year 1997 annual progress report. Simmons, A.

(ed.); Benner, W.H.; DePaolo, D.J.; Faybishenko, B.; Majer,

E.L.; Pallavicini, M.; Russo, R.E.; Shultz, P.G.; Wan, J.

Lawrence Berkeley National Lab.,Berkeley, CA (United

States). Oct 1997. 61p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States).

DOE Contract AC03-76SF00098. Order Number

DE98056098. Source: OSTI; NTIS; INIS; GPO Dep.

Lawrence Berkeley National Laboratory was awarded

eight Environmental Management Science Program (EMSP)

research grants in Fiscal Year 1996. This report summarizes

the progress of each grant in addressing significant DOE site

cleanup issues after completion of the first year of research.

The technical progress made to date in each of the research

projects is described in greater detail in individual progress

reports. The focus of the research projects covers a diversity

of areas relevant to site cleanup, including bioremediation,

health effects, characterization, and mixed waste. Some of

the projects cut across a number of focus areas. Three of

the projects are directed toward characterization and monitoring at the Idaho National Engineering and Environmental

Laboratory, as a test case for application to other sites.

468

(LBNL–41454)

What does a tensiometer measure in fractured rock?.

Finsterle, S.; Faybishenko, B. Lawrence Berkeley National

Lab., CA (United States). Feb 1998. 14p. Sponsored by USDOE Office of Environmental Management, Washington, DC

(United States). DOE Contract AC03-76SF00098. (CONF9710205–: Characterization and measurement of the

hydraulic properties of unsaturated porous media, Riverside,

CA (United States), 22-24 Oct 1997). Order Number

DE98052894. Source: OSTI; NTIS; GPO Dep.

Tensiometers are routinely used in both the laboratory

and the field for measuring the capillary pressure in unsaturated porous media. The authors conducted a laboratory

experiment on a fractured basalt core. They also examined

the performance of a tensiometer in fractured porous media

by means of numerical simulation, in which the tensiometer

itself and its interaction with the formation were explicitly

modeled. They conclude that the gauge pressure is primarily affected by the fracture rock component fracture or matrix

that conducts water into or out of the ceramic cup of the tensiometer. Fracture flow is accurately monitored during

imbibition events, whereas during drainage, the matrix capillary pressure is registered, leading to a strong hysteretic

behavior in the pressure measurements.

469

(LBNL–41920)

Numerical modeling of field tests in unsaturated fractured basalt at the Box Canyon site. Doughty, C.

Lawrence Berkeley National Lab., Earth Sciences Div.,

Berkeley, CA (United States). May 1998. 8p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract AC03-76SF00098.

(CONF-980559–: TOUGH ’98 workshop, Berkeley, CA

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

(United States), 4-6 May 1998). Order Number

DE98058300. Source: OSTI; INIS; NTIS; GPO Dep.

A TOUGH2 model of a ponded infiltration test has been

developed and used to predict the results of a field experiment conducted in the vadose zone of the fractured Snake

River Plain basalts, at the Box Canyon site in southeastern

idaho. The key question addressed is how fracture-pattern

characteristics and connectivity affect the pattern of liquid infiltration. The numerical model, a two-dimensional vertical

cross-section, uses half-meter discretization for the shallow

field site, which extends about 20 m from the ground surface

to an underlying perched water body. The model includes

explicit but highly simplified representations of major fractures and other important hydrological features. It adequately

reproduces the majority of the field observations, confirming

the notion that infiltration is largely fracture-controlled.

470

(ORNL/CP–93287)

Laboratory stabilization/solidification of surrogate and

actual mixed-waste sludge in glass and grout. Spence,

R.D.; Gilliam, T.M.; Mattus, C.H.; Mattus, A.J. Oak Ridge

National Lab., TN (United States). 3 Mar 1998. 31p. Sponsored by USDOE Office of Environmental Management,

Washington, DC (United States). DOE Contract AC05-

96OR22464. (CONF-980318–: 1998 American Institute of

Chemical Engineers (AIChE) spring meeting, New Orleans,

LA (United States), 8-12 Mar 1998). Order Number

DE98004885. Source: OSTI; NTIS; INIS; GPO Dep.

Grouting and vitrification are currently the most likely stabilization/solidification technologies for mixed wastes.

Grouting has been used to stabilize and solidify hazardous

and low-level waste for decades. Vitrification has long been

developed as a high-level-waste alternative and has been

under development recently as an alternative treatment

technology for low-level mixed waste. Laboratory testing has

been performed to develop grout and vitrification formulas

for mixed-waste sludges currently stored in underground

tanks at Oak Ridge National Laboratory (ORNL) and to

compare these waste forms. Envelopes, or operating windows, for both grout and soda-lime-silica glass formulations

for a surrogate sludge were developed. One formulation

within each envelope was selected for testing the sensitivity

of performance to variations (10 wt%) in the waste form

composition and variations in the surrogate sludge composition over the range previously characterized in the sludges.

In addition, one sludge sample of an actual mixed-waste

tank was obtained, a surrogate was developed for this

sludge sample, and grout and glass samples were prepared

and tested in the laboratory using both surrogate and the

actual sludge. The sensitivity testing of a surrogate tank

sludge in selected glass and grout formulations is discussed

in this paper, along with the hot-cell testing of an actual tank

sludge sample.

471

(ORNL/CP–94788)

Distribution of Fatty Acids and Triethanolamine in Synthetic Metalworking Fluid Aerosols Generated in the

Laboratory and Field. Ilgner, R.H., Palausky, A., Jenkins,

R.A. (Oak Ridge National Lab., TN (United States) Chemical

and Analytical Sciences Div.). Oak Ridge National Lab., TN

(United States). [1997]. 10p. Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract AC05-96OR22464. (CONF9709112–: Conference on the industrial metalworking

environment: assessment and control of metal removal

fluids, Detroit, MI (United States), 15 Sep 1997). Order Number DE98000702. Source: OSTI; NTIS; INIS; GPO Dep.

[540 409900].

Metalworking fluid mists were generated in the laboratory

with selected synthetic fluids by nebulization and with an air

sparging apparatus. Short chain fatty acid species were determined in the vapor and particulate phase of the resulting

aerosols using in-situ trimethyl silyl derivatization. Certain

fatty acid species in sparger generated mists were found in

the vapor phase in greater quantities relative to the particle

phase, compared with the corresponding amounts determined in nebulized mists. With one metalworking fluid, the

nonanoic acid vapor phase to particulate phase concentration ratio was over 14 fold higher with air sparged mists

(1.0) than with the corresponding nebulized mists (0.07).

The nonanoic acid vapor phase concentrations were 0.026

mg/m3 and 0.002 mg/m3 for sparged (bubbled) and nebulized mists respectively. This phenomenon was observed

with mists generated from several selected synthetic metalworking fluids. This could suggest that in the work place

environment, with a variety of mist generation mechanisms

occurring simultaneously, significant vapor phase concentrations of certain species could exist in an environment where

particulate levels are low. Vapor phase fatty acid levels could

remain relatively high in an occupational setting even when

mist levels are reduced with efficient air cleaning devices.

Results from mist generation experiments performed in the

laboratory, were compared with actual field data from a relatively clean metal machining operation. Anecdotal evidence

of potential irritation by short chain fatty acids prompted a

study of this industrial site. Numerous air scrubbing devices

were utilized at this industrial site to reduce airborne particulates, which typically ranged from 0.05 to 0.4 mg/m3.

Comparisons were made of triethanolamine and short chain

fatty acid concentrations in vapor and particulate phases

measured in the laboratory and work place environment.

472

(ORNL/CP–94841)

Basic and Acidic Leaching of Sludge from Melton Valley

Storage Tank W-25. Collins, J.L., Egan, B.Z., Beahm, E.C.,

Chase, C.W., Anderson, K.K. Oak Ridge National Lab., TN

(United States). Oct 1997. 33p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States). DOE Contract AC05-96OR22464. (CONF9710103–: 10. symposium on separation science and

technology for energy applications, Gatlinburg, TN (United

States), 20-24 Oct 1997). Order Number DE98000680.

Source: OSTI; NTIS; INIS; GPO Dep.

[540 549000].

Bench-scale leaching tests were conducted with samples

of tank waste sludge from the Melton Valley Storage Tank

(MVST) Facility at Oak Ridge National Laboratory (ORNL) to

evaluate separation technology processes for use in concentrating the radionuclides and reducing the volume of

waste for final disposal. This paper discusses the hot cell

apparatus, the characterization of the sludge, the leaching

methodology, and the results obtained from a variety of

basic and acidic leaching tests of samples of sludge at ambient temperature. Basic leaching tests were also conducted

at 75 and 95 deg C. The major alpha-,gamma., and betaemitting radionuclides in the centrifuged, wet sludge solids

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

were 137Cs, 60Co, 154Eu, 241Am, 244Cm 90Sr, Pu, U, and Th.

The other major metals (in addition to the U and Th) and anions were Na, Ca, Al, K, Mg, NO3

,CO32, OH, and O2

organic carbon content was 3.0 +/- 1.0%. The pH was 13. A

surprising result was that about 93% of the 137Cs in the centrifuged, wet sludge solids was bound in the solids and

could not be solubilized by basic leaching at ambient temperature and 75 deg C. However, the solubility of the 137Cs

was enhanced by heating the sludge to 95 deg C. In one of

the tests,about 42% of the 137Cs was removed by leaching

with 6.3 M NaOH at 95 deg C.Removing 137Cs from the W25 sludge with nitric acid was a slow process. About 13% of

the 137Cs was removed in 16 h with 3.0 M HNO3. Only 22%

of the 137Cs was removed in 117 h usi 6.0 M HNO3. Successive leaching of sludge solids with 0.5 M, 3.0 M, 3.0 M; and

6.0 M HNO3 for a total mixing time of 558 h removed 84%

of the 137Cs. The use of caustic leaching prior to HNO3

leaching, and the use of HF with HNO3 in acidic leaching,

increased the rate of 137Cs dissolution. (Abstract truncated)

473

(ORNL/CP–94912)

Cesium removal from high-pH, high-salt wastwater using crystalline silicotitanate sorbent. Walker, J.F. Jr.;

Taylor, P.A.; Lee, D.D. Oak Ridge National Lab., TN (United

States). 1997. 23p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE

Contract AC05-96OR22464. (CONF-9710103–: 10. symposium on separation science and technology for energy

applications, Gatlinburg, TN (United States), 20-24 Oct

1997). Order Number DE98001055. Source: OSTI; NTIS;

GPO Dep.

Treatment and disposal options for Department of Energy

(DOE) underground storage tank waste at Hanford, Savannah River, and Oak Ridge National Laboratory (ORNL) are

limited by high gamma radiation fields that are produced by

high concentrations of cesium in the waste. Treatment methods are needed to remove the cesium from the liquid waste

and thus concentrate the cesium into high-activity, remotehandled waste forms. The treated liquids could then be

processed and disposed of by more cost-effective means

with less radiation exposure to workers. A full-scale demonstration of one cesium removal technology is currently being

conducted at ORNL. This demonstration utilizes a modular,

mobile ion-exchange system and existing facilities for the

off-gas system, secondary containment, and utilities. The

ion-exchange material, crystalline silicotitanate (CST), was

chosen on the basis of its effectiveness in laboratory tests.

The CST, which was developed through a Cooperative Research and Development Agreement between DOE and

private industry, has several advantages over current organic ion-exchange technologies. These advantages include

(1) the ability to remove cesium in the presence of high concentrations of potassium, (2) a high affinity for cesium in

both alkaline and acidic conditions, (3) physical stability over

wide alkaline and acidic ranges, and (4) the elimination of

large volumes of secondary waste required for regeneration

of organic ion exchangers. Approximately 100,000 L of

wastewater will be processed during the demonstration. The

wastewater being processed has a high salt content, about

4 M NaNO3, and a pH of 12 to 13. This paper discusses the

results of the full-scale demonstration and compares these

results with data from the laboratory tests.

474

(ORNL/CP–94960)

Magnetic-seeding filtration. Ying, T.Y. (Georgia Institute of

Technology, Atlanta, GA (United States). School of Civil and

Environmental Engineering); Chin, C.J.; Lu, S.C.; Yiacoumi,

S. Oak Ridge National Lab., TN (United States). Oct 1997.

32p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC05-96OR22464. (CONF-9710103–: 10. symposium on

separation science and technology for energy applications,

Gatlinburg, TN (United States), 20-24 Oct 1997). Order

Number DE98001054. Source: OSTI; NTIS; INIS; GPO Dep.

Magnetic-seeding filtration consists of two steps: heterogeneous particle flocculation of magnetic and nonmagnetic

particles in a stirred tank and high-gradient magnetic filtration (HGMF). The effects of various parameters affecting

magnetic-seeding filtration (HGMF). The effects of various

parameters affecting magnetic seeding filtration are theoretically and experimentally investigated. A trajectory model

that includes hydrodynamic resistance, van der Waals, and

electrostatic forces is developed to calculate the flocculation

frequency in a turbulent-shear regime. Fractal dimension is

introduced to simulate the open structure of aggregates. A

magnetic-filtration model that consists of trajectory analysis,

a particle build-up model, a breakthrough model, and a bivariate population-balance model is developed to predict the

breakthrough curve of magnetic-seeding filtration. A good

agreement between modeling results and experimental data

is obtained. The results show that the model developed in

this study can be used to predict the performance of

magnetic-seeding filtration without using empirical coefficients or fitting parameters. 35 refs., 7 figs., 1 tab.

475

(ORNL/CP–94962)

Distillation under electric fields. Shah, V.M. (Univ. of

Tennessee, Knoxville, TN (United States). Chemical Engineering Dept.); Blankenship, K.D.; Tsouris, C. Oak Ridge

National Lab., TN (United States). 1997. 24p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract AC05-96OR22464.

(CONF-9710103–: 10. symposium on separation science

and technology for energy applications, Gatlinburg, TN

(United States), 20-24 Oct 1997). Order Number

DE98001053. Source: OSTI; NTIS; GPO Dep.

Distillation Is the most common separation process used

in the chemical and petroleum industry. Major limitations in

the applicability and efficiency of distillation come from thermodynamic equilibria, that is, vapor-liquid equilibria (VLE),

and heat and mass transfer rates. In this work, electric fields

are used to manipulate the VLE of mixtures. VLE experiments are performed for various binary mixtures in the

presence of electric fields on the order of a few kilovolts per

centimeter. The results show that the VLE is changed by

electric fields, with changes in the separation factor as high

as 10% being observed. Batch distillation experiments are

also carried out for binary mixtures of 2-propanol and water

with and without an applied electric field. Results show enhanced distillation rates and separation efficiency in the

presence of an electric field but decreased separation enhancement when the electric current is increased. The latter

phenomenon is caused by the formation at the surface of

the liquid mixture of microdroplets that are entrained by the

vapor. These observations suggest that there should be an

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

electric field strength for each system for which the separation enhancement is maximum.

476

(ORNL/CP–95082)

Topographical mapping system for radiological and hazardous environments acceptance testing. Armstrong,

G.A. (Oak Ridge National Lab., TN (United States)); Dochat,

G.R. Oak Ridge National Lab., TN (United States). [1997].

14p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC05-96OR22464 ; AC05-84OR21400. (CONF-971086–:

SPIE’s intelligent systems and advanced manufacturing

symposium: microrobotics and microsystem fabrication conference, Pittsburgh, PA (United States), 14-17 Oct 1997).

Order Number DE98000800. Source: OSTI; NTIS; INIS;

GPO Dep.

During the summer of 1996, the Topographical Mapping

System (TMS) for hazardous and radiological environments

and its accompanying three-dimensional (3-D) visualization

tool, the Interactive Computer-Enhanced Remote-Viewing

System (ICERVS), were delivered to Oak Ridge National

Laboratory (ORNL). ORNL and Mechanical Technology,

Inc., performed final acceptance testing of the TMS during

the next eight months. The TMS was calibrated and characterized during this period. This paper covers the calibration,

characterization, and acceptance testing of the TMS. Development of the TMS and ICERVS was initiated by the US

Department of Energy (DOE) for the purpose of characterization and remediation of underground storage tanks (USTs)

at DOE sites across the country. DOE required a 3-D, topographical mapping system suitable for use in hazardous and

radiological environments. The intended application is the

mapping of the interior of USTs as part of DOE’s waste

characterization and remediation efforts and to obtain baseline data on the content of the storage tank interiors as well

as data on changes in the tank contents and levels brought

about by waste remediation steps. Initially targeted for

deployment at the Hanford Washington site, the TMS is designed to be a self-contained, compact, and reconfigurable

system that is capable of providing rapid, variable-resolution

mapping information in poorly characterized workspaces

with a minimum of operator intervention.

477

(ORNL/CP–95423)

Advanced hydraulic fracturing methods to create in situ

reactive barriers. Murdoch, L. (FRX Inc., Cincinnati, OH

(United States)); Siegrist, B.; Meiggs, T. Oak Ridge National

Lab., TN (United States). 1997. 9p. Sponsored by USDOE

Office of Environmental Management, Washington, DC

(United States). DOE Contract AC05-96OR22464. (CONF970208–: International containment technology conference

and exhibition, St. Petersburg, FL (United States), 9-12 Feb

1997). Order Number DE98001942. Source: OSTI; NTIS;

INIS; GPO Dep.

This article describes the use of hydraulic fracturing to increase permeability in geologic formations where in-situ

remedial action of contaminant plumes will be performed.

Several in-situ treatment strategies are discussed including

the use of hydraulic fracturing to create in situ redox zones

for treatment of organics and inorganics. Hydraulic fracturing

methods offer a mechanism for the in-situ treatment of gently dipping layers of reactive compounds. Specialized

methods using real-time monitoring and a high-energy jet

during fracturing allow the form of the fracture to be influenced, such as creation of assymmetric fractures beneath

potential sources (i.e. tanks, pits, buildings) that should not

be penetrated by boring. Some examples of field applications of this technique such as creating fractures filled with

zero-valent iron to reductively dechlorinate halogenated hydrocarbons, and the use of granular activated carbon to

adsorb compounds are discussed.

478

(ORNL/CP–95593)

Real-time, automated characterization of surfaces for alpha and beta radiation. Egidi, P.V. (Oak Ridge National

Lab., Grand Junction, CO (United States). Environmental

Technology Section); Flynn, C.R.; Blair, M.S.; Selfridge, R.J.

Oak Ridge National Lab., Grand Junction, CO (United

States). [1997]. 7p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE

Contract AC05-96OR22464. (CONF-971222–: Exchange

1997, Miami, FL (United States), 4 Dec 1997). Order Number DE98001926. Source: OSTI; NTIS; INIS; GPO Dep.

A new data collection system, called ABACUS, has

been developed that automates and expedites the collection, conversion, and reporting of radiological survey data of

surfaces. Field testing of the system by Oak Ridge National

Laboratory/Environmental Technology Section is currently

underway. Preliminary results are presented. The system

detects, discriminates, and separately displays the results

for alpha and beta contamination scans on floors and walls

with a single pass. Fixed-position static counting is also possible for quantitative measuring. The system is currently

configured with five 100 cm2 dual-phosphor plastic scintillation detectors mounted in a lightweight aluminum fixture that

holds the detectors in a fixed array. ABACUS can be configured with other detectors if desired. Ratemeter/scalars

traditionally coupled to individual detectors have been replaced by a single unit that houses the power supply and

discriminator circuit boards to support up to five detectors.

The system is designed to be used by a single operator.

Each detector’s position and data are transmitted once per

second and recorded on a nearby laptop computer. The

data are converted to appropriate units, color-coded, and

mapped to display graphically the findings for each detector

in real-time. Reports can be generated immediately following the survey. Survey data can be exported in a variety of

formats. Benefits of ABACUS are: (1) immediate feedback

to decision makers using the observational approach to

characterization or remediation, (2) thorough documentation

of survey results, (3) increased statistical confidence in

scans by recording counts every second, (4) reduced paperwork and elimination of transcription errors, and (5) time and

cost savings for collection, conversion, mapping, evaluating,

and reporting data over traditional methods.

479

(ORNL/CP–95756)

Technological and economic update on the nitrate to

ammonia and ceramic process. Mattus, A.J. Oak Ridge

National Lab., Chemistry Div., TN (United States). May

1998. 7p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract AC05-96OR22464. (CONF-980905–: SPECTRUM ’98:

nuclear and hazardous waste management international

topical meeting, Denver, CO (United States), 13-18 Sep

119
ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

1998). Order Number DE98001903. Source: OSTI; NTIS;

INIS; GPO Dep.

The Nitrate to Ammonia and Ceramic (NAC) process,

which was developed several years ago at the Oak Ridge

National Laboratory (ORNL), still remains relatively unknown. This is despite its simplicity in converting nitrate or

nitrite to ammonia gas at high efficiency while forming a very

useful hydrated alumina-based solid that binds most metals

and nonmetals. Two recent Department of Energy (DOE)-

contracted total life-cycle cost analyses, related to treating

nitrate-based wastes at Hanford, Savannah River, and Oak

Ridge, have shown that the NAC technology is only onethird to one-fourth the cost of vitrification, electroreduction,

steam reforming, and plasma arc.

480

(ORNL/CP–96319)

Mixed Waste Focus Area Mercury Working Group: An

integrated approach to mercury waste treatment and

disposal. Conley, T.B.; Morris, M.I.; Osborne-Lee, I.W. Oak

Ridge National Lab., TN (United States). Jan 1998. 15p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC05-96OR22464. (CONF-980307–: Waste management

’98, Tucson, AZ (United States), 1-5 Mar 1998). Order Number DE98004116. Source: OSTI; INIS; NTIS; GPO Dep.

In May 1996, the US Department of Energy (DOE) Mixed

Waste Focus Area (MWFA) initiated the Mercury Working

Group (HgWG). The HgWG was established to address and

resolve the issues associated with mercury contaminated

mixed wastes. During the MWFA’s initial technical baseline

development process, three of the top four technology

deficiencies identified were related to the need for amalgamation, stabilization, and separation removal technologies

for the treatment of mercury and mercury contaminated

mixed waste. The HgWG is assisting the MWFA in soliciting,

identifying, initiating, and managing efforts to address these

areas. The focus of the HgWG is to better establish the mercury related treatment technologies at the DOE sites, refine

the MWFA technical baseline as it relates to mercury treatment, and make recommendations to the MWFA on how to

most effectively address these needs. Based on the scope

and magnitude of the mercury mixed waste problem, as defined by HgWG, solicitations and contract awards have been

made to the private sector to demonstrate both the amalgamation and stabilization processes using actual mixed

wastes. Development efforts are currently being funded that

will address DOE’s needs for separation removal processes.

This paper discusses the technology selection process, development activities, and the accomplishments of the HgWG

to date through these various activities.

481

(ORNL/CP–96394)

Removal of chlorinated and non-chlorinated alkanes in

a trickle-bed biofilter. Klasson, K.T.; Davison, B.H.; Barton, J.W.; Jacobs, J.E. Oak Ridge National Lab., TN (United

States). Jan 1998. 15p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States).

DOE Contract AC05-96OR22464. (CONF-980632–: 91.

annual meeting and exhibition of the Air and Waste Management Association, San Diego, CA (United States), 14-19

Jun 1998). Order Number DE98004265. Source: OSTI;

NTIS; GPO Dep.

Increasing restrictions in emissions from a variety of

industrial settings demand low cost removal of dilute contaminants in air. Many of these contaminants such as

volatile organic components (VOCs) and sulfur compounds

are biodegradable and can be removed from air streams via

biofiltration. The simplest form of biofiltration consists of

compost-based systems. More advanced systems designed

for unique contaminants are biofilters with bioactive

structured packing operating in trickle-bed mode. These advanced systems rely on a microbial consortium capable of

degrading the contaminants of concern and the consortium

usually is isolated or enriched from a more complex microbial mixture. This paper describes the use of a trickle-bed

reactor seeded with a microbial consortium enriched from a

methanotrophic culture. The microbial consortium has been

found to degrade chlorinated alkanes as the sole carbon

source. Degradation rates of alkane mixtures are presented

for the trickle-bed as well as results from batch cultures

experiments designed to study degradation of various chlorinated and non-chlorinated VOCs.

482

(ORNL/CP–96463)

Development and testing of spheroidal inorganic sorbents. Collins, J.L.; Anderson, K.K. Oak Ridge National

Lab., TN (United States). 29 Jan 1998. 10p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States);USDOE Office of Energy Research,

Washington, DC (United States). DOE Contract AC05-

96OR22464. (CONF-980335–: Efficient separations and

processing crosscutting program technical exchange meeting, Augusta, GA (United States), 17-19 Mar 1998). Order

Number DE98004055. Source: OSTI; NTIS; INIS; GPO Dep.

The general objectives of this task are to develop, prepare, and test spheroidal inorganic ion exchangers made by

the HMTA (hexamethylenetetramine) internal gelation process to remove radionuclides and heavy metals from waste

streams occurring at the various DOE sites. Inorganic ionexchange materials, such as sodium silicotitanate, sodium

titanate, ammonium molybdeophosphate, phosphotungstic

acid, hexacyanoferrates, titanium monohydrogen phosphate,

hydrous titanium oxide, polyantimonic acid, magnesium

oxide, etc. have high selectivities and efficiencies for separating and removing radionuclides (e.g., cesium, strontium,

technetium, iodine, europium, cerium, ruthenium, and zirconium), actinides, and other elements (such as lead, mercury,

silver, nickel, zinc, chromium, and fluoride) from aqueous

waste streams. The development of cesium specific spherical sorbents for treatment of acidic, high-salt waste solutions

was initiated in FY 1998. Acid-side treatment is important at

INEEL and could become important if acidic sludge washing

were to become a treatment option at Hanford, Savannah

River, or Oak Ridge. Zirconium monohydrogen phosphates

(ZrHP) embedded with ammonium molybdophosphate

(AMP) was the cesium selective inorganic sorbent chosen

for making microspheres. AMP is known to be a very effective sorbent for removing cesium from waste streams over a

wide range of acidity and salinity, and it has very rapid loading kinetics. The cesium can also be eluted from AMP with

ammonium salt solutions. AMP cannot be used as a sorbent

at pHs above 7 because it decomposes. In the pH range of

1 to 7, ZrHP is also a very effective sorbent for removing

Cs, Sr, Th, U(VI), Pu(IV), AM(III), Hg, and Pb from streams

of lower ionic concentrations.

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

483

(ORNL/CP–96538)

Reprocessing of Shallow Seismic Reflection Data to Image Faults Near a Hazardous Waste Site on the Oak

Ridge Reservation, Tennessee. Doll, W.E. Oak Ridge National Lab., TN (United States). 1997. 12p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract AC05-96OR22464.

(CONF-980336–: Symposium on application of geophysics

to engineering and environmental problems, Chicago, IL

(United States), 22-26 Mar 1998). Order Number

DE98004121. Source: OSTI; NTIS; GPO Dep.

Shallow seismic reflection data from Bear Creek Valley on

the Oak Ridge Reservation demonstrates that spectral balancing and tomographic refraction statics can be important

processing tools for shallow seismic data. At this site, reprocessing of data which had previously yielded no usable

CMP stacked sections was successful after application of

these processing techniques.

484

(ORNL/CP–97018)

Fission product solvent extraction. Moyer, B.A. (and others); Bonnesen, P.V.; Sachleben, R.A. Oak Ridge National

Lab., TN (United States);Argonne National Lab., IL (United

States);Pacific Northwest National Lab., Richland, WA

(United States);Lockheed Martin Idaho Technologies Co.,

Idaho National Engineering and Environmental Lab., Idaho

Falls, ID (United States). Feb 1998. 9p. Sponsored by USDOE Office of Environmental Management, Washington, DC

(United States). DOE Contract AC05-96OR22464 ; W31109-ENG-38 ; AC06-76RL01830 ; AC07-94ID13223.

(CONF-980335–: Efficient separations and processing

crosscutting program technical exchange meeting, Augusta,

GA (United States), 17-19 Mar 1998). Order Number

DE98003392. Source: OSTI; NTIS; INIS; GPO Dep.

Two main objectives concerning removal of fission products from high-level tank wastes will be accomplished in this

project. The first objective entails the development of an

acid-side Cs solvent-extraction (SX) process applicable to

remediation of the sodium-bearing waste (SBW) and dissolved calcine waste (DCW) at INEEL. The second objective

is to develop alkaline-side SX processes for the combined

removal of Tc, Cs, and possibly Sr and for individual separation of Tc (alone or together with Sr) and Cs. These

alkaline-side processes apply to tank wastes stored at Hanford, Savannah River, and Oak Ridge. This work exploits

the useful properties of crown ethers and calixarenes and

has shown that such compounds may be economically

adapted to practical processing conditions. Potential benefits for both acid- and alkaline-side processing include

order-of-magnitude concentration factors, high rejection of

bulk sodium and potassium salts, and stripping with dilute

(typically 10 mM) nitric acid. These benefits minimize the

subsequent burden on the very expensive vitrification and

storage of the high-activity waste. In the case of the

SRTALK process for Tc extraction as pertechnetate anion

from alkaline waste, such benefits have now been proven at

the scale of a 12-stage flowsheet tested in 2-cm centrifugal

contactors with a Hanford supernatant waste simulant.

SRTALK employs a crown ether in a TBP-modified aliphatic

kerosene diluent, is economically competitive with other applicable separation processes being considered, and has

been successfully tested in batch extraction of actual Hanford double-shell slurry feed (DSSF).

485

(ORNL/CP–97092)

Completion of the Radioactive Materials Packaging

Handbook. Shappert, L.B. Oak Ridge National Lab., TN

(United States). Feb 1998. 11p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States). DOE Contract AC05-96OR22464. (CONF-980507–:

PATRAM ’98: 12. international conference on packaging

and transportation of radioactive material, Paris (France),

10-15 May 1998). Order Number DE98004984. Source:

OSTI; NTIS; INIS; GPO Dep.

The Radioactive Materials Packaging Handbook: Design,

Operation and Maintenance, which will serve as a replacement for the Cask Designers Guide (Shappert, 1970), has

now been completed and submitted to the Oak Ridge National Laboratory (ORNL) electronics publishing group for

layout and printing; it is scheduled to be printed in late

spring 1998. The Handbook, written by experts in their particular fields, is a compilation of technical chapters that

address the design aspects of a package intended for transporting radioactive material in normal commerce; it was

prepared under the direction of M. E. Wangler of the US Department of Energy (DOE) and is intended to provide a

wealth of technical guidance that will give designers a better

understanding of the regulatory approval process, preferences of regulators on specific aspects of package design,

and the types of analyses that should be considered when

designing a package to carry radioactive materials.

486

(ORNL/CP–97102)

Predictive mathematical modeling of trickling bed biofilters for elucidating mass transfer and kinetic effects.

Barton, J.W.; Zhang, X.S.; Klasson, K.T.; Davison, B.H. Oak

Ridge National Lab., TN (United States). Mar 1998. 23p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). (CONF-980632–:

91. annual meeting and exhibition of the Air and Waste

Management Association, San Diego, CA (United States),

14-19 Jun 1998). Order Number DE98004893. Source:

OSTI; NTIS; GPO Dep.

Mathematical models of varying complexity have been

proposed in the open literature for describing uptake of

volatile organics in trickling bed biofilters. Many simpler descriptions yield relatively accurate solutions, but are limited

as predictive tools by numerous assumptions which decrease the utility of the model. Trickle bed operation on the

boundary between mass transfer and kinetic limitation

regimes serves as one example in which these models may

be insufficient. One-dimensional models may also fail to

consider important effects/relationships in multiple directions, limiting their usefulness. This paper discusses the use

of a predictive, two-dimensional mathematical model to describe microbial uptake, diffusion through a biofilm, and

mass transfer of VOCs from gas to liquid. The model is validated by experimental data collected from operating

trickle-bed bioreactors designed for removing sparingly soluble gaseous contaminants. Axial and radial (biofilm)

concentration profiles are presented, along with validation

results. Operation in regimes in which both mass transfer

and kinetic factors play significant roles are discussed,

along with predictive modeling implications.

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

487

(ORNL/CP–97105)

Certification testing for the ES-2 shipping package.

Feldman, M.R. (Lockheed Martin Energy Systems, Inc., Oak

Ridge, TN (United States)); Byington, G.A.; Handy, K.D.;

Shappert, L.B.; Handy, K.D.; Oaks, R.E. Jr.; Stumpfl, E. Oak

Ridge National Lab., TN (United States). Feb 1998. 11p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC05-96OR22464. (CONF-980507–: PATRAM ’98: 12. international conference on packaging and transportation of

radioactive material, Paris (France), 10-15 May 1998). Order

Number DE98004889. Source: OSTI; NTIS; INIS; GPO Dep.

The ES-2 is a multiconfiguration, Type B fissile material

shipping package, designed by the Y-12 Nuclear Packaging

Systems. It is unique in that a castable refractory material

performs primary impact absorption and thermal insulation

duties. This material, unlike the insulation often used in fissile material packages, such as Celotex and various foams,

is fireproof at temperatures associated with Type B package

testing (800 C). The ES-2 is designed to permit the use of

three different containment vessels which can result in as

many as six different configurations. Eight prototype units

were manufactured and successfully tested to US Federal

Regulatory Requirements.

488

(ORNL/CP–97136)

A simplified ALARA approach to demonstration of compliance with surface contaminated object regulatory

requirements. Pope, R.B. (Oak Ridge National Lab., TN

(United States)); Shappert, L.B.; Michelhaugh, R.D.; Boyle,

R.W.; Cook, J.C. Oak Ridge National Lab., TN (United

States). Feb 1998. 11p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States).

DOE Contract AC05-96OR22464. (CONF-980507–: PATRAM ’98: 12. international conference on packaging and

transportation of radioactive material, Paris (France), 10-15

May 1998). Order Number DE98004931. Source: OSTI;

NTIS; INIS; GPO Dep.

The US Department of Transportation (DOT) and the US

Nuclear Regulatory Commission (NRC) have jointly prepared a comprehensive set of draft guidance for consignors

and inspectors to use when applying the newly imposed

regulatory requirements for low specific activity (LSA) material and surface contaminated objects (SCOs). The guidance

is being developed to facilitate compliance with the new LSA

material and SCO requirements, not to impose additional requirements. These new requirements represent, in some

areas, significant departures from the manner in which

packaging and transportation of these materials and objects

were previously controlled. On occasion, it may be appropriate to use conservative approaches to demonstrate

compliance with some of the requirements, ensuring that

personnel are not exposed to radiation at unnecessary levels, so that exposures are kept as low as reasonably

achievable (ALARA). In the draft guidance, one such approach would assist consignors preparing a shipment of a

large number of SCOs in demonstrating compliance without

unnecessarily exposing personnel. In applying this approach, users need to demonstrate that four conditions are

met. These four conditions are used to categorize nonactivated, contaminated objects as SCO-2. It is expected

that, by applying this approach, it will be possible to categorize a large number of small contaminated objects as SCO-2

without the need for detailed, quantitative measurements of

fixed, accessible contamination, or of total (fixed and nonfixed) contamination on inaccessible surfaces. The method,

which is based upon reasoned argument coupled with limited measurements and the application of a sum of fractions

rule, is described and examples of its use are provided.

489

(ORNL/CP–97138)

Characterizing, for packaging and transport, large objects contaminated by radioactive material having a

limited A2 value. Pope, R.B. (Oak Ridge National Lab., TN

(United States)); Shappert, L.B.; Michelhaugh, R.D.; Cash,

J.M.; Best, R.E. Oak Ridge National Lab., TN (United

States). Feb 1998. 10p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States).

DOE Contract AC05-96OR22464. (CONF-980507–: PATRAM ’98: 12. international conference on packaging and

transportation of radioactive material, Paris (France), 10-15

May 1998). Order Number DE98004930. Source: OSTI;

NTIS; INIS; GPO Dep.

The International Atomic Energy Agency (IAEA) Regulations for the safe packaging and transportation of

radioactive materials follow a graded approach to the requirements for both packaging and controls during transport.

The concept is that, the lower the risk posed to the people

and the environment by the contents, (1) the less demanding are the packaging requirements and (2) the smaller in

number are the controls imposed on the transport of the material. There are likely to be a great number of situations

arising in coming years when large objects, contaminated

with radioactive material having unlimited A2 values will result from various decommissioning and decontamination (D

and D) activities and will then require shipment from the D

and D site to a disposal site. Such situations may arise relatively frequently during the cleanup of operations involving

mining, milling, feedstock, and uranium enrichment processing facilities. Because these objects are contaminated with

materials having an unlimited A2 value they present a low

radiological risk to worker and public safety and to the environment during transport. However, when these radioactive

materials reside on the surfaces of equipment and other

large objects, where the equipment and objects themselves

are not radioactive, the radioactive materials appear as

surface contamination and, if the contaminated object is categorized as a surface contaminated object, it would need to

be packaged for shipment according to the requirements of

the Regulations for SCO. Despite this categorization,

alternatives may be available which will allow these contaminants, when considered by themselves for packaging and

transport, to be categorized as either (1) a limited quantity of

radioactive material to be shipped in an excepted package

or (2) low specific activity (LSA) materials to be shipped in

an IP-1 package or possibly even shipped unpackaged.

These options are discussed in this paper.

490

(ORNL/CP–97154)

Transportation Routing Analysis Geographic Information System – TRAGIS, progress on improving a routing

tool. Johnson, P.E. (Oak Ridge National Lab., TN (United

States)); Lester, P.B. Oak Ridge National Lab., TN (United

States). May 1998. 11p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States).

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

DOE Contract AC05-96OR22464. (CONF-980507–: PATRAM ’98: 12. international conference on packaging and

transportation of radioactive material, Paris (France), 10-15

May 1998). Order Number DE98004927. Source: OSTI;

NTIS; INIS; GPO Dep.

The Transportation Routing Analysis Geographic Information System (TRAGIS) model provides a useful tool to

calculate and analyze transportation routes for radioactive

materials within the continental US. This paper outlines

some of the features available in this model.

491

(ORNL/CP–97224)

Global transportation cost modeling for long-range

planning. Pope, R.B. (Oak Ridge National Lab., TN (United

States)); Michelhaugh, R.D.; Singley, P.T.; Lester, P.B. Oak

Ridge National Lab., TN (United States). Feb 1998. 11p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC05-96OR22464. (CONF-980507–: PATRAM ’98: 12. international conference on packaging and transportation of

radioactive material, Paris (France), 10-15 May 1998). Order

Number DE98004891. Source: OSTI; NTIS; INIS; GPO Dep.

The US Department of Energy (DOE) is preparing to perform significant remediation activities of the sites for which it

is responsible. To accomplish this, it is preparing a corporate

global plan focused on activities over the next decade. Significant in these planned activities is the transportation of the

waste arising from the remediation. The costs of this transportation are expected to be large. To support the initial

assessment of the plan, a cost estimating model was developed, peer-reviewed against other available packaging and

transportation cost data, and applied to a significant number

of shipping campaigns of radioactive waste. This cost estimating model, known as the Ten-year Plan Transportation

Cost Model (TEPTRAM), can be used to model radioactive

material shipments between DOE sites or from DOE sites to

non-DOE destinations. The model considers the costs for

(a) recovering and processing of the wastes, (b)packaging

the wastes for transport, and (c) the carriage of the waste. It

also provides a rough order of magnitude estimate of labor

costs associated with preparing and undertaking the shipments. At the user’s direction, the model can also consider

the cost of DOE’s interactions with its external stakeholders

(e.g., state and local governments and tribal entities) and

the cost associated with tracking and communicating with

the shipments. By considering all of these sources of costs,

it provides a mechanism for assessing and comparing the

costs of various waste processing and shipping campaign

alternatives to help guide decision-making. Recent analyses

of specific planned shipments of transuranic (TRU) waste

which consider alternative packaging options are described.

These analyses show that options are available for significantly reducing total costs while still satisfying regulatory

requirements.

492

(ORNL/CP–97226)

Guidance and methods for satisfying low specific activity material and surface contaminated object regulatory

requirements. Pope, R.B. (Oak Ridge National Lab., TN

(United States)); Shappert, L.B.; Michelhaugh, R.D.; Boyle,

R.W.; Easton, E.P.; Cook, J.R. Oak Ridge National Lab., TN

(United States). Feb 1998. 12p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States). DOE Contract AC05-96OR22464. (CONF-980507–:

PATRAM ’98: 12. international conference on packaging

and transportation of radioactive material, Paris (France),

10-15 May 1998). Order Number DE98004929. Source:

OSTI; NTIS; INIS; GPO Dep.

The US Department of Transportation (DOT) and the US

Nuclear Regulatory Commission (NRC) have prepared a

comprehensive set of draft guidance for shippers and inspectors to use when applying the newly imposed regulatory

requirements for low specific activity (LSA) material and surface contaminated objects (SCOs). These requirements

represent significant departures in some areas from the

manner in which these materials and objects were regulated

by the earlier versions of the regulations. The proper interpretation and application of the regulatory criteria can

require a fairly complex set of decisions be made. To assist

those trying to apply these regulatory requirements, a detailed set of logic flow diagrams representing decisions

related to multiple factors were prepared and included in the

draft report for comment on Categorizing and Transporting

Low Specific Activity Materials and Surface Contaminated

Objects. These logic flow diagrams, as developed, are specific to the US regulations, but were readily adaptable to the

IAEA regulations. The diagrams have been modified accordingly and tied directly to specific paragraphs in IAEA Safety

Series No. 6. This paper provides the logic flow diagrams

adapted to the IAEA regulations, and demonstrates how

these diagrams can be used to assist consignors and inspectors in assessing compliance of shipments with the LSA

material and SCO regulatory requirements.

493

(ORNL/CP–97228)

Recent experience in planning, packaging and preparing noncommercial spent fuel for shipment in the

United States. Shappert, L.B. (Oak Ridge National Lab., TN

(United States)); Parks, C.V.; Turner, D.W.; Aramayo, G.A.

Oak Ridge National Lab., TN (United States). May 1998.

11p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC05-96OR22464. (CONF-980507–: PATRAM ’98: 12. international conference on packaging and transportation of

radioactive material, Paris (France), 10-15 May 1998). Order

Number DE98004928. Source: OSTI; NTIS; INIS; GPO Dep.

The US Department of Energy-Headquarters (DOE-HQ)

has issued a Record of Decision (ROD) which identified the

plan to be followed in managing spent nuclear fuel (SNF)

belonging to the Department. As a result, the aluminum-clad

fuels stored at Oak Ridge National Laboratory (ORNL) in

Oak Ridge, Tennessee, were directed to be shipped to the

Savannah River Site (SRS) near Aiken, South Carolina. The

BMI-1 cask was chosen to make the shipments of SNF from

dry storage that had to be placed in canisters. However, the

Certificate of Compliance (COC) for the BMI-1 cask limited

the fissile material loading to 800 g of unirradiated fissile

material for the cask configuration chosen. Because about

half of the canisters were already filled and sealed with

more fissile material than was permitted by the COC, approval to make these shipments in the BMI-1 was requested

from the Nuclear Regulatory Commission (NRC). A safety

analysis showed that the shipments could be made safely

under the conditions identified. The waiver was granted in

September 1997 and the three shipments were successfully

completed in January 1998.

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

494

(ORNL/CP–97640)

Large-scale treatment of high-salt, high-pH wastewater

for 137Cs and 90Sr removal, using crystalline silicotitanate resin. Taylor, P.A.; Walker, J.F.; Lee, D.D. Oak

Ridge National Lab., TN (United States). Apr 1998. 17p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC05-96OR22464. (CONF-980905–: SPECTRUM ’98: nuclear and hazardous waste management international

topical meeting, Denver, CO (United States), 13-18 Sep

1998). Order Number DE98005728. Source: OSTI; NTIS;

INIS; GPO Dep.

A full-scale demonstration of cesium removal technology

has been conducted at Oak Ridge National Laboratory

(ORNL). This demonstration utilized a modular, mobile ionexchange system and existing facilities for the off-gas

system, secondary containment, and utilities. The ionexchange material, crystalline silicotitanate (CST), was

selected on the basis of its effectiveness in laboratory tests.

The CST, which was developed through a Cooperative Research and Development Agreement between DOE and

private industry, is highly selective for removing cesium from

solutions containing high concentrations of other contaminants, such as sodium and potassium. Approximately

116,000 liters of supernate was processed during the

demonstration with  1,142 Ci of 137Cs removed from the

supernate and loaded onto 266 liters of the CST sorbent.

The supernate processed had a high salt content, about 4 M

NaNO3 and a pH of 12 to 13. The CST also loaded Ba, Pb,

Sr, U and Zn. Analysis of the spent sorbent has shown that

it is not hazardous under the Resource Conservation and

Recovery Act (RCRA). The cesium breakthrough curves for

the lab and full-scale columns agreed very well, suggesting

that lab-scale tests can be used to predict the performance

of larger systems. The cesium breakthrough curves for runs

at different flowrates show that film diffusion is significant in

controlling the mass transfer process. Operational factors

that increase the effect of film diffusion include the small

size and high porosity of the CST sorbent, and the relatively

low liquid velocity through the sorbent.

495

(ORNL/CP–97827)

Grout and vitrification formula development for immobilization of hazardous radioactive tank sludges at ORNL.

Gilliam, T.M.; Spence, R.D. Oak Ridge National Lab., TN

(United States). [1997]. 16p. Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract AC05-96OR22464. (CONF-970962–:

214. American Chemical Society meeting, Las Vegas, NV

(United States), 7-13 Sep 1997). Order Number

DE98003514. Source: OSTI; NTIS; INIS; GPO Dep.

Stabilization/solidification (S/S) has been identified as the

preferred treatment option for hazardous radioactive

sludges, and currently grouting and vitrification are considered the leading candidate S/S technologies. Consequently,

a project was initiated at Oak Ridge National Laboratory

(ORNL) to define composition envelopes, or operating

windows, for acceptable grout and glass formulations containing Melton Valley Storage Tank (MVST) sludges. The

resulting data are intended to be used as guidance for the

eventual treatment of the MVST sludges by the government

and/or private sector. Wastewater at ORNL is collected,

evaporated, and stored in the MVSTs pending treatment for

disposal. The waste separates into two phases: sludge and

supernate. The sludges in the tank bottoms have been accumulating for several years and contain a high amount of

radioactivity, with some classified as transuranic (TRU)

sludges. The available total constituent analysis for the

MVST sludge indicates that the Resource and Conservation

Recovery Act (RCRA) metal concentrations are high enough

to be potentially RCRA hazardous; therefore, these sludges

have the potential to be designated as mixed TRU waste. S/

S treatment must be performed to remove free liquids and

reduce the leach rate of RCRA metals. This paper focuses

on initial results for the development of the operating window for vitrification. However, sufficient data on grouting are

presented to allow a comparison of the two options.

496

(ORNL/CP–98259)

Testing of low-temperature stabilization alternatives for

salt containing mixed wastes – Approach and results to

date. Maio, V. (Lockheed Martin Idaho Technologies Co.,

Idaho Falls, ID (United States)); Loomis, G.; Spence, R.D.;

Smith, G.; Biyani, R.K.; Wagh, A. Oak Ridge National Lab.,

TN (United States). May 1998. 11p. Sponsored by USDOE

Office of Environmental Management, Washington, DC

(United States). DOE Contract AC05-96OR22464. (CONF980905–: SPECTRUM ’98: nuclear and hazardous waste

management international topical meeting, Denver, CO

(United States), 13-18 Sep 1998). Order Number

DE98005732. Source: OSTI; NTIS; INIS; GPO Dep.

Through its annual process of identifying technology deficiencies associated with waste treatment, the Department of

Energy’s (DOE) Mixed Waste Focus Area (MWFA) determined that the former DOE weapons complex lacks efficient

mixed waste stabilization technologies for salt containing

wastes. These wastes were generated as sludge and solid

effluents from various primary nuclear processes involving

acids and metal finishing; and well over 10,000 cubic meters

exist at 6 sites. In addition, future volumes of these problematic wastes will be produced as other mixed waste treatment

methods such as incineration and melting are deployed. The

current method used to stabilize salt waste for compliant

disposal is grouting with Portland cement. This method is inefficient since the highly soluble and reactive chloride,

nitrate, and sulfate salts interfere with the hydration and setting processes associated with grouting. The inefficiency

results from having to use low waste loadings to ensure a

durable and leach resistant final waste form. The following

five alternatives were selected for MWFA development funding in FY97 and FY98: phosphate bonded ceramics; sol-gel

process; polysiloxane; polyester resin; and enhanced

concrete. Comparable evaluations were planned for the stabilization development efforts. Under these evaluations each

technology stabilized the same type of salt waste surrogates. Final waste form performance data such as

compressive strength, waste loading, and leachability could

then be equally compared. Selected preliminary test results

are provided in this paper.

497

(ORNL/CP–98272)

A life cycle analysis approach to D and D decisionmaking. Yuracko, K.L. (Oak Ridge National Lab., TN

(United States)); Gresalfi, M.; Yerace, P.; Flora, J.; Krstich,

M.; Gerrick, D. Oak Ridge National Lab., TN (United States).

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

May 1998. 10p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE

Contract AC05-96OR22464. (CONF-980905–: SPECTRUM

’98: nuclear and hazardous waste management international topical meeting, Denver, CO (United States), 13-18

Sep 1998). Order Number DE98005729. Source: OSTI;

NTIS; INIS; GPO Dep.

This paper describes a life cycle analysis (LCA) approach

that makes decontamination and decommissioning (D and

D) of US Department of Energy facilities more efficient and

more responsive to the concerns of the society. With the

considerable complexity of D and D projects and their attendant environmental and health consequences, projects can

no longer be designed based on engineering and economic

criteria alone. Using the LCA D and D approach, the evaluation of material disposition alternatives explicitly includes

environmental impacts, health and safety impacts, socioeconomic impacts, and stakeholder attitudes – in addition to

engineering and economic criteria. Multi-attribute decision

analysis is used to take into consideration the uncertainties

and value judgments that are an important part of all material disposition decisions. Use of the LCA D and D approach

should lead to more appropriate selections of material disposition pathways and a decision-making process that is

both understandable and defensible. The methodology and

procedures of the LCA D and D approach are outlined and

illustrated by an application of the approach at the Department of Energy’s West Valley Demonstration Project.

Specifically, LCA was used to aid decisions on disposition of

soil and concrete from the Tank Pad D and D Project. A decision tree and the Pollution Prevention/Waste Minimization

Users Guide for Environmental Restoration Projects were

used to identify possible alternatives for disposition of the

soil and concrete. Eight alternatives encompassing source

reduction, segregation, treatment, and disposal were

defined for disposition of the soil; two alternatives were identified for disposition of the concrete. Preliminary results

suggest that segregation and treatment are advantageous in

the disposition of both the soil and the concrete. This and

other recent applications illustrate the strength and ease of

application of the LCA D and D approach.

498

(ORNL/CP–98274)

U.S. Department of Energy National Center of Excellence for Metals Recycle. Adams, V. (Dept. of Energy, Oak

Ridge, TN (United States)); Bennett, M.; Bishop, L. Oak

Ridge National Lab., TN (United States). May 1998. 10p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC05-96OR22464. (CONF-980905–: SPECTRUM ’98: nuclear and hazardous waste management international

topical meeting, Denver, CO (United States), 13-18 Sep

1998). Order Number DE98005730. Source: OSTI; NTIS;

INIS; GPO Dep.

The US Department of Energy (DOE) National Center of

Excellence for Metals Recycle has recently been established. The vision of this new program is to develop a DOE

culture that promotes pollution prevention by considering the

recycle and reuse of metal as the first and primary disposition option and burial as a last option. The Center of

Excellence takes the approach that unrestricted release of

metal is the first priority because it is the most cost-effective

disposition pathway. Where this is not appropriate, restricted

release, beneficial reuse, and stockpile of ingots are considered. Current recycling activities include the sale of 40,000

tons of scrap metal from the East Tennessee Technology

Park (formerly K-25 Plant) K-770 scrap yard, K-1064 surplus

equipment and machinery, 7,000 PCB-contaminated drums,

12,000 tons of metal from the Y-l2 scrap yard, and 1,000

metal pallets. In addition, the Center of Excellence is developing a toolbox for project teams that will contain a number

of specific tools to facilitate metals recycle. This Internetbased toolbox will include primers, computer programs, and

case studies designed to help sites to perform life cycle analysis, perform ALARA (As Low As is Reasonably Achievable)

analysis for radiation exposures, provide pollution prevention

information and documentation, and produce independent

government estimates. The use of these tools is described

for two current activities: disposition of scrap metal in the Y12 scrapyard, and disposition of PCB-contaminated drums.

499

(ORNL/CP–98275)

Process wastewater treatment with hydrogen-form CST

and chabazite zeolite. DePaoli, S.M.; Bostick, D.T. Oak

Ridge National Lab., TN (United States). May 1998. 10p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC05-96OR22464. (CONF-980905–: SPECTRUM ’98: nuclear and hazardous waste management international

topical meeting, Denver, CO (United States), 13-18 Sep

1998). Order Number DE98005731. Source: OSTI; INIS;

NTIS; GPO Dep.

Ion-exchange materials have been investigated for the removal of radionuclides from near-neutral-pH wastewaters

containing competing cations at concentrations greater than

those of the targeted species. Natural chabazite zeolite was

chosen as the baseline material for the removal of fission

products, namely 90Sr and 137Cs, from wastewater and

groundwater. The sorbent IONSIV IE-911, a crystalline silicotitanate manufactured by UOP, was recently tested in this

capacity and found to compare extremely well against the

baseline material in removing 90Sr and 137Cs from process

wastewater. This paper presents results of similar column

tests performed using both materials, as well as results from

batch experiments on actual wastewaters using IONSIV

IE-911.

500

(ORNL/CP–98301)

Separations/pretreatment considerations for Hanford

privatization phase 2. Hunt, R.D.; McGinnis, C.P.; Welch,

T.D. Oak Ridge National Lab., TN (United States). May

1998. 12p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract AC05-96OR22464. (CONF-980905–: SPECTRUM ’98:

nuclear and hazardous waste management international

topical meeting, Denver, CO (United States), 13-18 Sep

1998). Order Number DE98005746. Source: OSTI; NTIS;

INIS; GPO Dep.

The Tank Focus Area is funded to develop, demonstrate,

and deploy technologies that will assist in the treatment and

closure of its nuclear waste tanks. Pretreatment technologies developed to support the privatization effort by the

Department of Energy are reviewed. Advancements in evaporation, solid-liquid separation, sludge treatment, solids

controls, sodium management, and radionuclide removal

are considered.

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

501

(ORNL/CP–98302)

U.S. Department of Energy National Center of Excellence for Metals Recycle. Adams, V. (Dept. of Energy, Oak

Ridge, TN (United States)); Bennett, M.; Bishop, L. Oak

Ridge National Lab., TN (United States). Jun 1998. 13p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC05-96OR22464. (CONF-980654–: 14. DOE pollution prevention conference, Seattle, WA (United States), 2-4 Jun

1998). Order Number DE98005665. Source: OSTI; NTIS;

INIS; GPO Dep.

The US Department of Energy (DOE) National Center of

Excellence for Metals Recycle has recently been established. The vision of this new program is to develop a DOE

culture that promotes pollution prevention by considering the

recycle and reuse of metal as the first and primary disposition option and burial as a last option. The Center of

Excellence takes the approach that unrestricted release of

metal is the first priority because it is the most cost-effective

disposition pathway. Where this is not appropriate, restricted

release, beneficial reuse, and stockpile of ingots are considered. The Center has gotten off to a fast start. Current

recycling activities include the sale of 40,000 tons of scrap

metal from the East Tennessee Technology Park (formerly K25 Plant) K-770 scrap yard, K-1064 surplus equipment and

machinery, 7,000 PCB-contaminated drums, 12,000 tons of

metal from the Y-12 scrap yard, and 1,000 metal pallets. In

addition, the Center of Excellence is developing a toolbox

for project teams that will contain a number of specific tools

to facilitate metals recycle. This Internet-based toolbox will

include primers, computer software, and case studies designed to help sites to perform life cycle analysis, perform

ALARA (As Low As is Reasonably Achievable) analysis for

radiation exposures, produce pollution prevention information and documentation, manage their materials inventory,

produce independent government estimates, and implement

sale/service contracts. The use of these tools is described

for two current activities: disposition of scrap metal in the Y12 scrap yard, and disposition of PCB-contaminated drums.

Members of the Center look forward to working with all DOE

sites, regulatory authorities, the private sector, and other

stakeholders to achieve the metals recycle goals.

502

(ORNL/CP–98304)

Gunite and associated tanks remediation project recycling and waste minimization effort. Van Hoesen, S.D.;

Saunders, A.D. Oak Ridge National Lab., TN (United

States). May 1998. 10p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States).

DOE Contract AC05-96OR22464. (CONF-980654–: 14.

DOE pollution prevention conference, Seattle, WA (United

States), 2-4 Jun 1998). Order Number DE98005666.

Source: OSTI; NTIS; INIS; GPO Dep.

The Department of Energy’s Environmental Management

Program at Oak Ridge National Laboratory has initiated

clean up of legacy waste resulting from the Manhattan

Project. The gunite and associated tanks project has taken

an active pollution prevention role by successfully recycling

eight tons of scrap metal, reusing contaminated soil in the

Area of Contamination, using existing water (supernate) to

aid in sludge transfer, and by minimizing and reusing personal protective equipment (PPE) and on-site equipment as

much as possible. Total cost savings for Fiscal Year 1997

activities from these efforts are estimated at $4.2 million dollars.

503

(ORNL/CP–98309)

Large underground radioactive waste storage tanks

successfully cleaned at Oak Ridge National Laboratory.

Billingsley, K. (Solutions to Environmental Problems, Inc.,

Oak Ridge, TN (United States)); Burks, B.L.; Johnson, M.;

Mims, C.; Powell, J.; Hoesen, D. van. Oak Ridge National

Lab., TN (United States). May 1998. 11p. Sponsored by USDOE Office of Environmental Management, Washington, DC

(United States);USDOE Office of Financial Management and

Controller, Washington, DC (United States). DOE Contract

AC05-98OR22700. (CONF-980905–: SPECTRUM ’98: nuclear and hazardous waste management international

topical meeting, Denver, CO (United States), 13-18 Sep

1998). Order Number DE98005748. Source: OSTI; NTIS;

INIS; GPO Dep.

Waste retrieval operations were successfully completed in

two large underground radioactive waste storage tanks in

1997. The US Department of Energy (DOE) and the Gunite

Tanks Team worked cooperatively during two 10-week waste

removal campaigns and removed approximately 58,300 gallons of waste from the tanks. About 100 gallons of a sludge

and liquid heel remain in each of the 42,500 gallon tanks.

These tanks are 25 ft. in diameter and 11 ft. deep, and are

located in the North Tank Farm in the center of Oak Ridge

National Laboratory. Less than 2% of the radioactive contaminants remain in the tanks, proving the effectiveness of

the Radioactive Tank Cleaning System, and accomplishing

the first field-scale cleaning of contaminated underground

storage tanks with a robotic system in the DOE complex.

504

(ORNL/CP–98424)

Impact analysis of stainless steel spent fuel canisters.

Aramayo, G.A. (Oak Ridge National Lab., TN (United

States)); Turner, D.W. Oak Ridge National Lab., TN (United

States). Apr 1998. 9p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States).

DOE Contract AC05-84OR21400. (CONF-980708–: 1998

ASME/JSME joint pressure vessel and piping (PVP) conference, San Diego, CA (United States), 26-30 Jul 1998). Order

Number DE98005771. Source: OSTI; NTIS; INIS; GPO Dep.

This paper presents the results of the numerical analysis

performed to asses the structural integrity of spent nuclear

fuel (SNF) stainless steel canisters when subjected to impact loads associated with free gravity drops from heights

not exceeding 20 ft. The SNF canisters are to be used for

the Shipment of radioactive material from the Oak Ridge

National Laboratory (ORNL) Site to the Idaho National Engineering and Environmental Laboratory (INEEL) for storage.

The Idaho chemical Processing Plant Fuel Receipt Criteria

Questionnaire requires that the vertical drop accidents from

two heights be analyze. These heights are those that are

considered to be critical at the time of unloading the canisters from the shipping cask. The configurations analyzed

include a maximum payload of 90 lbs dropping from heights

of 20 and 3 ft. The nominal weight of the canister is 23.3 lbs.

The analysis has been performed using finite element methods. Innovative analysis techniques are used to capture the

effects of failure and separation of canister components.

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

The structural integrity is evaluated in terms of physical deformation and separation of the canister components that

may result from failure of components at selected interfaces.

505

(ORNL/CP–98899)

Caustic leaching of high-level radioactive tank sludge:

A critical literature review. McGinnis, C.P.; Welch, T.D.;

Hunt, R.D. Oak Ridge National Lab., TN (United States).

[1997]. [50p.] Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract AC05-96OR22464. (CONF-9710103–: 10. symposium

on separation science and technology for energy applications, Gatlinburg, TN (United States), 20-24 Oct 1997).

Order Number DE99000367. Source: OSTI; NTIS; INIS;

GPO Dep.

The Department of Energy (DOE) must treat and safely

dispose of its radioactive tank contents, which can be separated into high-level waste (HLW) and low-level waste (LLW)

fractions. Since the unit costs of treatment and disposal are

much higher for HLW than for LLW, technologies to reduce

the amount of HLW are being developed. A key process currently being studied to reduce the volume of HLW sludges is

called enhanced sludge washing (ESW). This process removes, by water washes, soluble constituents such as

sodium salts, and the washed sludge is then leached with

2–3 M NaOH at 60–100 C to remove nonradioactive metals

such as aluminum. The remaining solids are considered to

be HLW while the solutions are LLW after radionuclides

such as 137Cs have been removed. Results of bench-scale

tests have shown that the ESW will probably remove the

required amounts of inert constituents. While both experimental and theoretical results have shown that leaching

efficiency increases as the time and temperature of the

leach are increased, increases in the caustic concentration

above 2–3 M will only marginally improve the leach factors.

However, these tests were not designed to validate the assumption that the caustic used in the ESW process will

generate only a small increase (10 Mkg) in the amount of

LLW; instead, the test conditions were selected to maximize

leaching in a short period and used more water and caustic

than is planned during full-scale operations. Even though

calculations indicate that the estimate for the amount of LLW

generated by the ESW process appears to be reasonable, a

detailed study of the amount of LLW from the ESW process

is still required. If the LLW analysis indicates that sodium

management is critical, then a more comprehensive evaluation of the clean salt process or caustic recycle would be

needed. Finally, experimental and theoretical studies have

clearly demonstrated the need for the control of solids formation during and after leaching.

506

(ORNL/ER–297/R2)

Inactive tanks remediation program strategy and plans

for Oak Ridge National Laboratory, Oak Ridge, Tennessee. Oak Ridge National Lab., TN (United States);

STEP, Inc., Oak Ridge, TN (United States). Nov 1997. 34p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC05-84OR21400. Order Number DE98001276. Source:

OSTI; NTIS; INIS; GPO Dep.

This report presents plans and strategies for remediation

of the liquid low-level waste (LLLW) tanks that have been removed from service (also known as inactive tanks) at Oak

Ridge National Laboratory (ORNL) in Oak Ridge, Tennessee. These plans and strategies will be carried out by

the Environmental Restoration Program’s Inactive LLLW

Tank Program at ORNL. The approach to remediation of

each tank or tank farm must be adapted in response to the

specific circumstances of individual tank sites. The approach

will be tailored to accommodate feedback on lessons

learned from previous tank remediation activities and will not

be a rigid step-by-step approach that must be conducted

identically for every tank system. However, the approach will

follow a multistep decision process. The overall objective of

the Inactive Tank Program is to remediate all LLLW tanks

that have been removed from service to the extent practicable in accordance with the FFA requirements. The Inactive

Tank Program will focus on the remediation of the tank

residues and tank shell. This strategy is discussed in detail

in this report.

507

(ORNL/ER–326/R1)

Environmental health and safety plan for the Molten Salt

Reactor Experiment Remediation Project at Oak Ridge

National Laboratory, Oak Ridge, Tennessee. Burman,

S.N.; Tiner, P.F.; Gosslee, R.C. Oak Ridge National Lab.,

TN (United States). Jan 1998. [200p.] Sponsored by USDOE Office of Environmental Management, Washington, DC

(United States). DOE Contract AC05-96OR22464. Order

Number DE98003280. Source: OSTI; NTIS; INIS; GPO Dep.

The Lockheed Martin Energy Systems, Inc. (Energy Systems) policy is to provide a safe and healthful workplace for

all employees and subcontractors. The accomplishment of

this policy requires that operations at the Molten Salt Reactor Experiment (MSRE) facility at the Department of Energy

(DOE) Oak Ridge National Laboratory (ORNL) are guided by

an overall plan and consistent proactive approach to environmental protection and safety and health (S and H) issues.

The policy and procedures in this plan apply to all MSRE

operations. The provisions of this plan are to be carried out

whenever activities are initiated at the MSRE that could be a

threat to human health or the environment. This plan implements a policy and establishes criteria for the development

of procedures for day-to-day operations to prevent or minimize any adverse impact to the environment and personnel

safety and health and to meet standards that define acceptable management of hazardous and radioactive materials

and wastes. The plan is written to utilize past experience

and the best management practices to minimize hazards to

human health or the environment from events such as fires,

explosions, falls, mechanical hazards, or any unplanned release of hazardous or radioactive materials to the air.

508

(ORNL/ER–336/R1)

Quality assurance plan for the molten salt reactor experiment Remediation Project at Oak Ridge National

Laboratory, Oak Ridge, Tennessee. Oak Ridge National

Lab., TN (United States). Feb 1998. 60p. Sponsored by USDOE Office of Environmental Management, Washington, DC

(United States). DOE Contract AC05-96OR22464. Order

Number DE98004146. Source: OSTI; NTIS; INIS; GPO Dep.

This Quality Assurance Plan (QAP) identifies and

describes the systems utilized by Molten Salt Reactor Experiment (MSRE) Remediation Project personnel to implement

the requirements and associated applicable guidance contained in the Quality Program Description, Y/QD-15 Rev. 2

127
ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

(Martin Marietta Energy Systems, Inc., 1995) and Environmental Management and Enrichment Facilities Work Smart

Standards. This QAP defines the quality assurance (QA) requirements applicable to all activities and operations in and

directly pertinent to the MSRE Remediation Project. This

QAP will be periodically reviewed, revised, and approved as

necessary. This QAP identifies and describes the QA activities and procedures implemented by the various Oak Ridge

National Laboratory support organizations and personnel to

provide confidence that these activities meet the requirements of this project. Specific support organization (Division)

quality requirements, including the degree of implementation

of each, are contained in the appendixes of this plan.

509

(ORNL/ER–375/R1)

Project management plan for Waste Area Grouping 5

Old Hydrofracture Facility tanks contents removal at

Oak Ridge National Laboratory, Oak Ridge, Tennessee.

Oak Ridge National Lab., TN (United States); CDM Federal

Programs Corp., Oak Ridge, TN (United States). Feb 1998.

26p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC05-84OR21400. Order Number DE98003100. Source:

OSTI; NTIS; INIS; GPO Dep.

This revision (Rev. 1) updates the schedule and designation of responsibilities for the Old Hydrofracture Facility

(OHF) tanks contents removal project. Ongoing and planned

future activities include: cold testing of the sluicing and

pumping system; readiness assessment; equipment relocation and assembly; isotopic dilution of fissile radionuclides;

sluicing and transfer of the tanks contents; and preparation

of the Removal Action Completion Report. The most significant change is that the sluicing and pumping system has

been configured by and will be operated by CDM Federal

Programs Corporation. In addition, a new technical lead and

a new project analyst have been designated within Lockheed Martin Energy Systems, Inc. and Lockheed Martin

Energy Research Corp. The schedule for tanks contents removal has been accelerated, with transfer of the final batch

of tank slurry now scheduled for March 31, 1998 (instead of

November 10, 1998). The OHF sluicing and pumping project

is proceeding as a non-time-critical removal action under the

Comprehensive Environmental Response, Compensation,

and Liability Act. The purpose of the project is to remove the

contents from five inactive underground storage tanks, designated T-1, T-2, T-3, T-4, and T-9. The tanks contain an

estimated 52,700 gal of liquid and sludge, together comprising a radioactive inventory of approximately 30,000 Ci.

510

(ORNL/ER–404)

Technical safety requirments for the South Tank Farm

Remediation Project, Oak Ridge National Laboratory,

Oak Ridge, Tennessee. Platfoot, J.H. Oak Ridge National

Lab., TN (United States). Feb 1998. 41p. Sponsored by USDOE Office of Environmental Management, Washington, DC

(United States). DOE Contract AC05-96OR22464. Order

Number DE98004147. Source: OSTI; NTIS; INIS; GPO Dep.

The South Tank Farm (STF) is a series of six, 170,000-gal

underground, domed storage tanks that were placed into

service in 1943. The tanks were constructed of a concrete

mixture known as gunite. They were used as a portion of

the Liquid LOW-LEVEL WASTE (LLLW) System for the collection, neutralization, storage, and transfer of the aqueous

portion of the radioactive and/or hazardous chemical wastes

produced as part of normal facility operations at Oak Ridge

National Laboratory (ORNL). Although the last of the tanks

was taken out of service in 1986, they have been shown by

structural analysis to continue to be structurally sound. An

attempt was made in 1983 to empty the tanks; however, removal of all the sludge from the tanks was not possible with

the equipment and schedule available. Since removal of the

liquid waste in 1983, liquid continues to accumulate within

the tanks. The in-leakage is believed to be the result of

groundwater dripping into the tanks around penetrations in

the domes. The tanks are currently being maintained under

a Surveillance and Maintenance Program, which includes

activities such as level monitoring, vegetation control, High

Efficiency Particulate Air filter leakage requirement testing/

replacement, sign erection/repair, pump-out of excessive liquids, and instrument calibration/maintenance.

511

(ORNL/ER–404/R1)

Technical safety requirements for the South Tank Farm

remediation project, Oak Ridge National Laboratory,

Oak Ridge, Tennessee. Oak Ridge National Lab., TN

(United States). May 1998. 53p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States). DOE Contract AC05-98OR22700. Order Number

DE98005542. Source: OSTI; NTIS; INIS; GPO Dep.

The South Tank Farm (STF) is a series of six, 170,000-gal

underground, domed storage tanks that were placed into

service in 1943. The tanks were constructed of a concrete

mixture known as gunite. They were used as a portion of

the liquid low-level waste (LLLW) system for the collection,

neutralization, storage, and transfer of the aqueous portion

of the radioactive and/or hazardous chemical wastes produced as part of normal facility operations at Oak Ridge

National Laboratory (ORNL). Although the last of the tanks

was taken out of service in 1986, they have been shown by

structural analysis to continue to be structurally sound. An

attempt was made in 1983 to empty the tanks; however, removal of all the sludge from the tanks was not possible with

the equipment and schedule available. Since removal of the

liquid waste in 1983, liquid continues to accumulate within

the tanks. The in-leakage is believed to be the result of

groundwater dripping into the tanks around penetrations in

the domes. The tanks are currently being maintained under

a Surveillance and Maintenance Program, which includes

activities such as level monitoring, vegetation control, High

Efficiency Particulate Air filter leakage requirement testing/

replacement, sign erection/repair, pump-out of excessive liquids, and instrument calibration/maintenance. These tanks

are to undergo remediation and clean-up using sludge removal techniques and equipment planned for use in other

waste storage tanks throughout the US DOE complex. The

technical safety requirements are those operational requirements that specify the operating limits and surveillance

requirements, the basis thereof, safety boundaries, and the

management or administrative controls necessary to ensure

the safe operation of the STF remediation project.

512

(ORNL/ER–412/R1)

Sampling and analysis plan for the gunite and associated tanks interim remedial action, wall coring and

scraping at Oak Ridge National Laboratory, Oak Ridge,

Tennessee. Oak Ridge National Lab., TN (United States).

128
Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

Feb 1998. 21p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE

Contract AC05-84OR21400. Order Number DE98003099.

Source: OSTI; NTIS; INIS; GPO Dep.

This Sampling and Analysis Plan documents the procedures for collecting and analyzing wall core and wall

scraping samples from the Gunite and Associated Tanks.

These activities are being conducted to support the Comprehensive Environmental Response, Compensation, and

Liability Act at the gunite and associated tanks interim remedial action at Oak Ridge National Laboratory in Oak Ridge,

Tennessee. The sampling and analysis activities will be performed in concert with sludge retrieval and sluicing of the

tanks. Wall scraping and/or wall core samples will be collected from each quadrant in each tank by using a scraping

sampler and/or a coring drill deployed by the Houdini robot

vehicle. Each sample will be labeled, transported to the Radioactive Materials Analytical Laboratory, and analyzed for

physical and radiological characteristics, including total activity, gross alpha, gross beta, radioactive strontium and

cesium, and other alpha- and gamma-emitting radionuclides. The data quality objectives process, based on US

Environmental Protection Agency guidance, was applied to

identify the objectives of this sampling and analysis. The results of the analysis will be used to (1) validate predictions

of a strontium concrete diffusion model, (2) estimate the

amount of radioactivity remaining in the tank shells, (3) provide information to correlate with measurements taken by

the Gunite Tank Isotope Mapping Probe and the Characterization End Effector, and (4) estimate the performance of the

wall cleaning system. This revision eliminates wall-scraping

samples from all tanks, except Tank W-3. The Tank W-3 experience indicated that the wall scrapper does not collect

sufficient material for analysis.

513

(ORNL/ER–421)

Dry well conductivity monitoring report for Tanks W-8,

W-9, and W-10, Oak Ridge National Laboratory, Oak

Ridge, Tennessee. Oak Ridge National Lab., TN (United

States); Vista Research, Inc., Mountain View, CA (United

States). Oct 1997. 22p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States).

DOE Contract AC05-84OR21400. Order Number

DE98000608. Source: OSTI; NTIS; INIS; GPO Dep.

A treatability study and waste removal program are being

implemented for the Gunite ad Associated Tanks Operable

Unit at Oak Ridge National Laboratory, Oak Ridge, Tennessee. This report documents the instrumentation and

monitoring efforts to establish baseline conductivity conditions. The simulated liquid release (SLR) testing reported

here demonstrates the effectiveness of the Conductivitymonitoring method (CMM) as a liquid-release detection

method for consolidation Tanks W-8 and W-9 and Tank W10 in the South Tank Farm (STF). The results show the

remarkable sensitivity of the CMM to even very small simulated releases from the tank. The SLR testing for DW-8,

DW-9 and DW-10 show that the dry well conductivity monitoring will be effective in detecting potential releases from

the tanks during waste removal operations. The data in this

report also make clear statements about the inferred integrity of the tanks, tank pads, and drain system: (1) the

data substantiate earlier work and show that Tanks W-8, W9, and W-10 are not leaking; (2) the data show that the pads

under Tanks W-8, W-9, and W-10 are integral and connected to the dry wells; (3) the STF drain system appears to

be functioning properly. This report presents these results

and describes the release monitoring plan for the consolidation tanks and during waste removal operations at all of the

tanks in the STF.

514

(ORNL/ER–423)

Cold test plan for the Old Hydrofracture Facility tank

contents removal project, Oak Ridge National Laboratory, Oak Ridge, Tennessee. Oak Ridge National Lab.,

Oak Ridge, TN 37831 (United States);CDM Federal Programs Corp., Oak Ridge, TN 37830 (United States). Nov

1997. [200p.] Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract AC05-84OR21400. Order Number DE98005212.

Source: OSTI; NTIS; INIS; GPO Dep.

This Old Hydrofracture Facility (OHF) Tanks Contents Removal Project Cold Test Plan describes the activities to be

conducted during the cold test of the OHF sluicing and

pumping system at the Tank Technology Cold Test Facility

(TTCTF). The TTCTF is located at the Robotics and

Process Systems Complex at the Oak Ridge National Laboratory (ORNL). The cold test will demonstrate performance

of the pumping and sluicing system, fine-tune operating instructions, and train the personnel in the actual work to be

performed. After completion of the cold test a Technical

Memorandum will be prepared documenting completion of

the cold test, and the equipment will be relocated to the

OHF site.

515

(ORNL/ER–425/V1)

In situ vitrification demonstration at Pit 1, Oak Ridge

National Laboratory. Volume 1: Results of treatability

study. Spalding, B.P. (Oak Ridge National Lab., TN (United

States). Environmental Sciences Div.); Naney, M.T.; Cline,

S.R.; Bogle, M.A.; Tixier, J.S. Oak Ridge National Lab., TN

(United States). Dec 1997. 169p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States). DOE Contract AC05-84OR21400. Order Number

DE98001954. Source: OSTI; NTIS; INIS; GPO Dep.

A treatability study was initiated in October 1993 to apply

in situ vitrification (ISV) to at least two segments of Oak

Ridge National Laboratory (ORNL) seepage Pit 1 by the end

of fiscal year (FY) 1995. This treatability study was later extended to include all of Pit 1 and was performed to support

a possible Interim Record of Decision or removal action for

closure of one or more of the seepage pits and trenches beginning as early as FY 1997. This treatability study was

carried out to establish the field-scale technical performance

of ISV for (1) attaining the required depth, nominally 15 ft, to

incorporate source contamination within and beneath the

pits; (2) demonstrating field capability for the overlap of melt

settings which will be necessary to achieve fused, melted

segments of the source contamination; (3) demonstrating

off-gas handling technology for accommodating and

minimizing the volatilization of 137Cs; (4) demonstrating adequate site characterization techniques to predict ISV melting

kinetics, processing temperatures, and product durability;

and (5) promoting public acceptance of ISV technology by

demonstrating its safety, implementability, site impacts, and

air emissions and by coordinating the treatability study

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

within the regulatory closure process. In April 1996 an expulsion of an estimated 10% of the 196 Mg (216 tons) melt

body occurred resulting in significant damage to ISV equipment and, ultimately, led to an indefinite suspension of

further ISV operations at Pit 1. This report summarizes the

technical accomplishments and status of the project in fulfilling these objectives through September 1997.

516

(ORNL/ER–425/V2)

In situ vitrification demonstration at Pit 1, Oak Ridge National Laboratory. Volume 2: Site characterization report

of the Pit 1 area. Spalding, B.P.; Bogle, M.A.; Cline, S.R.;

Naney, M.T.; Gu, B. Oak Ridge National Lab., TN (United

States). Dec 1997. [200p.] Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract AC05-84OR21400. Order Number

DE98001955. Source: OSTI; NTIS; INIS; GPO Dep.

A treatability study was initiated in October 1993, initially

encompassing the application of in situ vitrification (ISV) to

at least two segments of Oak Ridge National Laboratory

(ORNL) seepage Pit 1 by the end of fiscal year (FY) 1995.

This treatability study was to have supported a possible

Interim Record of Decision (IROD) or removal action for closure of one or more of the seepage pits and trenches as

early as FY 1997. The Remedial Investigation/Feasibility

Study for Waste Area Grouping (WAG) 7, which contains

these seven seepage pits and trenches, will probably not

begin until after the year 2000. This treatability study will establish the field-scale technical performance of ISV for (1)

attaining the required depth, nominally 15 ft, to incorporate

source contamination within and beneath the pits; (2)

demonstrating field capability to overlap melt settings that

are necessary to achieve fused, melted segments of the

source contamination; (3) demonstrating off-gas handling

technology for accommodating and minimizing the

volatilization of 137Cs; (4) demonstrating adequate site characterization techniques to predict ISV melting kinetics,

processing temperatures, and product durability; and (5)

promoting public acceptance of ISV technology by demonstrating its safety, implementability, site impacts, and air

emissions and by coordinating the treatability study within

the regulatory closure process. This report summarizes the

site characterization information gathered through the end of

September 1996 which supports the planning and assessment of ISV for Pit 1 (objective 4 above).

517

(ORNL/ER–428)

Completion report for the isolation and remediation of

inactive liquid low-level radioactive waste tanks WC-5,

WC-6, WC-8, WC-19, 3002-A, 7560, and 7562 at Oak

Ridge National Laboratory Oak Ridge, Tennessee. Oak

Ridge National Lab., TN (United States). Dec 1997. 15p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC05-84OR21400. Order Number DE98001661. Source:

OSTI; NTIS; INIS; GPO Dep.

The Federal Facility Agreement (FFA) between the U.S.

Environmental Protection Agency (EPA), Tennessee Department of Environment and Conservation (TDEC), and U.S.

Department of Energy (DOE) requires that all liquid low-level

waste tanks at Oak Ridge National Laboratory removed

from service, designated in the FFA as Category D, be remediated in accordance with Comprehensive Environmental

Response, Compensation, and Liability Act (CERCLA) requirements. A human health risk screening assessment was

conducted for inactive Tanks WC-5, WC-6, WC-8, WC-19,

3002-A, 7560, and 7562 as part of an evaluation to determine the method of remediation necessary to safely and

permanently isolate and remediate the tanks. Risk screening

assessment results indicated that the health risks associated with these tanks were within or below the EPA range of

concern of 1 x 104 to 1 x 106. On the basis of these results and with regulators concurrence, it was determined

that either no action or in-place stabilization of the tanks

would satisfy risk-based remediation goals. Therefore, decisions were made and approved by DOE to remediate these

tanks in-place as maintenance actions rather than actions

under the CERCLA process. Letters documenting these decisions were approved by DOE and subsequently submitted

to TDEC and EPA, who concurred with the maintenance actions. Tanks WC-5, WC-6, WC-8, WC-19, 3002-A, 7560,

and 7562 were isolated from associated piping, electrical

systems, and instrumentation and were grouted in-place.

Tank 7562 was originally isolated from associated piping

and instrumentation and left in-place empty for future remedial consideration. Upon further consideration, the decision

was made by DOE, with concurrence by the regulators, to

complete the maintenance action of Tank 7562 by grouting it

in-place in March 1997.

518

(ORNL/ER–429)

ALARA plan for the Old Hydrofracture Facility tanks

contents removal project at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Oak Ridge National Lab., TN

(United States);CDM Federal Programs Corp., Oak Ridge,

TN (United States). Apr 1998. [100p.] Sponsored by USDOE Office of Environmental Management, Washington, DC

(United States). DOE Contract AC05-98OR22700. Order

Number DE98004692. Source: OSTI; NTIS; INIS; GPO Dep.

The purpose of the Old Hydrofracture Facility (OHF)

Tanks Contents Removal Project is to remove the liquid lowlevel waste from the five underground storage tanks located

at OHF and transfer the resulting slurry to the Melton Valley

Storage Tanks facility for treatment and disposal. Among the

technical objectives for the OHF Project, there is a specific

provision to maintain personnel exposures as low as reasonably achievable (ALARA) during each activity of the

project and to protect human health and the environment.

The estimated doses and anticipated conditions for accomplishing this project are such that an ALARA Plan is

necessary to facilitate formal radiological review of the campaign. This ALARA Plan describes the operational steps

necessary for accomplishing the job together with the associated radiological impacts and planned controls. Individual

and collective dose estimates are also provided for the various tasks. Any significant changes to this plan (i.e., planned

exposures that are greater than 10% of original dose estimates) will require formal revision and concurrence from all

parties listed on the approval page. Deviations from this

plan (i.e., work outside the scope covered by this plan) also

require the preparation of a task-specific ALARA Review

that will be amended to this plan with concurrence from all

parties listed on the approval page.

519

(ORNL/ER–429/A1)

ALARA plan for the Old Hydrofracture Facility tanks

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

contents removal project at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Amendment 1 for Appendix

B: Install flex-pipe on tank riser spools. Oak Ridge National Lab., TN (United States);CDM Federal Programs

Corp., Oak Ridge, TN (United States). 13 May 1998. 13p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC05-98OR22700. Order Number DE98005168. Source:

OSTI; NTIS; INIS; GPO Dep.

This amendment to Appendix B contains the specific

ALARA evaluations for installing flex-pipe on riser spools to

accommodate ventilation duct connections to the north risers of each tank. The work will be a routine task that is part

of the Equipment Installation and Mobilization phase of the

project. The dose rates were estimated using the recent Radiological Surveillance Section radiological survey:

SAAS-97-063S. Task B-6 has been added to the OHF

Project ALARA review process to address a field decision to

modify an approach to installing the tank ventilation system.

The revised approach will incorporate 12-in. diameter, 36-in.

long, stainless steel flex-pipe connected to each north riser

spool to address the problem of pipe fitting multiple bends

and turns expected with the 12-in. PVC duct. This improved

approach will reduce the time necessary to install the duct

system between the tanks and the ventilation skid. However,

the task includes opening the 12-in. riser spool connections

to replace the currently installed blind gaskets. Since a riser

spool for each tank will be opened, there is a potential for

significant personnel exposure and spread of contamination

that will addressed through this ALARA review process.

520

(ORNL/ER–433/V1)

Old hydrofracture facility tanks contents removal action

operations plan at the Oak Ridge National Laboratory,

Oak Ridge, Tennessee. Volume 1: Text. Volume 2:

Checklists and work instructions. CDM Federal Programs

Corp., Oak Ridge, TN (United States). May 1998. 53p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC05-98OR22700. Order Number DE98005138. Source:

OSTI; NTIS; INIS; GPO Dep.

This Operations Plan summarizes the operating activities

for transferring contents of five low-level (radioactive) liquid

waste storage tanks associated with the Old Hydrofracture

Facility (OHF) to the Melton Valley Storage Tanks (MVST)

for secure storage. The transfer will be accomplished

through sluicing and pumping operations which are designed to pump the slurry in a closed circuit system using a

sluicing nozzle to resuspend the sludge. Once resuspended,

the slurry will be transferred to the MVST. The report documenting the material transfer will be prepared after transfer

of the tank materials has been completed. The OBF tanks

contain approximately 52,600 gal (199,000 L) of low-level

radioactive waste consisting of both sludge and supernatant.

This material is residual from the now-abandoned grout injection operations conducted from 1964 to 1980. Total curie

content is approximately 30,000 Ci. A sluicing and pumping

system has been specifically designed for the OHF tanks

contents transfer operations. This system is remotely operated and incorporates a sluicing nozzle and arm (Borehole

Miner) originally designed for use in the mining industry. The

Borehole Miner is an in-tank device designed to deliver a

high pressure jet spray via an extendable nozzle. In addition

to removing the waste from the tanks, the use of this equipment will demonstrate applicability for additional

underground storage tank cleaning throughout the U.S. Department of Energy complex. Additional components of the

complete sluicing and pumping system consist of a high

pressure pumping system for transfer to the MVST, a low

pressure pumping system for transfer to the recycle tank, a

ventilation system for providing negative pressure on tanks,

and instrumentation and control systems for remote operation and monitoring.

521

(ORNL/ER–434)

Dismantlement and removal of Old Hydrofracture Facility bulk storage bins and water tank, Oak Ridge National

Laboratory, Oak Ridge, Tennessee. Oak Ridge National

Lab., TN (United States);Allied Technology Group, Inc., Oak

Ridge, TN (United States). Mar 1998. 112p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract AC05-84OR21400. Order

Number DE98003426. Source: OSTI; NTIS; INIS; GPO Dep.

The Old Hydrofracture Facility (OHF), located at Oak

Ridge National Laboratory (ORNL), was constructed in 1963

to allow experimentation and operations with an integrated

solid storage, mixing, and grout injection facility. During its

operation, OHF blended liquid low-level waste with grout

and used a hydrofracture process to pump the waste into a

deep low-permeable shale formation. Since the OHF Facility

was taken out of service in 1980, the four bulk storage bins

located adjacent to Building 7852 had deteriorated to the

point that they were a serious safety hazard. The ORNL

Surveillance and Maintenance Program requested and received permission from the US Department of Energy to

dismantle the bins as a maintenance action and send the

free-released metal to an approved scrap metal vendor. A

25,000-gal stainless steel water tank located at the OHF site

was included in the scope. A fixed-price subcontract was

signed with Allied Technology Group, Inc., to remove the

four bulk storage bins and water tank to a staging area

where certified Health Physics personnel could survey, segregate, package, and send the radiologically clean scrap

metal to an approved scrap metal vendor. All radiologically

contaminated metal and metal that could not be surveyed

was packaged and staged for later disposal. Permissible

personnel exposure limits were not exceeded, no injuries

were incurred, and no health and safety violations occurred

throughout the duration of the project. Upon completion of

the dismantlement, the project had generated 53,660 lb of

clean scrap metal (see Appendix D). This resulted in $3,410

of revenue generated and a cost avoidance of an estimated

$100,000 in waste disposal fees.

522

(ORNL/ER–436)

Groundwater quality assessment report for Solid Waste

Storage Area 6 at Oak Ridge National Laboratory, Oak

Ridge, Tennessee – 1997. Oak Ridge National Lab., TN

(United States). Feb 1998. 186p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States). DOE Contract AC05-84OR21400. Order Number

DE98003432. Source: OSTI; NTIS; INIS; GPO Dep.

Solid Waste Storage Area (SWSA) 6, located at the US

Department of Energy (DOE) Oak Ridge National Laboratory

(ORNL) facility, is a shallow land burial site for low-level radioactive waste (LLW) and other waste types. Wastes were

131
ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

disposed of in unlined trenches and auger holes from 1969

until May 1986, when it was determined that Resource Conservation and Recovery Act (RCRA) regulated wastes were

being disposed of there. DOE closed SWSA 6 until changes

in operating procedures prevented the disposal of RCRA

wastes at SWSA 6. The site, which reopened for waste disposal activities in July 1986, is the only currently operating

disposal area for low-level radioactive waste at ORNL. In addition to SWSA 6, it was determined that hazardous wastes

were treated at the Explosives Detonation Trench (EDT).

Explosives and shock-sensitive chemicals such as picric

acid, phosphorus, and ammonium nitrate were detonated;

debris from the explosions was backfilled into the trench.

523

(ORNL/ER–437)

GAAT dry well conductivity monitoring report, July 1997

through January 1998, Oak Ridge National Laboratory,

Oak Ridge, Tennessee. Oak Ridge National Lab., TN

(United States);Vista Research, Inc., Oak Ridge, TN (United

States). 13 Mar 1998. 32p. Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract AC05-84OR21400. Order Number

DE98003406. Source: OSTI; NTIS; INIS; GPO Dep.

A waste removal program is being implemented for the

Gunite and Associated Tanks (GAAT) Operable Unit at Oak

Ridge National Laboratory (ORNL), Oak Ridge, Tennessee.

The waste is being removed by means of remotely operated, in-tank, confined sluicing equipment. The waste

removal operations in Tanks W-3 and W-4 in the North Tank

Farm (NTF) have been completed and the equipment is being moved to the South Tank Farm (STF), where it will be

used to remove the sludges from the six STF tanks (W-5,

W-6, W-7, W-8, W-9, and W-10) beginning later this year.

During sluicing operations the dry wells adjacent to each of

the tanks are instrumented so that potential releases can be

detected by means external to the tank. The method of detection is by monitoring the electrical conductivity of the

water in the dry well associated with each tank. This report

documents the dry well conductivity monitoring data for the

period from July 1997 through January 1998. The dry wells

monitored during this period include DW-3, DW-4, DW-8,

DW-9, and DW-10. The conductivity of the water passing

through Pump Station 1 (PS 1) was also monitored. The

principal activities that occurred during this period were the

sluicing of Tanks W-3 and W-4 in the NTF, transfer of tank

liquids from the NTF to the STF, and the installation of new

risers, tank dome leveling, and emplacement of stabilized

base backfill in the STF. Presented in this report are the dry

well conductivity, rainfall, tank level, and STF construction

information that is relevant to the analysis and interpretation

of the monitoring data for the reporting period. A thorough

analysis of the monitoring results for the period indicates

that no releases have occurred from the gunite tanks being

monitored.

524

(ORNL/M–3788)

Active Sites Environmental Monitoring Program FY 1994

annual report. Morrissey, C.M.; Cunningham, G.R. Oak

Ridge National Lab., TN (United States). Apr 1998. 71p.

Sponsored by USDOE, Washington, DC (United

States);USDOE Office of Environmental Management,

Washington, DC (United States). DOE Contract AC05-

96OR22464. Order Number DE98058112. Source: OSTI;

NTIS; INIS; GPO Dep.

Environmental Sciences Division publication number 4336.

Chapter III of the US Department of Energy (DOE) Order

5820.2A (DOE 1988) specifies requirements for the management of facilities that were used for the disposal of

radioactive solid low-level waste (LLW) on or after the date

of the order (September 26, 1988). Activities in Solid Waste

Storage Area (SWSA) 6 at Oak Ridge National Laboratory

(ORNL) are governed by Chapter III. Chapter II of 5820.2A

covers the transuranic (TRU) waste storage areas in SWSA

5 North at ORNL. Both chapters require environmental monitoring to provide early warning of leaks before such leaks

pose a threat to human health or the environment. Chapter

III also requires the monitoring of LLW disposal facilities so

that their performance can be evaluated. In order to comply

with this Order, the Environmental Sciences Division (ESD)

at ORNL implements the Active Sites Environmental Monitoring Program (ASEMP) for the Radioactive Solid Waste

Operations (RSWO) Department within the Waste Management and Remedial Action Division (WMRAD) at ORNL. The

scope of the ASEMP includes all ORNL waste disposal sites

that were active on or after the date of the Order and that

are under the operational control of the RSWO Department

of WMRAD. This report continues a series of annual and

semiannual reports that present the results of ASEMP monitoring activities. This report details monitoring data for fiscal

year (FY) 1994 and is divided into three major areas: SWSA

6, including the Interim Waste Management Facility (IWMF)

and the Hillcut Disposal Test Facility (HDTF), the low-level

Liquid-Waste Solidification Project (LWSP), and the TRUwaste storage areas in SWSA 5 N. This report presents a

summary of the methodology used to gather data for each

major area along with the results obtained during FY 1994.

Tables of data collected are presented in Appendix A.

Program-specific procedures used to collect the data are

presented at the end of the report in Appendix B.

525

(ORNL/M–5507)

Active Sites Environmental Monitoring Program FY 1996

annual report. Morrissey, C.M.; Marshall, D.S.; Cunningham, G.R. Oak Ridge National Lab., TN (United States).

Nov 1997. 85p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE

Contract AC05-96OR22464. Order Number DE98003775.

Source: OSTI; NTIS; INIS; GPO Dep.

Environmental Sciences Div. publication number 4611.

This report summarizes the activities of the Active Sites

Environmental Monitoring Program (ASEMP) from October

1995 through September 1996. The Radioactive Solid Waste

Operations Group (RSWOG) of the Waste Management and

Remedial Action Division (WMRAD) and the Environmental

Sciences Division (ESD) at Oak Ridge National Laboratory

(ORNL) established ASEMP in 1989. The purpose of the

program is to provide early detection and performance monitoring at active low-level waste (LLW) disposal sites in Solid

Waste Storage Area (SWSA) 6 and transuranic (TRU) waste

storage sites in SWSA 5 North as required by Chapters 2

and 3 of US Department of Energy Order 5820.2A.

526

(ORNL/M–6163)

Active sites environmental monitoring program FY 1997

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

annual report. Morrissey, C.M.; Marshall, D.S.; Cunningham, G.R. Oak Ridge National Lab., TN (United States).

Mar 1998. 76p. Sponsored by USDOE, Washington, DC

(United States);USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC05-96OR22464. Order Number DE98054810. Source:

OSTI; NTIS; INIS; GPO Dep.

Environmental Sciences Division publication number 4714.

This report summarizes the activities conducted by the

Active Sites Environmental Monitoring Program (ASEMP)

from October 1996 through September 1997. The purpose

of the program is to provide early detection and performance monitoring at active low-level waste (LLW) disposal

sites in Solid Waste Storage Area (SWSA) 6 and transuranic

(TRU) waste storage sites in SWSA 5 North. This report

continues a series of annual and semiannual reports that

present the results of ASEMP monitoring activities. This report details monitoring results for fiscal year (FY) 1997 from

SWSA 6, including the Interim Waste Management Facility

(IWMF) and the Hillcut Disposal Test Facility (HDTF), and

(2) TRU-waste storage areas in SWSA 5 N. This report

presents a summary of the methodology used to gather data

for each major area along with the FY 1997 results. Figures

referenced in the text are found in Appendix A and data tables are presented in Appendix B.

527

(ORNL/M–6549)

Development of nuclear analysis capabilities for DOE

waste management activities. Parks, C.V.; DeHart, M.D.;

Broadhead, B.L.; Hopper, C.M.; Petrie, L.M. Oak Ridge National Lab., TN (United States). May 1998. 5p. Sponsored

by USDOE, Washington, DC (United States);USDOE Office

of Environmental Management, Washington, DC (United

States). DOE Contract AC05-96OR22464. Order Number

DE98058119. Source: OSTI; NTIS; INIS; GPO Dep.

The objective of this project is to develop and demonstrate prototypic analysis capabilities that can be used by

the nuclear safety analysis practitioners to: (1) demonstrate

a more thorough understanding of the underlying physics

phenomena that can lead to improved reliability and defensibility of safety evaluations; and (2) optimize operations

related to the handling, storage, transportation, and disposal

of fissile material and DOE spent fuel. To address these

problems, the project will investigate the implementation of

sensitivity and uncertainty methods within existing Monte

Carlo codes used for criticality safety analyses, as well as

within a new deterministic code that allows specification of

arbitrary grids to accurately model the geometry details

required in a criticality safety analysis. This capability can facilitate improved estimations of the required subcritical

margin and potentially enable the use of a broader range of

experiments in the validation process. The new arbitrary-grid

radiation transport code will also enable detailed geometric

modeling valuable for improved accuracy in application to a

myriad of other problems related to waste characterization.

Application to these problems will also be explored.

528

(ORNL/TM–13169)

Hot demonstration of proposed commercial cesium removal technology. Lee, D.D.; Travis, J.R.; Gibson, M.R.

Oak Ridge National Lab., TN (United States). Dec 1997.

64p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States);USDOE Assistant

Secretary for Policy, Planning and Program Evaluation,

Washington, DC (United States). DOE Contract AC05-

96OR22464. Order Number DE98003624. Source: OSTI;

NTIS; INIS; GPO Dep.

This report describes the work done in support of the development of technology for the continuous removal and

concentration of radioactive cesium in supernatant from

Melton Valley Storage Tanks (MVSTs) at the ORNL site. The

primary objective was to test candidate absorbers and ion

exchangers under continuous-flow conditions using actual

supernatant from the MVSTs. An experimental system contained in a hot-cell facility was constructed to test the

materials in columns or modules using the same batch of

supernatant to allow comparison on an equal basis. Resorcinol/formaldehyde (RF) resin was evaluated at three flow

rates with 50% breakthrough ranges of 35 to 50 column volumes (CV) and also through a series of five loading/elution/

regeneration cycles. The results reported here include the

cesium loading breakthrough curves, elution curves (when

applicable), and operational problems and observations for

each material. The comparative evaluations should provide

critical data for the selection of the sorbent for the ORNL

Cesium Removal Demonstration project. These results will

be used to help determine the design parameters for

demonstration-scale systems. Such parameters include

rates of cesium removal, quantity of resin or sorbent to be

used, and elution and regeneration requirements, if applicable.

529

(ORNL/TM–13325)

Development of a path forward for special-case wastes

at the Oak Ridge Reservation. Osborne-Lee, I.W. (Oak

Ridge National Lab., TN (United States)); Lotts, A.L.; Robinette, R.J. Oak Ridge National Lab., TN (United States). 1

Oct 1997. 105p. Sponsored by USDOE, Washington, DC

(United States);USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC05-96OR22464. Order Number DE98003611. Source:

OSTI; NTIS; INIS; GPO Dep.

This report addresses the management of the inventory of

existing and potential surplus equipment and materials at

the Oak Ridge Reservation (ORR) that are candidates for

various waste or surplus material categories, including special case waste (SCW). This inventory is called candidate

equipment and materials (CEM). This report presents a

logical method for disposition of this and future CEM, summarizes the inventory, and suggests preliminary dispositions

for the CEM. Also, recommendations are offered for an improved CEM management strategy and actions in this and

future years to implement that strategy.

530

(ORNL/TM–13351-Add.1)

Statistical description of liquid low-level waste system

supernatant liquids at Oak Ridge National Laboratory,

Oak Ridge, Tennessee. DeVore, J.R. (ed.); Bayne, C.K.;

Walker, A.B. Oak Ridge National Lab., TN (United States).

Oct 1997. 51p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE

Contract AC05-96OR22464. Order Number DE98003650.

Source: OSTI; NTIS; INIS; GPO Dep.

The Department of Energy has presented plans for processing transuranic low level liquid wastes located at ORNL.

The Tennessee Department of Health and Environment has

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

mandated the beginning of processing of these wastes by

the year 2002, looking towards permanent disposal at a site

located off the reservation. In order to meet this schedule,

the DOE will solicit bids from various private sector companies to construct a processing facility to be operated by the

private sector on a contract basis. In support of the Request

for Proposal (RFP) process to accomplish the private sector

involvement, this report is being written to give potential

vendors information about the wastes contained in the

ORNL tank farm system. This addendum report consolidates all data that presently exist on the properties and

composition of the waste supernatant liquids, and presents

methods to calculate the error bounds of the data in the best

technically defensible manner possible.

531

(ORNL/TM–13363)

Hot demonstration of proposed commercial cesium removal technology: Progress report. Lee, D.D.; Travis,

J.R.; Gibson, M.R. Oak Ridge National Lab., TN (United

States). Dec 1997. 88p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States).

DOE Contract AC05-96OR22464. Order Number

DE98054255. Source: OSTI; NTIS; INIS; GPO Dep.

Cesium, strontium, and technetium radionuclides constitute a small fraction of the primarily sodium and potassium

salts present in supernatants that are being stored in tanks

at Hanford, Oak Ridge, Savannah River, and Idaho and

must be remediated. Nuclide removal technologies supplied

by the US Department of Energy Office of Science and

Technology’s Efficient Separations and Processing (ESP)

Cross-Cutting Program have been previously proposed and

tested in small batch and column tests using both simulated

and actual supernatants. These technologies must now be

tested and the most appropriate ones selected using a flow

system of a scale suitable to obtain engineering data that

can be applied to the design of pilot-scale equipment. This

report describes the operation of the experimental test unit

that is located in Building 4501 (ORNL) and the results using the sorbent materials that were tested.

532

(ORNL/TM–13451)

Evaluation of operating characteristics for a chabazite

zeolite system for treatment of process wastewater at

Oak Ridge National Laboratory. Kent, T.E.; Perona, J.J.;

Jennings, H.L.; Lucero, A.J.; Taylor, P.A. Oak Ridge National Lab., TN (United States). Feb 1998. 58p. Sponsored

by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract AC05-96OR22464.

Order Number DE98006010. Source: OSTI; NTIS; INIS;

GPO Dep.

Laboratory and pilot-scale testing were performed for development and design of a chabazite zeolite ion-exchange

system to replace existing treatment systems at the Process

Waste Treatment Plant (PWTP) at Oak Ridge National Laboratory (ORNL). The process wastewater treatment systems

at ORNL need upgrading to improve efficiency, reduce

waste generation, and remove greater quantities of contaminants from the wastewater. Previous study indicated that

replacement of the existing PWTP systems with an ionexchange system using chabazite zeolite will satisfy these

upgrade objectives. Pilot-scale testing of the zeolite system

was performed using a commercially available ion-exchange

system to evaluate physical operating characteristics and to

validate smaller-scale column test results. Results of this

test program indicate that (1) spent zeolite can be sluiced

easily and completely from a commercially designed vessel,

(2) clarification followed by granular anthracite prefilters is

adequate pretreatment for the zeolite system, and (3) the

length of the mass transfer zone was comparable with that

obtained in smaller-scale column tests. Laboratory studies

were performed to determine the loading capacity of the zeolite for selected heavy metals. These test results indicated

fairly effective removal of silver, cadmium, copper, mercury,

nickel, lead, and zinc from simple water solutions. Heavymetals data collected during pilot-scale testing of actual

wastewater indicated marginal removal of iron, copper, and

zinc. Reduced effectiveness for other heavy metals during

pilot testing can be attributed to the presence of interfering

cations and the relatively short zeolite/wastewater contact

time. Flocculating agents (polyelectrolytes) were tested for

pretreatment of wastewater prior to the zeolite flow-through

column system. Several commercially available polyelectrolytes were effective in flocculation and settling of

suspended solids in process wastewater.

533

(ORNL/TM–13496)

Alternative methods to determine headwater benefits.

Bao, Y.S.; Perlack, R.D.; Sale, M.J. Oak Ridge National

Lab., TN (United States). 10 Nov 1997. 68p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract AC05-96OR22464. Order

Number DE98054232. Source: OSTI; NTIS; GPO Dep.

In 1992, the Federal Energy Regulatory Commission

(FERC) began using a Flow Duration Analysis (FDA)

methodology to assess headwater benefits in river basins

where use of the Headwater Benefits Energy Gains (HWBEG) model may not result in significant improvements in

modeling accuracy. The purpose of this study is to validate

the accuracy and appropriateness of the FDA method for

determining energy gains in less complex basins. This report presents the results of Oak Ridge National Laboratory’s

(ORNL’s) validation of the FDA method. The validation is

based on a comparison of energy gains using the FDA

method with energy gains calculated using the MWBEG

model. Comparisons of energy gains are made on a daily

and monthly basis for a complex river basin (the Alabama

River Basin) and a basin that is considered relatively simple

hydrologically (the Stanislaus River Basin). In addition to

validating the FDA method, ORNL was asked to suggest

refinements and improvements to the FDA method. Refinements and improvements to the FDA method were carried

out using the James River Basin as a test case.

534

(ORNL/TM–13497)

Evaluation of improved techniques for the removal of

fission products from process wastewater and groundwater: FY 1997 status. Bostick, D.T.; DePaoli, S.M.; Guo,

B. Oak Ridge National Lab., TN (United States). Feb 1998.

100p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC05-96OR22464. Order Number DE98054245. Source:

OSTI; NTIS; INIS; GPO Dep.

The primary goals of this effort in FY 1997 were to survey

local end users of wastewater treatment technology and

then to evaluate recently available treatment processes in

light of user needs. Survey results indicate that local sites

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

are confronted with a limited, and shrinking, budget for treating aqueous waste streams. Therefore, a process will be

selected primarily on the basis of sorbent costs, use of existing equipment, and disposal costs for spent processing

materials. Current laboratory testing and economic studies

have been directed toward addressing the technical issues

specific to the removal of 90Sr and 137Cs from groundwater

and process wastewater. This year’s efforts have concentrated on evaluating the engineered form of crystalline

silicotitanates (CSTs) for near neutral pH applications. Both

powder and pellet forms of CST can be obtained through

UOP; this task evaluated only the engineered form of the

sorbent for wastewater remediation. Preliminary experimental efforts included measuring the average particle size,

surface water content, total sodium content, ion exchange

capacity, and equilibration mixing time. The as received material contains approximately 10% fines, which adhere to the

CST pellet. The cesium and strontium ion-exchange capacities, based on multiple contacts with 50 ppm of the metal,

are 0.8 meq/g and 1.1 meq/g, respectively. Batch tests indicated that an equilibrium mixing time of 100 h was required

for cesium sorption. Group 2 cations (Sr, Ca, and Mg) required greater than 500 h. Particle diffusion coefficients were

estimated for each of these cations from the batch studies.

535

(ORNL/TM–13501)

Out-of-tank evaporator demonstration. Final report.

Lucero, A.J. (and others); Jennings, H.L.; VanEssen, D.C.

Oak Ridge National Lab., TN (United States). Feb 1998.

58p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC05-96OR22464. Order Number DE98052496. Source:

OSTI; NTIS; INIS; GPO Dep.

The project reported here was conducted to demonstrate

a skid-mounted, subatmospheric evaporator to concentrate

liquid low-level waste (LLLW) stored in underground tanks at

Oak Ridge National Laboratory (ORNL). This waste is similar to wastes stored at Hanford and Savannah River. A

single-stage subatmospheric evaporator rated to produce 90

gallons of distillate per hour was procured from Delta Thermal, Inc., of Pensacola, Florida, and installed in an existing

building. During the 8-day demonstration, 22,000 gal of

LLLW was concentrated by 25% with the evaporator system.

Decontamination factors achieved averaged 5 x 106 (i.e.,

the distillate contained five million times less Cesium 137

than the feed). Evaporator performance substantially exceeded design requirements and expectations based on

bench-scale surrogate test data. Out-of tank evaporator

demonstration operations successfully addressed the feasibility of hands-on maintenance. Demonstration activities

indicate that: (1) skid-mounted, mobile equipment is a viable

alternative for the treatment of ORNL LLLW, and (2) handson maintenance and decontamination for movement to

another site is achievable. Cost analysis show that 10% of

the demonstration costs will be immediately recovered by

elimination of solidification and disposal costs. The entire

cost of the demonstration can be recovered by processing

the inventory of Melton Valley Storage Tank waste and/or

sluice water prior to solidifications. An additional savings of

approximately $200,000 per year can be obtained by processing newly generated waste through the system. The

results indicate that this type of evaporator system should

be considered for application across the DOE complex. 25

refs., 11 figs., 2 tabs.

536

(ORNL/TM–13503)

Cesium removal demonstration utilizing crystalline silicotitanate sorbent for processing Melton Valley Storage

Tank supernate: Final report. Walker, J.F. Jr. (and others);

Taylor, P.A.; Cummins, R.L. Oak Ridge National Lab., TN

(United States). Mar 1998. [200p.] Sponsored by USDOE

Office of Environmental Management, Washington, DC

(United States). DOE Contract AC05-96OR22464. Order

Number DE98058130. Source: OSTI; NTIS; INIS; GPO Dep.

This report provides details of the Cesium Removal

Demonstration (CsRD), which was conducted at Oak Ridge

National Laboratory (ORNL) on radioactive waste from the

Melton Valley Storage Tanks. The CsRD was the first largescale use of state-of-the-art sorbents being developed by

private industry for the selective removal of cesium and

other radionuclides from liquid wastes stored across the

DOE complex. The crystalline silicotitanate sorbent used in

the demonstration was chosen because of its effectiveness

in laboratory tests using bench-scale columns. The demonstration showed that the cesium could be removed from the

supernate and concentrated on a small-volume, solid waste

form that would meet the waste acceptance criteria for the

Nevada Test Site. During this project, the CsRD system processed > 115,000 L (30,000 gal) of radioactive supernate

with minimal operational problems. Sluicing, drying, and remote transportation of the sorbent, which could not be done

on a bench scale, were successfully demonstrated. The system was then decontaminated to the extent that it could be

contact maintained with the use of localized shielding only.

By utilizing a modular, transportable design and placement

within existing facilities, the system can be transferred to different sites for reuse. The initial unit has now been removed

from the process building and is presently being reinstalled

for use in baseline operations at ORNL.

537

(ORNL/TM–13506)

Passivation of fluorinated activated charcoal. Del Cul,

G.D.; Trowbridge, L.D.; Simmons, D.W.; Williams, D.F.;

Toth, L.M. Oak Ridge National Lab., TN (United States). Oct

1997. 66p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract AC05-96OR22464. Order Number DE98051991.

Source: OSTI; NTIS; INIS; GPO Dep.

The Molten Salt Reactor Experiment (MSRE), at the Oak

Ridge National Laboratory has been shut down since 1969

when the fuel salt was drained from the core into two

Hastelloy N tanks at the reactor site. In 1995, a multiyear

project was launched to remediate the potentially hazardous

conditions generated by the movement of fissile material

and reactive gases from the storage tanks into the piping

system and an auxiliary charcoal bed (ACB). The top 12 in.

of the ACB is known by gamma scan and thermal analysis

to contain about 2.6 kg U-233. According to the laboratory

tests, a few feet of fluorinated charcoal are believed to extend beyond the uranium front. The remainder of the ACB

should consist of unreacted charcoal. Fluorinated charcoal,

when subjected to rapid heating, can decompose generating

gaseous products. Under confined conditions, the sudden

exothermic decomposition can produce high temperatures

and pressures of near-explosive characteristics. Since it will

be necessary to drill and tap the ACB to allow installation of

piping and instrumentation for remediation and recovery activities, it is necessary to chemically convert the reactive

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

fluorinated charcoal into a more stable material. Ammonia

can be administered to the ACB as a volatile denaturing

agent that results in the conversion of the CxF to carbon and

ammonium fluoride, NH4F. The charcoal laden with NH4F

can then be heated without risking any sudden decomposition. The only consequence of heating the treated material

will be the volatilization of NH4F as a mixture of NH3 and

HF, which would primarily recombine as NH4F on surfaces

below 200 C. The planned scheme for the ACB denaturing

is to flow diluted ammonia gas in steps of increasing NH3

concentration, 2% to 50%, followed by the injection of pure

ammonia. This report summarizes the planned passivation

treatment scheme to stabilize the ACB and remove the potential hazards. (Abstract truncated)

538

(ORNL/TM–13513)

Current and projected liquid low-level waste generation

at ORNL. DePaoli, S.M.; Walker, A.B. Oak Ridge National

Lab., TN (United States). Mar 1998. 34p. Sponsored by USDOE Office of Environmental Management, Washington, DC

(United States). DOE Contract AC05-96OR22464. Order

Number DE98054243. Source: OSTI; NTIS; INIS; GPO Dep.

Liquid low level waste (LLLW) is generated by various

programs and projects throughout Oak Ridge National Laboratory (ORNL). This waste is collected via bottles, trucks, or

underground collection tanks. It is then neutralized with

sodium hydroxide, reduced in volume at the ORNL LLLW

evaporator, and stored as concentrated LLLW in one of

twelve storage tanks. Many other tanks (called inactive

tanks), which contain historical liquids and sludges generated by past activities, will be remediated; the sludges and

associated sluicing and scabbling liquids will then be transferred to the active system for treatment and storage. This

report presents historical and projected data concerning the

volume and the characterization of LLLW, both prior to and

after evaporation. Storage space for projected waste generation is also discussed.

539

(ORNL/TM–13516)

R-matrix analysis of 235U neutron transmission and

cross sections in the energy range 0 to 2.25 keV. Leal,

L.C.; Derrien, H.; Larson, N.M.; Wright, R.Q. Oak Ridge National Lab., TN (United States). Nov 1997. 117p. Sponsored

by USDOE, Washington, DC (United States);USDOE Office

of Environmental Management, Washington, DC (United

States). DOE Contract AC05-96OR22464. Order Number

DE98007037. Source: OSTI; NTIS; INIS; GPO Dep.

This document describes a new R-matrix analysis of 235U

cross section data in the energy range from 0 to 2,250 eV.

The analysis was performed with the computer code

SAMMY, that has recently been updated to permit, for the

first time, inclusion of both differential and integral data

within the analysis process. Fourteen differential data sets

and six integral quantities were used in this evaluation: two

measurements of fission plus capture, one of fission plus

absorption, six of fission alone, two of transmission, and one

of eta, plus standard values of thermal cross sections for fission, capture, and scattering, and of K1 and the Westcott

g-factors for both fission and absorption. An excellent representation was obtained for the high-resolution transmission,

fission, and capture cross-section data as well as for the integral quantities. The result is a single set of resonance

parameters spanning the entire range up to 2,250 eV, a decided improvement over the present ENDF/VI evaluation, in

which eleven discrete resonance parameter sets are required to cover that same energy range. This new evaluation

is expected to greatly improve predictability of the criticality

safety margins for nuclear systems in which 235U is present.

540

(ORNL/TM–13526)

Programmatic and technical requirements for the FMDP

fresh MOX fuel transport package. Ludwig, S.B. (and others); Michelhaugh, R.D.; Pope, R.B. Oak Ridge National

Lab., TN (United States). Dec 1997. [100p.] Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract AC05-96OR22464. Order

Number DE98007040. Source: OSTI; NTIS; INIS; GPO Dep.

This document is intended to guide the designers of the

package to all pertinent regulatory and other design requirements to help ensure the safe and efficient transport of the

weapons-grade (WG) fresh MOX fuel under the Fissile Materials Disposition Program. To accomplish the disposition

mission using MOX fuel, the unirradiated MOX fuel must be

transported from the MOX fabrication facility to one or more

commercial reactors. Because the unirradiated fuel contains

large quantities of plutonium and is not sufficient radioactive

to create a self-protecting barrier to deter the material from

theft, DOE intends to use its fleet of safe secure trailers

(SSTs) to provide the necessary safeguards and security for

the material in transit. In addition to these requirements,

transport of radioactive materials must comply with regulations of the Department of Transportation and the Nuclear

Regulatory Commission (NRC). In particular, NRC requires

that the packages must meet strict performance requirements. The requirements for shipment of MOX fuel (i.e.,

radioactive fissile materials) specify that the package design

is certified by NRC to ensure the materials contained in the

packages are not released and remain subcritical after undergoing a series of hypothetical accident condition tests.

Packages that pass these tests are certified by NRC as a

Type B fissile (BF) package. This document specifies the

programmatic and technical design requirements a package

must satisfy to transport the fresh MOX fuel assemblies.

541

(ORNL/TM–13534)

X-231A demonstration of in-situ remediation of DNAPL

compounds in low permeability media by soil fracturing

with thermally enhanced mass recovery or reactive barrier destruction. Siegrist, R.L. (Oak Ridge National Lab.,

TN (United States)); Lowe, K.S.; Murdoch, L.D.; Slack,

W.W.; Houk, T.C. Oak Ridge National Lab., TN (United

States). Mar 1998. [300p.] Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract AC05-96OR22464. Order Number

DE98058134. Source: OSTI; NTIS; INIS; GPO Dep.

The overall goal of the program of activities is to demonstrate robust and cost-effective technologies for in situ

remediation of DNAPL compounds in low permeability media (LPM), including adaptations and enhancements of

conventional technologies to achieve improved performance

for DNAPLs in LPM. The technologies sought should be potential for application at simple, small sites (e.g., gasoline

underground storage tanks) as well as at complex, larger

sites (e.g., DOE land treatment units). The technologies involved in the X-231A demonstration at Portsmouth Gaseous

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

Diffusion Plant (PORTS) utilized subsurface manipulation of

the LPM through soil fracturing with thermally enhanced

mass recovery or horizontal barrier in place destruction. To

enable field evaluation of these approaches, a set of four

test cells was established at the X-231A land treatment unit

at the DOE PORTS plant in August 1996 and a series of

demonstration field activities occurred through December

1997. The principal objectives of the PORTS X-231A

demonstration were to: determine and compare the operational features of hydraulic fractures as an enabling

technology for steam and hot air enhanced soil vapor

extraction and mass recovery, in situ interception and reductive destruction by zero valent iron, and in situ interception

and oxidative destruction by potassium permanganate; determine the interaction of the delivered agents with the LPM

matrix adjacent to the fracture and within the fractured zone

and assess the beneficial modifications to the transport and/

or reaction properties of the LPM deposit; and determine the

remediation efficiency achieved by each of the technology

strategies.

542

(ORNL/TM–13536)

Progress report and technology status development of

an EG and G Berthold LB-150 alpha/beta particulate

monitor for use on the East Tennessee Technology Park

Toxic Substances Control Act Incinerator. Shor, J.T.

(Oak Ridge National Lab., TN (United States). Chemical

Technology Div.); Singh, S.P.N.; Gibson, L.V. Jr. Oak Ridge

National Lab., Chemical Technology Div., TN (United

States). Jun 1998. 57p. Sponsored by USDOE, Washington,

DC (United States);USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC05-96OR22464 ; AC05-84OR21400. Order Number

DE98058135. Source: OSTI; NTIS; INIS; GPO Dep.

The purpose of this project was to modify and evaluate a

commercially available EG and G Berthold LB-150

alpha-beta radionuclide particulate monitor for the hightemperature and moisture-saturation conditions of the East

Tennessee Technology Park (formerly K-25 Site) Toxic Substances Control Act (TSCA) Incinerator stack. The monitor

was originally outfitted for operation at gas temperatures of

150 F on the defunct Los Alamos National Laboratory

(LANL) controlled air incinerator, and the objective was to

widen its operating envelope. A laboratory apparatus was

constructed that simulated the effects of water-saturated air

at the TSCA Incinerator stack-gas temperatures, 183 F. An

instrumented set of heat exchangers was constructed to

then condition the gas so that the radionuclide monitor could

be operated without condensation. Data were collected

under the conditions of the elevated temperatures and humidities and are reported herein, and design considerations

of the apparatus are provided. The heat exchangers and humidification equipment performed as designed, the Mylar

film held, and the instrument suffered no ill effects. However,

for reasons as yet undetermined, the sensitivity of the radionuclide detection diminishes as the gas temperature is

elevated, whether the gas is humidified or not. The manufacturer has had no experience with (a) the operation of the

monitor under these conditions and (b) any commercial market that might exist for an instrument that operates under

these conditions. The monitor was not installed into the

radiologically contaminated environment of the TSCA Incinerator stack pending resolution of this technical issue.

543

(ORNL/TM–13546)

Characterization of the C1 and C2 waste tanks located

in the BVEST system at ORNL. Keller, J.M.; Giaquinto,

J.M. Oak Ridge National Lab., TN (United States). Feb

1998. 88p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract AC05-96OR22464. Order Number DE98006008.

Source: OSTI; NTIS; INIS; GPO Dep.

There was a major effort to sample and analyze the Active Liquid Low-Level Waste (LLLW) tanks at ORNL which

include the Melton Valley Storage Tanks (MVST) and the

Bethel Valley Evaporator Service Tanks (BVEST). The characterization data summarized in this report was needed to

address waste processing options, address concerns dealing with the performance assessment (PA) data for the

Waste Isolation Pilot Plant (WIPP), evaluate the waste characteristics with respect to the waste acceptance criteria

(WAC) for WIPP and Nevada Test Site (NTS), address

criticality concerns, and meet DOT requirements for transporting the waste. This report discusses the analytical

characterization data for the supernatant and sludge in the

BVEST waste tanks C-1 and C-2. The isotopic data

presented in this report supports the position that fissile isotopes of uranium (233U and 235U) and plutonium (239Pu and 241Pu) were denatured as required by the administrative

controls stated in the ORNL LLLW waste acceptance criteria

(WAC). In general, the sludge in tanks C1 and C2 was

found to be hazardous based on RCRA characteristics and

the transuranic alpha activity was well above the 100 nCi/g

limit for TRU waste. Additional characteristics of the C1 and

C2 sludge inventory relative to the WIPP WAC limits for fissile gram equivalent, plutonium equivalent activity, and

thermal power from decay heat were estimated from the

data in this report and found to be far below the upper

boundary for any of the remote-handled transuranic waste

(RH-TRU) requirements for disposal of the waste in WIPP.

544

(ORNL/TM–13557)

Temperature inversions in the vicinity of Oak Ridge,

Tennessee, as characterized by tethersonde data. Blasing, T.J.; Wang, J.C.; Lombardi, D.A. Oak Ridge National

Lab., Energy Div., TN (United States). Jan 1998. 30p. Sponsored by USDOE Office of Environmental Management,

Washington, DC (United States). DOE Contract AC05-

96OR22464. Order Number DE98007469. Source: OSTI;

NTIS; INIS; GPO Dep.

Accidental releases of hazardous materials to the atmosphere may result from fires that create a buoyant plume

which may rise several hundred meters above the ground.

For such buoyant release cases, estimates of ground-level

concentrations may be as much as a factor of 100 lower

than similar, nonbuoyant releases. For the Oak Ridge

Reservation, safety analyses often examine buoyant release

accident scenarios and resulting downwind, ground-level

consequence estimates. For these analyses, careful consideration of buoyant plume rise is important. Plume rise can be

limited by a stable vertical atmospheric temperature profile,

commonly called an inversion, where the air temperature increases with height. There is a concern that inversions may

interact with the complex terrain on the Oak Ridge Reservation, particularly at the Y-12 Plant, which is located in a

relatively shallow but narrow valley, to trap the plume and

increase ground-level consequences. The purpose of this

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

paper is to review the available meteorological data that provide information on inversions in the Oak Ridge area.

545

(ORNL/TM–13566)

Homogeneous Reactor Experiment (HRE) Pond cryogenic barrier technology demonstration: Pre-barrier

subsurface hydrology and contaminant transport investigation. Moline, G.R. Oak Ridge National Lab., TN (United

States). Mar 1998. 57p. Sponsored by USDOE, Washington,

DC (United States);USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC05-96OR22464. Order Number DE98058137. Source:

OSTI; NTIS; INIS; GPO Dep.

Environmental Sciences Division publication 4732.

The Homogeneous Reactor Experiment (HRE) Pond is

the site of a former impoundment for radioactive wastes that

has since been drained, filled with soil, and covered with an

asphalt cap. The site is bordered to the east and south by a

tributary that empties into Melton Branch Creek and that

contains significant concentrations of radioactive contaminants, primarily 90Sr. Because of the proximity of the

tributary to the HRE disposal site and the probable flow of

groundwater from the site to the tributary, it is hypothesized

that the HRE Pond is a source of contamination to he creek.

As a means for temporary containment of contaminants

within the impoundment, a cryogenic barrier technology

demonstration was initiated in FY96 with a background

hydrologic investigation that continued through FY97. Cryogenic equipment installation was completed in FY97, and

freezing was initiated in September of 1997. This report documents the results of a hydrologic and geologic investigation

of the HRE Pond/cryogenic barrier site. The purpose of this

investigation is to evaluate the hydrologic conditions within

and around the impoundment in order to meet the following

objectives: (1) to provide a pre-barrier subsurface hydrologic

baseline for post-barrier performance assessment; (2) to

confirm that the impoundment is hydraulically connected to

the surrounding sediments; and (3) to determine the likely

contaminant exit pathways from the impoundment. The

methods of investigation included water level and temperature monitoring in a network of wells and standpipes in and

surrounding the impoundment, a helium tracer test conducted under ambient flow conditions, and geologic logging

during the drilling of boreholes for installation of cryogenic

probes and temperature monitoring wells.

546

(ORNL/TM–13575)

Demonstration of Mixed Waste Debris Macroencapsulation Using Sulfur Polymer Cement. Mattus, C.H. Oak

Ridge National Lab., TN (United States). Jul 1998. 53p.

Sponsored by USDOE, Washington, DC (United

States);USDOE Office of Environmental Management,

Washington, DC (United States). DOE Contract AC05-

96OR22464. Order Number DE98058140. Source: OSTI;

NTIS; INIS; GPO Dep.

This report covers work performed during FY 1997 as part

of the Evaluation of Sulfur Polymer Cement Fast-Track System Project. The project is in support of the ”Mercury

Working Group/Mercury Treatment Demonstrations - Oak

Ridge” and is described in technical task plan (TTP) OR16MW-61. Macroencapsulation is the treatment technology

required for debris by the U.S. Environmental Protection

Agency Land Disposal Restrictions (LDR) under the Resource Conservation and Recovery Act. Based upon the

results of previous work performed at Oak Ridge, the concept of using sulfur polymer cement (SPC) for this purpose

was submitted to the Mixed Waste Focus Area (MWFA). Because of the promising properties of the material, the MWFA

accepted this Quick Win project, which was to demonstrate

the feasibility of macroencapsulation of actual mixed waste

debris stored on the Oak Ridge Reservation. The waste acceptance criteria from Envirocare, Utah, were chosen as a

standard for the determination of the final waste form produced. During this demonstration, it was shown that SPC

was a good candidate for macroencapsulation of mixed

waste debris, especially when the debris pieces were dry.

The matrix was found to be quite easy to use and, once the

optimum operating conditions were identified, very straightforward to replicate for batch treatment. The demonstration

was able to render LDR compliant more than 400 kg of

mixed wastes stored at the Oak Ridge National Laboratory.

547

(ORNL/TM–13577)

Strategies for the cost effective treatment of Oak Ridge

legacy wastes. Compere, A.L.; Griffith, W.L.; Huxtable,

W.P.; Wilson, D.F. Oak Ridge National Lab., TN (United

States). Mar 1998. 24p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States).

DOE Contract AC05-96OR22464. Order Number

DE98058141. Source: OSTI; NTIS; INIS; GPO Dep.

Research and development treatment strategies for treatment or elimination of several Oak Ridge plant liquid, solid,

and legacy wastes are detailed in this report. Treatment

strategies for volumetrically contaminated nickel; enriched

uranium-contaminated alkali metal fluorides; uraniumcontaminated aluminum compressor blades; large,

mercury-contaminated lithium isotope separations

equipment; lithium process chlorine gas streams; highconcentration aluminum nitrate wastes, and high-volume,

low-level nitrate wastes are discussed. Research needed to

support engineering development of treatment processes is

detailed.

548

(ORNL/TM–13578)

Demonstration of fluidic pulse jet mixing for a horizontal

waste storage tank. Kent, T.E.; Taylor, S.A.; Moore, J.W.;

Stellern, J.L.; Billingsley, K.M. Oak Ridge National Lab., TN

(United States). Jan 1998. 87p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States). DOE Contract AC05-96OR22464. Order Number

DE98052498. Source: OSTI; NTIS; INIS; GPO Dep.

A fluidic pulse jet mixing system, designed and fabricated

by AEA Technology of the United Kingdom, was successfully demonstrated for mobilization and retrieval of remote

handled transuranic (RH-TRU) sludge from a 50,000-gal horizontal waste storage tank at Oak Ridge National Laboratory

(ORNL). The pulse jet system, consisting of seven modular

equipment skids, was installed and commissioned in about

7 weeks and operated remotely for 52 days to remove about

88% of the sludge in the tank. The system used specially

designed fluidic jet pumps and pulse vessels, along with existing submerged nozzles for mixing the settled sludges with

existing supernate in the tank. The operation also used existing piping and progressive cavity pumps for retrieval and

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

transfer of the mixture. A total of 64,000 gal of liquid was required to transfer 6300 gal of sludge to the Melton Valley

Storage Tanks (MVSTs) designated for consolidation of all

ORNL RH-TRU sludges. Of the liquid used for the retrieval,

88% was existing or recycled tank supernate and only 7770

gal of additional process water was added to the system.

Minimizing the addition of process water is extremely important at ORNL, where tank system storage capacity is limited.

A simple manual sluicer was used periodically to wash down

and aid the removal of localized sludge heels.

549

(ORNL/TM–13581)

Liquid and gaseous waste operations section. Annual

operating report CY 1997. Maddox, J.J.; Scott, C.B. Oak

Ridge National Lab., TN (United States). Mar 1998. 127p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC05-96OR22464. Order Number DE98052497. Source:

OSTI; NTIS; INIS; GPO Dep.

This document presents information on the liquid and

gaseous wastes operations section for calendar year 1997.

Operating activities, upgrade activities, and maintenance activities are described.

550

(ORNL/TM–13582)

Multi-weight isotherm results for mercury removal in

upper East Fork Popular Creek water. Bostick, D.A.; Klasson, K.T. Oak Ridge National Lab., TN (United States). Feb

1998. 24p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract AC05-96OR22464. Order Number DE98052510.

Source: OSTI; NTIS; INIS; GPO Dep.

Many sorbents have been developed for the removal of

mercury and heavy metals from waters; however, the majority of data published to date do not address the removal of

mercury to the target levels represented in this project. The

application to which these sorbents are targeted for use is

the removal of mercury from microgram-per-liter levels to

low nanogram-per-liter levels. Sorbents with thiouronium,

thiol, amine, sulfur, and proprietary functional groups were

selected for these studies. The initial mercury content in the

majority of the batch samples was significantly augmented

so that the equilibrium concentration was similar to that

found in the original stream sample for at least one sample.

Mercury was successfully removed from actual water via adsorption onto Ionac SR-4 (by Sybron Chemicals, Inc.),

Keyle:X (by SolmeteX), and Mersorb (by Nucon International, Inc.) resins to levels below the target goal of 12 ng/L.

A thiol-based resin (Ionac SR-4) performed the best, indicating that over 200,000 volumes of water could be treated

with one volume of resin. The cost of the resin is approximately $0.24 per 1000 gal of water.

551

(ORNL/TM–13587)

Comparative testing of slurry monitors. Hylton, T.D. (Oak

Ridge National Lab., TN (United States)); Bayne, C.K.; Anderson, M.S.; Van Essen, D.C. Oak Ridge National Lab., TN

(United States). May 1998. [200p.] Sponsored by USDOE,

Washington, DC (United States);USDOE Office of Environmental Management, Washington, DC (United States). DOE

Contract AC05-96OR22464. Order Number DE98058144.

Source: OSTI; NTIS; INIS; GPO Dep.

The US Department of Energy (DOE) has millions of gallons of radioactive liquid and sludge wastes that must be

retrieved from underground storage tanks, transferred to

treatment facilities, and processed to a final waste form. The

wastes will be removed from the current storage tanks by

mobilizing the sludge wastes and mixing them with the liquid

wastes to create slurries. Each slurry would then be transferred by pipeline to the desired destination. To reduce the

risk of plugging a pipeline, the transport properties (e.g.,

density, suspended solids concentration, viscosity, particle

size range) of the slurry should be determined to be within

acceptable limits prior to transfer. These properties should

also be monitored and controlled within specified limits while

the slurry transfer is in progress. The DOE issued a call for

proposals for developing on-line instrumentation to measure

the transport properties of slurries. In response to the call for

proposals, several researchers submitted proposals and

were funded to develop slurry monitoring instruments.

These newly developed DOE instruments are currently in

the prototype stage. Before the instruments were installed in

a radioactive application, the DOE wanted to evaluate them

under nonradioactive conditions to determine if they were

accurate, reliable, and dependable. The goal of this project

was to test the performance of the newly developed DOE

instruments along with several commercially available instruments. The baseline method for comparison utilized the

results from grab-sample analyses.

552

(ORNL/TM–13590)

Development testing of the chemical analysis automation polychlorinated biphenyl standard analysis method

during surface soils sampling at the David Witherspoon

1630 site. Hunt, M.A. (and others); Klatt, L.N.; Thompson,

D.H. Oak Ridge National Lab., TN (United States). Feb

1998. 63p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract AC05-96OR22464. Order Number DE98052502.

Source: OSTI; NTIS; INIS; GPO Dep.

The Chemical Analysis Automation (CAA) project is developing standardized, software-driven, site-deployable robotic

laboratory systems with the objective of lowering the persample analysis cost, decreasing sample turnaround time,

and minimizing human exposure to hazardous and radioactive materials associated with DOE remediation projects.

The first integrated system developed by the CAA project is

designed to determine polychlorinated biphenyls (PCB) content in soil matrices. A demonstration and development

testing of this system was conducted in conjuction with surface soil characterization activities at the David Witherspoon

1630 Site in Knoxville, Tennessee. The PCB system consists of five hardware standard laboratory modules (SLMs),

one software SLM, the task sequence controller (TSC), and

the human-computer interface (HCI). Four of the hardware

SLMs included a four-channel Soxhlet extractor, a highvolume concentrator, a column cleanup, and a gas

chromatograph. These SLMs performed the sample preparation and measurement steps within the total analysis

protocol. The fifth hardware module was a robot that transports samples between the SLMs and the required

consumable supplies to the SLMs. The software SLM is an

automated data interpretation module that receives raw data

from the gas chromatograph SLM and analyzes the data to

yield the analyte information. The TSC is a software system

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

that provides the scheduling, management of system resources, and the coordination of all SLM activities. The HCI

is a graphical user interface that presents the automated laboratory to the analyst in terms of the analytical procedures

and methods. Human control of the automated laboratory is

accomplished via the HCI. Sample information required for

processing by the automated laboratory is entered through

the HCI. Information related to the sample and the system

status is presented to the analyst via graphical icons.

553

(ORNL/TM–13593)

A field trial of novel bifunctional resins for removing

pertechnetate (TcO4

) from contaminated groundwater.

Gu, B. (Oak Ridge National Lab., TN (United States));

Liang, L.; Brown, G.M.; Bonnesen, P.V.; Moyer, B.A.;

Alexandratos, S.D.; Ober, R. Oak Ridge National Lab., TN

(United States). Mar 1998. 35p. Sponsored by USDOE,

Washington, DC (United States);USDOE Office of Environmental Management, Washington, DC (United States). DOE

Contract AC05-96OR22464. Order Number DE98058145.

Source: OSTI; NTIS; GPO Dep.

Environmental Sciences Division publication number 4757.

A field trial using a custom-designed bifunctional synthetic

resin prepared at the University of Tennessee and designed

to selectively remove pertechnetate (TcO4

) from groundwater was conducted in summer 1997 at the Northwest

Plume Pump-and-Treat Facility at the US Department of Energy’s Paducah Gaseous Diffusion Plant (PGDP) site. The

bifunctional resin, RO-02-119, was a copolymer of vinylbenzylchloride and divinylbenzene that had been functionalized

with trihexylamine and triethylamine. The experiment was a

parallel test of the synthetic resin and a commercial resin,

Purolite A-520E, to directly compare the performance of the

two resins. Purolite resin is currently used by the treatment

facility to remove Tc-99 from the contaminated groundwater

containing 1,000 pCi/L TcO4

. A total of 692,000 bed

volumes of groundwater was passed through the column

containing the synthetic resin (RO-02-119) whereas only

205,000 bed volumes of groundwater were passed

through the Purolite resin column because of reduced hydraulic conductivity and clogging within the latter column.

Despite less groundwater passing through the Purolite resin

column, however, the breakthrough of TcO4

 occurred earlier in the Purolite column than in the RO-02-119 column.

554

(ORNL/TM–13617)

Implementation of passive samplers for monitoring

volatile organic compounds in ground water at the

Kansas City Plant. Gardner, F.G. (Oak Ridge National

Lab., Grand Junction, CO (United States)); Korte, N.E.;

Wilson-Nichols, M.J.; Baker, J.L.; Ramm, S.G. Oak Ridge

National Lab., Grand Junction, CO (United States). Jun

1998. 23p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract AC05-96OR22464. Order Number DE99000348.

Source: OSTI; NTIS; INIS; GPO Dep.

Passive sampling for monitoring volatile organic compounds (VOCs) has been suggested as a possible

replacement to the traditional bailer method used at the Department of Energy Kansas City Plant (KCP) for routine

groundwater monitoring. To compare methods, groundwater

samples were collected from 19 KCP wells with VOC concentrations ranging from non-detectable to > 100,000 f

microg g/L. Analysis of the data was conducted using

means and medians of multiple measurements of TCE, 1,2-

DCE, 1,1-DCE and VC. All 95% confidence intervals of

these VOCs overlap, providing evidence that the two methods are similar. The study also suggests that elimination of

purging and decontamination of sampling equipment reduces the labor required to sample by approximately 32%.

Also, because the passive method generates no waste water, there are no associated disposal costs. The results

suggest evidence to continue studies and efforts to replace

traditional bailer methods with passive sampling at KCP

based on cost and the similarity of the methods.

555

(ORNL/TM–13630)

North Tank Farm data report for the Gunite and Associated Tanks at Oak Ridge National Laboratory. Rule, V.A.

(XL Associates, Inc., Oak Ridge, TN (United States)); Burks,

B.L.; Hoesen, S.D. van. Oak Ridge National Lab., TN

(United States);XL Associates, Inc., Oak Ridge, TN (United

States). May 1998. [200p.] Sponsored by USDOE, Washington, DC (United States);USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract AC05-98OR22700 ; AC05-96OR22464. Order Number

DE98058150. Source: OSTI; NTIS; INIS; GPO Dep.

The US Department of Energy (DOE) Office of Science

and Technology, in cooperation with the Oak Ridge Environmental Management Program, has developed and

demonstrated the first full-scale remotely operated system

for cleaning radioactive liquid and waste from large underground storage tanks. The remotely operated waste retrieval

system developed and demonstrated at Oak Ridge National

Laboratory (ORNL) is designed to accomplish both retrieval

of bulk waste, including liquids, thick sludge, and scarified

concrete, and final tank cleaning. This report provides a

summary of the North Tank Farm (NTF) operations data and

an assessment of the performance and efficiency of the

waste retrieval system during NTF operations data and an

assessment of the performance and efficiency of the waste

retrieval system during NTF operations. The organization of

this report is as follows: Section 1 provides an introduction

to the report. Section 2 describes the NTF tank structures

(W-3 and W-4 only) and the contents of the tanks. Section 3

outlines the objectives of the NTF testing and explains how

these objectives were met. Section 4 provides a description

of the various operating systems used in the NTF operations. Sections 5 and 6 present a summary of the data

collected during NTF operations. Section 7 summarizes the

maintenance activities performed and Section 8 summarizes

the on-the-job training performed in the NTF. Section 9

summarizes the capital cost for the waste retrieval and characterization equipment and operating costs for performing

the NTF work. Section 10 provides observations and

lessons learned, and Section 11 provides a summary and

conclusions.

556

(ORNL/TM–13645)

A retrospective study of the chemical analysis cost for

the remediation of Lower East Fork Poplar Creek, Oak

Ridge, Tennessee. Klatt, L.N. Oak Ridge National Lab., TN

(United States). Jun 1998. 26p. Sponsored by USDOE,

Washington, DC (United States);USDOE Office of Environmental Management, Washington, DC (United States). DOE

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

Contract AC05-96OR22464. Order Number DE98058152.

Source: OSTI; NTIS; INIS; GPO Dep.

A retrospective study of the remediation of Lower East

Fork Poplar Creek (LEFPC) in Oak Ridge, Tennessee was

completed. The study was conducted by reviewing the

public Comprehensive Environmental Response, Compensation, and Liability Act record documents associated with

the remediation of LEFPC and through discussions with the

project staff involved or familiar with the project. The remediation took place in two phases. The first phase involved the

excavation of about 5,560 yd3 of soil at the National

Oceanic and Atmospheric Administration (NOAA) locations

in 1996. The second phase involved the excavation of

39,200 yd3 at another NOAA location and at the Bruner location in 1997. For the entire project (remedial investigation

through cleanup), a total of 7,708 samples (1 sample for

each 5.8 yd3 of soil remediated) were analyzed for mercury.

The project obtained special regulatory approval to use two

methods for the determination of mercury in soils that are

not part of the Resource Conservation and Recovery Act

SW-846 methods manual. The mercury analysis cost was

$678,000, which represents 9.6% of the cleanup cost. During the cleanup phase of the project, an on-site laboratory

was used. The estimated cost savings that the on-site laboratory provided fall into two categories: direct reduction of

costs associated with chemical analysis and sample shipment totaling approximately $38,000, which represents a

5.3% savings relative to the estimated cost of using an offsite laboratory, and savings in the amount of $890,000

(12.5% of the $7.1 M cleanup cost), associated with expediting execution of the cleanup work by providing rapid (< 3

hours) sample result turnaround time. (Abstract truncated)

557

(ORNL/TM–13653)

Grout and glass performance in support of stabilization/

solidification of ORNL tank sludges. Spence, R.D.; Mattus, C.H.; Mattus, A.J. Oak Ridge National Lab., TN (United

States). Sep 1998. 97p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States).

DOE Contract AC05-96OR22464. Order Number

DE99000341. Source: OSTI; NTIS; INIS; GPO Dep.

Wastewater at Oak Ridge National Laboratory (ORNL) is

collected, evaporated, and stored in the Melton Valley Storage Tanks (MVST) and Bethel Valley Evaporator Storage

Tanks (BVEST) pending treatment for disposal. In addition,

some sludges and supernatants also requiring treatment

remain in two inactive tank systems: the gunite and associated tanks (GAAT) and the old hydrofracture (OHF) tank.

The waste consists of two phases: sludge and supernatant.

The sludges contain a high amount of radioactivity, and

some are classified as TRU sludges. Some Resource Conservation and Recovery Act (RCRA) metal concentrations

are high enough to be defined as RCRA hazardous; therefore, these sludges are presumed to be mixed TRU waste.

Grouting and vitrification are currently two likely stabilization/

solidification alternatives for mixed wastes. Grouting has

been used to stabilize/solidify hazardous and low-level

radioactive waste for decades. Vitrification has been developed as a high-level radioactive alternative for decades and

has been under development recently as an alternative disposal technology for mixed waste. The objective of this

project is to define an envelope, or operating window, for

grout and glass formulations for ORNL tank sludges. Formulations will be defined for the average composition of each

of the major tank farms (BVEST/MVST, GAAT, and OHF)

and for an overall average composition of all tank farms.

This objective is to be accomplished using surrogates of the

tank sludges with hot testing of actual tank sludges to check

the efficacy of the surrogates.

558

(ORNL/TM–13654)

Process waste treatment system upgrades: Clarifier

startup at the nonradiological wastewater treatment

plant. Lucero, A.J.; McTaggart, D.R.; Van Essen, D.C.;

Kent, T.E.; West, G.D.; Taylor, P.A. Oak Ridge National

Lab., TN (United States). Jul 1998. 13p. Sponsored by USDOE, Washington, DC (United States);USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract AC05-96OR22464. Order Number

DE98058153. Source: OSTI; NTIS; INIS; GPO Dep.

The Waste Management Operations Division at Oak

Ridge National Laboratory recently modified the design of a

reactor/clarifier at the Nonradiological Wastewater Treatment

Plant, which is now referred to as the Process Waste Treatment Complex–Building 3608, to replace the sludge-blanket

softener/clarifier at the Process Waste Treatment Plant, now

referred to as the Process Waste Treatment ComplexBuilding 3544 (PWTC-3544). This work was conducted

because periodic hydraulic overloads caused poor watersoftening performance in the PWTC-3544 softener, which

was detrimental to the performance and operating costs of

downstream ion-exchange operations. Over a 2-month time

frame, the modified reactor/clarifier was tested with nonradiological wastewater and then with radioactive wastewater to

optimize softening performance. Based on performance to

date, the new system has operated more effectively than the

former one, with reduced employee radiological exposure,

less downtime, lower costs, and improved effluent quality.

559

(ORNL/TM–13660)

Status report on solid control in leachates. Beahm, E.C.

(Oak Ridge National Lab., TN (United States)); Weber, C.F.;

Lee, D.D.; Dillow, T.A.; Hunt, R.D.; Keswa, C.M.; OsseoAsare, K.; Spear, K.E. Oak Ridge National Lab., TN (United

States). Jul 1998. 98p. Sponsored by USDOE, Washington,

DC (United States);USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC05-96OR22464. Order Number DE98058154. Source:

OSTI; NTIS; INIS; GPO Dep.

Sludge pretreatment will involve some combination of

washing and leaching with sodium hydroxide solutions to

remove soluble salts and amphoteric material such as alumina. It is of paramount importance to prevent gelation and

uncontrolled solid formation in tanks, transfer lines, and process equipment. An evaluation of results of washing and

caustic leaching indicates that washing is more effective in

dissolving sludge solids than subsequent sodium hydroxide

treatment. Only aluminum and chromium were removed

more effectively by caustic leaching than by water washing.

560

(ORNL/TM–13663)

Caustic leaching of high-level radioactive tank sludge:

A critical literature review. McGinnis, C.P.; Welch, T.D.;

Hunt, R.D. Oak Ridge National Lab., TN (United States).

Aug 1998. 21p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

Contract AC05-96OR22464. Order Number DE99000333.

Source: OSTI; NTIS; INIS; GPO Dep.

The Department of Energy (DOE) must treat and safely

dispose of its radioactive tank contents, which can be separated into high-level waste (HLW) and low-level waste (LLW)

fractions. Since the unit costs of treatment and disposal are

much higher for HLW than for LLW, technologies to reduce

the amount of HLW are being developed. A key process currently being studied to reduce the volume of HLW sludges is

called enhanced sludge washing (ESW). This process removes, by water washes, soluble constituents such as

sodium salts, and the washed sludge is then leached with

2–3 M NaOH at 60–100 C to remove nonradioactive metals

such as aluminum. The remaining solids are considered to

be HLW while the solutions are LLW after radionuclides

such as 137Cs have been removed. Results of bench-scale

tests have shown that the ESW will probably remove the

required amounts of inert constituents. While both experimental and theoretical results have shown that leaching

efficiency increases as the time and temperature of the

leach are increased, increases in the caustic concentration

above 2–3 M will only marginally improve the leach factors.

However, these tests were not designed to validate the assumption that the caustic used in the ESW process will

generate only a small increase (10 Mkg) in the amount of

LLW; instead the test conditions were selected to maximize

leaching in a short period and used more water and caustic

than is planned during full-scale operations. Even though

calculations indicate that the estimate for the amount of LLW

generated by the ESW process appears to be reasonable, a

detailed study of the amount of LLW from the ESW process

is still required. If the LLW analysis indicates that sodium

management is critical, then a more comprehensive evaluation of the clean salt process or caustic recycle would be

needed. Finally, experimental and theoretical studies have

clearly demonstrated the need for the control of solids formation during and after leaching.

561

(ORNL/TM–13668)

HYDROBIOGEOCHEM: A coupled model of HYDROlogic

transport and mixed BIOGEOCHEMical kinetic/

equilibrium reactions in saturated-unsaturated media.

Yeh, G.T. (Pennsylvania State Univ., University Park, PA

(United States). Dept. of Civil and Environmental Engineering); Salvage, K.M.; Gwo, J.P.; Zachara, J.M.; Szecsody,

J.E. Oak Ridge National Lab., TN (United States). Jul 1998.

[400p.] Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC05-84OR21400. Order Number DE99000336. Source:

OSTI; NTIS; GPO Dep.

Center for Computational Sciences publication number

0007.

The computer program HYDROBIOGEOCHEM is a coupled model of HYDROlogic transport and BIOGEOCHEMical

kinetic and/or equilibrium reactions in saturated/unsaturated

media. HYDROBIOGEOCHEM iteratively solves the twodimensional transport equations and the ordinary differential

and algebraic equations of mixed biogeochemical reactions.

The transport equations are solved for all aqueous chemical

components and kinetically controlled aqueous species. HYDROBIOGEOCHEM is designed for generic application to

reactive transport problems affected by both microbiological

and geochemical reactions in subsurface media. Input to the

program includes the geometry of the system, the spatial

distribution of finite elements and nodes, the properties of

the media, the potential chemical and microbial reactions,

and the initial and boundary conditions. Output includes the

spatial distribution of chemical and microbial concentrations

as a function of time and space, and the chemical speciation at user-specified nodes.

562

(PNNL–11218)

STOMP Subsurface Transport Over Multiple Phases:

User’s guide. White, M.D.; Oostrom, M. Pacific Northwest

Lab., Richland, WA (United States). Oct 1997. 218p. Sponsored by USDOE Office of Environmental Management,

Washington, DC (United States);Nuclear Regulatory Commission, Washington, DC (United States). DOE Contract

AC06-76RL01830. Order Number DE98050087. Source:

OSTI; NTIS; INIS; GPO Dep.

The U.S. Department of Energy, through the Office of

Technology Development, has requested the demonstration

of remediation technologies for the cleanup of volatile organic compounds and associated radionuclides within the

soil and groundwater at arid sites. This demonstration program, called the VOC-Arid Soils Integrated Demonstration

Program (Arid-ID), has been initially directed at a volume of

unsaturated and saturated soil contaminated with carbon

tetrachloride, on the Hanford Site near Richland, Washington. A principal subtask of the Arid-ID program involves the

development of an integrated engineering simulator for

evaluating the effectiveness and efficiency of various remediation technologies. The engineering simulator’s intended

users include scientists and engineers who are investigating

soil physics phenomena associated with remediation technologies. Principal design goals for the engineer simulator

include broad applicability, verified algorithms, quality assurance controls, and validated simulations against laboratory

and field-scale experiments. An important goal for the simulator development subtask involves the ability to scale

laboratory and field-scale experiments to full-scale remediation technologies, and to transfer acquired technology to

other arid sites. The STOMP (Subsurface Transport Over

Multiple Phases) simulator has been developed by the Pacific Northwest National Laboratory for modeling remediation

technologies. Information on the use, application, and theoretical basis of the STOMP simulator theory and discussions

on the governing equations, constitutive relations, and numerical solution algorithms for the STOMP simulator.

563

(PNNL–11495)

Chemical information on tank supernatants, Cs adsorption from tank liquids onto Hanford sediments, and field

observations of Cs migration from past tank leaks.

Serne, R.J.; Zachara, J.M.; Burke, D.S. Pacific Northwest

Lab., Richland, WA (United States). Jan 1998. 96p. Sponsored by USDOE Office of Environmental Management,

Washington, DC (United States). DOE Contract AC06-

76RL01830. Order Number DE98051885. Source: OSTI;

NTIS; INIS; GPO Dep.

Borehole gamma-logging profiles beneath the SX-Tank

Farm suggest that contamination from Cs-137 extends to at

least a depth of 40 m (130 ft), and may extend even deeper.

What is presently not known is the pathway that Cs-137 has

taken to reach these depths. In this report we provide an

analysis of the chemistry of tank supernates with emphasis

on the REDOX waste stream disposed in SX tanks, Cs

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

chemistry in aqueous solutions and adsorption properties

onto minerals, available data on Cs adsorption onto Hanford

sediments, and information on Cs migration from other Hanford tank leaks that have been studied. The data in this

report was used to help guide the vadose zone transport

analysis of the SX Tank Farm presented in a companion report. The goal of the vadose zone transport modelling is to

attempt to explain the depth and extent of the Cs-137 plume

under the SX Tank farm, specifically in the vicinity of the

greatest leak, near the SX-109 Tank as inferred from the

gamma logs (DOE 1996). In solution Cs is present as the

monovalent cation and shows very little tendency to form

aqueous complexes with inorganic or organic ligands. Cs is

expected to adsorb primarily onto selective minerals that

have unique adsorption sites. The small Cs+ ion is accommodated on these frayed edge and interlayer sites.

Adsorption within the interlayers often leads to collapse of

the layers such that the Cs+ ion is effectively trapped and

not readily exchangeable by all other common cations. The

degree of adsorption is thus only moderately dependent on

the types and high concentrations of other cations in leaking

tank liquors.

564

(PNNL–11557-5)

Hanford annual first quarter seismic report, fiscal year

1998: Seismicity on and near the Hanford Site, Pasco

Basin, Washington. Hartshorn, D.C.; Reidel, S.P.; Rohay,

A.C. Pacific Northwest National Lab., Richland, WA (United

States). Feb 1998. 30p. Sponsored by USDOE Assistant

Secretary for Management and Administration, Washington,

DC (United States);USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC06-76RL01830. Order Number DE98052278. Source:

OSTI; NTIS; GPO Dep.

Hanford Seismic Monitoring provides an uninterrupted collection of high-quality raw and processed seismic data from

the Hanford Seismic Network (HSN) for the US Department

of Energy and its contractors. The staff also locates and

identifies sources of seismic activity and monitors changes

in the historical pattern of seismic activity at the hanford

Site. The data are compiled, archived, and published for use

by the Hanford Site for waste management, Natural Phenomena Hazards assessments, and engineering design and

construction. In addition, the seismic monitoring organization

works with the Hanford Site Emergency Services Organization to provide assistance in the event of an earthquake on

the Hanford Site. The HSN and the Eastern Washington Regional Network (EWRN) consist of 41 individual sensor sites

and 15 radio relay sites maintained by the Hanford Seismic

Monitoring staff. The operational rate for the first quarter of

FY98 for stations in the HSN was 98.5%. The operational

rate for the first quarter of FY98 for stations of the EWRN

was 99.1%. For the first quarter of FY98, the acquisition

computer triggered 184 times. Of these triggers 23 were local earthquakes: 7 in the Columbia River Basalt Group, and

16 in the crystalline basement. The geologic and tectonic

environments where these earthquakes occurred are discussed in this report. The most significant earthquakes in

this quarter were a series of six events which occurred in

the Cold Creek depression (approximately 4 km SW of the

200 West Area), between November 6 and November 11,

1997. All events were deep (> 15 km) and were located in

the crystalline basement. The first event was the largest,

having a magnitude of 3.49 Mc. Two events on November 9,

1997 had magnitudes of 2.81 and 2.95 Mc, respectively. The

other events had magnitudes between 0.7 and 1.2 Mc.

565

(PNNL–11634)

Gas treatment of Cr(VI)-contaminated sediment samples

from the North 60’s pits of the chemical waste landfill.

Thornton, E.C.; Amonette, J.E. Pacific Northwest Lab., Richland, WA (United States). Dec 1997. 67p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract AC06-76RL01830. Order

Number DE98051354. Source: OSTI; NTIS; INIS; GPO Dep.

Twenty sediment samples were collected at depths ranging from 5 to 100 ft (1.5 to 30 m) beneath a

metal-contaminated plating-waste site and extensively characterized for Cr(VI) content and environmental availability.

Three samples were selected for treatment with diluted gas

mixtures with the objective of converting Cr(VI) to Cr(III),

which is relatively nontoxic and immobile. These tests were

designed to provide information needed to evaluate the potential application of gas injection as an in situ remediation

technique. Gas treatment was performed in small columns

(4.9-cm ID, 6.4- to 13.9-cm long) using 100 ppm (L L1)

H2S or ethylene mixtures in N2. Treatment progress during

the tests involving H2S was assessed by monitoring the

breakthrough of H2S. Evaluation of H2S treatment efficacy

included (1) water-leaching of treated and untreated

columns for ten days, (2) repetitive extraction of treated and

untreated subsamples by water, 0.01 M phosphate (pH 7) or

6 M HCl solutions, and (3) Cr K-edge X-ray absorption nearedge structure (XANES) spectroscopy of treated and

untreated subsamples. Results of the water-leaching studies

showed that the H2S treatment decreased Cr(VI) levels in

the column effluent by 90% to nearly 100%. Repetitive extractions by water and phosphate solutions echoed these

results, and the extraction by HCl released only 35-40% as

much Cr in the treated as in the untreated samples. Analysis

by XANES spectroscopy showed that a substantial portion

of the Cr in the samples remained as Cr(VI) after treatment,

even though it was not available to the water and phosphate

extracting solutions. These results suggest that this residual

Cr(VI) is present in low solubility phases such as PbCrO4 or

sequestered in unreacted grain interiors under impermeable

coatings formed during H2S treatment. However, this fraction is essentially immobile and thus unavailable to the

environment.

566

(PNNL–11670-Rev.1)

Organic tanks safety program, FY97 waste aging studies. Revision 1. Camaioni, D.M.; Samuels, W.D.; Linehan,

J.C.; Sharma, A.K.; Hogan, M.O.; Lilga, M.A.; Clauss, S.A.;

Wahl, K.L.; Campbell, J.A. Pacific Northwest National Lab.,

Richland, WA (United States). Feb 1998. 81p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract AC06-76RL01830. Order

Number DE98052136. Source: OSTI; NTIS; INIS; GPO Dep.

To model tank waste aging and interpret tank waste speciation results, the authors began measuring the reactivity of

organic complexants and related compounds towards

radiation-induced oxidation reactions. Because of the high

efficiency of scavenging of the primary radicals of water

radiolysis by nitrate and nitrite ion, the major radiolyticallygenerated radicals in these solutions, and in Hanford tank

143
ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

wastes, are NO2, NO and O. Prior to this effort, little quantitative information existed for the reactions of these radicals

with organic compounds such as those that were used in

Hanford processes. Therefore, modeling of actual waste aging, or even simulated waste aging, was not feasible without

measuring reactivities and determining reaction paths. The

authors have made the first rate measurements of complexant aging and determined some of their degradation

products.

567

(PNNL–11677)

International waste management fact book. Amaya, J.P.;

LaMarche, M.N.; Upton, J.F. Pacific Northwest Lab., Richland, WA (United States). Oct 1997. 266p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract AC06-76RL01830. Order

Number DE98052581. Source: OSTI; NTIS; INIS; GPO Dep.

Many countries around the world are faced with nuclear

and environmental management problems similar to those

being addressed by the US Department of Energy. The purpose of this Fact Book is to provide the latest information on

US and international organizations, programs, activities and

key personnel to promote mutual cooperation to solve these

problems. Areas addressed include all aspects of closing

the commercial and nuclear fuel cycle and managing the

wastes and sites from defense-related, nuclear materials

production programs.

568

(PNNL–11678-Rev.1)

Nuclear magnetic resonance measurement of ammonia

diffusion in dense solid-liquid slurries. Revision 1. Bobroff, S. (Univ. of California, Davis, CA (United States).

Dept. of Chemical Engineering); Phillips, R.J.; Shekarriz, A.

Pacific Northwest National Lab., Richland, WA (United

States). Jan 1998. 21p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States).

DOE Contract AC06-76RL01830. Order Number

DE98051732. Source: OSTI; NTIS; INIS; GPO Dep.

The flammability and toxicity of ammonia released from

the nuclear waste tanks at Hanford have been the subject of

several recent studies. These releases may occur episodically, such as the buoyant plume releases occurring in

various double-shell tanks (DSTs); gradually through the

surface of the waste; or from the partially saturated saltcakes in the single-shell tanks during salt-well pumping. The

diffusion of ammonium ions in aqueous solutions was measured by nuclear magnetic resonance (NMR) using the

pulsed field gradient (PFG) method. The ammonium ions

were obtained from aqueous solutions of ammonium chloride, ammonium sulfate, ammonium bicarbonate, and

ammonium hydroxide. The translational diffusion of the ammonium ions was determined by measuring the diffusion of

nitrogen nuclei in solution. Results showed that the ammonium diffusion coefficient can be measured in aqueous

solutions with concentrations as low as 20 103 M. Typical values measured for the diffusion coefficient of the

ammonium ion are 2 105 cm2/s (10%), similar to the

values found for pure water. Due to the effect of the solution

pH upon the NMR relaxation parameters for 14N, measurements are constrained to pH values below 8.5. However,

15N labeled ammonia is less sensitive to the solution pH, extending the measurement range to pH of 9.5. The results

show that the solution viscosity has a measurable impact on

the diffusion coefficient. The diffusion coefficient is almost inversely proportional to the relative viscosity of the solution,

irrespective of how the viscosity is increased. Further, a

randomly-packed porous bed of 200 f microg m PMMA resulted in a reduction of  30% in the diffusion coefficient as

a result of hindered diffusion.

569

(PNNL–11702-Rev.1)

Chemical pathways for the formation of ammonia in

Hanford wastes. Stock, L.M.; Pederson, L.R. Pacific Northwest National Lab., Richland, WA (United States). Dec

1997. 41p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract AC06-76RL01830. Order Number DE98051752.

Source: OSTI; NTIS; INIS; GPO Dep.

This report reviews chemical reactions leading to the formation of ammonia in Hanford wastes. The general features

of the chemistry of the organic compounds in the Hanford

wastes are briefly outlined. The radiolytic and thermal free

radical reactions that are responsible for the initiation and

propagation of the oxidative degradation reactions of the

nitrogen-containing complexants, trisodium HEDTA and

tetrasodium EDTA, are outlined. In addition, the roles played

by three different ionic reaction pathways for the oxidation of

the same compounds and their degradation products are

described as a prelude to the discussion of the formation of

ammonia. The reaction pathways postulated for its formation

are based on tank observations, laboratory studies with simulated and actual wastes, and the review of the scientific

literature. Ammonia derives from the reduction of nitrite ion

(most important), from the conversion of organic nitrogen in

the complexants and their degradation products, and from

radiolytic reactions of nitrous oxide and nitrogen (least important).

570

(PNNL–11703)

Descriptive models for single-jet sluicing of sludge

waste. Erian, F.F.; Mahoney, L.A.; Terrones, G. Pacific

Northwest National Lab., Richland, WA (United States). Dec

1997. 36p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract AC06-76RL01830. Order Number DE98051304.

Source: OSTI; NTIS; INIS; GPO Dep.

Mobilization of sludge waste stored in underground storage tanks can be achieved safely and reliably by sluicing. In

the project discussed in this report, the waste in Hanford

single-shell Tank 241-C-106 will be mobilized by sluicing, retrieved by a slurry retrieval pump, and transferred via an

1800-ft slurry pipeline to Tank 241-AY-102. A sluicing strategy must be developed that ensures efficient use of the

deployed configuration of the sluicing system: the nozzle(s)

and the retrieval pump(s). Given a sluicing system configuration in a particular tank, it is desirable to prescribe the

sequential locations at which the sludge will be mobilized

and retrieved and the rate at which these mobilization and

retrieval processes take place. In addition, it is necessary to

know whether the retrieved waste slurry meets the requirements for cross-site slurry transport. Some of the physical

phenomena that take place during mobilization and retrieval

and certain aspects of the sluicing process are described in

this report. First, a mathematical model gives (1) an idealized geometrical representation of where, within the

confines of a storage tank containing a certain amount of

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

settled waste, sludge can be removed and mobilized; and

(2) a quantitative measure of the amount of sludge that can

be removed during a sluicing campaign. A model describing

an idealized water jet issuing from a circular nozzle located

at a given height above a flat surface is also presented in

this report. This dynamic water-jet model provides the basis

for improving the geometrical sluicing model presented next.

In this model the authors assume that the water jet follows a

straight trajectory toward a target point on a flat surface.

However, the water jet does not follow a straight line in the

actual tank, and using the true trajectory will allow a more

accurate estimate of the amount of disturbed material. (Abstract truncated)

571

(PNNL–11706)

Waste behavior during horizontal extrusion: Effect of

waste strength for bentonite and kaolin/ludox simulants

and strength estimates for wastes from Hanford waste

tanks 241-SY-103, AW-101, AN-103, and S-102. Gauglitz,

P.A.; Aikin, J.T. Pacific Northwest Lab., Richland, WA

(United States). Oct 1997. 79p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States). DOE Contract AC06-76RL01830. Order Number

DE98050605. Source: OSTI; NTIS; INIS; GPO Dep.

The Hanford Site has 149 single-shell tanks (SSTs) and

28 double-shell tanks (DSTs) containing radioactive wastes

that are complex mixes of radioactive and chemical products. Some of these wastes are known to generate mixtures

of flammable gases, including hydrogen, nitrous oxide, and

ammonia. Nineteen of these SSTs and six of the DSTs have

been placed on the Flammable Gas Watch List because

they are known or suspected, in all but one case, to retain

these flammable gases. Because these gases are

flammable, their retention and episodic release pose a number of safety concerns. Understanding the physical

mechanisms and waste properties that contribute to the retention and release of these gases will help to resolve the

Flammable Gas Safety Issue. The strength of the waste

plays a central role in the mechanisms of both bubble retention and bubble release. While recent in-situ measurements

from the ball rheometer have provided results for five of the

DSTs, waste strength measurements are typically not available for any of the SSTs or for the DSTs that have not been

characterized with the ball rheometer. The overall purpose

of this study is to develop a method to obtain strength estimates for actual wastes from observations of the wastes’

behavior during extrusion from core samplers. The first objective of the study was to quantify waste behavior during

horizontal extrusion by documenting the extrusion behavior

of simulants with known strengths; the second was to estimate the strength of actual waste based on these simulant

standards. Results showed a reproducible extrusion behavior for bentonite clay and kaolin/Ludox simulants over

strengths ranging from 30 to 6,500 Pa. The extrusion behavior was documented with both video recordings and still

images. Based on these visual standards, strength estimates were made for wastes from DSTs 241-SY-103,

241-AW-101, and 241-AN-103 and SST 241-S-102.

572

(PNNL–11714)

Mercury separation from concentrated potassium iodide/iodine leachate using Self-Assembled Mesoporous

Mercaptan Support (SAMMS) technology. Mattigod, S.V.

(and others); Feng, X.; Fryxell, G.E. Pacific Northwest Lab.,

Richland, WA (United States). Oct 1997. 31p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract AC06-76RL01830. Order

Number DE98050091. Source: OSTI; NTIS; INIS; GPO Dep.

A study was conducted to demonstrate the effectiveness

of a novel adsorber, the Self-Assembled Mesoporous Mercaptan Support (SAMMS) material to remove mercury (Hg)

from potassium iodide/iodine (KI/I2) waste streams. This

study included investigations of the SAMMS material’s

binding kinetics, loading capacity, and selectivity for Hg adsorption from surrogate and actual KI/I2 waste solutions.

The kinetics data showed that binding of Hg by the adsorber

material occurs very rapidly, with 82% to 95% adsorption

occurring within the first 5 min. No significant differences in

the rate of adsorption were noted between pH values of 5

and 9 and at Hg concentrations of 100 mg/1. Within the

same range of pH values, an approximate four-fold increase

in initial Hg concentration resulted in a two-fold increase in

the rate of adsorption. In all cases studied, equilibrium

adsorption occured within 4 h. The loading capacity experiments in KI/I2 surrogate solutions indicated Hg adsorption

densities between 26 to 270 mg/g. The loading density increased with increasing solid: solution ratio and decreasing

iodide concentrations. Values of distribution coefficients

(1.3x105 to >2.6x108 ml/g) indicated that material adsorbs

Hg with very high specificity from KI/I2 surrogate solutions.

Reduction studies showed that compared to metallic iron

(Fe), sodium dithionite can very rapidly reduce iodine as the

triiodide species into the iodide form. Adsorption studies

conducted with actual KI/I2 leachates confirmed the highly

specific Hg adsorption properties (Kd>6x107 to>1x108 ml//

g) of the adsorber material. Following treatment, the Hg concentrations in actual leachates were below instrumental

detection limits (i.e., < 0.00005 mg/l), indicating that the KI

solutions can be recycled.

573

(PNNL–11738)

Organic analysis progress report FY 1997. Clauss, S.A.;

Grant, K.E.; Hoopes, V.; Mong, G.M.; Steele, R.; Bellofatto,

D.; Sharma, A. Pacific Northwest National Labs., Richland,

WA (United States). Apr 1998. 130p. Sponsored by USDOE

Office of Environmental Management, Washington, DC

(United States). DOE Contract AC06-76RL01830. Order

Number DE98052811. Source: OSTI; NTIS; INIS; GPO Dep.

The Organic Analysis and Methods Development Task is

being conducted by Pacific Northwest National Laboratory

(PNNL) as part of the Organic Tank Waste Safety Project.

The objective of the task is to apply developed analytical

methods to identify and/or quantify the amount of particular

organic species in tank wastes. In addition, this task provides analytical support for the Gas Generation Studies

Task, Waste Aging, and Solubility Studies. This report

presents the results from analyses of tank waste samples

archived at Pacific Northwest National Laboratory (PNNL)

and received from the Project Hanford Management Contractor (PHMC), which included samples associated with

both the Flammable Gas and Organic Tank Waste Safety

Programs. The data are discussed in Section 2.0. In addition, the results of analytical support for analyzing (1)

simulated wastes for Waste Aging, (2) tank waste samples

for Gas Generation, and (3) simulated wastes associated

with solubility studies discussed in Sections 3.0, 4.0, and

5.0, respectively. The latter part of FY 1997 was devoted to

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

documenting the analytical procedures, including derivation

gas chromatography/mass spectrometry (GC/MS) and GC/

FID for quantitation, ion-pair chromatography (IPC), IC, and

the cation exchange procedure for reducing the radioactivity

of samples. The documentation of analytical procedures is

included here and discussed in Section 6.0 and Section 7.0

discusses other analytical procedures. The references are

listed in Section 8.0 and future plans are discussed in Section 9.0. Appendix A is a preprint of a manuscript accepted

for publication. Appendix B contains the cc mail messages

and chain-of-custody forms for the samples received for

analyses. Appendix C contains the test plan for analysis of

tank waste samples.

574

(PNNL–11746)

Comparison of inorganic ion exchange materials for removing cesium, strontium, and transuranic elements

from K-basin water. Brown, G.N.; Bontha, J.R.; Carson,

K.J.; Elovich, R.J.; DesChane, J.R. Pacific Northwest Lab.,

Richland, WA (United States). Oct 1997. 54p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract AC06-76RL01830. Order

Number DE98050506. Source: OSTI; NTIS; INIS; GPO Dep.

TTP No. RL3-6-C3-42.

The work presented in this report was conducted by the

Pacific Northwest National Laboratory (PNNL) under the Efficient Separations and Crosscutting Program (ESP), Office of

Science and Technology, U.S. Department of Energy (DOE).

The objective of this work was to investigate radionuclide

uptake by several newly produced ion exchange materials

under actual waste conditions, and to compare the performance of those materials with that of commercially available

ion exchangers. The equilibrium uptake data presented in

this report are useful for identifying potential materials that

are capable of removing cesium and strontium from 105-KE

Basin water. The data show the relative selectivities of the

ion exchange materials under similar operating conditions.

Additional flow studies are needed to predict material capacities and to develop complete ion exchange process flow

sheets. The materials investigated in this study include commercially available ion exchangers such as IONSIV IE-911

(manufactured by UOP), clinoptilolite (a naturally occurring

zeolite), and materials produced on an experimental basis

by AlliedSignal (biotites and nonatitanates), 3M (hexacyanoferrates), Selion Technologies, Inc. (hexacyanoferrates and

titanates), and Texas A&M University (pharmacosiderites, biotites, and nonatitanates). In all, the performance of 14 ion

exchange materials was evaluated at two solution-toexchanger mass ratios (i.e., 104 and 105) using actual

105-KE Basin water. Evaluation consisted of determining

cesium and strontium batch distribution coefficients, loading,

and decontamination factors. Actual 105-KE Basin water

was obtained from a sample collected during the sludge dissolution work conducted by PNNL in FY 1996. This sample

was taken from the bottom of the basin and contained

significantly higher concentrations of the radioactive constituents than do samples taken from the top of the basin.

575

(PNNL–11759)

Retained gas sampler extractor mixing and mass transfer rate study: Experimental and simulation results.

Recknagle, K.P.; Bates, J.M.; Shekarriz, A. Pacific Northwest National Lab., Richland, WA (United States). Nov

1997. 28p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract AC06-76RL01830. Order Number DE98051303.

Source: OSTI; NTIS; INIS; GPO Dep.

Research staff at Pacific Northwest National Laboratory

conducted experimental testing and computer simulations of

the impeller-stirred Retained Gas Sampler (RGS) gas

extractor system. This work was performed to verify experimentally the effectiveness of the extractor at mixing viscous

fluids of both Newtonian and non-Newtonian rheology representative of Hanford single- and double-shell wastes,

respectively. Developing the computational models and validating their results by comparing them with experimental

results would enable simulations of the mixing process for a

range of fluid properties and mixing speeds. Five tests were

performed with a full-scale, optically transparent model extractor to provide the data needed to compare mixing times

for fluid rheology, mixer rotational direction, and mixing

speed variation. The computer model was developed and

exercised to simulate the tests. The tests demonstrated that

rotational direction of the pitched impeller blades was not as

important as fluid rheology in determining mixing time. The

Newtonian fluid required at least six hours to mix at the hot

cell operating speed of 3 rpm, and the non-Newtonian fluid

required at least 46 hours at 3 rpm to become significantly

mixed. In the non-Newtonian fluid tests, stagnant regions

within the fluid sometimes required days to be fully mixed.

Higher-speed (30 rpm) testing showed that the laminar mixing time was correlated to mixing speed. The tests

demonstrated that, using the RGS extractor and current procedures, complete mixing of the waste samples in the hot

cell should not be expected. The computer simulation of

Newtonian fluid mixing gave results comparable to the test

while simulation of non-Newtonian fluid mixing would require

further development. In light of the laboratory test results,

detailed parametric analysis of the mixing process was not

performed.

576

(PNNL–11771)

Crystalline silicotitanate gate review analysis. Schlahta,

S.N. (and others); Carreon, R.; Gentilucci, J.A. Pacific

Northwest Lab., Richland, WA (United States). Nov 1997.

19p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC06-76RL01830. Order Number DE98051229. Source:

OSTI; NTIS; INIS; GPO Dep.

Crystalline silicotitanate (CST) is an ion-exchange method

for removing radioactive cesium from tank waste to allow the

separation of the waste into high- and low-level fractions.

The CST, originally developed Sandia National Laboratories

personnel in association with Union Oil Products Corporation, has both a high affinity and selectivity for sorbing

cesium-137 from highly alkaline or acidic solutions. For several years now, the U.S. Department of Energy has funded

work to investigate applying CST to large-scale removal of

cesium-137 from radioactive tank wastes. In January 1997,

an expert panel sponsored by the Tanks Focus Area met to

review the current state of the technology and to determine

whether it was ready for routine use. The review also sought

to identify any technical issues that must be resolved or

additional CST development that must occur before full implementation by end-users. The CST Gate Review Group

concluded that sufficient work has been done to close developmental work on CST and turn the remaining site-specific

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

tasks over to the users. This report documents the review

group’s findings, issues, concerns, and recommendations as

well as responses from the Tanks Focus Area expert staff to

specific pretreatment and immobilization issues.

577

(PNNL–11773)

Atmospheric dispersion of ammonia accidentally

released from the 242-A Evaporator, Hanford Site, Richland, Washington. Daling, P.M.; Lavender, J.C. Pacific

Northwest Lab., Richland, WA (United States). Nov 1997.

28p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC06-76RL01830. Order Number DE98051168. Source:

OSTI; NTIS; INIS; GPO Dep.

Two errors have been identified in the authorization basis

for the 242-A Evaporator at the Hanford Site. These errors,

which appear in the 242-A Evaporator/Crystallizer Final

Safety Analysis Report analysis of ammonia gas concentrations accidentally released from the 242-A Evaporator, are:

(1) the vessel ventilation system flow rate used in the previous calculations is a factor of ten higher than the actual flow

rate, and (2) the previous calculations did not account for

the ammonia source term reduction that would occur via

condensation of ammonia vapors, which will remove a large

fraction of the ammonia from the exhaust gas stream. The

purpose of this document is to correct these errors and

recalculate the maximum ground-level concentrations of ammonia released to the environment as a result of potential

errors in blending Evaporator feed. The errors offset each

other somewhat, so it is unlikely that the 242-A Evaporator

has operated outside its current authorization basis.

However, the errors must be corrected and the results incorporated into a revision of the 242-A Evaporator/Crystallizer

Safety Analysis Report, WHC-SD-WM-SAR-023. An EPAapproved atmospheric dispersion model, SCREEN3, was

used to recalculate the maximum ground-level concentrations of ammonia that would be released from the 242-A

Evaporator as a result of a feed-blending error. The results

of the re-analysis of the 242-A Evaporator’s ammonia release scenario are as follows. The onsite receptor 100 m

away from the release point (242-A vessel vent stack) is

projected to be exposed to a maximum ground-level concentration of ammonia of 8.3 ppm. The maximally-exposed

offsite receptor, located at the nearest Hanford Site boundary 16 km away from the 242-A vessel vent stack, will be

exposed to a maximum ground-level concentration of 0.11

ppm ammonia.

578

(PNNL–11777)

Composition and quantities of retained gas measured in

Hanford waste tanks 241-U-103, S-106, BY-101, and BY109. Mahoney, L.A.; Antoniak, Z.I.; Bates, J.M. Pacific

Northwest National Lab., Richland, WA (United States). Dec

1997. [200p.] Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract AC06-76RL01830. Order Number DE98051462.

Source: OSTI; NTIS; INIS; GPO Dep.

This report provides the results obtained for the singleshell tanks (SSTs) sampled with the Retained Gas Sampler

(RGS) during 1997: Tanks 241-U-103, 241-S-106, 241-BY101, and 241-BY-109. The RGS is a modified version of the

core sampler used at Hanford. It is designed specifically to

be used in concert with the gas extraction equipment in the

hot cell to capture and extrude a gas-containing waste

sample in a hermetically sealed system. The four tanks represent several different types of flammable gas SSTs. Tank

U-103 is on the Flammable Gas Watch List (FGWL) and is

one of the highest-priority group of SSTs that show evidence

of significant gas retention. Tank S-106, though not a FGWL

tank, has a uniquely high barometric pressure response and

continuing rapid surface level rise, indicating a large and increasing volume of retained gas. Tanks BY-101 and BY-109

are not on the FGWL but were chosen to test the effect of

recent salt-well pumping on gas retention. Section 2 of this

report provides an overview of the process by which

retained gases in the Hanford tanks are sampled and analyzed. A detailed description of the procedure used to

reduce and analyze the data is provided in Section 3. Tankby-tank results are covered in Section 4 (with the data

presented in the order in which the tanks were sampled),

and an RGS system performance overview is given in Section 5. Section 6 presents conclusions from these analyses

and recommendations for further research. The cited references are listed in Section 7. Appendix A describes the

procedures used to extract gas and ammonia from the samples, Appendix B contains detailed laboratory data from

each of the tanks, and Appendix C gives field sampling data.

579

(PNNL–11787)

TEMPEST code modifications and testing for erosionresisting sludge simulations. Onishi, Y.; Trent, D.S.

Pacific Northwest National Lab., Richland, WA (United

States). Jan 1998. 52p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States).

DOE Contract AC06-76RL01830. Order Number

DE98051733. Source: OSTI; NTIS; INIS; GPO Dep.

The TEMPEST computer code has been used to address

many waste retrieval operational and safety questions regarding waste mobilization, mixing, and gas retention.

Because the amount of sludge retrieved from the tank is directly related to the sludge yield strength and the shear

stress acting upon it, it is important to incorporate the sludge

yield strength into simulations of erosion-resisting tank waste

retrieval operations. This report describes current efforts to

modify the TEMPEST code to simulate pump jet mixing of

erosion-resisting tank wastes and the models used to test

for erosion of waste sludge with yield strength. Test results

for solid deposition and diluent/slurry jet injection into sludge

layers in simplified tank conditions show that the modified

TEMPEST code has a basic ability to simulate both the mobility and immobility of the sludges with yield strength.

Further testing, modification, calibration, and verification of

the sludge mobilization/immobilization model are planned

using erosion data as they apply to waste tank sludges.

580

(PNNL–11798)

Application of the risk-based strategy to the Hanford

tank waste organic-nitrate safety issue. Hunter, V.L.; Colson, S.D.; Ferryman, T.; Gephart, R.E.; Heasler, P.;

Scheele, R.D. Pacific Northwest National Lab., Richland,

WA (United States). Dec 1997. [200p.] Sponsored by USDOE Office of Environmental Management, Washington, DC

(United States). DOE Contract AC06-76RL01830. Order

Number DE98051681. Source: OSTI; NTIS; INIS; GPO Dep.

This report describes the results from application of the

Risk-Based Decision Management Approach for Justifying

147
ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

Characterization of Hanford Tank Waste to the organicnitrate safety issue in Hanford single-shell tanks (SSTs).

Existing chemical and physical models were used, taking

advantage of the most current (mid-1997) sampling and

analysis data. The purpose of this study is to make specific

recommendations for planning characterization to help

ensure the safety of each SST as it relates to the organicnitrate safety issue. An additional objective is to

demonstrate the viability of the Risk-Based Strategy for addressing Hanford tank waste safety issues.

581

(PNNL–11800)

Composite analysis for low-level waste disposal in the

200 area plateau of the Hanford Site. Kincaid, C.T. (and

others); Bergeron, M.P.; Cole, C.R. Pacific Northwest Lab.,

Richland, WA (United States). Mar 1998. 579p. Sponsored

by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract AC06-76RL01830.

Order Number DE98052818. Source: OSTI; NTIS; INIS;

GPO Dep.

This report presents the first iteration of the Composite

Analysis for Low-Level Waste Disposal in the 200 Area

Plateau of the Hanford Site (Composite Analysis) prepared

in response to the U.S. Department of Energy Implementation Plan for the Defense Nuclear Facility Safety Board

Recommendation 94-2. The Composite Analysis is a companion document to published analyses of four active or

planned low-level waste disposal actions: the solid waste

burial grounds in the 200 West Area, the solid waste burial

grounds in the 200 East Area, the Environmental Restoration Disposal Facility, and the disposal facilities for

immobilized low-activity waste. A single Composite Analysis

was prepared for the Hanford Site considering only sources

on the 200 Area Plateau. The performance objectives prescribed in U.S. Department of Energy guidance for the

Composite Analysis were 100 mrem in a year and examination of a lower dose (30 mrem in a year) to ensure the “as

low as reasonably achievable” concept is followed. The 100

mrem in a year limit was the maximum allowable allpathways dose for 1000 years following Hanford Site

closure, which is assumed to occur in 2050. These performance objectives apply to an accessible environment

defined as the area between a buffer zone surrounding an

exclusive waste management area on the 200 Area Plateau,

and the Columbia River. Estimating doses to hypothetical future members of the public for the Composite Analysis was

a multistep process involving the estimation or simulation of

inventories; waste release to the environment; migration

through the vadose zone, groundwater, and atmospheric

pathways; and exposure and dose. Doses were estimated

for scenarios based on agriculture, residential, industrial,

and recreational land use. The radionuclides included in the

vadose zone and groundwater pathway analyses of future

releases were carbon-14, chlorine-36, selenium-79,

technetium-99, iodine-129, and uranium isotopes.

582

(PNNL–11801)

Three-dimensional analysis of future groundwater flow

conditions and contaminant plume transport in the Hanford Site unconfined aquifer system: FY 1996 and 1997

status report. Cole, C.R.; Wurstner, S.K.; Williams, M.D.;

Thorne, P.D.; Bergeron, M.P. Pacific Northwest Lab., Richland, WA (United States). Dec 1997. 130p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract AC06-76RL01830. Order

Number DE98051992. Source: OSTI; NTIS; INIS; GPO Dep.

A three-dimensional numerical model of groundwater flow

and transport, based on the Coupled Fluid Energy, and Solute Transport (CFEST) code, was developed for the

Hanford Site to support the Hanford Groundwater Project

(HGWP), managed by Pacific Northwest National

Laboratory. The model was developed to increase the understanding and better forecast the migration of several

contaminant plumes being monitored by the HGWP, and to

support the Hanford Site Composite Analysis for low-level

waste disposal in the 200-Area Plateau. Recent modeling

efforts have focused on continued refinement of an initial

version of the three-dimensional model developed in 1995

and its application to simulate future transport of selected

contaminant plumes in the aquifer system. This version of

the model was updated using a more current version of the

CFEST code called CFEST96. Prior to conducting simulations of contaminant transport with the three-dimensional

model, a previous steady-state, two-dimensional model of

the unconfined aquifer system was recalibrated to 1979

water-table conditions with a statistical inverse method implemented in the CFEST-INV computer code. The results of

the recalibration were used to refine the three-dimensional

conceptual model and to calibrate it with a conceptualization

that preserves the two-dimensional hydraulic properties and

knowledge of the aquifer’s three-dimensional properties for

the same 1979 water-table conditions. The transient behavior of the three-dimensional flow model was also calibrated

by adjusting model storage properties (specific yield) until

transient water-table predictions approximated observed

water-table elevations between 1979 and 1996.

583

(PNNL–11836-Rev.1)

Flammable gas issues in double-contained receiver

tanks. Revision 1. Peurrung, L.M.; Mahoney, L.A.; Stewart,

C.W.; Gauglitz, P.A.; Pederson, L.R.; Bryan, S.A.; Shepard,

C.L. Pacific Northwest National Lab., Richland, WA (United

States). Jun 1998. 170p. Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract AC06-76RL01830. Order Number

DE98054466. Source: OSTI; NTIS; INIS; GPO Dep.

Four double-contained receiver tanks (DCRTs) at Hanford

will be used to store salt-well pumped liquids from tanks on

the Flammable Gas Watch List. This document was created

to serve as a technical basis or reference document for

flammable gas issues in DCRTs. The document identifies,

describes, evaluates, and attempts to quantify potential gas

carryover and release mechanisms. It estimates several key

parameters needed for these calculations, such as initial

aqueous concentrations and ventilation rate, and evaluates

the uncertainty in those estimates. It justifies the use of the

Schumpe model for estimating vapor-liquid equilibrium constants. It identifies several potential waste compatibility

issues (such as mixing and pH or temperature changes) that

could lead to gas release and provides a basis for calculating their effects. It evaluates the potential for gas retention in

precipitated solids within a DCRT and whether retention

could lead to a buoyant displacement instability (rollover)

event. It discusses rates of radiolytic, thermal, and corrosive

hydrogen generation within the DCRT. It also describes in

detail the accepted method of calculating the lower flammability limit (LFL) for mixtures of flammable gases.

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

584

(PNNL–11836-Rev.2)

Flammable gas issues in double-contained receiver

tanks. Revision 2. Peurrung, L.M.; Mahoney, L.A.; Stewart,

C.W.; Gauglitz, P.A.; Pederson, L.R.; Bryan, S.A.; Shepard,

C.L. Pacific Northwest National Lab., Richland, WA (United

States). Aug 1998. [150p.] Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract AC06-76RL01830. Order Number

DE98058899. Source: OSTI; NTIS; INIS; GPO Dep.

Four double-contained receiver tanks (DCRTs) at Hanford

will be used to store salt-well pumped liquids from tanks on

the Flammable Gas Watch List. This document was created

to serve as a reference document describing the current

knowledge of flammable gas issues in DCRTs. The document identifies, describes, evaluates, and attempts to

quantify potential gas carryover and release mechanisms. It

estimates several key parameters needed for these calculations, such as initial aqueous concentrations and ventilation

rate, and evaluates the uncertainty in those estimates. It

justifies the use of the Schumpe model for estimating vaporliquid equilibrium constants. It identifies several potential

waste compatibility issues (such as mixing and pH or temperature changes) that could lead to gas release and

provides a basis for calculating their effects. It evaluates the

potential for gas retention in precipitated solids within a

DCRT and whether retention could lead to a buoyant displacement instability (rollover) event. It discusses rates of

radiolytic, thermal, and corrosive hydrogen generation within

the DCRT. It also describes in detail the accepted method of

calculating the lower flammability limit (LFL) for mixtures of

flammable gases. The report incorporates these analyses

into two models for calculating headspace flammability, one

based on instantaneous equilibrium between dissolved

gases and the headspace and one incorporating limited release rates based on mass-transfer considerations. Finally, it

demonstrates the use of both models to estimate headspace

flammable gas concentrations and minimum ventilation rates

required to maintain concentrations below 25% of the LFL.

585

(PNNL–11852(Draft))

Risk based requirements for long term stewardship: A

proof-of-principle analysis of an analytic method tested

on selected Hanford locations. Jarvis, T.T. (and others);

Andrews, W.B.; Buck, J.W. Pacific Northwest Lab., Richland, WA (United States). Mar 1998. 56p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract AC06-76RL01830. DEAC06-76RLO 1830. Order Number DE98052629. Source:

OSTI; NTIS; INIS; GPO Dep.

Since 1989, the Department of Energy’s (DOE) Environmental Management (EM) Program has managed the

environmental legacy of US nuclear weapons production, research and testing at 137 facilities in 31 states and one US

territory. The EM program has conducted several studies on

the public risks posed by contaminated sites at these facilities. In Risks and the Risk Debate [DOE, 1995a], the

Department analyzed the risks at sites before, during, and

after remediation work by the EM program. The results indicated that aside from a few urgent risks, most hazards

present little inherent risk because physical and active site

management controls limit both the releases of site contaminants, and public access to these hazards. Without these

controls, these sites would pose greater risks to the public.

Past risk reports, however, provided little information about

post-cleanup risk, primarily because of uncertainty about future site uses and site characteristics at the end of planned

cleanup activities. This is of concern because in many cases

current cleanup technologies, and remedies, will last a

shorter period of time than the waste itself and the resulting

contamination will remain hazardous.

586

(PNNL–11887)

TWRS privatization phase 1 monitoring wells engineering study. Williams, B.A.; Newcomer, D.R. Pacific

Northwest National Lab., Richland, WA (United States). Apr

1998. 70p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract AC06-76RL01830. Order Number DE98053011.

Source: OSTI; NTIS; INIS; GPO Dep.

This engineering study provides an evaluation of existing

wells and boreholes (wells) within the proposed location for

the Tank Waste Remediation System (TWRS) Privatization

Phase 1 demonstration site. Phase 1 is part of the TWRS

program that was established to manage, retrieve, treat,

immobilize, and dispose of high-level waste stored in underground tanks at the Hanford Site. This evaluation is to

determine which wells will remain active within the demonstration site based on regulatory, programmatic, or other

beneficial use requirements. An initial evaluation of wells

within the demonstration site was conducted in 1996. However, changes in construction plans and expansion of the

demonstration site necessitated a reevaluation and reclassification of the wells that are within the expanded site.

Impacted wells include many of those previously evaluated

as well as additional wells identified in or near the expansion

areas. Thirty-three wells exist within and immediately

adjacent to the identified boundary of the proposed demonstration site. The wells identified for decommissioning will be

abandoned according to the well decommissioning plan. Future well requirements within the site include replacement

wells for those wells impacted by construction activities, replacements for Resource Conservation and Recovery Act of

1976 (RCRA) wells going dry, and a new characterization

well installed to support a TWRS Phase 2 site assessment.

587

(PNNL–11890)

Baseline estimate of the retained gas volume in Tank

241-C-106. Stewart, C.W.; Chen, G. Pacific Northwest National Lab., Richland, WA (United States). Jun 1998. 34p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC06-76RL01830. Order Number DE98054531. Source:

OSTI; NTIS; INIS; GPO Dep.

This report presents the results of a study of the retained

gas volume in Hanford Tank 241-C-106 (C-106) using the

barometric pressure effect method. This estimate is required

to establish the baseline conditions for sluicing the waste

from C-106 into AY-102, scheduled to begin in the fall of

1998. The barometric pressure effect model is described,

and the data reduction and detrending techniques are detailed. Based on the response of the waste level to the

larger barometric pressure swings that occurred between

October 27, 1997, and March 4, 1998, the best estimate

and conservative (99% confidence) retained gas volumes in

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

C-106 are 24 scm (840 scf) and 50 scm (1,770 scf), respectively. This is equivalent to average void fractions of 0.025

and 0.053, respectively.

588

(PNNL–11900)

Interaction of Pu(IV,VI) hydroxides/oxides with metal hydroxides/oxides in alkaline media. Fedoseev, A.M.

(Russian Academy of Sciences, Moscow (Russian Federation). Inst. of Physical Chemistry); Krot, N.N.; Budantseva,

N.A.; Bessonov, A.A.; Nikonov, M.V.; Grigoriev, M.S.; Garnov, A.Y.; Perminov, V.P.; Astafurova, L.N. Pacific

Northwest National Lab., Richland, WA (United States). Aug

1998. 58p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract AC06-76RL01830. Order Number DE98058293.

Source: OSTI; NTIS; INIS; GPO Dep.

The primary goal of this investigation was to obtain data

on the possibility, extent, and characteristics of interaction of

Pu(IV) and (VI) with hydroxides and oxides of d-elements

and other metals [Al(III), LA(III), and U(VI)] in alkaline

media. Such information is important in fundamental understanding of plutonium disposition and behavior in Hanford

Site radioactive tank waste sludge. These results supply

essential data for determining criticality safety and in understanding transuranic waste behavior in storage, retrieval,

and treatment of Hanford Site tank waste.

589

(PNNL–11901)

Plutonium(IV) precipitates formed in alkaline media in

the presence of various anions. Krot, N.N.; Shilov, V.P.;

Yusov, A.B.; Tananaev, I.G.; Grigoriev, M.S.; Garnov, A.Yu.;

Perminov, V.P.; Astafurova, L.N. Pacific Northwest National

Lab., Richland, WA (United States). Sep 1998. [50p.] Sponsored by USDOE Office of Environmental Management,

Washington, DC (United States). DOE Contract AC06-

76RL01830. Order Number DE98058986. Source: OSTI;

NTIS; INIS; GPO Dep.

The tendency of Pu(IV) to hydrolyze and form true solutions, colloid solutions, or insoluble precipitates has been

known since the Manhattan Project. Since then, specific

studies have been performed to examine in detail the equilibria of Pu(IV) hydrolytic reactions in various media. Great

attention also has been paid to the preparation, structure,

and properties of Pu(IV) polymers or colloids. These compounds found an important application in sol-gel technology

for the preparation of nuclear fuel materials. A most important result of these works was the conclusion that Pu(IV)

hydroxide, after some aging, consists of very small PuO2

crystallites and should therefore be considered to be Pu(IV)

hydrous oxide. However, studies of the properties and behavior of solid Pu(IV) hydroxide in complex heterogeneous

systems are rare. The primary goal of this investigation was

to obtain data on the composition and properties of Pu(IV)

hydrous oxide or other compounds formed in alkaline media

under different conditions. Such information is important to

understand Pu(IV) behavior and the forms of its existence in

the Hanford Site alkaline tank waste sludge. This knowledge

then may be applied in assessing plutonium criticality hazards in the storage, retrieval, and treatment of Hanford Site

tank wastes as well as in understanding its contribution to

the transuranic waste inventory (threshold at 100 nCi/g or

about 5 106 M) of the separate solution and solid

phases.

590

(PNNL–11903)

Groundwater monitoring plan for the Hanford Site 216-

B-3 pond RCRA facility. Barnett, D.B.; Chou, C.J. Pacific

Northwest National Lab., Richland, WA (United States). Jun

1998. [250p.] Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract AC06-76RL01830. Order Number DE98054558.

Source: OSTI; NTIS; INIS; GPO Dep.

The 216-B-3 pond system was a series of ponds for

disposal of liquid effluent from past Hanford production facilities. In operation since 1945, the B Pond system has been a

RCRA facility since 1986, with Resource Conservation and

Recovery Act (RCRA) interim-status groundwater monitoring

in place since 1988. In 1994, discharges were diverted from

the main pond, where the greatest potential for contamination was thought to reside, to the 3C expansion pond. In

1997, all discharges to the pond system were discontinued.

In 1990, the B Pond system was elevated from detection

groundwater monitoring to an assessment-level status because total organic halogens and total organic carbon were

found to exceed critical means in two wells. Subsequent

groundwater quality assessment failed to find any specific

hazardous waste contaminant that could have accounted for

the exceedances, which were largely isolated in occurrence.

Thus, it was recommended that the facility be returned to

detection-level monitoring.

591

(PNNL–11909-Rev.1)

Organic tanks safety program waste aging studies. Final

report, Revision 1. Camaioni, D.M. (and others); Samuels,

W.D.; Linehan, J.C. Pacific Northwest National Lab., Richland, WA (United States). Sep 1998. [150p.] Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract AC06-76RL01830. Order

Number DE98059302. Source: OSTI; NTIS; INIS; GPO Dep.

Uranium and plutonium production at the Hanford Site

produced large quantities of radioactive byproducts and contaminated process chemicals that are stored in underground

tanks awaiting treatment and disposal. Having been made

strongly alkaline and then subjected to successive water

evaporation campaigns to increase storage capacity, the

wastes now exist in the physical forms of saltcakes, metal

oxide sludges, and aqueous brine solutions. Tanks that contain organic process chemicals mixed with nitrate/nitrite salt

wastes might be at risk for fuel-nitrate combustion accidents. This project started in fiscal year 1993 to provide

information on the chemical fate of stored organic wastes.

While historical records had identified the organic compounds originally purchased and potentially present in

wastes, aging experiments were needed to identify the probable degradation products and evaluate the current hazard.

The determination of the rates and pathways of degradation

have facilitated prediction of how the hazard changes with

time and altered storage conditions. Also, the work with

aged simulated waste contributed to the development of analytical methods for characterizing actual wastes. Finally,

the results for simulants provide a baseline for comparing

and interpreting tank characterization data.

592

(PNNL–11919)

Integrating pretreatment and retrieval: Results from the

July 1997 Tanks Focus Area workshop. Pacific Northwest

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

National Lab., Richland, WA (United States). Jul 1998. 31p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC06-76RL01830. Order Number DE98057776. Source:

OSTI; NTIS; INIS; GPO Dep.

If scientists and researchers working to solve the tank

waste challenges, technical program office managers at the

tank sites, and others understand the connection between

retrieval and pretreatment activities, more efficient processes and reduced costs can be achieved. To make this

possible, researchers involved in retrieval and pretreatment

activities met at the Conference Center in Richland, Washington, on July 16 and 17, 1997, to discuss the connections

between these activities. The purpose of the workshop was

to help participants (1) gain a better understanding of retrieval and pretreatment process needs and experiences; (2)

gain practical knowledge of the applications, capabilities,

and requirements of retrieval and pretreatment technologies

being developed and deployed; and (3) focus on identifying

and troubleshooting interface issues and problems. The end

product of this meeting was to create a checklist of retrieval

and pretreatment parameters to consider when developing

new technologies or managing work at the sites in these areas. For convenience, the information is also organized by

pretreatment parameter and retrieval-pretreatment parameter in Section 5.0.

593

(PNNL–11920)

Performance evaluation of rotating pump jet mixing of

radioactive wastes in Hanford Tanks 241-AP-102 and -

104. Onishi, Y.; Recknagle, K.P. Pacific Northwest National

Lab., Richland, WA (United States). Jul 1998. [45p.] Sponsored by USDOE Office of Environmental Management,

Washington, DC (United States). DOE Contract AC06-

76RL01830. Order Number DE98057836. Source: OSTI;

NTIS; INIS; GPO Dep.

The purpose of this study was to confirm the adequacy of

a single mixer pump to fully mix the wastes that will be

stored in Tanks 241-AP-102 and -104. These Hanford

double-shell tanks (DSTs) will be used as staging tanks to

receive low-activity wastes from other Hanford storage tanks

and, in turn, will supply the wastes to private waste vitrification facilities for eventual solidification. The TEMPEST

computer code was applied to Tanks AP-102 and -104 to

simulate waste mixing generated by the 60-ft/s rotating jets

and to determine the effectiveness of the single rotating

pump to mix the waste. TEMPEST simulates flow and mass/

heat transport and chemical reactions (equilibrium and kinetic reactions) coupled together. Section 2 describes the

pump jet mixing conditions the authors evaluated, the modeling cases, and their parameters. Section 3 reports model

applications and assessment results. The summary and

conclusions are presented in Section 4, and cited references are listed in Section 5.

594

(PNNL–11923)

Sampling and analysis plan for the former Atomic Energy Commission bus lot property. Nielson, R.R. Pacific

Northwest National Lab., Richland, WA (United States). Jul

1998. [100p.] Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract AC06-76RL01830. Order Number DE98059318.

Source: OSTI; NTIS; INIS; GPO Dep.

This sampling and analysis plan (SAP) presents the rationale and strategy for the sampling and analysis activities

proposed in support of an initial investigation of the former

Atomic Energy Commission (AEC) bus lot property currently

owned by Battelle Memorial Institute. The purpose of the

proposed sampling and analysis activity is to investigate the

potential for contamination above established action levels.

The SAP will provide defensible data of sufficient quality and

quantity to support recommendations of whether any further

action within the study area is warranted. To assist in

preparing sampling plans and reports, the Washington State

Department of Ecology (Ecology) has published Guidance

on Sampling and Data Analysis Methods. To specifically address sampling plans for petroleum-contaminated sites,

Ecology has also published Guidance for Remediation of

Petroleum Contaminated Sites. Both documents were used

as guidance in preparing this plan. In 1992, a soil sample

was taken within the current study area as part of a project

to remove two underground storage tanks (USTs) at Battelle’s Sixth Street Warehouse Petroleum Dispensing Station

(Section 1.3). The results showed that the sample contained

elevated levels of total petroleum hydrocarbons (TPH) in the

heavy distillate range. This current study was initiated in part

as a result of that discovery. The following topics are considered: the historical background of the site, current site

conditions, previous investigations performed at the site, an

evaluation based on the available data, and the contaminants of potential concern (COPC).

595

(PNNL–11925)

Waste tank ventilation rates measured with a tracer gas

method. Huckaby, J.L.; Evans, J.C.; Sklarew, D.S.;

Mitroshkov, A.V. Pacific Northwest National Lab., Richland,

WA (United States). Aug 1998. [50p.] Sponsored by USDOE

Office of Environmental Management, Washington, DC

(United States). DOE Contract AC06-76RL01830. Order

Number DE98058853. Source: OSTI; NTIS; INIS; GPO Dep.

Passive ventilation with the atmosphere is used to prevent

accumulation of waste gases and vapors in the headspaces

of 132 of the 177 high-level radioactive waste Tanks at the

Hanford Site in Southeastern Washington State. Measurements of the passive ventilation rates are needed for the

resolution of two key safety issues associated with the rates

of flammable gas production and accumulation and the

rates at which organic salt-nitrate salt mixtures dry out. Direct measurement of passive ventilation rates using mass

flow meters is not feasible because ventilation occurs va

multiple pathways to the atmosphere (i.e., via the filtered

breather riser and unsealed tank risers and pits), as well as

via underground connections to other tanks, junction boxes,

and inactive ventilation systems. The tracer gas method discussed in this report provides a direct measurement of the

rate at which gases are removed by ventilation and an indirect measurement of the ventilation rate. The tracer gas

behaves as a surrogate of the waste-generated gases, but it

is only diminished via ventilation, whereas the waste gases

are continuously released by the waste and may be subject

to depletion mechanisms other than ventilation. The fiscal

year 1998 tracer studies provide new evidence that

significant exchange of air occurs between tanks via the underground cascade pipes. Most of the single-shell waste

tanks are connected via 7.6-cm diameter cascade pipes to

one or two adjacent tanks. Tracer gas studies of the Tank U102/U-103 system indicated that the ventilation occurring via

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

the cascade line could be a significant fraction of the total

ventilation. In this two-tank cascade, air evidently flowed

from Tank U-103 to Tank U-102 for a time and then was observed to flow from Tank U-102 to Tank U-103.

596

(PNNL–11926)

Ventilation rates calculated from hydrogen release data

in tanks equipped with standard hydrogen monitoring

systems (SHMS). Sklarew, D.S.; Huckaby, J.L. Pacific

Northwest National Lab., Richland, WA (United States). Sep

1998. 22p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract AC06-76RL01830. Order Number DE98058987.

Source: OSTI; NTIS; INIS; GPO Dep.

This report describes a method for estimating the ventilation rates of the high-level radioactive waste tank

headspaces at the Hanford Site in Southeastern Washington

state. The method, using hydrogen concentration data, is

applied to all passively ventilated and selected mechanically

ventilated tanks equipped with Standard Hydrogen Monitoring Systems (SHMS) and covers the time period from when

the SHMS were installed through July 12, 1998. Results of

the analyses are tabulated and compared with results from

tracer gas studies and similar analyses of SHMS data. The

method relies on instances of above-normal hydrogen releases and assumes the rate at which hydrogen is released

by the waste is otherwise approximately constant. It also assumes that hydrogen is uniformly distributed in the tank

headspace, so that at any given time the concentration of

hydrogen in the effluent is approximately equal to the average headspace concentration and that measured by the

SHMS. In general, the greatest single source of error in the

method is the determination of the baseline hydrogen concentration, which in this study has been estimated by visual

inspection of plotted data. Uncertainties in the calculated

ventilation rates due to inaccurate baseline measurements

are examined by performing a sensitivity analysis with upper

and lower bounding values for the baseline concentration (in

addition to the best estimate). A table lists the tanks considered in this report and the range of estimated ventilation

rates obtained for each tank. When multiple events of

above-normal hydrogen releases were observed, the range

of estimated ventilation rates is given. Resulting values and

their variability are consistent with those determined using

tracer gases.

597

(PNNL–11930)

Calculation of combustible waste fraction (CWF) estimates used in organics safety issue screening. Heasler,

P.G.; Gao, F.; Toth, J.J. Pacific Northwest National Lab.,

Richland, WA (United States). Aug 1998. 492p. Sponsored

by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract AC06-76RL01830.

Order Number DE98058233. Source: OSTI; NTIS; INIS;

GPO Dep.

This report describes how in-tank measurements of moisture (H2O) and total organic carbon (TOC) are used to

calculate combustible waste fractions (CWF) for 138 of the

149 Hanford single shell tanks. The combustible waste fraction of a tank is defined as that proportion of waste that is

capable of burning when exposed to an ignition source.

These CWF estimates are used to screen tanks for the organics complexant safety issue. Tanks with a suitably low

fraction of combustible waste are classified as safe. The calculations in this report determine the combustible waste

fractions in tanks under two different moisture conditions:

under current moisture conditions, and after complete dry

out. The first fraction is called the wet combustible waste

fraction (wet CWF) and the second is called the dry combustible waste fraction (dry CWF). These two fractions are

used to screen tanks into three categories: if the wet CWF

is too high (above 5%), the tank is categorized as unsafe; if

the wet CWF is low but the dry CWF is too high (again,

above 5%), the tank is categorized as conditionally safe;

finally, if both the wet and dry CWF are low, the tank is categorized as safe. Section 2 describes the data that was

required for these calculations. Sections 3 and 4 describe

the statistical model and resulting fit for dry combustible

waste fractions. Sections 5 and 6 present the statistical

model used to estimate wet CWF and the resulting fit. Section 7 describes two tests that were performed on the dry

combustible waste fraction ANOVA model to validate it.

Finally, Section 8 presents concluding remarks. Two Appendices present results on a tank-by-tank basis.

598

(PNNL–11933)

Survey of radiological contaminants in the near-shore

environment at the Hanford Site 100-N Area reactor. Van

Verst, S.P. (Washington State Dept. of Health, Olympia, WA

(United States)); Albin, C.L.; Patton, G.W.; Blanton, M.L.;

Poston, T.M.; Cooper, A.T.; Antonio, E.J. Pacific Northwest

National Lab., Richland, WA (United States). Sep 1998.

[150p.] Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC06-76RL01830. Order Number DE98059301. Source:

OSTI; NTIS; INIS; GPO Dep.

Past operations at the Hanford Site 100-N Area reactor

resulted in the release of radiological contaminants to the

soil column, local groundwater, and ultimately to the nearshore environment of the Columbia River. In September

1997, the Washington State Department of Health (WDOH)

and the Hanford Site Surface Environmental Surveillance

Project (SESP) initiated a special study of the near-shore

vicinity at the Hanford Site’s retired 100-N Area reactor.

Environmental samples were collected and analyzed for radiological contaminants (3H, 90Sr, and gamma/emitters),

with both the WDOH and SESP analyzing a portion of the

samples. Samples of river water, sediment, riverbank

springs, periphyton, milfoil, flying insects, clam shells, and

reed canary grass were collected. External exposure rates

were also measured for the near-shore environment in the

vicinity of the 100-N Area. In addition, samples were collected at background locations above Vernita Bridge.

599

(PNNL–11935)

Dryout modeling in support of the organic tank safety

project. Simmons, C.S. Pacific Northwest National Lab.,

Richland, WA (United States). Aug 1998. 57p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract AC06-76RL01830. Order

Number DE98058856. Source: OSTI; NTIS; INIS; GPO Dep.

This work was performed for the Organic Tank Safety

Project to evaluate the moisture condition of the waste surface organic-nitrate bearing tanks that are classified as

being conditionally safe because sufficient water is present.

This report describes the predictive modeling procedure

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

used to predict the moisture content of waste in the future,

after it has been subjected to dryout caused by water vapor

loss through passive ventilation. This report describes a simplified procedure for modeling the drying out of tank waste.

Dryout occurs as moisture evaporates from the waste into

the headspace and then exits the tank through ventilation.

The water vapor concentration within the waste of the

headspace is determined by the vapor-liquid equilibrium,

which depends on the waste’s moisture content and temperature. This equilibrium has been measured experimentally

for a variety of waste samples and is described by a curve

called the water vapor partial pressure isotherm. This curve

describes the lowering of the partial pressure of water vapor

in equilibrium with the waste relative to pure water due to the

waste’s chemical composition and hygroscopic nature. Saltcake and sludge are described by two distinct calculations

that emphasize the particular physical behavior or each. A

simple, steady-state model is devised for each type to obtain

the approximate drying behavior. The report shows the application of the model to Tanks AX-102, C-104, and U-105.

600

(PNNL–11945)

Organic tank safety project: Equilibrium moisture determination task, FY 1998 annual progress report. Scheele,

R.D.; Bredt, P.R.; Sell, R.L. Pacific Northwest National Lab.,

Richland, WA (United States). Aug 1998. [100p.] Sponsored

by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract AC06-76RL01830.

Order Number DE98058430. Source: OSTI; NTIS; INIS;

GPO Dep.

During fiscal year 1998, PNNL investigated the effect of

PH2O at or near maximum tank waste surface temperatures

on the equilibrium water content of selected Hanford waste

samples. These studies were performed to determine how

dry organic-bearing wastes will become if exposed to environmental Hanford water partial pressures. The samples

tested were obtained from Organic Watch List Tanks. At 26

C, the lowest temperature used, the water partial pressures

ranged from 2 to 22 torr. At 41 C, the highest temperature

used, the water partial pressures ranged from 3.5 to 48 torr.

When the aliquots exposed to the lowest and highest water

partial pressures reached their equilibrium or nearequilibrium water contents, they were exchanged to

determine if hysteresis occurred. In some experiments, once

equilibrated, aliquots not used in the hysteresis experiments

were allowed to equilibrate at room temperature (23 C) until

the hysteresis experiments ended; this provides a measure

of the effect of temperature.

601

(PNNL–11955)

Organic speciation of AX-102, BX-104, C-104, C-201, and

C-202 tank wastes. Campbell, J.A.; Sharma, A.K.; Clauss,

S.A.; Mong, G.M.; Bellofatto, D.L. Pacific Northwest National

Lab., Richland, WA (United States). Aug 1998. 8p. Sponsored by USDOE Office of Environmental Management,

Washington, DC (United States). DOE Contract AC06-

76RL01830. Order Number DE98058970. Source: OSTI;

NTIS; INIS; GPO Dep.

This report describes the work performed during FY 1998

by Pacific Northwest National Laboratory to identify organic

components in Hanford waste tank samples to support resolution of the organic tank safety issue. The major focus

during FY 1998 was the analysis of actual tank wastes under Hanford Analytical Services Quality Assurance

(HASQARD) compliance. Samples from Tanks AX-102, C104, BX-104, C-201, and C-202 were analyzed for organic

constituents. Samples were analyzed using derivatization

gas chromatography/flame ionization detection for chelators

and chelator fragments, ion chromatography for

low-molecular-weight organic acids, and ion-pair chromatography for chelators. The major components identified include

low-molecular-weight acids (e.g., oxalic acid), chelators

(e.g., EDTA) and chelator fragments.

602

(PNNL–11968)

Performance evaluation of the PITBULL pump for the

removal of hazardous waste. Hatchell, B.K.; Combs, W.H.;

Hymas, C.R.; Powell, M.R.; Rinker, M.W.; White, M. Pacific

Northwest National Lab., TN (United States). Sep 1998.

[75p.] Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC06-76RL01830. Order Number DE98059319. Source:

OSTI; NTIS; INIS; GPO Dep.

One objective of the Waste Removal Project at the

Department of Energy’s Savannah River Site (SRS) is to explore methods to successfully remove waste heels that will

remain in the high-level waste tanks after bulk waste removal has been completed. Tank closure is not possible

unless this residue is removed. As much as 151,000 liters of

residue can remain after a conventional waste removal campaign. The waste heels can be comprised of sludge, zeolite,

and silica. The heels are generally hardened or compacted

insoluble particulate with relatively rapid settling velocities. A

PITBULL pump is being considered by SRS to retrieve

sludge-type waste from Tank 19. Sections 1 through 4 of

this report present the scope and objectives of the test program, describe the principles of operation of the PITBULL,

and present the test approach, set-up, and instrumentation.

Test results, including pumping rates with water and slurry,

are provided in Section 5, along with considerations for remote operation. Conclusions and recommendations are

provided in Section 6.

603

(PNNL–11970)

Monitoring bank erosion at the Locke Island Archaeological National Register District: Summary of 1996/

1997 field activities. Nickens, P.R. (ed.); Bjornstad, B.N.;

Nickens, P.R.; Cadoret, N.A.; Wright, M.K. Pacific Northwest

National Lab., Richland, WA (United States). Aug 1998.

[150p.] Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC06-76RL01830. Order Number DE98058488. Source:

OSTI; NTIS; GPO Dep.

Locke Island is located in the Columbia River in southcentral Washington. The US Department of Energy (DOE)

owns Locke Island as part of its Hanford Site. In the 1960s

and 1970s, as a result of intensive irrigation developments

on the inland shoreline to the east of the island, the White

Bluffs, which form the eastern boundary of the Columbia

River channel in this area, began to show geological failures

as excess irrigation water seeped out along the bluffs. One

of the largest such failures, known as the Locke Island

Landslide, is located just east of Locke Island. By the early

1980s, this landslide mass had moved westward into the

river channel toward the island and was diverting the current

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

at the island’s eastern perimeter. Erosion of the bank in the

center of the island accelerated, threatening the cultural

resources. By the early 1990s, the erosion had exposed cultural features and artifacts along the bank, leading to the

beginning of intermittent monitoring of the cutbank. In 1994,

DOE initiated more scheduled, systematic monitoring of island erosion to better understand the physical processes

involved as well as mitigate ongoing loss of the archaeological record.

604

(PNNL–11981)

Mechanisms of gas retention and release: Experimental

results for Hanford single-shell waste tanks 241-A-101,

241-S-106, and 241-U-103. Rassat, S.D.; Caley, S.M.;

Bredt, P.R.; Gauglitz, P.A.; Rinehart, D.E.; Forbes, S.V. Pacific Northwest National Lab., Richland, WA (United States).

Sep 1998. 65p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE

Contract AC06-76RL01830. Order Number DE98058803.

Source: OSTI; NTIS; INIS; GPO Dep.

The 177 underground waste storage tanks at the Hanford

Site contain millions of gallons of radioactive waste resulting

from the purification of nuclear materials and related processes. Through various mechanisms, flammable gas

mixtures of hydrogen, ammonia, methane, and nitrous oxide

are generated and retained in significant quantities within

the waste in many (25) of these tanks. The potential for

large releases of retained gas from these wastes creates a

flammability hazard. It is a critical component of the effort to

understand the flammability hazard and a primary goal of

this laboratory investigation to establish an understanding of

the mechanisms of gas retention and release in these

wastes. The results of bubble retention experimental studies

using waste samples from several waste tanks and a variety

of waste types support resolution of the Flammable Gas

Safety Issue. Gas bubble retention information gained in the

pursuit of safe storage will, in turn, benefit future waste operations including salt-well pumping, waste transfers, and

sluicing/retrieval.

605

(PNNL–11988)

Purification of alkaline solutions and wastes from actinides and technetium by coprecipitation with some

carriers using the method of appearing reagents: Final

Report. Peretrukhin, V.F. (Russian Academy of Sciences,

Moscow (Russian Federation). Inst. of Physical Chemistry);

Silin, V.I.; Kareta, A.V.; Gelis, A.V.; Shilov, V.P.; German,

K.E.; Firsova, E.V.; Maslennikov, A.G.; Trushina, V.E. Pacific Northwest National Lab., Richland, WA (United States).

Sep 1998. 55p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE

Contract AC06-76RL01830. Order Number DE98059329.

Source: OSTI; NTIS; INIS; GPO Dep.

The coprecipitation of transuranium elements (TRU) and

technetium from alkaline solutions and from simulants of

Hanford Site tank wastes has been studied in reducing and

oxidizing conditions on uranium(IV,VI) hydroxocompounds,

tetraalkylammonium perrhenate and perchlorate, and on hydroxides of Fe(III), Co(III), Mn(II), and Cr(III) using the

method of appearing reagents (MAR). Coprecipitations in

alkaline solution have been shown to give high decontamination factors (DF) at low content of carrier and in the

presence of high salt concentrations. Uranium(IV) hydroxide

in concentrations higher than 3 103 M coprecipitates Pu

and Cm in any oxidation state from 0.2 to 4 M NaOH with

DFs of 110 to 1000 and Np and Tc with DFs of 51 to 176.

Technetium (VII) coprecipitates with (5 to 8) 104 M tetrabutylammonium (TBA) perrhenate in 0.01 to 0.02 M TBA

hydroxide from 0.5 to 1.5 M NaOH to give DFs of 150 to

200. Coprecipitations of Np and Pu with Co(OH)3, Fe(OH)3,

Cr(OH)3, and Mn(OH)2 obtained by the MAR from precursors in the range from pH 10.5 to 0.4 M NaOH give DFs

from 80 to 400.

606

(PNNL–11989)

Integrated monitoring plan for the Hanford groundwater

monitoring project. Hartman, M.J.; Dresel, P.E.; McDonald, J.P.; Mercer, R.B.; Newcomer, D.R.; Thornton, E.C.

Pacific Northwest National Lab., Richland, WA (United

States). Sep 1998. [200p.] Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract AC06-76RL01830. Order Number

DE98059078. Source: OSTI; NTIS; INIS; GPO Dep.

Groundwater is monitored in hundreds of wells at the

Hanford Site to fulfill a variety of requirements. Separate

monitoring plans are prepared for various requirements, but

sampling is coordinated and data are shared among users

to avoid duplication of effort. The US Department of Energy

(DOE) manages these activities through the Hanford

Groundwater Monitoring Project (groundwater project),

which is the responsibility of Pacific Northwest National Laboratory. The groundwater project does not include all of the

monitoring to assess performance of groundwater remediation or all monitoring associated with active facilities. This

document is the first integrated monitoring plan for the

groundwater project and contains: well and constituent lists

for monitoring required by the Atomic Energy Act of 1954

and its implementing orders; other, established monitoring

plans by reference; and a master well/constituent/frequency

matrix for the entire Hanford Site.

607

(PNNL–11996)

Investigation of flammable gas and thermal safety issues for retrieval of waste from Tank 241-AN-105. Caley,

S.M.; Stewart, C.W.; Antoniak, Z.I.; Cuta, J.M.; Mahoney,

L.A.; Panisko, F.E. Pacific Northwest National Lab., Richland, WA (United States). Sep 1998. 50p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract AC06-76RL01830. Order

Number DE98059303. Source: OSTI; NTIS; INIS; GPO Dep.

The primary purpose of this report is to identify and resolve some of the flammable gas and thermal safety issues

potentially associated with the retrieval of waste from Tank

241-AN-105 (AN-105), which is the first double-shell tank

scheduled for waste retrieval at Hanford. The planned retrieval scenario includes the following steps in AN-105: (1)

degas the tank using two submerged mixing pumps, (2) turn

off the mixer pump(s) and allow any suspended solids to

settle, (3) decant the supernatant to the intermediate feed

staging tank(s) (IFSTs) (AP-102 and/or AP-104) using water/

caustic dilution at the transfer pump inlet, (4) add the remaining dilution water/caustic to the slurry remaining in

AN-105, (5) mix the tank with the mixer pump(s) until the

soluble solids dissolve, (6) turn off the mixer pump(s) and let

the insoluble solids settle, and (7) decant the new supernatant to the IFST(s), leaving the insoluble solids behind.

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

Three waste retrieval safety issues are addressed in this report. They are (1) the controlled degassing of AN-105 to

ensure that the headspace remains <25% of the lower

flammability limit (LFL), (2) an assessment of how dissolved

gas (mainly ammonia) released during the transfer of the

supernatant in AN-105 to the IFSTs and the water/caustic dilution of the remaining slurry in AN-105 will affect the

flammability in these tanks; and (3) an assessment of the

maximum waste temperatures that might occur in AN-105

during retrieval operations.

608

(PNNL–11999)

Demonstration of strontium removal from Hanford NArea well water. Carlson, C.D.; DesChane, J.R.; Corneillie,

T.M. Pacific Northwest National Lab., Richland, WA (United

States). Sep 1998. 34p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States).

DOE Contract AC06-76RL01830. Order Number

DE98059362. Source: OSTI; NTIS; INIS; GPO Dep.

As part of the Efficient Separations and Processing Crosscutting Program, the Pacific Northwest National Laboratory

conducted this study to demonstrate the efficiency of several

ion-exchange materials in removing strontium-90 from actual groundwater from the Hanford N-Springs Pump and

Treat Demonstration Facility. The objective of this experiment was to determine the strontium-loading distribution

coefficients (Kds) for some titanate ion-exchange materials,

modified minerals, and organic ion-exchange resins. The

equilibrium uptake data presented in this report are useful

for identifying potential materials that are capable of removing strontium from N-area groundwaters. The data show the

relative selectivities of the ion-exchange materials under

similar operating conditions, and show that additional flow

studies are needed to predict materials capacities and to develop complete ion-exchange process flow sheets. The

materials investigated in this study include commercially

available ion exchangers such as IONSIV IE-911 (manufactured by UOP) and SuperLig 644 (IBC Advanced

Technologies, Inc.), and materials produced on an experimental basis by Allied Signal (nontitanates), Selion Inc.

(titanates), and Pennsylvania State University (modified

mica). In all, the performance of seven different ionexchange materials was evaluated using actual N-Area

groundwater. The evaluation consisted of the determining

strontium batch distribution coefficients, loading, and decontamination factors. Tests were performed at two different

solution-to-exchanger mass ratios (i.e., phase ratios) of

2000 and 4000 using actual N-Area groundwater samples

from three different wells. Actual N-Area groundwater used

in the present study was obtained from three monitoring

wells in FY 1998. These samples were taken from wells with

strontium-90 concentrations ranging from 0.25 to 3.9 pCi/L.

609

(PNNL–12001)

Low-pressure, single-point grout injection for tank heel

sludge mixing and in-situ immobilization. Whyatt, G.A.;

Hymas, C.R. Pacific Northwest National Lab., Richland, WA

(United States). Sep 1998. 45p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States). DOE Contract AC06-76RL01830. Order Number

DE98059321. Source: OSTI; NTIS; INIS; GPO Dep.

This report describes tests conducted in an approximately

9-ft diameter test tank situated outside the 336 building in

Hanford’s 300 area. The tests were performed to measure

the ability of jets of grout slurry to mobilize and mix simulated tank sludge. The technique is intended for in situ

immobilization of tank waste heels. The current approach

uses a single, rotated, larger-diameter nozzle driven at

lower pressure. Due to the larger diameter, the potential for

plugging is reduced and the effective radius around an injection point over which the jet is effective in mobilizing sludge

from the tank bottom can be made larger. A total of three

grout injection tests were conducted in a 9-ft diameter tank.

In each case, a 2-in. layer of kaolin clay paste was placed

on a dry tank floor to simulate a sludge heel. The clay was

covered with 4 inches of water. The grout slurry, consisting

of Portland cement, class F fly ash, and eater, was prepared

and delivered by an offsite vendor. In the third test, the

sludge in half of the tank was replaced by a layer of 20x50

mesh zeolite, and bentonite clay was added to the grout formulation. After injection, the grout was allowed to set and

then the entire grout monolith was manually broken up and

excavated using a jack hammer. Intact pieces of clay were

visually apparent due to a sharp color contrast between the

grout and clay. Remaining clay deposits were collected and

weighed and suspended clay pieces within the monolith

were photographed. The mobilization performance of the

grout jets exceeded expectations.

610

(PNNL–12003)

Summary of uncertainty estimation results for Hanford

tank chemical and radionuclide inventories. Ferryman,

T.A. (and others); Amidan, B.G.; Chen, G. Pacific Northwest

National Lab., Richland, WA (United States). Sep 1998.

198p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC06-76RL01830. Order Number DE98059363. Source:

OSTI; NTIS; INIS; GPO Dep.

The exact physical and chemical nature of 55 million gallons of radioactive waste held in 177 underground waste

tanks at the Hanford Site is not known in sufficient detail to

support safety, retrieval, and immobilization missions. The

Hanford Engineering Analysis Best-Basis team has made

point estimates of the inventories in each tank. The purpose

of this study is to estimate probability distributions for each

of the analytes and tanks for which the Hanford Best-Basis

team has made point estimates. Uncertainty intervals can

then be calculated for the Best-Basis inventories and should

facilitate the cleanup missions. The methodology used to

generate the results published in the Tank Characterization

Database (TCD) and summarized in this paper is based on

scientific principles, sound technical knowledge of the realities associated with the Hanford waste tanks, the chemical

analysis of actual samples from the tanks, the Hanford BestBasic research, and historical data records. The

methodology builds on research conducted by Pacific Northwest National Laboratory (PNNL) over the last few years.

Appendix A of this report summarizes the results of the

study. The full set of results (in percentiles, 1–99) is available through the TCD, (http://twins.pnl.gov:8001).

611

(PNNL–12007)

Fabrication and testing of engineered forms of selfassembled monolayers on mesoporous silica (SAMMS)

material. Mattigod, S.V. (Pacific Northwest National Lab.,

Richland, WA (United States)); Liu, J.; Fryxell, G.E.;

155
ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

Baskaran, S.; Gong, M.; Nie, Z.; Feng, X.; Klasson, K.T. Pacific Northwest National Lab., Richland, WA (United States).

Sep 1998. 27p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE

Contract AC06-76RL01830. Order Number DE98059366.

Source: OSTI; NTIS; GPO Dep.

A number of engineered forms such as flexible extrudates, beads, and rods were fabricated using thiol-SAMMS

(Self-Assembled Monolayers on Mesoporous Silica) and

tested for their mercury adsorption capacities. The flexible

extrudate form had a mercury adsorption capacity of 340

mg/g but was found to be structurally unstable. A structurally

sound bead form of thiol-SAMMS was fabricated with 5, 10,

25, and 40% by weight clay binder (attapulgite) and

successfully functionalized. A structurally stable but nonoptimized rod form of thiol-SAMMS was also fabricated.

Bench-scale processes were developed to silanize and

functionalize mesoporous silica beads made with attapulgite

clay binder. Contact angle measurements were conducted

to assess the degree of surface coverage by functional

groups on mesoporous silica materials.

612

(PNNL-SA–28461-Rev.1)

Proceedings of the efficient separations and processing

crosscutting program 1997 technical exchange meeting.

Gephart, J.M. (ed.). Science, Inc., Anaheim, CA (United

States). [1997]. 211p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States).

DOE Contract AC06-76RL01830. (CONF-970148–Rev.1:

Efficient Separations and Processing (ESP) Crosscutting

Program FY 1997 technical exchange meeting, Gaithersburg, MD (United States), 28-30 Jan 1997). Order Number

DE97052111. Source: OSTI; NTIS; INIS; GPO Dep.

This document contains summaries of technology development presented at the 1997 Efficient Separations and

Processing Crosscutting Program (ESP-CP) Technical Exchange Meeting (TEM), held January 28-30, 1997, in

Gaithersburg, Maryland. The ESP-CP is sponsored by the

U.S. Department of Energy’s Office of Environmental Management (DOE/EM), Office of Science and Technology. The

ESP-CP TEM is held annually to: (1) Present current technology development activities funded by the ESP-CP.

Developers of ESP-CP-funded technologies describe the

problems and needs addressed by their technologies; the

technical approach, accomplishments, and resolution of issues; the strategy and schedule for commercialization; and

evolving potential applications. Representatives from DOE/

EM’s Focus Areas also present their technology needs. (2)

Promote the exchange of technical information among those

developing new separations technologies, those responsible

for providing new separations technologies to meet DOE/EM

needs, and those who need or will potentially make use of

such technologies. (3) Familiarize the ESP-CP Technical

Review Team with the FY 1997 program and solicit reviewers’ views on the program as a whole. This meeting is not a

program review of the individual tasks, but instead focuses

on the technical aspects and implementation of ESP-CPsponsored technology or data. This document also contains

a list of ESP-CP-sponsored publications, presentations, and

patents. Separate abstracts have been indexed into the energy database for contributions to this proceedings.

613

(RFP–5083)

Basis of Estimate Software Tool (BEST) - a practical solution to part of the cost and schedule integration

puzzle. Murphy, L.; Bain, P. EG and G Rocky Flats, Inc.,

Golden, CO (United States). 1997. 6p. Sponsored by USDOE Office of Environmental Management, Washington, DC

(United States). DOE Contract AC34-90RF62349. (CONF970335–6: Waste Management ‘97, Tucson, AZ (United

States), 2-7 Mar 1997). Order Number DE97002595.

Source: OSTI; NTIS; INIS; GPO Dep.

The Basis of Estimate Software Tool (BEST) was developed at the Rocky Flats Environmental Technology Site

(Rocky Flats) to bridge the gap that exists in conventional

project control systems between scheduled activities, their

allocated or assigned resources, and the set of assumptions

(basis of estimate) that correlate resources and activities.

Having a documented and auditable basis of estimate

(BOE) is necessary for budget validation, work scope analysis, change control, and a number of related management

control functions. The uniqueness of BEST is demonstrated

by the manner in which it responds to the diverse needs of

the heavily regulated environmental workplace - containing

many features not found in conventional off-the-shelf

software products. However, even companies dealing in relatively unregulated work places will find many attractive

features in BEST. This product will be of particular interest

to current Government contractors and contractors preparing proposals that may require subsequent validation. 2 figs.

614

(RFP–5098-Pt.2)

Safety Analysis and Risk Assessment Handbook, new

guidance to the safety analyst. Peterson, V.L. (Rocky

Flats Environmental Technology Site, Golden, CO (United

States)). Rocky Flats Environmental Technology Site,

Golden, CO (United States). [1997]. 5p. Sponsored by USDOE Office of Environmental Management, Washington, DC

(United States). DOE Contract AC34-90DP62349. (CONF970661–11-Pt.2: 1997 safety analysis workshop, Oakland,

CA (United States), 9-13 Jun 1997). Order Number

DE97007029. Source: OSTI; NTIS; INIS; GPO Dep.

New guidance to the safety analyst has been developed

at the Rocky Flats Environmental Technology Site (RFETS)

in the form of the new Safety Analysis and Risk Assessment

Handbook (SARAH). Although the older guidance (the

Rocky Flats Risk Assessment Guide) continues to be used

for updating the Final Safety Analysis Reports (FSARs) developed in the mid-1980s, this new guidance is used with all

new authorization basis documents. With the RFETS mission change in the early 1990s came the need to establish

new authorization basis documents for its facilities, whose

missions had changed. The methodology and databases for

performing the evaluations that support the new authorization basis documents needed to be standardized, to avoid

the use of different approaches and/or databases for similar

accidents in different facilities. This paper presents this new

standardized approach, the SARAH.

615

(RFP–5108)

Workforce mobilization for D&D at the Rocky Flats Environmental Technology Site (RFETS). Coles, G.W.

(Kaiser-Hill, Rocky Flats, CO (United States)); Easdon, R.C.;

Bourgeois, T.G. EG and G Rocky Flats, Inc., Golden, CO

156
Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

(United States). 1997. 6p. Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract AC34-90RF62349. (CONF-970335–

2: Waste Management ‘97, Tucson, AZ (United States), 2-7

Mar 1997). Source: Kaiser-Hill Co., LLC, Golden, CO

(United States).

The Rocky Flats Plant (RFP) was a nuclear production facility. Products from RFP included nuclear and non-nuclear

parts used by other plants to assemble weapons. Operations

at the plant generally included metal recovery, processing,

machining, assembly, and the physical and administrative

support functions associated with this type of production.

Construction of the Site began in the early 1950’s. The Site

was an active production facility through the Cold War. After

nuclear production operations ceased, the Site was

renamed to become the Rocky Flats Environmental Technology Site (Site). Labor policies and precedence began to

evolve from the time of initial construction. This paper reviews the labor situation at the plants at the commencement

of D&D activities, the problems that were created by that environment, and the efforts made to adjust labor policies to

aid effective implementation of D&D activities. Mobilization

of the D&D workforce required specific planning for effective

implementation. Work assignments for D&D activities had to

receive approval prior to performing activities. Once established, the appropriate funding was secured to allow hiring,

training and deployment of the workforce. An infrastructure

was established to manage activities and control work on a

day to day basis. The result of the Site effort in this area

provided for an immediate positive impact to D&D activities.

616

(RFP–5117)

NRC regulation of DOE facilities. Buhl, A.R. (Kaiser-Hill,

Golden, CO (United States)); Edgar, G.; Silverman, D.; Murley, T. Rocky Flats Environmental Technology Site, Golden,

CO (United States). [1997]. 8p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States). DOE Contract AC34-90RF62349. Order Number

DE97008351. Source: OSTI; NTIS; INIS; GPO Dep.

The US Department of Energy (DOE), its contractors, and

the Nuclear Regulatory Commission (NRC) are in for major

changes if the DOE follows through on its intentions

announced December 20, 1996. The DOE is seeking legislation to establish the NRC as the regulatory agency with

jurisdiction over nuclear health, safety, and security at a

wide range of DOE facilities. At this stage, it appears that as

many as 200 (though not all) DOE facilities would be affected. On March 28, 1997, the NRC officially endorsed

taking over the responsibility for regulatory oversight of DOE

nuclear facilities as the DOE had proposed, contingent upon

adequate funding, staffing resources, and a clear delineation

of NRC authority. This article first contrasts the ways in

which the NRC and the DOE carry out their basic regulatory

functions. Next, it describes the NRC’s current authority

over DOE facilities and the status of the DOE’s initiative to

expand that authority. Then, it discusses the basic changes

and impacts that can be expected in the regulation of DOE

facilities. The article next describes key lessons learned

from the recent transition of the GDPs from DOE oversight

to NRC regulation and the major regulatory issues that

arose in that transition. Finally, some general strategies are

suggested for resolving issues likely to arise as the NRC assumes regulatory authority over DOE facilities.

617

(RFP–5137)

Natural succession impeded by smooth brome (Bromus

inermis) and intermediate wheatgrass (Agropyron intermedium) in an abandoned agricultural field. Nelson, J.K.

(PTI Environmental Services, Boulder, CO (United States)).

EG and G Rocky Flats, Inc., Golden, CO (United States).

Rocky Flats Plant. [1997]. 8p. Sponsored by USDOE Office

of Environmental Management, Washington, DC (United

States). DOE Contract AC34-90DP62349. (CONF-971165–:

1997 international conference on ecological restoration and

regional conservation strategies, Ft. Lauderdale, FL (United

States), 12-15 Nov 1997). Order Number DE98000626.

Source: OSTI; NTIS; GPO Dep.

In 1975, an abandoned agricultural field at Rocky Flats

Environmental Technology Site (Site) that had been cultivated for more than 38 years, was seeded with smooth

brome (Bromus inermis) and intermediate wheatgrass

(Agropyron intermedium). Although these species are commonly planted in reclamation and roadside seed mixtures,

few studies have documented their impact on the reestablishment of native plant communities. In 1994, species

richness, cover, and biomass were sampled in the agricultural field and compared to the surrounding mixed-grass

prairie at the Site. The agricultural field contained only 61

plant species (62% native), compared to 143 species (81%

native) in the surrounding mixed-grass prairie. Community

similarity based on species presence/absence was 0.47

(Sorensen coefficient of similarity). Basal vegetative cover

was 11.2% in the agricultural field and 29.1% in the mixedgrass prairie. Smooth brome and intermediate wheatgrass

accounted for 93% of the relative foliar cover and 96% of

the biomass in the agricultural field. The aggressive nature

of these two planted species has impeded the natural succession of the agricultural field to a more native prairie

community. Studies of natural succession on abandoned

fields and roads in northeastern Colorado have indicated that

if left alone, fields would return to their native climax state in

approximately 50 years and would be approaching their native state after 20–25 years. Based on the results of this

study, this agricultural field may take more than 100 years to

return to a native mixed-grass prairie state and it may never

achieve a native state without human intervention.

618

(RFP–5153)

Status and use of the Rocky Flats Environmental Technology Site Pipe Overpack Container for TRU waste

storage and shipments. Thorp, D.T. (Safe Sites of Colorado, L.L.C., Golden, CO (United States)); Geinitz, R.R.;

Rivera, M.A. Rockwell International, Rocky Flats Plant,

Golden, CO (United States). 3 Mar 1998. 11p. Sponsored

by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract AC34-90RF62349.

(CONF-980307–: Waste management ’98, Tucson, AZ

(United States), 1-5 Mar 1998). Order Number

DE98002857. Source: OSTI; NTIS; INIS; GPO Dep.

The Pipe Overpack Container was designed to optimize

shipments of high plutonium content transuranic waste from

Rocky Flats Environmental Technology Site (RFETS) to

Waste Isolation Pilot Plant (WIPP). The container was approved for use in the TRUPACT-II shipping container by the

Nuclear Regulatory Commission in February 1997. The container optimizes shipments to WIPP by increasing the

TRUPACT-II criticality limit from 325 fissile grams equivalent

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

(FGE) to 2,800 FGE and provides additional shielding for

handling wastes with high americium-241 (Am-241) content.

The container was subsequently evaluated and approved for

storage of highly dispersible TRU wastes and residues at

RFETS. Thermal evaluation of the container shows that the

container will mitigate the impact of a worst case thermal

event from reactive or potentially pyrophoric materials.

These materials contain hazards postulated by the Defense

Nuclear Facilities Safety Board for interim storage. Packaging these reactive or potentially pyrophoric residues in the

container without stabilizing the materials is under consideration at RFETS. The design, testing, and evaluations used

in the approvals, and the current status of the container usage, will be discussed.

619

(RFP–5154)

The use of filtered bags to increase waste payload capacity. Dustin, D.F. (Safe Sites of Colorado, Golden, CO

(United States)); Thorp, D.T.; Rivera, M.A. Safe Sites of

Colorado, Golden, CO (United States). 3 Mar 1998. 13p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC34-90RF62349. (CONF-980307–: Waste management

’98, Tucson, AZ (United States), 1-5 Mar 1998). Order Number DE98002855. Source: OSTI; NTIS; INIS; GPO Dep.

For the past few years, the Department of Energy has favored the direct disposal of low plutonium content residue

materials from Rocky Flats rather than engage in expensive

and time consuming plutonium recovery operations. One

impediment to direct disposal has been the wattage limit imposed by the Waste Isolation Pilot Plant on hydrogenous

materials such as combustibles and sludges. The issue of

concern is the radiolytic generation and accumulation of hydrogen and other explosive gases in waste containers. The

wattage limits that existed through 1996 restricted the

amount of plutonium bearing hydrogenous materials that

could be packaged in a WIPP bound waste drum to only a

fraction of the capacity of a drum. Typically, only about one

kilogram of combustible residue could be packaged in a

waste drum before the wattage limit was exceeded resulting

in an excessively large number of drums to be procured,

stored, shipped, and interred. The Rocky Flats Environmental Technology Site has initiated the use of filtered plastic

bags (called bag-out bags) used to remove transuranic

waste materials from glove box lines. The bags contain

small, disk like HEPA filters which are effective in containing

radioactively contaminated particulate material but allow for

the diffusion of hydrogen gas. Used in conjunction with filtered 55 gallon drums, filtered bag-out bags were pursued

as a means to increase the allowable wattage limits for selected residue materials. In February 1997, the Nuclear

Regulatory Commission approved the use of filtered bag-out

bags for transuranic waste materials destined for WIPP. The

concomitant increase in wattage limits now allows for approximately four times the payload per waste drum for

wattage limited materials.

620

(RFP–5155)

Cementation of residue ion exchange resins at Rocky

Flats. Dustin, D.F.; Beckman, T.D.; Madore, C.M. Safe

Sites of Colorado, Golden, CO (United States). 3 Mar 1998.

13p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC34-90RF62349. (CONF-980307–: Waste management

’98, Tucson, AZ (United States), 1-5 Mar 1998). Order Number DE98002858. Source: OSTI; NTIS; INIS; GPO Dep.

Ion exchange resins have been used to purify nitric acid

solutions of plutonium at Rocky Flats since the 1950s. Spent

ion exchange resins were retained for eventual recovery of

residual plutonium, typically by incineration followed by the

aqueous extraction of plutonium from the resultant ash. The

elimination of incineration as a recovery process in the late

1980s and the absence of a suitable alternative process for

plutonium recovery from resins led to a situation where

spent ion exchange resins were simply placed into temporary storage. This report describes the method that Rocky

Flats is currently using to stabilize residue ion exchange

resins. The objective of the resin stabilization program is:

(1) to ensure their safety during interim storage at the site,

and (2) to prepare them for ultimate shipment to the Waste

Isolation Pilot Plant (WIPP) in New Mexico. Included in the

discussion is a description of the safety concerns associated

with ion exchange resins, alternatives considered for their

stabilization, the selection of the preferred treatment

method, the means of implementing the preferred option,

and the progress to date.

621

(RFP–5158)

Progress in stabilization of plutonium and residues

since DNFSB recommendation 94-1. Ball, J.M.; Dustin,

D.F. Safe Sites of Colorado, Golden, CO (United States). 3

Mar 1998. 10p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE

Contract AC34-90RF62349. (CONF-980307–: Waste management ’98, Tucson, AZ (United States), 1-5 Mar 1998).

Order Number DE98002856. Source: OSTI; NTIS; INIS;

GPO Dep.

There are approximately 100 metric tons of residues at

the Rocky Flats Environmental Technology Site containing

approximately 3 metric tons of plutonium. The residues are

byproducts of past plutonium operations incinerator ash; pyrochemical salts; graphite; sand, slag, and crucible; and

miscellaneous forms of combustibles, glass, metal, and

sludges. In September 1993, a report was released (Reference 1) which identified concerns with the chemical stability

of the residues and with the integrity of packaging. In May

1997, the Defense Nuclear Facility Safety Board published

recommendation 94-1 citing a concern for the residue stability and requiring that the possibly unstable residues be

processed within 3 years and all others within 5 years. A

risk categorization scheme was developed which assigned a

numerical risk to each residue type based on the probability

and consequence of occurrence of failures associated with

the hazards identified. The residues were ranked for priority

of stabilization actions. Urgent concerns were resolved. All

residue drums were vented to eliminate the potential for hydrogen and other explosive gas accumulation. Leaded

rubber gloves and ion exchange resins were washed to

eliminate the explosion potential. An aggressive characterization program was implemented to search for any

additional safety or environmental concerns and to gain

more definitive information concerning the choice of processes for stabilization and disposition of the residues. This

paper provides background on the safety issues and

summarizes recent characterization data. The residue processing and disposition plans, including schedule and cost,

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

are also summarized in the paper. Finally, the paper addresses initiatives undertaken by Safe Sites of Colorado to

accelerate the residue program.

622

(RFP–5188)

Year 2000 compliance concerns with the ISA Thermoluminescent Dosimetry Data Processing (TL-DP) software

system. Saviz, K. Safe Sites of Colorado, Rocky Flats Environmental Technology Site, Golden, CO (United States). 26

May 1998. 42p. Sponsored by USDOE, Washington, DC

(United States);USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC34-90DP62349. (CONF-980661–: 17. annual international Panasonic TLD users symposium, Santa Rosa, CA

(United States), 8-12 Jun 1998). Order Number

DE98005674. Source: OSTI; NTIS; INIS; GPO Dep.

The year 2000 is rapidly approaching, and there is a good

chance that computer systems that utilize two digit year

dates will experience problems in retrieval of date information. The ISA Thermoluminescent Dosimetry Data

Processing (TL-DP) software and computer system has

been reviewed for Year 2000 compliance issues.

623

(RFP–5189)

Panasonic dosimetry system performance testing and

results at nuclear accident dose levels 500 rad to 10,000

rad. Klueber, M.R. Safe Sites of Colorado, Rocky Flats Environmental Technology Site, Golden, CO (United States). 6

Apr 1998. 10p. Sponsored by USDOE, Washington, DC

(United States);USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC34-90DP62349. (CONF-980661–: 17. annual international Panasonic TLD users symposium, Santa Rosa, CA

(United States), 8-12 Jun 1998). Order Number

DE98005675. Source: OSTI; NTIS; INIS; GPO Dep.

Panasonic thermoluminescent dosimeters (TLDs) are

used as the photon dose assessment part of the personal

nuclear accident dosimeter (PNAD) and may be used for the

same purpose with the fixed nuclear accident dosimeter

(FNAD). To demonstrate compliance with 10CFR835.1304

(and, its predecessor, DOE Order 5480.11), several sets of

dosimeters were irradiated to photon doses above the upper

limit of the DOELAP testing standard, DOE/EH-0026 and

DOE/EH-0027. The upper range of the test was 10,000

rads, using both low energy (70 keV) and high energy (662

keV and 1,332 keV) sources. The testing indicated that the

Panasonic TLD system is capable of meeting the requirements of 10CFR835.1304 and DOE Order 5480.11.

624

(SAND–96-2656C)

Implementation of chemical controls through a backfill

system for the Waste Isolation Pilot Plant (WIPP).

Bynum, R.V. (Science Applications International Corp., Albuquerque, NM (United States)); Stockman, C.; Wang, Yifeng;

Peterson, A.; Krumhansl, J.; Nowak, J.; Chu, M.S.Y.; Cotton, J.; Patchet, S.J. Sandia National Labs., Albuquerque,

NM (United States). [1997]. 10p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States). DOE Contract AC04-94AL85000. (CONF-971040–

2: ICEM ‘97: 6. international conference on radioactive

waste management and environmental remediation, Singapore (Singapore), 12-16 Oct 1997). Order Number

DE97007458. Source: OSTI; NTIS; INIS; GPO Dep.

A backfill system has been designed for the WIPP which

will control the chemical environment of the post-closure

repository to a domain where the actinide solubility is within

its lowest region. The actinide solubility is highly dependent

on the chemical species which constitute the fluid, the resulting pH of the fluid, and oxidation state of the actinide

which is stable under the specific conditions. The implementation of magnesium oxide (MgO) as the backfill material not

only controls the pH of the expected fluids but also effectively removes the carbonate from the system, which has a

significant impact for actinide solubility. The selection

process, emplacement system, design, and confirmatory experimental results are presented.

625

(SAND–96-2815C)

Studies of photoredox reactions on nanosize

semiconductors. Wilcoxon, J.P. (Sandia National Labs., Albuquerque, NM (United States)); Parsapour, F.; Kelly, D.F.

Sandia National Labs., Albuquerque, NM (United States).

[1997]. 6p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract AC04-94AL85000. (CONF-970578–1: 4. international

conference on quantum confinement: nanoscale materials,

devices and systems, Montreal (Canada), 4-9 May 1997).

Order Number DE97001883. Source: OSTI; NTIS; GPO

Dep.

Light induced electron transfer (ET) from nanosize semiconductors Of MoS2 to organic electron acceptors such as

2,2’-bipyridine (bpy) and methyl substituted 4,4’,5,5’-

tetramethyl- 2,2’-bipyridine (tmb) was studied by static and

time resolved photoluminescence spectroscopy. The kinetics of ET were varied by changing the nanocluster size (the

band gap), the electron acceptor, and the polarity of the solvent. MoS2 is an especially interesting semiconductor

material as it is an indirect semiconductor in bulk form, and

has a layered covalent bonding arrangement which is highly

resistant to photocorrosion.

626

(SAND–96-2991C)

Condensed summary of the systems prioritization

method as a decision-aiding approach for the Waste

Isolation Pilot Plant. Boak, D.M. (and others); Prindle,

N.H.; Lincoln, R. Sandia National Labs., Albuquerque, NM

(United States). 1997. 9p. Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract AC04-94AL85000. (CONF-970674–

1: ESREL ’97: international conference on safety and

reliability, Lisbon (Portugal), 17-20 Jun 1997). Order Number DE97003821. Source: OSTI; NTIS; INIS; GPO Dep.

In March 1994, the US Department of Energy Carlsbad

Area Office (DOE/CAO) implemented a performance based

decision-aiding method to assist in programmatic prioritization within the Waste Isolation Pilot Plant (WIPP) project.

The prioritization was with respect to 40 CFR Part 191.13(a)

and 40 CFR part 268.6. U.S. Environmental Protection

Agency (EPA) requirements for long-term isolation of radioactive and hazardous wastes. The Systems Prioritization

Method (SPM), was designed by Sandia National Laboratories to: (1) identify programmatic options (activities), their

costs and durations; (2) analyze combinations of activities in

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

terms of their predicted contribution to long-term performance of the WIPP disposal system; and (3) analyze cost,

duration, and performance tradeoffs. SPM results were the

basis for activities recommended to DOE/CAO in May 1995.

SPM identified eight activities (less than 15% of the 58

proposed for consideration) predicted to be essential in addressing key regulatory issues. The SPM method proved

useful for risk or performance-based prioritization in which

options are interdependent and system behavior is nonlinear. 10 refs., 2 figs., 1 tab.

627

(SAND–97-0028C)

A new and superior ultrafine cementitious grout. Ahrens,

E.H. Sandia National Labs., Albuquerque, NM (United

States). 1997. 10p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE

Contract AC04-94AL85000. (CONF-970747–1: Geo Logan

conference ‘97, Logan, UT (United States), 16-18 Jul 1997).

Order Number DE97004626. Source: OSTI; NTIS; INIS;

GPO Dep.

Sealing fractures in nuclear waste repositories concerns

all programs investigating deep burial as a means of disposal. Because the most likely mechanism for contaminant

migration is by dissolution and movement through groundwater, sealing programs are seeking low-viscosity sealants

that are chemically, mineralogically, and physically compatible with the host rock. This paper presents the results of

collaborative work directed by Sandia National Laboratories

(SNL) and supported by Whiteshell Laboratories, operated

by Atomic Energy of Canada, Ltd. The work was undertaken

in support of the Waste Isolation Pilot Plant (WIPP), an

underground nuclear waste repository located in a salt formation east of Carlsbad, NM. This effort addresses the

technology associated with long-term isolation of nuclear

waste in a natural salt medium. The work presented is part

of the WIPP plugging and sealing program, specifically the

development and optimization of an ultrafine cementitious

grout that can be injected to lower excessive, strain-induced

hydraulic conductivity in the fractured rock termed the

Disturbed Rock Zone (DRZ) surrounding underground excavations. Innovative equipment and procedures employed in

the laboratory produced a usable cement-based grout; 90%

of the particles were smaller than 8 microns and the average particle size was 4 microns. The process involved

simultaneous wet pulverization and mixing. The grout was

used for a successful in situ test underground at the WIPP.

Injection of grout sealed microfractures as small as 6 microns (and in one rare instance, 3 microns) and lowered the

gas transmissivity of the DRZ by up to three orders of magnitude. Following the WIPP test, additional work produced

an improved version of the grout containing particles 90%

smaller than 5 microns and averaging 2 microns. This grout

will be produced in dry form, ready for the mixer.

628

(SAND–97-0099C)

The effects of heterogeneities on the performance of

capillary barriers for waste isolation. Ho, C.K.; Webb,

S.W. Sandia National Labs., Albuquerque, NM (United

States). [1997]. 8p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE

Contract AC04-94AL85000. (CONF-970208–2: International

containment technology conference and exhibition, St. Petersburg, FL (United States), 9-12 Feb 1997). Order Number

DE97002471. Source: OSTI; NTIS; INIS; GPO Dep.

The effects of heterogeneities on the performance of capillary barriers is investigated by simulating three systems

comprised of a fine soil layer overlying a coarse gravel layer

with homogeneous, layered heterogeneous, and random

heterogeneous property fields. The amount of lateral diversion above the coarse layer under steady-state infiltration

conditions is compared between the simulations. Results indicate that the performance of capillary barriers may be

significantly influenced by the spatial variability of the properties. The layered heterogeneous system performed best

as a result of horizontal features within the fine layer that

acted as additional local capillary barriers that delayed

breakthrough into the coarse layer. The random heterogeneous system performed worst because of channeled flow

that produced localized regions of water breakthrough into

the coarse layer. These results indicate that engineered

capillary barriers may be improved through emplacement

and packing methods that induce a layered system similar

to the layered heterogeneous field simulated in this study.

629

(SAND–97-0111C)

Principles and objectives of containment verification

and performance monitoring and technology selection.

Reichhardt, D.K. (MSE Technology Applications, Inc., Butte,

MT (United States)); Hart, A.T.; Betsill, J.D. Sandia National

Labs., Albuquerque, NM (United States). [1997]. 7p. Sponsored by USDOE Office of Environmental Management,

Washington, DC (United States). DOE Contract AC04-

94AL85000. (CONF-970208–3: International containment

technology conference and exhibition, St. Petersburg, FL

(United States), 9-12 Feb 1997). Order Number

DE97002472. Source: OSTI; NTIS; GPO Dep.

While a number of technologies or methods of subsurface

imaging and monitoring exist, most require some adaptation

to meet the site-specific objectives of a particular in-situ

waste containment/stabilization verification and monitoring

program. The selection of methods and their site-specific

adaptation must be based on sound, scientific principles.

Given this, specific information about the site and the objectives of the containment or remediation are required to

design and implement an appropriate and effective

verification and monitoring program. Site and technology information that must be considered and how it affects the

selection and adaptation of monitoring technologies is presented. In general, this information includes the objectives

of the containment or remediation, the verification and monitoring systems, and the physical properties of the site and

the waste containment/stabilization system. The objectives

of the containment or remediation and the verification and

monitoring system must be defined to provide a goal for the

technology developer’s design. The physical properties of

the site and the waste containment/stabilization system are

required to ensure the proper technology is selected. A conceptual framework and examples are given to demonstrate

the impacts of these aspects on technology selection.

630

(SAND–97-0147C)

Comparison of lumped-element and transmission-line

models for thickness-shear-mode quartz resonator

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

sensors. Cernosek, R.W. (Sandia National Laboratories, Albuquerque, NM (United States)); Martin, S.J.; Hillman, A.R.

Sandia National Labs., Albuquerque, NM (United States).

1997. 27p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract AC04-94AL85000. (CONF-9705139–1: 51. IEEE

meeting of the frequency control symposium, Orlando, FL

(United States), 28-30 May 1997). Order Number

DE97007805. Source: OSTI; NTIS; GPO Dep.

Both a transmission-line model and its simpler variant, a

lumped-element model, can be used to predict the

responses of a thickness-shear-mode quartz resonator sensor. Relative deviations in the parameters computed by the

two models (shifts in resonant frequency and motional

resistance) do not exceed 3% for most practical sensor configurations operating at the fundamental resonance. If the

ratio of the load surface mechanical impedance to the

quartz shear characteristic impedance does not exceed 0.1,

the lumped-element model always predicts responses within

1% of those for the transmission-line model.

631

(SAND–97-0173C)

Graphical programming of telerobotic tasks. Small, D.E.

(Sandia National Labs., Albuquerque, NM (United States).

Intelligent Systems and Robotics Center); McDonald, M.J.

Sandia National Labs., Albuquerque, NM (United States).

[1997]. 6p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract AC04-94AL85000. (CONF-970462–6: 7. American

Nuclear Society topical meeting on robotics and remote

handling, Savannah, GA (United States), 27 Apr - 1 May

1997). Order Number DE97002539. Source: OSTI; NTIS;

INIS; GPO Dep.

With a goal of producing faster, safer, and cheaper technologies for nuclear waste cleanup, Sandia is actively

developing and extending intelligent systems technologies.

Graphical Programming is a key technology for robotic

waste cleanup that Sandia is developing for this goal. This

paper describes Sancho, Sandia most advanced Graphical

Programming supervisory software. Sancho, now operational on several robot systems, incorporates all of Sandia’s

recent advances in supervisory control. Sancho, developed

to rapidly apply Graphical Programming on a diverse set of

robot systems, uses a general set of tools to implement task

and operational behavior. Sancho can be rapidly reconfigured for new tasks and operations without modifying the

supervisory code. Other innovations include task-based interfaces, event-based sequencing, and sophisticated GUI

design. These innovations have resulted in robot control

programs and approaches that are easier and safer to use

than teleoperation, off-line programming, or full automation.

632

(SAND–97-0281C)

Electrokinetic demonstration at Sandia National Laboratories: Use of transference numbers for site

characterization and process evaluation. Lindgren, E.R.

(Sandia National Labs, Environmental Restoration Technologies, Albuquerque, NM (United States)); Mattson, E.D.

Sandia National Labs., Albuquerque, NM (United States).

[1997]. 9p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract AC04-94AL85000. (CONF-970335–14: Waste

Management ‘97, Tucson, AZ (United States), 2-7 Mar

1997). Order Number DE97003005. Source: OSTI; NTIS;

INIS; GPO Dep.

Electrokinetic remediation is generally an in situ method

using direct current electric potentials to move ionic contaminants and/or water to collection electrodes. The method has

been extensively studied for application in saturated clayey

soils. Over the past few years, an electrokinetic extraction

method specific for sandy, unsaturated soils has been developed and patented by Sandia National Laboratories. A

RCRA RD&D permitted demonstration of this technology for

the in situ removal of chromate contamination from unsaturated soils in a former chromic acid disposal pit was

operated during the summer and fall of 1996. This large

scale field test represents the first use of electrokinetics for

the removal of heavy metal contamination from unsaturated

soils in the United States and is part of the US EPA Superfund Innovative Technology Evaluation (SITE) Program.

Guidelines for characterizing a site for electrokinetic remediation are lacking, especially for applications in unsaturated

soil. The transference number of an ion is the fraction of the

current carried by that ion in an electric field and represents

the best measure of contaminant removal efficiency in most

electrokinetic remediation processes. In this paper we compare the transference number of chromate initially present in

the contaminated unsaturated soil, with the transference

number in the electrokinetic process effluent to demonstrate

the utility of evaluating this parameter.

633

(SAND–97-282C)

Cost comparisons of alternative landfill final covers.

Dwyer, S.F. Sandia National Labs., Albuquerque, NM

(United States). [1997]. 8p. Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract AC04-94AL85000. (CONF-970208–

5: International containment technology conference and

exhibition, St. Petersburg, FL (United States), 9-12 Feb

1997). Order Number DE97003030. Source: OSTI; NTIS;

GPO Dep.

A large-scale field demonstration comparing and contrasting final landfill cover designs has been constructed and is

currently being monitored. Four alternative cover designs

and two conventional designs (a RCRA Subtitle “D” Soil

Cover and a RCRA Subtitle “C” Compacted Clay Cover)

were constructed of uniform size, side-by-side. The demonstration is intended to evaluate the various cover designs

based on their respective water balance performance, ease

and reliability of construction, and cost. This paper provides

an overview of the construction costs of each cover design.

634

(SAND–97-0283C)

The residuals analysis project: Evaluating disposal options for treated mixed low-level waste. Waters, R.D.;

Gruebel, M.M.; Case, J.T.; Letourneau, M.J. Sandia National Labs., Albuquerque, NM (United States). [1997]. 11p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC04-94AL85000. (CONF-970335–13: Waste Management

‘97, Tucson, AZ (United States), 2-7 Mar 1997). Order Number DE97003006. Source: OSTI; NTIS; INIS; GPO Dep.

For almost four years, the U.S. Department of Energy

(DOE) through its Federal Facility Compliance Act Disposal

Workgroup has been working with state regulators and governors’ offices to develop an acceptable configuration for

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

disposal of its mixed low-level waste (MLLW). These interactions have resulted in screening the universe of potential

disposal sites from 49 to 15 and conducting ”performance

evaluations” for those fifteen sites to estimate their technical

capabilities for disposal of MLLW. In the residuals analysis

project, we estimated the volume of DOE’s MLLW that will

require disposal after treatment and the concentrations of

radionuclides in the treated waste. We then compared the

radionuclide concentrations with the disposal limits determined in the performance evaluation project for each of the

fifteen sites. The results are a scoping-level estimate of the

required volumetric capacity for MLLW disposal and the

identification of waste streams that may pose problems for

disposal based on current treatment plans. The analysis

provides technical information for continued discussions between the DOE and affected States about disposal of MLLW

and systematic input to waste treatment developers on disposal issues.

635

(SAND–97-0337C)

In situ remediation of uranium contaminated groundwater. Dwyer, B.P.; Marozas, D.C. Sandia National Labs.,

Albuquerque, NM (United States). [1997]. 7p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract AC04-94AL85000.

(CONF-970208–8: International containment technology

conference and exhibition, St. Petersburg, FL (United

States), 9-12 Feb 1997). Order Number DE97003213.

Source: OSTI; NTIS; INIS; GPO Dep.

In an effort to develop cost-efficient techniques for remediating uranium contaminated groundwater at DOE Uranium

Mill Tailing Remedial Action (UMTRA) sites nationwide, Sandia National Laboratories (SNL) deployed a pilot scale

research project at an UMTRA site in Durango, CO. Implementation included design, construction, and subsequent

monitoring of an in situ passive reactive barrier to remove

Uranium from the tailings pile effluent. A reactive subsurface

barrier is produced by emplacing a reactant material (in this

experiment various forms of metallic iron) in the flow path of

the contaminated groundwater. Conceptually the iron media

reduces and/or adsorbs uranium in situ to acceptable regulatory levels. In addition, other metals such as Se, Mo, and

As have been removed by the reductive/adsorptive process.

The primary objective of the experiment was to eliminate the

need for surface treatment of tailing pile effluent. Experimental design, and laboratory and field results are discussed

with regard to other potential contaminated groundwater

treatment applications.

636

(SAND–97-0338C)

Development of a cement-polymer close-coupled subsurface barrier technology. Dwyer, B.P. (Sandia National

Labs., Albuquerque, NM (United States)); Heiser, J.; Stewart, W.; Phillips, S. Sandia National Labs., Albuquerque, NM

(United States). [1997]. 7p. Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract AC04-94AL85000. (CONF-970208–

9: International containment technology conference and

exhibition, St. Petersburg, FL (United States), 9-12 Feb

1997). Order Number DE97003214. Source: OSTI; NTIS;

INIS; GPO Dep.

The primary objective of this project was to further develop

close-coupled barrier technology for the containment of subsurface waste or contaminant migration. A close-coupled

barrier is produced by first installing a conventional cement

grout curtain followed by a thin inner lining of a polymer

grout. The resultant barrier is a cement polymer composite

that has economic benefits derived from the cement and

performance benefits from the durable and chemically resistant polymer layer. The technology has matured from a

regulatory investigation of issues concerning barriers and

barrier materials to a pilot-scale, multiple individual column

injections at Sandia National Labs (SNL) to full scale

demonstration. The feasibility of this barrier concept was

successfully proven in a full scale ”cold site” demonstration

at Hanford, WA. Consequently, a full scale deployment of

the technology was conducted at an actual environmental

restoration site at Brookhaven National Lab (BNL), Long

Island, NY. This paper discusses the installation and performance of a technology deployment implemented at OU-1 an

Environmental Restoration Site located at BNL.

637

(SAND–97-0360C)

United States of America activities relative to the International Atomic Energy Agency (IAEA) initiative:

Records management for deep geologic repositories.

Warner, P.J. Sandia National Labs., Albuquerque, NM

(United States). 1997. 16p. Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract AC04-94AL85000. (CONF-970335–

31: Waste Management ‘97, Tucson, AZ (United States),

2-7 Mar 1997). Order Number DE97004381. Source: OSTI;

NTIS; INIS; GPO Dep.

The International Atomic Energy Agency (IAEA) has conducted consultant and advisory meetings to prepare a

Technical Document which is intended to provide guidance

to all IAEA Member States (otherwise known as countries)

that are currently planning, designing, constructing or operating a deep or near surface geological repository for the

storage and protection of vitrified high-level radioactive

waste, spent fuel waste and TRU-waste (transuranic).

Eleven countries of the international community are

presently in various stages of siting, designing, or constructing deep geologic repositories. Member States of the IAEA

have determined that the principle safety of such completed

and operation sites must not rely solely on long term institutional arrangements for the retention of information. It is

believed that repository siting, design, operation and postoperation information should be gathered, managed and

retained in a manner that will provide information to future

societies over a very long period of time. The radionuclide

life is 10,000 years thus the retention of information must

outlive current societies, languages, and be continually

migrated to new technology to assure retrieval. This presentation will provide an overview of the status of consideration

and implementation of these issues within the United States

efforts relative to deep geologic repository projects.

638

(SAND–97-0383C)

Mixed low-level waste form evaluation. Pohl, P.I.; Cheng,

Wu-Ching; Wheeler, T.; Waters, R.D. Sandia National Labs.,

Albuquerque, NM (United States). 1997. 14p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract AC04-94AL85000.

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

(CONF-970335–29: Waste Management ‘97, Tucson, AZ

(United States), 2-7 Mar 1997). Order Number

DE97004383. Source: OSTI; NTIS; INIS; GPO Dep.

A scoping level evaluation of polyethylene encapsulation

and vitreous waste forms for safe storage of mixed low-level

waste was performed. Maximum permissible radionuclide

concentrations were estimated for 15 indicator radionuclides

disposed of at the Hanford and Savannah River sites with

respect to protection of the groundwater and inadvertent intruder pathways. Nominal performance improvements of

polyethylene and glass waste forms relative to grout are reported. These improvements in maximum permissible

radionuclide concentrations depend strongly on the radionuclide of concern and pathway. Recommendations for future

research include improving the current understanding of the

performance of polymer waste forms, particularly macroencapsulation. To provide context to these estimates, the

concentrations of radionuclides in treated DOE waste should

be compared with the results of this study to determine required performance.

639

(SAND–97-0422C)

Implementation of a fully automated process purge-andtrap gas chromatograph at an environmental

remediation site. Blair, D.S.; Morrison, D.J. Sandia National

Labs., Albuquerque, NM (United States). 1997. 17p. Sponsored by USDOE Office of Environmental Management,

Washington, DC (United States). DOE Contract AC04-

94AL85000. (CONF-970113–1: Field analytical methods for

hazardous wastes and toxic chemicals conference, Las Vegas, NV (United States), 29-31 Jan 1997). Order Number

DE97003183. Source: OSTI; NTIS; INIS; GPO Dep.

The AQUASCAN, a commercially available, fully automated purge-and-trap gas chromatograph from Sentex

Systems Inc., was implemented and evaluated as an infield, automated monitoring system of contaminated

groundwater at an active DOE remediation site in Pinellas,

FL. Though the AQUASCAN is designed as a stand alone

process analytical unit, implementation at this site required

additional hardware. The hardware included a sample dilution system and a method for delivering standard solution to

the gas chromatograph for automated calibration. As a result of the evaluation the system was determined to be a

reliable and accurate instrument. The AQUASCAN reported

concentration values for methylene chloride, trichloroethylene, and toluene in the Pinellas ground water were within

20% of reference laboratory values.

640

(SAND–97-0480C)

3D electromagnetic inversion for environmental site

characterization. Alumbaugh, D.L.; Newman, G.A. Sandia

National Labs., Albuquerque, NM (United States). 1997.

11p. Sponsored by USDOE Office of Energy Research,

Washington, DC (United States). DOE Contract AC04-

94AL85000. (CONF-970344–2: SAGEEP ’97: 10. annual

symposium on the application of geophysics to environmental and engineering problems, Reno, NV (United States),

23-26 Mar 1997). Order Number DE97004207. Source:

OSTI; NTIS; GPO Dep.

A 3-D non-linear electromagnetic inversion scheme has

been developed to produce images of subsurface conductivity structure from electromagnetic geophysical data. The

solution is obtained by successive linearized model updates

where full forward modeling is employed at each iteration to

compute model sensitivities and predicted data. Regularization is applied to the problem to provide stability. Because

the inverse part of the problem requires the solution of 10’s

to 100’s of thousands of unknowns, and because each

inverse iteration requires many forward models to be computed, the code has been implemented on massively

parallel computer platforms. The use of the inversion code

to image environmental sites is demonstrated on a data set

collected with the Apex Parametrics ‘MaxMin I-8S’ over a

section of stacked barrels and metal filled boxes at the

Idaho National Laboratory’s ‘Cold Test Pit’. The MaxMin is a

loop-loop frequency domain system which operates from

440 Hz up to 56 kHz using various coil separations; for this

survey coil separations of 15, 30 and 60 feet were employed. The out-of phase data are shown to be of very good

quality while the in-phase are rather noisy due to slight mispositioning errors, which cause improper cancellation of the

primary free space field in the receiver. Weighting the data

appropriately by the estimated noise and applying the inversion scheme is demonstrated to better define the structure

of the pit. In addition, comparisons are given for single coil

separations and multiple separations to show the benefits of

using multiple offset data.

641

(SAND–97-0485C)

Traceability and retrievability: Documentation, the

bridge from science to compliance. Warner, P.J. (Sandia

National Labs., Albuquerque, NM (United States). Nuclear

Waste Management Programs Center). Sandia National

Labs., Albuquerque, NM (United States). [1997]. 9p. Sponsored by USDOE Office of Environmental Management,

Washington, DC (United States). DOE Contract AC04-

94AL85000. (CONF-970648–2: Department of Energy

(DOE) records management conference: illuminating our

legacy, focusing our future, Las Vegas, NV (United States),

23-26 Jun 1997). Order Number DE97007131. Source:

OSTI; NTIS; INIS; GPO Dep.

In this day of regulatory compliance, the fact that good

science was practiced and documented is, in and of itself,

not enough to assure a successful licensing or permitting result. A new level of documentation, that clearly walks a

non-project reviewer through the traceability of all activities

and decisions is required for successful acceptance of scientific results. Compliance reviewers (whether the Nuclear

Regulatory Commission (NRC), Environmental Protection

Agency (EPA), etc.) expect to verify the results of the scientific and program activities without the physical presence of

the person or persons that conducted the activity. Traceability of activities and associated decisions through the

retrieval of all associated records is a must. This presentation is based on lessons learned from the various quality

assurance (QA) audits and program reviews of Sandia National Laboratories, Nuclear Waste Management Programs

Center, scientific and programmatic documentation. The authors build a bridge from science to compliance from

lessons learned. Here now is a somewhat fictional rendition

of actual scientific testing and compliance support activities.

642

(SAND–97-0660C)

Metal sorption on kaolinite. Westrich, H.R. (Sandia

National Labs., Albuquerque, NM (United States). Geochemistry Dept.); Brady, P.V.; Cygan, R.T.; Nagy, K.L.;

163
ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

Anderson, H.L. Sandia National Labs., Albuquerque, NM

(United States). [1997]. 9p. Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

States);Nuclear Regulatory Commission, Washington, DC

(United States). DOE Contract AC04-94AL85000. (CONF970537–1: 18. annual DOE low-level radioactive waste

management conference, Salt Lake City, UT (United

States), 20-22 May 1997). Order Number DE97003785.

Source: OSTI; NTIS; INIS; GPO Dep.

A key issue in performance assessment of low-level

radioactive waste sites is predicting the transport and retardation of radionuclides through local soils under a variety of

hydrologic and geochemical conditions. Improved transport

codes should include a mechanistic model of radionuclide

retardation. The authors have been investigating metal sorption (Cs+, Sr2+, and Ba2+) on a simple clay mineral

(kaolinite) to better understand the geochemical interactions

of common soil minerals with contaminated groundwaters.

These studies include detailed characterizations of kaolinite

surfaces, experimental adsorption measurements, surface

complexation modeling, and theoretical simulations of cation

sorption. The aluminol edge (010) site has been identified

as the most likely site for metal sorption on kaolinite in natural solutions. Relative metal binding strengths decrease from

Ba2+ to Sr2+ to Cs+, with some portion sorbed on both kaolinite edges and basal surfaces. Some Cs+ also appears to

be irreversibly sorbed on both sites. Molecular dynamics

simulations suggest that Cs+ is sorbed at aluminol (010)

edge sites as an inner-sphere complex and weakly sorbed

as an outer-sphere complex on (001) basal surfaces. These

results provide the basis to understand and predict metal

sorption onto kaolinite, and a framework to characterize

sorption processes on more complex clay minerals.

643

(SAND–97-0709C)

Characterization of septic and drain system releases at

Sandia National Laboratories, New Mexico. Sanders,

M.R. (CDM Federal Programs Corp. (United States)); Galloway, R.B. Sandia National Labs., Albuquerque, NM

(United States). [1997]. 6p. Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract AC04-94AL85000. (CONF-971030–

1: 70. annual conference and exposition of the Water

Environment Federation, Chicago, IL (United States), 18-22

Oct 1997). Order Number DE97004036. Source: OSTI;

NTIS; INIS; GPO Dep.

Sandia National Laboratories/New Mexico (SNL/NM) is

located in Albuquerque, New Mexico. The SNL/NM Environmental Restoration (ER) Project is tasked with performing

the assessment and remediation of environmental releases

resulting from the almost 50 years of engineering development and testing activities. Operable Unit 1295, Septic

Tanks and Drainfields, includes inactive septic and drain

systems at 23 separate ER sites that were listed as Solid

Waste Management Units (SWMUs) in the SNL/NM Resource Conservation and Recovery Act (RCRA) Hazardous

and Solid Waste Amendments (HSWA) Module Permit.

These sites were identified, based on process histories and

interviews with facility personnel, as the subset of all SNL/

NM septic and drain systems that had the highest potential

for releases of hazardous and radioactive wastes into the

environment. An additional 101 septic and drain systems not

currently classified as SWMUs also have been identified as

needing future characterization.

644

(SAND–97-0776C)

Developing the Sandia National Laboratories transportation infrastructure for isotope products and wastes.

Trennel, A.J. Sandia National Labs., Albuquerque, NM

(United States). Nov 1997. 10p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States). DOE Contract AC04-94AL85000. (CONF-980507–:

PATRAM ’98: 12. international conference on packaging

and transportation of radioactive material, Paris (France),

10-15 May 1998). Order Number DE98001386. Source:

OSTI; NTIS; INIS; GPO Dep.

The US Department of Energy (DOE) plans to establish a

medical isotope project that would ensure a reliable domestic supply of molybdenum-99 (99Mo) and related medical

isotopes (Iodine-125, Iodine-131, and Xenon-133). The Department’s plan for production will modify the Annular Core

Research Reactor (ACRR) and associated hot cell facility at

Sandia National Laboratories (SNL)/New Mexico and the

Chemistry and Metallurgy Research facility at Los Alamos

National Laboratory (LANL). Transportation activities associated with such production is discussed.

645

(SAND–97-0810C)

Rapid world modelling from a mobile platform. Barry,

R.E. (Oak Ridge National Lab., TN (United States)); Jones,

J.P.; Little, C.Q.; Wilson, C.W. Sandia National Labs., Albuquerque, NM (United States). 1997. 7p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract AC04-94AL85000.

(CONF-970469–13: 1997 international conference on

robotics and automation, Albuquerque, NM (United States),

20-25 Apr 1997). Order Number DE97004633. Source:

OSTI; NTIS; INIS; GPO Dep.

The ability to successfully use and interact with a computerized world model is dependent on the ability to create an

accurate world model. The goal of this project was to develop a prototype system to remotely deploy sensors into a

workspace, collect surface information, and rapidly build an

accurate world model of that workspace. A key consideration

was that the workspace areas are typically hazardous environments, where it is difficult or impossible for humans to

enter. Therefore, the system needed to be fully remote, with

no external connections. To accomplish this goal, an electric, mobile platform with battery power sufficient for both the

platform and sensor electronics was procured and 3D range

sensors were deployed on the platform to capture surface

data within the workspace. A radio Ethernet connection was

used to provide communications to the vehicle and all onboard electronics. Video from on-board cameras was also

transmitted to the base station and used to teleoperate the

vehicle. Range data generated by the on-board 3D sensors

was transformed into surface maps, or models. Registering

the sensor location to a consistent reference frame as the

platform moved through the workspace allowed construction

of a detailed 3D world model of the extended workspace.

646

(SAND–97-0850C)

Radioactive material package closures with the use of

shape memory alloys. Koski, J.A.; Bronowski, D.R. Sandia

National Labs., Albuquerque, NM (United States). Nov 1997.

9p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

AC04-94AL85000. (CONF-980507–: PATRAM ’98: 12. international conference on packaging and transportation of

radioactive material, Paris (France), 10-15 May 1998). Order

Number DE98000849. Source: OSTI; NTIS; INIS; GPO Dep.

When heated from room temperature to 165 C, some

shape memory metal alloys such as titanium-nickel alloys

have the ability to return to a previously defined shape or

size with dimensional changes up to 7%. In contrast, the

thermal expansion of most metals over this temperature

range is about 0.1 to 0.2%. The dimension change of shape

memory alloys, which occurs during a martensite to austenite phase transition, can generate stresses as high as 700

MPa (100 kspi). These properties can be used to create a

closure for radioactive materials packages that provides for

easy robotic or manual operations and results in reproducible, tamper-proof seals. This paper describes some

proposed closure methods with shape memory alloys for radioactive material packages. Properties of the shape

memory alloys are first summarized, then some possible alternative sealing methods discussed, and, finally, results

from an initial proof-of-concept experiment described.

647

(SAND–97-0851C)

Gas generation phenomena in radioactive waste transportation packaging. Nigrey, P.J. Sandia National Labs.,

Albuquerque, NM (United States). Nov 1997. 10p. Sponsored by USDOE Office of Environmental Management,

Washington, DC (United States). DOE Contract

AC04-94AL85000. (CONF-980507–: PATRAM ’98: 12. international conference on packaging and transportation of

radioactive material, Paris (France), 10-15 May 1998). Order

Number DE98001246. Source: OSTI; NTIS; INIS; GPO Dep.

The interaction of radiation from radioactive materials with

the waste matrix can lead to the deterioration of the waste

form resulting in the possible formation of gaseous species.

Depending on the type and characteristics of the radiation

source, the generation of hydrogen may predominate. Since

the interaction of alpha particles with the waste form results

in significant energy transfer, other gases such as carbon

oxides, methane, nitrogen oxides, oxygen, water, and helium are possible. The type of gases produced from the

waste forms is determined by the mechanisms involved in

the waste degradation. For transuranic wastes, the identified

degradation mechanisms are reported to be caused by radiolysis, thermal decomposition or dewatering, chemical

corrosion, and bacterial action. While all these mechanisms

may be responsible for the buildup of gases during the storage of wastes, radiolysis and thermal decomposition appear

to be the main contributors during waste transport

operations. In this paper, the authors provide a review of applicable gas generation data resulting from the degradation

of various waste forms under conditions typical for transport.

The effects of radiolytic and thermal degradation mechanisms will be discussed in the context of transportation

safety.

648

(SAND–97-0853C)

Design of an experiment to measure the fire exposure

of radioactive materials packages aboard container

cargo ships. Koski, J.A. Sandia National Labs., Albuquerque, NM (United States). Nov 1997. 10p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract AC04-94AL85000.

(CONF-980507–: PATRAM ’98: 12. international conference

on packaging and transportation of radioactive material,

Paris (France), 10-15 May 1998). Order Number

DE98001124. Source: OSTI; NTIS; INIS; GPO Dep.

The test described in this paper is intended to measure

the typical accident environment for a radioactive materials

package in a fire aboard a container cargo ship. A stack of

nine used standard cargo containers will be variously loaded

with empty packages, simulated packages and combustible

cargo and placed over a large hydrocarbon pool fire of one

hour duration. Both internal and external fire container fire

environments typical of on-deck stowage will be measured

as well as the potential for container to container fire

spread. With the use of the inverse heat conduction calculations, the local heat transfer to the simulated packages can

be estimated from thermocouple data. Data recorded will

also provide information on fire durations in each container,

fire intensity and container to container fire spread characteristics.

649

(SAND–97-0854C)

Prediction of packaging seal life using thermoanalytical

techniques. Nigrey, P.J. Sandia National Labs., Albuquerque, NM (United States). Nov 1997. 10p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract AC04-94AL85000.

(CONF-980507–: PATRAM ’98: 12. international conference

on packaging and transportation of radioactive material,

Paris (France), 10-15 May 1998). Order Number

DE98001307. Source: OSTI; NTIS; INIS; GPO Dep.

In this study, Thermogravimetric Analysis (TGA) has been

used to study silicone, Viton and Ethylene Propylene

(EPDM) rubber. The studies have shown that TGA accurately predicts the relative order of thermo-oxidative stability

of these three materials from the calculated activation energies. As expected, the greatest thermal stability was found

in silicone rubber followed by Viton and EPDM rubber. The

calculated lifetimes for these materials were in relatively

close agreement with published values. The preliminary results also accurately reflect decreased thermal stability and

lifetime for EPDM rubber exposed to radiation and chemicals. These results suggest TGA provides a rapid method to

evaluate material stability.

650

(SAND–97-0861C)

Effects of simulant mixed waste on EPDM and butyl

rubber. Nigrey, P.J.; Dickens, T.G. Sandia National Labs.,

Albuquerque, NM (United States). Nov 1997. 8p. Sponsored

by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract AC04-94AL85000.

(CONF-980507–: PATRAM ’98: 12. international conference

on packaging and transportation of radioactive material,

Paris (France), 10-15 May 1998). Order Number

DE98001247. Source: OSTI; NTIS; INIS; GPO Dep.

The authors have developed a Chemical Compatibility

Testing Program for the evaluation of plastic packaging

components which may be used in transporting mixed waste

forms. In this program, they have screened 10 plastic materials in four liquid mixed waste simulants. These plastics

were butadiene-acrylonitrile copolymer (Nitrile) rubber,

cross-linked polyethylene, epichlorohydrin rubber, ethylenepropylene (EPDM) rubber, fluorocarbons (Viton and Kel-F),

polytetrafluoro-ethylene (Teflon), high-density polyethylene,

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

isobutylene-isoprene copolymer (Butyl) rubber, polypropylene, and styrene-butadiene (SBR) rubber. The selected

simulant mixed wastes were (1) an aqueous alkaline mixture

of sodium nitrate and sodium nitrite; (2) a chlorinated hydrocarbon mixture; (3) a simulant liquid scintillation fluid; and (4)

a mixture of ketones. The screening testing protocol involved

exposing the respective materials to approximately 3 kGy of

gamma radiation followed by 14-day exposures to the waste

simulants at 60 C. The rubber materials or elastomers were

tested using Vapor Transport Rate measurements while the

liner materials were tested using specific gravity as a metric.

The authors have developed a chemical compatibility program for the evaluation of plastic packaging components

which may be incorporated in packaging for transporting

mixed waste forms. From the data analyses performed to

date, they have identified the thermoplastic, polychlorotrifluoroethylene, as having the greatest chemical compatibility

after having been exposed to gamma radiation followed by

exposure to the Hanford Tank simulant mixed waste. The

most striking observation from this study was the poor performance of polytetrafluoroethylene under these conditions.

In the evaluation of the two elastomeric materials they have

concluded that while both materials exhibit remarkable resistance to these environmental conditions, EPDM has a

greater resistance to this corrosive simulant mixed waste.

651

(SAND–97-0865C)

SeaRAM: A DOE evaluation of maritime accident risk

assessment data and methods. Sprung, J.L.; Ammerman,

D.J.; Koski, J.A. Sandia National Labs., Albuquerque, NM

(United States). Mar 1998. 11p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States). DOE Contract AC04-94AL85000. (CONF-980507–:

PATRAM ’98: 12. international conference on packaging

and transportation of radioactive material, Paris (France),

10-15 May 1998). Order Number DE98004464. Source:

OSTI; NTIS; INIS; GPO Dep.

The SeaRAM Program conducted for the US Department

of Energy by Sandia National Laboratories has developed

estimates of the frequencies of occurrence of ship fires and

ship collisions, the fraction of all ship fires and ship collisions

that might be sufficiently severe to challenge the integrity of

a Type B spent fuel transportation cask, the magnitude of

the radioactive source terms that might be released from a

Type B spent fuel transportation cask due to loss of cask integrity, and the magnitude of the radiological consequences

that might be caused by the radioactive release.

652

(SAND–97-0893C)

Calculation of population doses with RADTRAN for

route segments that have an unpopulated near-field region. Kanipe, F.L.; Neuhauser, S.; Sprung, J.L. Sandia

National Labs., Albuquerque, NM (United States). Mar 1998.

11p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC04-94AL85000. (CONF-980507–: PATRAM ’98: 12. international conference on packaging and transportation of

radioactive material, Paris (France), 10-15 May 1998). Order

Number DE98004426. Source: OSTI; NTIS; INIS; GPO Dep.

The RADTRAN code (Neuhauser and Kanipe, 1994) models the radiological consequences of the transportation of

radioactive materials, both the exposures that will occur if

the transport occurs without incident, and the exposures that

may occur should the transport vehicle be involved in an accident while en route. Because accidents might occur at any

point along a transportation route, RADTRAN divides the

route into segments (links) and uses a uniform population

density and constant meteorological conditions (wind speed

and atmospheric stability) to represent the population and

weather characteristics of each route segment. A way to

perform RADTRAN calculations, that allows an unpopulated

near-field region along a transportation link to be

approximately modeled, is described, validated, and then illustratively applied to a coastal sailing route.

653

(SAND–97-0896C)

Experimental ship fire measurements with simulated

radioactive cargo. Koski, J.A. (Sandia National Labs., Albuquerque, NM (United States)); Arviso, M.; Bobbe, J.G.;

Wix, S.D.; Cole, J.K.; Hohnstreiter, G.F.; Beene, D.E. Jr.;

Keane, M.P. Sandia National Labs., Albuquerque, NM

(United States). Oct 1997. 10p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States). DOE Contract AC04-94AL85000. (CONF-980507–:

PATRAM ’98: 12. international conference on packaging

and transportation of radioactive material, Paris (France),

10-15 May 1998). Order Number DE98000926. Source:

OSTI; NTIS; INIS; GPO Dep.

Results from a series of eight test fires ranging in size

from 2.2 to 18.8 MW conducted aboard the Coast Guard fire

test ship Mayo Lykes at Mobile, Alabama are presented and

discussed. Tests aboard the break bulk type cargo ship consisted of heptane spray fires simulating engine room and

galley fires, wood crib fires simulating cargo hold fires, and

pool fires staged for comparison to land based regulatory

fire results. Primary instrumentation for the tests consisted

of two pipe calorimeters that simulated a typical package

shape for radioactive materials packages.

654

(SAND–97-0904C)

The electromagnetic integrated demonstration at the

Idaho National Engineering Laboratory cold test pit. Pellerin, L. (Lawrence Berkeley National Lab., CA (United

States)); Alumbaugh, D.L.; Pfeifer, M.C. Sandia National

Labs., Albuquerque, NM (United States). 1997. 11p. Sponsored by USDOE Office of Environmental Management,

Washington, DC (United States). DOE Contract AC04-

94AL85000. (CONF-970344–3: SAGEEP ’97: 10. annual

symposium on the application of geophysics to environmental and engineering problems, Reno, NV (United States),

23-26 Mar 1997). Order Number DE97004644. Source:

OSTI; NTIS; INIS; GPO Dep.

The electromagnetic integrated demonstration (EMID) is a

baseline study in electromagnetic (EM) exploration of the

shallow subsurface (< 10 m). Eleven distinct EM systems,

covering the geophysical spectrum, acquired data on a grid

over the Idaho National Engineering Laboratory (INEL) Cold

Test Pit (CTP). The systems are investigated and evaluated

for the purpose of identifying and reviewing existing geophysical characterization instrumentation (commercial and

experimental), integrating those technologies with multidimensional interpretational algorithms, and identifying gaps

in shallow subsurface EM imaging technology. The EMID

data, are valuable for testing and evaluating new interpretational software, and developing techniques for integrating

multiple datasets. The experimental field techniques shows

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

how the acquisition of data in a variety of array configurations can considerably enhance interpretation. All data are

available on the world wide web. Educators and students

are encouraged to use the data for both classroom and

graduate studies. The purpose of this paper is to explain

why, where, how and what kind of data were collected. It is

left to the reader to assess the value of a given system for

their particular application. Information about the EMID is organized into two general categories: survey description and

system evaluation.

655

(SAND–97-0905C)

Comparison of Ross’ capillary barrier diversion formula

with detailed numerical simulations. Webb, S.W. Sandia

National Labs., Albuquerque, NM (United States). 1997. 9p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC04-94AL85000. (CONF-970208–14: International

containment technology conference and exhibition, St. Petersburg, FL (United States), 9-12 Feb 1997). Order Number

DE97004637. Source: OSTI; NTIS; GPO Dep.

Ross developed an analytical relationship to calculate the

diversion length of a tilted fine-over-coarse capillary barrier.

Oldenburg and Pruess compared simulation results using

upstream and harmonic weighting to the diversion length

predicted by Ross formula with mixed results; the qualitative

agreement is reasonable but the quantitative comparison is

poor, especially for upstream weighting. The proximity of the

water table to the fine-coarse interface at breakthrough is a

possible reason for the poor agreement. In the present

study, the Oldenburg and Pruess problem is extended to

address the water table issue. When the water table is sufficiently far away from the interface at breakthrough, good

qualitative and quantitative agreement is obtained using upstream weighting.

656

(SAND–97-0906C)

Prediction of tilted capillary barrier performance. Webb,

S.W.; McCord, J.T.; Dwyer, S.F. Sandia National Labs., Albuquerque, NM (United States). 1997. 16p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract AC04-94AL85000.

(CONF-970208–13: International containment technology

conference and exhibition, St. Petersburg, FL (United

States), 9-12 Feb 1997). Order Number DE97004651.

Source: OSTI; NTIS; GPO Dep.

Capillary barriers, consisting of tilted fine-over-coarse layers under unsaturated conditions, have been suggested as

landfill covers to divert water infiltration away from sensitive

underground regions, especially for arid and semi-arid regions. The Hydrological Evaluation of Landfill Performance

(HELP) computer code is an evaluation tool for landfill

covers used by designers and regulators. HELP is a quasitwo-dimensional model that predicts moisture movement into

and through the underground soil and waste layers. Processes modeled within HELP include precipitation, runoff,

evapotranspiration, unsaturated vertical drainage, saturated

lateral drainage, and leakage through liners. Unfortunately,

multidimensional unsaturated flow phenomena that are necessary for evaluating tilted capillary barriers are not included

in HELP. Differences between the predictions of the HELP

and those from a multidimensional unsaturated flow code

are presented to assess the two different approaches. Comparisons are presented for the landfill covers including

capillary barrier configurations at the Alternative Landfill

Cover Demonstration (ALCD) being conducted at Sandia.

657

(SAND–97-0908C)

Geothermal drilling technology update. Glowka, D.A.

Sandia National Labs., Albuquerque, NM (United States).

1997. 11p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE

Contract AC04-94AL85000. (CONF-970376–1: 15. US Department of Energy’s geothermal program review, San

Francisco, CA (United States), 24-26 Mar 1997). Order

Number DE97004630. Source: OSTI; NTIS; GPO Dep.

Sandia National Laboratories conducts a comprehensive

geothermal drilling research program for the US Department

of Energy, Office of Geothermal Technologies. The program

currently includes seven areas: lost circulation technology,

hard-rock drill bit technology, high-temperature instrumentation, wireless data telemetry, slimhole drilling technology,

Geothermal Drilling Organization (GDO) projects, and drilling

systems studies. This paper describes the current status of

the projects under way in each of these program areas.

658

(SAND–97-0916C)

Examples of technical innovations in rock property

measurements prompted by the Waste Isolation Pilot

Plant. Christian-Frear, T.L. Sandia National Labs., Albuquerque, NM (United States). 1997. 6p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract AC04-94AL85000.

(CONF-970684–3: 1997 national convention of Society of

Women Engineers (SWE), Albuquerque, NM (United

States), 24 Jun 1997). Order Number DE97007554. Source:

OSTI; NTIS; INIS; GPO Dep.

The Waste Isolation Pilot Plant (WIPP) is the U.S. Department of Energy’s (DOE) planned repository for transuranic

waste generated by defense programs. The WIPP repository

660 meters underground in bedded salt. Bedded salt was

chosen for the repository because of salt’s small moisture

content, extremely low permeability, and its natural ability to

flow or creep, effectively encapsulating the waste in the longterm. However, because of these unique characteristics, the

ability to measure properties at in situ conditions are beyond

the realm of most standard experimental equipment. Thus a

suite of new experimental systems and techniques has been

developed to measure properties in extremely “tight” (low

permeability) rocks. Also, innovations in rock property measurements have been made for standard porous media

through the research conducted to characterize the rocks

above the repository. A number of the new systems and

techniques developed through the WIPP are presented in

this paper. Examples include permeameters, two-phase flow

characterization equipment, techniques for evaluation of salt

healing, and characterization of diffusive processes.

659

(SAND–97-1082C)

A testing program to evaluate the effects of simulant

mixed wastes on plastic transportation packaging components. Nigrey, P.J. (Sandia National Labs., Albuquerque,

NM (United States). Transportation Systems Dept.); Dickens,

T.G.; Dickman, P.T. Sandia National Labs., Albuquerque,

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

NM (United States). [1997]. 18p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States). DOE Contract AC04-94AL85000. (CONF-970857–

1: 4. biennial ASME mixed waste symposium, Baltimore,

MD (United States), 17-21 Aug 1997). Order Number

DE97006866. Source: OSTI; NTIS; INIS; GPO Dep.

Based on regulatory requirements for Type A and B

radioactive material packaging, a Testing Program was developed to evaluate the effects of mixed wastes on plastic

materials which could be used as liners and seals in transportation containers. The plastics evaluated in this program

were butadiene-acrylonitrile copolymer (Nitrile rubber),

cross-linked polyethylene, epichlorohydrin, ethylenepropylene rubber (EPDM), fluorocarbons, high-density

polyethylene (HDPE), butyl rubber, polypropylene, polytetrafluoroethylene, and styrene-butadiene rubber (SBR).

These plastics were first screened in four simulant mixed

wastes. The liner materials were screened using specific

gravity measurements and seal materials by vapor transport

rate (VTR) measurements. For the screening of liner materials, Kel-F, HDPE, and XLPE were found to offer the greatest

resistance to the combination of radiation and chemicals.

The tests also indicated that while all seal materials passed

exposure to the aqueous simulant mixed waste, EPDM and

SBR had the lowest VTRs. In the chlorinated hydrocarbon

simulant mixed waste, only Viton passed the screening

tests. In both the simulant scintillation fluid mixed waste and

the ketone mixture waste, none of the seal materials met

the screening criteria. Those materials which passed the

screening tests were subjected to further comprehensive

testing in each of the simulant wastes. The materials were

exposed to four different radiation doses followed by exposure to a simulant mixed waste at three temperatures and

four different exposure times (7, 14, 28, 180 days). Materials

were tested by measuring specific gravity, dimensional,

hardness, stress cracking, VTR, compression set, and tensile properties. The second phase of this Testing Program

involving the comprehensive testing of plastic liner has been

completed and for seal materials is currently in progress.

660

(SAND–97-1085C)

Computer-assisted comparison of analysis and test results in transportation experiments. Knight, R.D. (Gram,

Inc., Albuquerque, NM (United States)); Ammerman, D.J.;

Koski, J.A. Sandia National Labs., Albuquerque, NM (United

States). 10 May 1998. 8p. Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract AC04-94AL85000. (CONF-980507–:

PATRAM ’98: 12. international conference on packaging

and transportation of radioactive material, Paris (France),

10-15 May 1998). Order Number DE98004286. Source:

OSTI; NTIS; INIS; GPO Dep.

As a part of its ongoing research efforts, Sandia National

Laboratories’ Transportation Surety Center investigates the

integrity of various containment methods for hazardous materials transport, subject to anomalous structural and

thermal events such as free-fall impacts, collisions, and fires

in both open and confined areas. Since it is not possible to

conduct field experiments for every set of possible conditions under which an actual transportation accident might

occur, accurate modeling methods must be developed

which will yield reliable simulations of the effects of accident

events under various scenarios. This requires computer

software which is capable of assimilating and processing

data from experiments performed as benchmarks, as well

as data obtained from numerical models that simulate the

experiment. Software tools which can present all of these

results in a meaningful and useful way to the analyst are a

critical aspect of this process. The purpose of this work is to

provide software resources on a long term basis, and to ensure that the data visualization capabilities of the Center

keep pace with advancing technology. This will provide

leverage for its modeling and analysis abilities in a rapidly

evolving hardware/software environment.

661

(SAND–97-1248C)

Regulatory and extra-regulatory testing to demonstrate

radioactive material packaging safety. Ammerman, D.J.

Sandia National Labs., Albuquerque, NM (United States).

1997. 9p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract AC04-94AL85000. (CONF-970537–5: 18. annual DOE

low-level radioactive waste management conference, Salt

Lake City, UT (United States), 20-22 May 1997). Order

Number DE97007552. Source: OSTI; NTIS; INIS; GPO Dep.

Packages for the transportation of radioactive material

must meet performance criteria to assure safety and environmental protection. The stringency of the performance

criteria is based on the degree of hazard of the material being transported. Type B packages are used for transporting

large quantities of radioisotopes (in terms of A2 quantities).

These packages have the most stringent performance criteria. Material with less than an A2 quantity are transported in

Type A packages. These packages have less stringent performance criteria. Transportation of LSA and SCO materials

must be in “strong-tight” packages. The performance requirements for the latter packages are even less stringent.

All of these package types provide a high level of safety for

the material being transported. In this paper, regulatory tests

that are used to demonstrate this safety will be described.

The responses of various packages to these tests will be

shown. In addition, the response of packages to extraregulatory tests will be discussed. The results of these tests

will be used to demonstrate the high level of safety provided

to workers, the public, and the environment by packages

used for the transportation of radioactive material.

662

(SAND–97-1309C)

Long-term brine migration through an engineered shaft

seal system. Fryar, D.G. (INTERA Inc., Austin, TX (United

States)); Beach, J.A.; Kelley, V.A.; Knowles, M.K. Sandia

National Labs., Albuquerque, NM (United States). [1997].

8p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC04-94AL85000. (CONF-970665–2: American Society of

Information Science conference, Scottsdale, AZ (United

States), Jun 1997). Order Number DE97006891. Source:

OSTI; NTIS; INIS; GPO Dep.

The shaft seal system for the Waste Isolation Pilot Plant

(WIPP) must provide a barrier to the migration of fluids

within the shafts to prevent the release of contaminants to

the accessible environment. To investigate the performance

of the shaft seal system, a set of fluid flow performance

models was developed based upon the physical characteristics of the WIPP shaft seal system and the surrounding

geologic media. This paper describes the results of a numerical model used to investigate the long-term potential for

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

brine migration through the shaft seal system. Modeling

results demonstrate that the WIPP shaft seal system will effectively limit brine migration within the repository shafts.

663

(SAND–97-1310C)

A method of modeling time-dependent rock damage

surrounding underground excavations in multiphase

groundwater flow. Christian-Frear, T. (Sandia National

Labs., Albuquerque, NM (United States). Geohydrology

Dept.); Freeze, G. Sandia National Labs., Albuquerque, NM

(United States). [1997]. 7p. Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract AC04-94AL85000. (CONF-970663–

3: 4. ASCE congress on computing in civil engineering,

Philadelphia, PA (United States), 16-18 Jun 1997). Order

Number DE97006890. Source: OSTI; NTIS; INIS; GPO Dep.

Underground excavations produce damaged zones surrounding the excavations which have disturbed hydrologic

and geomechanical properties. Prediction of fluid flow in

these zones must consider both the mechanical and fluid

flow processes. Presented here is a methodology which utilizes a mechanical model to predict damage and disturbed

rock zone (DRZ) development around the excavation and

then uses the predictions to develop time-dependent DRZ

porosity relationships. These relationships are then used to

adjust the porosity of the DRZ in the fluid flow model based

upon the time and distance from the edge of the excavation.

The application of this methodology is presented using a

site-specific example from the Waste Isolation Pilot Plant, a

US Department of Energy facility in bedded salts being evaluated for demonstration of the safe underground disposal of

transuranic waste from US defense-related activities.

664

(SAND–97-1311C)

Calculation of density and permeability of compacted

crushed salt within an engineered shaft sealing system.

Loken, M. (RE/SPEC Inc., Rapid City, SD (United States));

Statham, W. Sandia National Labs., Albuquerque, NM

(United States). [1997]. 9p. Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract AC04-94AL85000. (CONF-970663–

4: 4. ASCE congress on computing in civil engineering,

Philadelphia, PA (United States), 16-18 Jun 1997). Order

Number DE97006889. Source: OSTI; NTIS; INIS; GPO Dep.

Crushed salt from the host Salado Formation is proposed

as a sealing material in one component of a multicomponent

seal system design for the shafts of the Waste Isolation Pilot

Plant (WIPP), a mined geological repository for storage and

disposal of transuranic radioactive wastes located near

Carlsbad, New Mexico. The crushed salt will be compacted

and placed at a density approaching 90% of the intact density of the host Salado salt. Creep closure of the shaft will

further compact the crushed salt over time, thereby reducing

the crushed-salt permeability from the initial state and creating an effective long-term seal. A structural model and a

fluid flow model have been developed to provide an estimate of crushed-salt reconsolidation rate as a function of

depth, time, and pore pressure. Model results are obtained

in terms of crushed-salt permeability as a function of time

and depth within the salt column. Model results indicate that

average salt column permeability will be reduced to 3.3 

1020 m2 in about 100 years, which provides for an acceptable long-term seal component.

665

(SAND–97-1336C)

Beyond pretty pictures: Quantifying porous media

properties and transport processes using transmission

and emission CT. Sandia National Labs., Albuquerque, NM

(United States). [1997]. 6p. Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract AC04-94AL85000. (CONF-970864–

1: Applications of emerging technologies in hydrology,

Minneapolis, MN (United States), 10-14 Aug 1997). Order

Number DE97007140. Source: OSTI; NTIS; INIS; GPO Dep.

While gaining increasing interest, the use of Computerized Tomography (CT) in porous media studies has been

limited by the availability of quantitative methods of analysis.

Three methods are presented for the analysis of CT data

and applied to images obtained from gamma transmission

and gamma emission systems. The first utilizes measurement statistics and image histograms to provide exact

estimates of multiple component volume contents. An improved thresholding technique in the second method allows

an identification of individual voxel composition. The threshold utilizes error statistics to eliminate the arbitrary nature of

current methods. Emission tomography images of solute

transport are shown in the third procedure to provide in-situ

measures of transport in fractured media. Application of

each method is demonstrated on samples of the Culebra

Dolomite of the Rustler Formation, New Mexico. Dolomite

cores were collected by horizontal drilling at a depth of 218

m in the air intake shaft of the Waste Isolation Pilot Plant located near Carlsbad, New Mexico.

666

(SAND–97-1357C)

A comparison of regulatory impacts to real target

impacts. Ammerman, D.J. Sandia National Labs., Albuquerque, NM (United States). May 1998. 10p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract AC04-94AL85000.

(CONF-980507–: PATRAM ’98: 12. international conference

on packaging and transportation of radioactive material,

Paris (France), 10-15 May 1998). Order Number

DE98003334. Source: OSTI; NTIS; INIS; GPO Dep.

The purpose of this paper is to discuss the relative severity of regulatory impacts onto an essentially rigid target to

impacts at higher velocities onto real targets. For impacts

onto the essentially rigid target all of the kinetic energy of

the package is absorbed by deformation of the package. For

impacts onto real targets the kinetic energy is absorbed by

deformation of the target as well as by deformation of the

package. The amount of kinetic energy absorbed by the target does not increase the severity of the impact.

667

(SAND–97-1358C)

The effect of cargo on the crush loading of RAM transportation packages in ship collisions. Radloff, H.D.;

Ammerman, D.J. Sandia National Labs., Albuquerque, NM

(United States). Mar 1998. 10p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States). DOE Contract AC04-94AL85000. (CONF-980507–:

PATRAM ’98: 12. international conference on packaging

and transportation of radioactive material, Paris (France),

10-15 May 1998). Order Number DE98003346. Source:

OSTI; NTIS; INIS; GPO Dep.

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

Recent intercontinental radioactive material shipping campaigns have focused public and regulatory attention on the

safety of transport of this material by ocean-going vessels.

One major concern is the response of the vessel and onboard radioactive material (RAM) packages during a severe

ship-to-ship collision. These collisions occur at velocities

less than the velocity obtained in the Type B package regulatory impact event and the bow of the striking ship is less

rigid than the unyielding target used in those tests (Ammerman and Daidola, 1996). This implies that ship impact is not

a credible scenario for damaging the radioactive material

packages during ship collisions. It is possible, however, for

these collisions to generate significant amounts of crush

force by the bow of the impacting ship overrunning the

package. It is the aim of this paper to determine an upper

bound on the magnitude of this crush force taking into account the strength of the radioactive material carrying vessel

and any other cargo that may be stowed in the same hold

as the radioactive material.

668

(SAND–97-1359C)

Development of a container for the transportation and

storage of plutonium bearing materials. Ammerman, D.

(Sandia National Labs., Albuquerque, NM (United States));

Geinitz, R.; Thorp, D.; Rivera, M. Sandia National Labs., Albuquerque, NM (United States). Mar 1998. 10p. Sponsored

by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract AC04-94AL85000.

(CONF-980507–: PATRAM ’98: 12. international conference

on packaging and transportation of radioactive material,

Paris (France), 10-15 May 1998). Order Number

DE98003335. Source: OSTI; NTIS; INIS; GPO Dep.

There is a large backlog of plutonium contaminated materials at the Rocky Flats Environmental Technology Site near

Denver, Colorado, USA. The clean-up of this site requires

this material to be packaged in such a way as to allow for

efficient transportation to other sites or to a permanent geologic repository. Prior to off-site shipment of the material, it

may be stored on-site for a period of time. For this reason, it

is desirable to have a container capable of meeting the requirements for storage as well as the requirements for

transportation. Most of the off-site transportation is envisioned to take place using the TRUPACT-II Type B

package, with the Waste Isolation Pilot Plant (WIPP) as the

destination. Prior to the development of this new container,

the TRUPACT-II had a limit of 325 FGE (fissile gram equivalents) of plutonium due to criticality control concerns.

Because of the relatively high plutonium content in the material to be transported, transporting 325 FGE per

TRUPACT-II is uneconomical. Thus, the purpose of the new

containers is to provide criticality control to increase the allowed TRUPACT-II payload and to provide a safe method

for on-site storage prior to transport. This paper will describe

the analysis and testing used to demonstrate that the Pipe

Overpack Container provides safe on-site storage of plutonium bearing materials in unhardened buildings and

provides criticality control during transportation within the

TRUPACT-II. Analyses included worst-case criticality analyses, analyses of fork-lift time impacts, and analyses of roof

structure collapse onto the container. Testing included

dynamic crush tests, bare pipe impact tests, a 30-minute totally engulfing pool-fire test, and multiple package impact

tests in end-on and side-on orientations.

669

(SAND–97-1365C)

Testing and analysis to determine the shell thickness

required to prevent puncture. Ammerman, D.J.; Radloff,

H.D.; Eifert, E.J. Sandia National Labs., Albuquerque, NM

(United States). May 1998. 10p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States). DOE Contract AC04-94AL85000. (CONF-980507–:

PATRAM ’98: 12. international conference on packaging

and transportation of radioactive material, Paris (France),

10-15 May 1998). Order Number DE98003333. Source:

OSTI; NTIS; INIS; GPO Dep.

Type B radioactive material packages are required to

withstand a hypothetical puncture accident of a free fall from

a height of one meter onto a 15 cm diameter mild steel

puncture probe. For many packages it is desirable to have

this accident event not result in puncture or tearing of the

outer shell of the package. The wall thickness necessary to

prevent this has historically been determined by test or the

use of empirical relations. This technique generally results in

overly conservative designs, but the degree of conservatism

is uncertain. The use of modem finite element codes to determine package response to puncture accidents can result

in designs that are both safe and economical. The work reported in this paper is aimed at developing a method to

analytically determine the wall thickness required to prevent

puncture. For designers and regulators to have confidence

in this analytical method, however, it must be benchmarked

against test results. A series of tests has been conducted

with differing shell thicknesses, shell materials of mild steel

and stainless steel, and shell backing materials of lead,

foam, and air. The results of these tests have been compared with pre-test analytical predictions of the response

obtained from the nonlinear transient dynamic finite element

program PRONTO-2D. From this comparison it can be seen

that the finite element method can accurately predict the response of packages to puncture accidents. This implies that

an analytical technique based on the finite element method

can be used to design packages having known response

and margin of safety against tearing of the outer shell. In addition, the analytical technique can accurately predict the

deformed shape of the package following the test. This may

be important for subsequent calculations, such as external

dose and heat input during a thermal event.

670

(SAND–97-1459C)

Pollution prevention and waste minimization opportunity assessment in environmental restoration. Roybal,

J.A.; Willison, C.P. Sandia National Labs., Albuquerque, NM

(United States). [1997]. 11p. Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract AC04-94AL85000. (CONF-970854–:

13. pollution prevention conference, Atlanta, GA (United

States), 26-28 Aug 1997). Order Number DE98000212.

Source: OSTI; NTIS; INIS; GPO Dep.

The Environmental Restoration (ER) Project at Sandia

National Laboratories implicitly subscribed to the philosophy

of pollution prevention and waste minimization. As a result

of a Department of Energy (DOE) offer, Pollution Prevention

Opportunity Assessments (PPOA) were conducted at two

ER sites and a decontamination and Demolition (D and D)

site. The purpose of one of the PPOAs was to identify pollution prevention (P2) opportunities during environmental

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

remediation at the Classified Waste Landfill located at Sandia National Laboratories, New Mexico (SNL/NM). The

remediation activities at this site are scheduled to begin in

the fall of 1997. The PPOA included presentations by the

team members, a tour of the site, and a brainstorming session to list the waste streams, identify P2 opportunities and

rank them in order of priority. Twenty-five P2 opportunities

were identified during the brainstorming session of which

twenty-two opportunities were selected for further investigation. Those twenty-two opportunities are discussed in this

paper. A cost benefit analysis was performed for each P2

opportunity based on the estimated waste volume, feasibility, and cost. Pollution Prevention by Design (P2D) was

incorporated into the PPOA to introduce waste minimization

techniques that can be used during the planning phase of

restoration projects.

671

(SAND–97-1465C)

Studies of photoredox reactions on nanosize

semiconductors. Wilcoxon, J.P. (Sandia National Labs., Albuquerque, NM (United States)); Parsapour, F.; Kelley, D.F.

Sandia National Labs., Albuquerque, NM (United States).

[1997]. 12p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract AC04-94AL85000. (CONF-970517–9: 191. meeting of

the Electrochemical Society, Inc., Montreal (Canada), 4-9

May 1997). Order Number DE97006874. Source: OSTI;

NTIS; GPO Dep.

Light induced electron transfer (ET) from nanosize semiconductors of MoS2 to organic electron acceptors such as

2,20

-bipyridine (bpy) and methyl substituted 4,40,5,50-

tetramethyl-2,20

-bipyridine (tmb) was studied by static and

time resolved photoluminescence spectroscopy. The kinetics of ET were varied by changing the nanocluster size (the

band gap), the electron acceptor, and the polarity of the solvent. MoS2 is an especially interesting semiconductor

material as it is an indirect semiconductor in bulk form, and

has a layered covalent bonding arrangement which is highly

resistant to photocorrosion. Et occurs following photoexcitation of the direct band gap. Quantum confinement results in

the smaller nanoclusters having higher conduction band

energies, and therefore larger ET driving forces. The ET reaction energies may be varied by changing the electron

acceptor, by varying the size of the MoS2 nanocluster or by

varying the polarity of the solvent. In addition, varying the

polarity of the solvent affects the reorganization energy and

the barrier to electron transfer. TMB is harder to reduce, and

thus has a smaller ET driving force than bpy. The solvent

polarity is varied by varying the composition of acetonitrile/

benzene mixed solvents.

672

(SAND–97-1500C)

Low-level radioactive waste transportation safety history. McClure, J.D. (Sandia National Labs., Albuquerque,

NM (United States). Transportation Systems Analysis Dept.).

Sandia National Labs., Albuquerque, NM (United States).

[1997]. 10p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract AC04-94AL85000. (CONF-970537–10: 18. annual

DOE low-level radioactive waste management conference,

Salt Lake City, UT (United States), 20-22 May 1997). Order

Number DE97006875. Source: OSTI; NTIS; INIS; GPO Dep.

The Radioactive Materials Incident Report (RMIR) database was developed fin 1981 at the Transportation

Technology Center of Sandia National Laboratories to support its research and development activities for the US

department of Energy (DOE). This database contains information about radioactive material (RAM) transportation

incidents that have occurred in the US since 1971. These

data were drawn from the US Department of Transportation’s (DOT) Hazardous Materials Incident Report system,

from Nuclear Regulatory Commission (NRC) files, and from

various agencies including state radiological control offices.

Support for the RMIR data base is funded by the US DOE

National Transportation Program (NTP). Transportation

events in RMIR are classified in one of the following ways:

as a transportation accident, as a handling accident, or as a

reported incident. This presentation will provide definitions

for these classifications and give examples of each. The primary objective of this presentation is to provide information

on nuclear materials transportation accident/incident events

involving low-level waste (LLW) that have occurred in the

US for the period 1971 through 1996. Among the areas to

be examined are: transportation accidents by mode, package response during accidents, and an examination of

accidents where release of contents has occurred. Where

information is available, accident and incident history and

package response for LLW packages in transportation accidents will be described.

673

(SAND–97-1645C)

Application of the RADTRAN 5 stop model. Neuhauser,

K.S.; Kanipe, R.L.; Weiner, R.F. Sandia National Labs., Albuquerque, NM (United States). [1997]. 7p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract AC04-94AL85000.

(CONF-980507–: PATRAM ’98: 12. international conference

on packaging and transportation of radioactive material,

Paris (France), 10-15 May 1998). Order Number

DE98004422. Source: OSTI; NTIS; INIS; GPO Dep.

A number of environmental impact analyses with the

RADTRAN computer code have shown that dose to persons

at stops is one of the largest components of incident-free

dose during overland carriage of spent fuel and other radioactive materials (e.g., USDOE, 1994). The input data

used in these analyses were taken from a 1983 study that

reports actual observations of spent fuel shipments by truck.

Early RADTRAN stop models, however, were insufficiently

flexible to take advantage of the detailed information in the

study. A more recent study of gasoline service stations that

specialize in servicing large trucks, which are the most likely

stop locations for shipments of Type B packages in the

United States, has provided additional, detailed data on refueling/meal stops. The RADTRAN 5 computer code for

transportation risk analysis allows exposures at stops to be

more fully modeled than have previous releases of the code

and is able to take advantage of detailed data. It is the intent of this paper first to compare results from RADTRAN

and RADTRAN 5 for the old, low-resolution form of input

data, and then to demonstrate what effect the new data and

input format have on stop-dose estimates for an individual

stop and for a hypothetical shipment route. Finally, these

estimated public doses will be contrasted with doses calculated for a special population group – inspectors.

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

674

(SAND–97-2291C)

A risk-based decision-aiding tool for waste disposal.

Weiner, R.F. (Sandia National Labs., Albuquerque, NM

(United States)); Reiser, A.S.; Elcock, C.G.; Nevins, S. Sandia National Labs., Albuquerque, NM (United States). 1997.

15p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC04-94AL85000. (CONF-970857–2: 4. biennial ASME

mixed waste symposium, Baltimore, MD (United States), 17-

21 Aug 1997). Order Number DE98000040. Source: OSTI;

NTIS; INIS; GPO Dep.

N-CART (the National Spent Nuclear Fuel Program Cost

Analysis and Risk Tool) is being developed to aid in low-risk,

cost-effective, timely management of radioactive waste and

spent nuclear fuel, and can therefore be used in management of mixed waste. N-CART provides evaluation of

multiple alternatives and presents the consequences of proposed waste management activities in a clear and concise

format. N-CART’s decision-aiding analyses include comparisons and sensitivity analyses of multiple alternatives and

allows the user to perform quick turn-around “what if” studies to investigate various scenarios. Uncertainties in data

(such as cost and schedule of various activities) are represented as distributions. N-CART centralizes documentation

of the bases of program alternatives and program decisions,

thereby supporting responses to stakeholders concerns.

The initial N-CART design considers regulatory requirements, costs, and schedules for alternative courses of

action. The final design will include risks (public health, occupational, economic, scheduling), economic benefits, and

the impacts of secondary waste generation. An optimization

tool is being incorporated that allows the user to specify the

relative importance of cost, time risks, and other bases for

decisions. The N-CART prototype can be used to compare

the costs and schedules of disposal alternatives for mixed

low-level radioactive waste (MLLW) and greater-than-ClassC (GTCC) waste, as well as spent nuclear fuel (SNF) and

related scrap material.

675

(SAND–97-2390C)

Performance assessment in support of compliance certification application for the WIPP project. Jow, H.N.

(Sandia National Labs., Albuquerque, NM (United States));

Anderson, D.R.; Marietta, M.; Helton, J.; Basabilvazo, G.

Sandia National Labs., Albuquerque, NM (United States).

Mar 1998. 6p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE

Contract AC04-94AL85000. (CONF-971040–: ICEM ‘97: 6.

international conference on radioactive waste management

and environmental remediation, Singapore (Singapore), 12-

16 Oct 1997). Order Number DE98002839. Source: OSTI;

NTIS; INIS; GPO Dep.

The Waste Isolation Pilot Plant (WIPP) is being developed

by the US Department of Energy for the geologic (deep

underground) disposal of transuranic (TRU) waste. A Compliance Certification Application (CCA) of the WIPP (1) for

such disposal was submitted to the US Environmental Protection Agency (EPA) in October, 1996, and is currently

under review, with a decision anticipated in late 1997. An

important component of the CCA is a performance assessment (PA) for the WIPP carried out by Sandia National

Laboratories. The final outcome of the PA is a complementary cumulative distribution function (CCDF) for radionuclide

releases from the WIPP to the accessible environment and

an assessment of the confidence with which this CCDF can

be estimated. This paper describes the computational process used to develop the CCDF. The results of uncertainty

and sensitivity analysis are also presented.

676

(SAND–97-2592)

Electrokinetic demonstration at the unlined chromic

acid pit. Lindgren, E.R. (Sandia National Labs., Albuquerque, NM (United States)); Hankins, M.G.; Mattson,

E.D.; Duda, P.M. Sandia National Labs., Albuquerque, NM

(United States). Jan 1998. 158p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States). DOE Contract AC04-94AL85000. Order Number

DE98004158. Source: OSTI; NTIS; INIS; GPO Dep.

Heavy-metal contaminated soils are a common problem

at Department of Energy (DOE)-operated sites and privately

owned facilities throughout the nation. One emerging technology which can remove heavy metals from soil in situ is

electrokinetics. To conduct electrokinetic (EK) remediation,

electrodes are implanted into the ground, and a direct

current is imposed between the electrodes. Metal ions dissolved in the soil pore water migrate towards an electrode

where they can be removed. The electrokinetic program at

Sandia National Laboratories (SNL) has been focusing on

electrokinetic remediation for unsaturated soils. A patent

was awarded for an electrokinetic electrode system designed at SNL for applications to unsaturated soils. Current

research described in this report details an electrokinetic remediation field demonstration of a chromium plume that

resides in unsaturated soil beneath the SNL Chemical

Waste Landfill (CWL). This report describes the processes,

site investigation, operation and monitoring equipment, testing procedures, and extraction results of the electrokinetic

demonstration. This demonstration successfully removed

chromium contamination in the form of chromium(VI) from

unsaturated soil at the field scale. After 2700 hours of operation, 600 grams of Cr(VI) was extracted from the soil

beneath the SNL CWL in a series of thirteen tests. The contaminant was removed from soil which has moisture

contents ranging from 2 to 12 weight percent. This demonstration was the first EK field trial to successfully remove

contaminant ions from and soil at the field scale. Although

the new patented electrode system was successful in

removing an anionic contaminant (i.e., chromate) from unsaturated sandy soil, the electrode system was a prototype

and has not been specifically engineered for commercialization. A redesign of the electrode system as indicated by the

results of this research is suggested for future EK field trials.

677

(SAND–97-2707C)

A model for predicting damage dependent response of

inelastic media with microstructure. Allen, D.H. (Texas A

and M Univ., College Station, TX (United States).

Aerospace Engineering Dept.); DeVries, K.L.; Hurtado, L.D.

Sandia National Labs., Albuquerque, NM (United States).

Dec 1997. 24p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE

Contract AC04-94AL85000. (CONF-980902–: 35. annual

technical meeting of the Society of Engineering Science,

Pullman, WA (United States), 27-30 Sep 1998). Order Number DE98001367. Source: OSTI; NTIS; GPO Dep.

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

This paper presents a model developed for predicting the

mechanical response of inelastic media with heterogeneous

microstructure. Particular emphasis is given to the development of microstructural damage along grains. The model is

developed within the concepts of continuum mechanics, with

special emphasis on the development of internal boundaries

in the continuum by utilizing fracture mechanics-based cohesive zone models. In addition, the grains are assumed to

be characterized by nonlinear viscoplastic material behavior.

Implementation of the model to a finite element computational algorithm is also briefly described, and example

solutions are obtained. Finally, homogenization procedures

are discussed for obtaining macroscopic damage dependent

mechanical constitutive equations that may then be utilized

to construct a well-posed boundary value problem for the

macroscopically homogenized damage dependent medium.

678

(SAND–97-2708C)

Science to compliance: The WIPP success story.

Howarth, S.M.; Chu, M.S.; Shephard, L.E. Sandia National

Labs., Albuquerque, NM (United States). 14 Nov 1997. 10p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC04-94AL85000. (CONF-980516–: 1998 international

high-level radioactive waste management conference, Las

Vegas, NV (United States), 11-14 May 1998). Order Number

DE98001311. Source: OSTI; NTIS; INIS; GPO Dep.

The Waste Isolation Pilot Plant (WIPP) in southeast New

Mexico has been studied as a transuranic waste repository

for the past 23 years. During this time, an extensive site

characterization, design, construction, and experimental program was completed to provide in-depth understanding of

the dominant processes that are most likely to influence the

containment of radionuclides for 10,000 years. The success

of the program, however, is defined by the regulator in the

context of compliance with performance criteria, rather than

by the in-depth technical understanding typical of most scientific programs. The WIPP project was successful in

making a transformation from science to compliance by refocusing and redirecting programmatic efforts toward the

singular goal of meeting regulatory compliance requirements

while accelerating the submittal of the Compliance Certification Application (CCA) by two months from the April 1994

Disposal Decision Plan (DDP) date of December 1996, and

by reducing projected characterization costs by more than

40%. This experience is unparalleled within the radioactive

waste management community and has contributed to numerous lessons learned from which the entire community

can benefit.

679

(SAND–97-2764C)

WIPP Compliance Certification Application calculations

parameters. Part 1: Parameter development. Howarth,

S.M. Sandia National Labs., Albuquerque, NM (United

States). 14 Nov 1997. 8p. Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract AC04-94AL85000. (CONF-980516–:

1998 international high-level radioactive waste management

conference, Las Vegas, NV (United States), 11-14 May

1998). Order Number DE98001310. Source: OSTI; NTIS;

INIS; GPO Dep.

The Waste Isolation Pilot Plant (WIPP) in southeast New

Mexico has been studied as a transuranic waste repository

for the past 23 years. During this time, an extensive site

characterization, design, construction, and experimental

program was completed, which provided in-depth understanding of the dominant processes that are most likely to

influence the containment of radionuclides for 10,000 years.

Nearly 1,500 parameters were developed using information

gathered from this program; the parameters were input to

numerical models for WIPP Compliance Certification Application (CCA) Performance Assessment (PA) calculations.

The CCA probabilistic codes frequently require input values

that define a statistical distribution for each parameter. Developing parameter distributions begins with the assignment

of an appropriate distribution type, which is dependent on

the type, magnitude, and volume of data or information

available. The development of the parameter distribution

values may require interpretation or statistical analysis of

raw data, combining raw data with literature values, scaling

of lab or field data to fit code grid mesh sizes, or other transformation. Parameter development and documentation of

the development process were very complicated, especially

for those parameters based on empirical data; they required

the integration of information from Sandia National Laboratories (SNL) code sponsors, parameter task leaders (PTLs),

performance assessment analysts (PAAs), and experimental

principal investigators (PIs). This paper, Part 1 of two parts,

contains a discussion of the parameter development process, roles and responsibilities, and lessons learned. Part 2

will discuss parameter documentation, traceability and retrievability, and lessons learned from related audits and

reviews.

680

(SAND–97-2767C)

Truck transport of RAM: Risk effects of avoiding

metropolitan areas. Mills, G.S.; Neuhauser, K.S. Sandia

National Labs., Albuquerque, NM (United States). Nov 1997.

10p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC04-94AL85000. (CONF-980507–: PATRAM ’98: 12. international conference on packaging and transportation of

radioactive material, Paris (France), 10-15 May 1998). Order

Number DE98001125. Source: OSTI; NTIS; INIS; GPO Dep.

In the transport of radioactive material (RAM), e.g., spent

nuclear fuel (SNF), stakeholders are generally most concerned about risks in high population density areas along

transportation routes because of the perceived high consequences of potential accidents. The most significant portions

of a transcontinental route and an alternative examined previously were evaluated again using population density data

derived from US Census Block data. This method of characterizing population that adjoins route segments offers

improved resolution of population density variations, especially in high population density areas along typical transport

routes. Calculated incident free doses and accident dose

risks for these routes, and the rural, suburban and urban

segments are presented for comparison of their relative

magnitudes. The results indicate that modification of this

route to avoid major metropolitan areas through use of nonInterstate highways increases total risk yet does not

eliminate a relatively small urban component of the accident

dose risk. This conclusion is not altered by improved resolution of route segments adjoining high density populations.

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

681

(SAND–97-2768C)

Study of the components of evacuation times. Mills,

G.S.; Neuhauser, K.S.; Smith, J.D. Sandia National Labs.,

Albuquerque, NM (United States). Nov 1997. 8p. Sponsored

by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract AC04-94AL85000.

(CONF-980507–: PATRAM ’98: 12. international conference

on packaging and transportation of radioactive material,

Paris (France), 10-15 May 1998). Order Number

DE98001126. Source: OSTI; NTIS; INIS; GPO Dep.

The magnitudes of accident dose risks calculated by the

RADTRAN code depend directly on the time span between

an accidental release and evacuation of the affected area

surrounding potential radionuclide releases. In a previous

study of truck and rail transportation accidents, and other incidents requiring evacuations, a lognormal distribution of

evacuation times (time span from decision to evacuate until

complete) was developed, which provided a better model for

this parameter than the practice of using a highly conservative value of 24 hours. However, the distribution did not

account for time required for responders to arrive on the

scene, to evaluate the hazards to surrounding population

and to initiate an evacuation. Data from US Department of

Transportation (DOT) accident statistics have been collected

and their distribution functions determined. The separate

distribution functions were combined into a single, comprehensive distribution which may be sampled to supply values

of the RADTRAN input parameter, EVACUATION. A sample

RADTRAN calculation illustrating the effect on risks of using

the distribution versus the original (24 hour), conservative

point-estimate are also presented.

682

(SAND–97-2769C)

Extension of ship accident analysis to multiple-package

shipments. Mills, G.S.; Neuhauser, K.S. Sandia National

Labs., Albuquerque, NM (United States). Nov 1997. 9p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC04-94AL85000. (CONF-980507–: PATRAM ’98: 12. international conference on packaging and transportation of

radioactive material, Paris (France), 10-15 May 1998). Order

Number DE98001127. Source: OSTI; NTIS; INIS; GPO Dep.

Severe ship accidents and the probability of radioactive

material release from spent reactor fuel casks were investigated previously. Other forms of RAM, e.g., plutonium oxide

powder, may be shipped in large numbers of packagings

rather than in one to a few casks. These smaller, more numerous packagings are typically placed in ISO containers

for ease of handling, and several ISO containers may be

placed in one of several holds of a cargo ship. In such

cases, the size of a radioactive release resulting from a severe collision with another ship is determined not by the

likelihood of compromising a single, robust package but by

the probability that a certain fraction of 10’s or 100’s of individual packagings is compromised. The previous analysis

involved a statistical estimation of the frequency of accidents which would result in damage to a cask located in one

of seven cargo holds in a collision with another ship. The results were obtained in the form of probabilities (frequencies)

of accidents of increasing severity and of release fractions

for each level of severity. This paper describes an extension

of the same general method in which the multiple packages

are assumed to be compacted by an intruding ship’s bow

until there is no free space in the hold. At such a point, the

remaining energy of the colliding ship is assumed to be dissipated by progressively crushing the RAM packagings and

the probability of a particular fraction of package failures is

estimated by adaptation of the statistical method used previously. The parameters of a common, well characterized

packaging, the 6M with 2R inner containment vessel, were

employed as an illustrative example of this analysis method.

However, the method is readily applicable to other packagings for which crush strengths have been measured or can

be estimated with satisfactory confidence.

683

(SAND–97-2777C)

Designing a database for performance assessment:

Lessons learned from WIPP. Martell, M.A. (Sandia National Labs., Albuquerque, NM (United States)); Schenker,

A. Sandia National Labs., Albuquerque, NM (United States).

Dec 1997. 6p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE

Contract AC04-94AL85000. (CONF-980516–: 1998 international high-level radioactive waste management conference,

Las Vegas, NV (United States), 11-14 May 1998). Order

Number DE98001679. Source: OSTI; NTIS; INIS; GPO Dep.

The Waste Isolation Pilot Plant (WIPP) Compliance Certification Application (CCA) Performance Assessment (PA)

used a relational database that was originally designed only

to supply the input parameters required for implementation

of the PA codes. Reviewers used the database as a point of

entry to audit quality assurance measures for control, traceability, and retrievability of input information used for

analysis, and output/work products. During these audits it

became apparent that modifications to the architecture and

scope of the database would benefit the EPA regulator and

other stakeholders when reviewing the recertification application. This paper contains a discussion of the WPP PA CCA

database and lessons learned for designing a database.

684

(SAND–97-2797C)

“We crash, burn, and crush”: A history of packaging at

Sandia National Laboratories, 1978–1997. Mora, C.J.; McConnell, P. Sandia National Labs., Albuquerque, NM (United

States). Nov 1997. 10p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States).

DOE Contract AC04-94AL85000. (CONF-980507–: PATRAM ’98: 12. international conference on packaging and

transportation of radioactive material, Paris (France), 10-15

May 1998). Order Number DE98000841. Source: OSTI;

NTIS; INIS; GPO Dep.

Even prior to the beginning of the nuclear age, the packaging and transportation of nuclear materials was a prime

national concern. Nuclear materials such as uranium and

plutonium had to be transported safely (and secretly) to the

Manhattan Engineer District Laboratory in Los Alamos, New

Mexico. The subsequent post war use of nuclear power for

the generation of electricity and accelerated weapons development programs resulted in radioactive waste byproducts,

such as spent fuel and plutonium, that were stored on site at

utilities and federal weapons sites. While projected repositories for long term storage of radioactive waste are being

planned, both low and high level radioactive materials on

occasion must be moved safely. Movement to interim

storage and, for low level waste, repository sites, is accomplished by a combination of truck, rail, ship, and air. The US

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

Department of Energy (DOE) directs transportation activities

including cask development technology for use in single or

multimodal (a combination of land, water, and air) transport.

In 1978, Sandia National Laboratories was selected as the

lead contractor for basic transportation technology. This report is divided into the following topics: (1) early research

and development (1936–1978); (2) radioactive material

package test (1975–1977); (3) the SNL Transportation Technology Center; (4) TRUPACT-II; (5) beneficial uses of

shipping system casks; (6) C-141B drop tests; (7) MIDAS;

(8) MOSAIK; (9) SEARAM; (10) PATRAM; and (11) a

chronology of transportation activities.

685

(SAND–97-2812C)

WIPP Compliance Certification Application calculations

parameters. Part 2: Parameter documentation. Howarth,

S.M. Sandia National Labs., Albuquerque, NM (United

States). 14 Nov 1997. 9p. Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract AC04-94AL85000. (CONF-980516–:

1998 international high-level radioactive waste management

conference, Las Vegas, NV (United States), 11-14 May

1998). Order Number DE98001680. Source: OSTI; NTIS;

INIS; GPO Dep.

The Waste Isolation Pilot Plant (WIPP) in southeast New

Mexico has been studied as a transuranic waste repository

for the past 23 years. During this time, an extensive site

characterization, design, construction, and experimental

program was completed, which provided in depth understanding of the dominant processes that are most likely to

influence the containment of radionuclides for 10,000 years.

Nearly 1,500 parameters were developed using information

gathered from this program and were input to numerical

models for WIPP Compliance Certification Application (CCA)

Performance Assessment (PA) calculations. The CCA probability models require input parameters that are defined by a

statistical distribution. Developing parameters begins with

the assignment of an appropriate distribution type, which is

dependent on the type, magnitude, and volume of data or

information available. Parameter development may require

interpretation or statistical analysis of raw data, combining

raw data with literature values, scaling laboratory or field

data to fit code grid mesh sizes, or other transformations.

Documentation of parameter development is designed to

answer two questions: What source information was used to

develop this parameter? and Why was this particular data

set/information used? Therefore, complete documentation

requires integrating information from code sponsors, parameter task leaders, performance assessment analysts, and

experimental principal investigators. This paper, Part 2 of 2

parts, contains a discussion of the WIPP CCA PA Parameter Tracking System, document traceability and retrievability,

and lessons learned from related audits and reviews.

686

(SAND–97-2813C)

QA lessons learned for parameter control from the

WIPP Project. Richards, R.R. Sandia National Labs., Albuquerque, NM (United States). Jan 1998. 4p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract AC04-94AL85000.

(CONF-980516–: 1998 international high-level radioactive

waste management conference, Las Vegas, NV (United

States), 11-14 May 1998). Order Number DE98004101.

Source: OSTI; INIS; NTIS; GPO Dep.

This paper provides a summary of lessons learned from

experiences on the Waste Isolation Pilot Plant (WJPP)

Project in implementation of quality assurance controls surrounding inputs for performance assessment analysis. Since

the performance assessment (PA) process is inherent in

compliance determination for any waste repository, these

lessons-learned are intended to be useful to investigators,

analysts, and Quality Assurance (QA) practitioners working

on high level waste disposal projects. On the WIPP Project,

PA analyses for regulatory-compliance determination utilized

several inter-related computer programs (codes) that mathematically modeled phenomena such as radionuclide release,

retardation, and transport. The input information for those

codes are the parameters that are the subject of this paper.

Parameters were maintained in a computer database, which

was then queried electronically by the PA codes whenever

input was needed as the analyses were run.

687

(SAND–97-2824C)

Anticipating Potential Waste Acceptance Criteria for Defense Spent Nuclear Fuel. Rechard, R.P. (Sandia National

Labs., Albuquerque, NM (United States). Nuclear Waste

Management Center); Lord, M.E.; Stockman, C.T.; McCurley, R.D. Sandia National Labs., Albuquerque, NM (United

States). 1997. 17p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE

Contract AC04-94AL85000. (CONF-980307–: Waste management ’98, Tucson, AZ (United States), 1-5 Mar 1998).

Order Number DE98001265. Source: OSTI; NTIS; INIS;

GPO Dep.

The Office of Environmental Management of the U.S. Department of Energy is responsible for the safe management

and disposal of DOE owned defense spent nuclear fuel and

high level waste (DSNF/DHLW). A desirable option, direct

disposal of the waste in the potential repository at Yucca

Mountain, depends on the final waste acceptance criteria,

which will be set by DOE’s Office of Civilian Radioactive

Waste Management (OCRWM). However, evolving regulations make it difficult to determine what the final acceptance

criteria will be. A method of anticipating waste acceptance

criteria is to gain an understanding of the DOE owned waste

types and their behavior in a disposal system through a performance assessment and contrast such behavior with

characteristics of commercial spent fuel. Preliminary results

from such an analysis indicate that releases of 99Tc and

237Np from commercial spent fuel exceed those of the

DSNF/DHLW; thus, if commercial spent fuel can meet the

waste acceptance criteria, then DSNF can also meet the criteria. In large part, these results are caused by the small

percentage of total activity of the DSNF in the repository

(1.5%) and regulatory mass (4%), and also because commercial fuel cladding was assumed to provide no protection.

688

(SAND–97-2832C)

Balancing compliance and cost when implementing a

Quality Assurance program. Pickering, S.Y. Sandia National Labs., Albuquerque, NM (United States). Dec 1997.

8p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC04-94AL85000. (CONF-980516–: 1998 international

high-level radioactive waste management conference, Las

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

Vegas, NV (United States), 11-14 May 1998). Order Number

DE98001681. Source: OSTI; NTIS; INIS; GPO Dep.

When implementing a Quality Assurance (QA) program,

compliance and cost must be balanced. A QA program must

be developed that hits the mark in terms of adequate control

and documentation, but does not unnecessarily expand resources. As the Waste Isolation Pilot Plant (WIPP) has

moved towards certification, Sandia National Laboratories

has learned much about balancing compliance and costs.

Some of these lessons are summarized here.

689

(SAND–97-2845C)

Reduction of Np(VI) and Pu(VI) by organic chelating

agents. Reed, D.T. (Argonne National Lab., IL (United

States)); Wygmans, D.G.; Aase, S.B.; Banaszak, J.E. Sandia National Labs., Albuquerque, NM (United

States);Argonne National Lab., IL (United States). Jun 1998.

18p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC04-94AL85000 ; W-31109-ENG-38. (CONF-971090–: 8.

international conference on fusion reactor materials

(ICFRM), Sendai (Japan), 26-31 Oct 1997). Order Number

DE98005702. Source: OSTI; NTIS; INIS; GPO Dep.

The reduction of NpO2

2+ and PuO22+ by oxalate, citrate,

and ethylenediaminetetraacetic acid (EDTA) was investigated in low ionic strength media and brines. This was done

to help establish the stability of the An(VI) oxidation state

depended on the pH nd relative strength of the various oxidation state-specific complexes. At low ionic strength and

pH 6, NpO2

2+ was rapidly reduced to form NpO2+ organic

complexes. At longer times, Np(IV) organic complexes were

observed in the presence of citrate. PuO2

2+ was predominantly reduced to Pu4+, resulting in the formation of organic

complexes or polymeric/hydrolytic precipitates. The relative

rates of reduction to the An(V) complex were EDTA > citrate > oxalate. Subsequent reduction to An(IV) complexes,

however, occurred in the following order: citrate > EDTA >

oxalate because of the stability of the An(VI)-EDTA complex.

The presence of organic complexants led to the rapid reduction of NpO2

2+ and PuO22+ in G-Seep brine at pHs 5 and 7.

At pHs 8 and 10 in ERDA-6 brine, carbonate and hydrolytic

complexes predominated and slowed down or prevented the

reduction of An(VI) by the organics present.

690

(SAND–97-2850C)

An overview of performance assessment for the Waste

Isolation Pilot Plant. Jow, Hong-Nian (Sandia National

Labs., Albuquerque, NM (United States)); Anderson, D.R.;

Marietta, M. Sandia National Labs., Albuquerque, NM

(United States). 1997. 9p. Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract AC04-94AL85000. (CONF-970335–:

Waste Management ‘97, Tucson, AZ (United States), 2-7

Mar 1997). Order Number DE98001484. Source: OSTI;

NTIS; INIS; GPO Dep.

This paper presents an overview of the methodology used

in the recent performance assessment (PA) to support the

U.S. Department of Energy (DOE) Carlsbad Area Office’s

(CAO’s) Waste Isolation Pilot Plant (WIPP) Compliance Certification Application (CCA). The results of this recently

completed WIPP PA will be presented. Major release modes

contributing to the total radionuclide release to the accessible environment will be discussed. Comparison of the mean

complementary cumulative distribution function (CCDF)

curve against the Environmental Protection Agency (EPA)

radionuclide release limits will be presented.

691

(SAND–97-2851C)

Critical scientific issues in the demonstration of WIPP

compliance with EPA repository standards. Weart, W.D.;

Chu, M.S.Y. Sandia National Labs., Albuquerque, NM

(United States). 1997. 10p. Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract AC04-94AL85000. (CONF-970335–:

Waste Management ‘97, Tucson, AZ (United States), 2-7

Mar 1997). Order Number DE98001485. Source: OSTI;

NTIS; INIS; GPO Dep.

The Department of Energy submitted a Compliance Certification Application for the Waste Isolation Pilot Plant to the

Environmental Protection Agency (EPA) in October, 1996. A

critical part of this application was a Performance Assessment which predicts the cumulative radioactive release to

the accessible environment over a time period of 10,000

years. Comparison of this predicted release to the EPA

standard shows a comfortable margin of compliance. The

scientific understanding that was critical to developing this

assessment spans a broad range of geotechnical disciplines, and required a thorough understanding of the site’s

geology and hydrology. Evaluation of the geologic processes which are active in the site region establishes that

there will be no natural breach of site integrity for millions of

years, far longer than the 10,000 year regulatory period. Inadvertent human intrusion is, therefore, the only credible

scenario to lead to potential radioactive release to the accessible environment. To substantiate this conclusion and to

quantify these potential releases from human intrusion, it

has been necessary to develop an understanding of the following processes: (1) salt creep and shaft seal efficacy; (2)

gas generation from organic decomposition of waste materials and anoxic corrosion of metals in the waste and waste

packages; (3) solubilities for actinides in brine; (4) fluid flow

in Salado formation rocks, and (5) hydrologic transport of

actinides in the overlying dolomite aquifers. Other issues

which had to be evaluated to allow definition of breach scenarios were brine reservoir occurrences and their associated

reservoir parameters, consequences of mining over the

repository, and drilling for natural resources in the vicinity of

the repository. Results of all these studies will be briefly

summarized in this paper.

692

(SAND–97-2909C)

Radioactive material (RAM) transportation accident and

incident experience in the U.S.A. (1971–1997). McClure,

J.D. (Sandia National Labs., Albuquerque, NM (United

States). Transportation Systems Analysis Dept.); Yoshimura,

H.R.; Fagan, H.F.; Thomas, T. Sandia National Labs., Albuquerque, NM (United States). Nov 1997. 10p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract AC04-94AL85000.

(CONF-980507–: PATRAM ’98: 12. international conference

on packaging and transportation of radioactive material,

Paris (France), 10-15 May 1998). Order Number

DE98001309. Source: OSTI; NTIS; INIS; GPO Dep.

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

The Radioactive Materials Incident Report (RMIR)

database was developed in 1981 at the Transportation Technology Center of Sandia National Laboratories to support its

research and development activities for the US Department

of Energy (DOE). This database contains information about

radioactive materials transportation incidents that have occurred in the US since 1971. These data were drawn from

the US Department of Transportation’s (DOT) Hazardous

Materials Incident Report system, from Nuclear Regulatory

Commission (NRC) files, and from various agencies including state radiological control offices. Support for the RMIR

data base is funded by the National Transportation Program

(EM-70) of the US Department of Energy. Transportation

events in RMIR are classified in one of the following ways:

as a transportation accident, as a handling accident, or as a

reported incident. This presentation will provide definitions

for these classifications and give examples of each. The primary objective of this presentation is to provide information

on nuclear materials transportation accident incident events

in the US for the period 1971–1997. Among the areas to be

examined are: transportation accidents by mode, package

response during accidents and an examination of accidents

where release of contents has occurred.

693

(SAND–97-2999C)

PASS: a component of Desk Top PA for the WIPP. Crawford, M.B. (Galson Sciences Ltd., Oakham (United

Kingdom)); Wilmot, R.D.; Galson, D.A.; Swift, P.N.; Fewell,

M.E. Sandia National Labs., Albuquerque, NM (United

States). Jan 1998. 10p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States).

DOE Contract AC04-94AL85000. (CONF-970426–: International high-level radioactive waste management conference,

Las Vegas, NV (United States), 29 Apr - 2 May 1997). Order

Number DE98003085. Source: OSTI; NTIS; INIS; GPO Dep.

There is a growing recognition internationally of the need

to demonstrate comprehensiveness in order to build confidence in performance assessments (PAs) for radioactive

waste disposal projects. This has resulted in a number of

methodologies being developed to formalize the process of

defining and documenting the decision basis that underlies

a PA. Such methodologies include process influence diagrams and the rock engineering system (RES) matrix.

However, these methodologies focus mainly on the conceptualization of the disposal system and do not provide a

ready framework to document the decisions behind the

model development and parameterization of the PA system.

The Performance Assessment Support System (PASS) is a

flexible electronic tool designed to increase the transparency

and traceability of decision making in the entire PA process.

An application of PASS has been developed for the Waste

Isolation Pilot Plant (WIPP) where it forms an important

component of Desk Top PA, a PC-based PA computational

environment under development at Sandia National Laboratories to document, plan, and support management

decisions and to assess performance for the WIPP recertification process. This desk-top PA environment is also aimed

at providing scientifically-based decision support for assessing the performance of nuclear and hazardous waste

management and environmental clean-up systems.

694

(SAND–97-3097C)

A Modular Approach to Redundant Robot Control. Anderson, R.J. Sandia National Labs., Albuquerque, NM

(United States). Dec 1997. 9p. Sponsored by USDOE Office

of Environmental Management, Washington, DC (United

States). DOE Contract AC04-94AL85000. (CONF-970469–:

1997 international conference on robotics and automation,

Albuquerque, NM (United States), 20-25 Apr 1997). Order

Number DE98001676. Source: OSTI; NTIS; INIS; GPO Dep.

This paper describes a modular approach for computing

redundant robot kinematics. First some conventional redundant control methods are presented and shown to be

’passive control laws’, i.e. they can be represented by a network consisting of passive elements. These networks are

then put into modular form by applying scattering operator

techniques. Additional subnetwork modules can then be

added to further shape the motion. Modules for obstacle detection, joint limit avoidance, proximity sensing, and for

imposing nonlinear velocity constraints are presented. The

resulting redundant robot control system is modular, flexible

and robust.

695

(SAND–98-0001C)

Hydraulic Characterization Activities in Support of the

Shaft-Seals Fluid-Flow Modeling Integration into the

WIPP EPA Compliance Certification Application.

Knowles, M.K. (Sandia National Labs., Albuquerque, NM

(United States)); Hurtado, L.D.; Dale, Tim. Sandia National

Labs., Albuquerque, NM (United States). [Dec 1997]. 6p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC04-94AL85000. (CONF-971224–: Field Testing and Associated Modeling (FTAM) of potential high-level nuclear

waste geologic disposal sites, Berkeley, CA (United States),

15-16 Dec 1997). Order Number DE98003014. Source:

OSTI; NTIS; INIS; GPO Dep.

The Waste Isolation Pilot Plant (WIPP) is a planned geologic repository for permanent disposal of transuranic waste

generated by the U.S. Department of Energy. Disposal regions consist of panels and drifts mined from the bedded

salt of the Salado Formation at a depth of approximately

650 m below the surface. This lithology is part of the 225

million year old Delaware Basin, and is geographically located in southeastern New Mexico. Four shafts service the

facility needs for air intake, exhaust, waste handling, and

salt handling. As the science advisor for the project, Sandia

National Laboratories developed the WIPP shaft sealing

system design. This design is a fundamental component of

the application process for facility licensing, and has been

found acceptable by stakeholders and regulatory agencies.

The seal system design is founded on results obtained from

laboratory and field experiments, numerical modeling, and

engineering judgment. This paper describes a field test program to characterize the fluid flow properties in the WIPP

shafts at representative seal locations. This work was conducted by Duke Engineering and Services under contract to

Sandia National Laboratories in support of the seal system

design.

696

(SAND–98-0030)

Planning and scheduling for agile manufacturers: The

Pantex Process Model. Kjeldgaard, E.A. (Sandia National

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

Labs., Albuquerque, NM (United States). Transportation

Systems Analysis Dept.); Jones, D.A.; List, G.F.; Tumquist,

M.A. Sandia National Labs., Albuquerque, NM (United

States). Feb 1998. 44p. Sponsored by USDOE Office of Financial Management and Controller, Washington, DC

(United States);USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC04-94AL85000. Order Number DE98003409. Source:

OSTI; NTIS; GPO Dep.

Effective use of resources that are shared among multiple

products or processes is critical for agile manufacturing.

This paper describes the development and implementation

of a computerized model to support production planning in a

complex manufacturing system at the Pantex Plant, a US

Department of Energy facility. The model integrates two different production processes (nuclear weapon disposal and

stockpile evaluation) that use common facilities and personnel at the plant. The two production processes are

characteristic of flow-shop and job shop operations. The

model reflects the interactions of scheduling constraints,

material flow constraints, and the availability of required

technicians and facilities. Operational results show significant productivity increases from use of the model.

697

(SAND–98-0049)

Analysis of hydraulic tests of the Culebra and Magenta

Dolomites and Dewey Lake Redbeds conducted at the

Waste Isolation Pilot Plant Site. Beauheim, R.L. (Sandia

National Labs., Albuquerque, NM (United States). Geohydrology Dept.); Ruskauff, G.J. Sandia National Labs.,

Albuquerque, NM (United States). Sep 1998. 243p. Sponsored by USDOE Office of Environmental Management,

Washington, DC (United States). DOE Contract AC04-

94AL85000. Order Number DE99000491. Source: OSTI;

NTIS; INIS; GPO Dep.

This report presents interpretations of hydraulic tests conducted at 15 well locations in the vicinity of the Waste

Isolation Pilot Plant (WIPP) in southeastern New Mexico between 1980 and 1996. The WIPP is a US Department of

Energy (DOE) facility to demonstrate safe disposal of transuranic wastes arising form the nation’s defense programs.

The WIPP repository lies within bedded halite of the Salado

Formation, 2,155 ft below ground surface. The tests reported herein were, with two exceptions, conducted in the

Culebra Dolomite member of the Rustler Formation, which

overlies the Salado Formation. The remaining tests were

conducted in the Magenta Member of the Rustler and in the

overlying formation, the Dewey Lake Redbeds. This report

completes the documentation of hydraulic-test interpretations used as input to the WIPP Compliance Certification

Application (US DOE, 1996).

698

(SAND–98-0059C)

Modeling fires in adjacent ship compartments with computational fluid dynamics. Wix, S.D.; Cole, J.K.; Koski,

J.A. Sandia National Labs., Albuquerque, NM (United

States). 10 May 1998. 10p. Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract AC04-94AL85000. (CONF-980507–:

PATRAM ’98: 12. international conference on packaging

and transportation of radioactive material, Paris (France),

10-15 May 1998). Order Number DE98004285. Source:

OSTI; NTIS; INIS; GPO Dep.

This paper presents an analysis of the thermal effects on

radioactive (RAM) transportation packages with a fire in an

adjacent compartment. An assumption for this analysis is

that the adjacent hold fire is some sort of engine room fire.

Computational fluid dynamics (CFD) analysis tools were

used to perform the analysis in order to include convective

heat transfer effects. The analysis results were compared to

experimental data gathered in a series of tests on tile US

Coast Guard ship Mayo Lykes located at Mobile, Alabama.

699

(SAND–98-0072)

Milestones for disposal of radioactive waste at the

Waste Isolation Pilot Plant (WIPP) in the United States.

Rechard, R.P. Sandia National Labs., Albuquerque, NM

(United States). Apr 1998. 41p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States). DOE Contract AC04-94AL85000. Order Number

DE98004732. Source: OSTI; NTIS; INIS; GPO Dep.

Since its identification as a potential deep geologic repository in about 1973, the regulatory assessment process for

the Waste Isolation Pilot Plant (WIPP) in New Mexico has

developed over the past 25 years. National policy issues,

negotiated agreements, and court settlements over the first

half of the project had a strong influence on the amount and

type of scientific data collected. Assessments and studies

before the mid 1980s were undertaken primarily (1) to satisfy needs for environmental impact statements, (2) to

develop general understanding of selected natural phenomena associated with nuclear waste disposal, or (3) to satisfy

negotiated agreements with the State of New Mexico. In the

last third of the project, federal compliance policy and actual

regulations were sketched out, but continued to evolve until

1996. During this eight-year period, four preliminary

performance assessments, one compliance performance assessment, and one verification performance assessment

were performed.

700

(SAND–98-0163)

An effective waste management process for segregation

and disposal of legacy mixed waste at Sandia National

Laboratories/New Mexico. Hallman, A.K. (Sandia National

Labs., Albuquerque, NM (United States)); Meyer, D.;

Rellergert, C.A.; Schriner, J.A. Sandia National Labs., Albuquerque, NM (United States). Apr 1998. 25p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States);USDOE Assistant Secretary for Environment, Safety, and Health, Washington, DC (United States).

DOE Contract AC04-94AL85000. Order Number

DE98004702. Source: OSTI; NTIS; INIS; GPO Dep.

Sandia National Laboratories/New Mexico (SNL/NM) is a

research and development facility that generates many

highly diverse, low-volume mixed waste streams. Under the

Federal Facility Compliance Act, SNL/NM must treat its

mixed waste in storage to meet the Land Disposal Restrictions treatment standards. Since 1989, approximately 70

cubic meters (2,500 cubic feet) of heterogeneous, poorly

characterized and inventoried mixed waste was placed in

storage that could not be treated as specified in the SNL/

NM Site Treatment Plan. A process was created to sort the

legacy waste into sixteen well-defined, properly characterized, and accurately inventoried mixed waste streams

(Treatability Groups) and two low-level waste streams ready

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

for treatment or disposal. From June 1995 through September 1996, the entire volume of this stored mixed waste was

sorted and inventoried. This process was planned to meet

the technical requirements of the sorting operation and to

identify and address the hazards this operation presented.

The operations were routinely adapted to safely and efficiently handle a variety of waste matrices, hazards, and

radiological conditions. This flexibility was accomplished

through administrative and physical controls integrated into

the sorting operations. Many Department of Energy facilities

are currently facing the prospect of sorting, characterizing,

and treating a large inventory of mixed waste. The process

described in this report is a proven method for preparing a

diverse, heterogeneous mixed waste volume into segregated, characterized, inventoried, and documented waste

streams ready for treatment or disposal.

701

(SAND–98-0163C)

An Effective Waste Management Process for Segregation and Disposal of Legacy Mixed Waste at Sandia

National Laboratories/New Mexico. Hallman, Anne K.

(Sandia National Labs., Albuquerque, NM (United States));

Meyer, Dann; Rellergert, Carla A.; Schriner, Joseph A. Sandia National Labs., Albuquerque, NM (United States). [Jan

1998]. 19p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE

Contract AC04-94AL85000. (CONF-980307–: Waste management ’98, Tucson, AZ (United States), 1-5 Mar 1998).

Order Number DE98002722. Source: OSTI; NTIS; INIS;

GPO Dep.

Sandia National Laboratories/New Mexico (SNL/NM) is a

research and development facility that generates many

highly diverse, low-volume mixed waste streams. Under the

Federal Facility Compliance Act, SNL/NM must treat its

mixed waste in storage to meet the Land Disposal Restrictions treatment standards. Since 1989, approximately 70

cubic meters (2500 cubic feet) of heterogeneous, poorly

characterized and inventoried mixed waste was placed in

storage that could not be treated as specified in the SNL/

NM Site Treatment Plan. A process was created to sort the

legacy waste into sixteen well- defined, properly characterized, and precisely inventoried mixed waste streams

(Treatability Groups) and two low-level waste streams ready

for treatment or disposal. From June 1995 through September 1996, the entire volume of this stored mixed waste was

sorted and inventoried through this process. This process

was planned to meet the technical requirements of the sorting operation and to identify and address the hazards this

operation presented. The operations were routinely adapted

to safely and efficiently handle a variety of waste matrices,

hazards, and radiological conditions. This flexibility was accomplished through administrative and physical controls

integrated into the sorting operations. Many Department of

Energy facilities are currently facing the prospect of sorting,

characterizing, and treating a large inventory of mixed

waste. The process described in this paper is a proven

method for preparing a diverse, heterogeneous mixed waste

volume into segregated, characterized, inventoried, and

documented waste streams ready for treatment or disposal.

702

(SAND–98-0178C)

Physical and mechanical properties of degraded waste

surrogate material. Hansen, F.D. (Sandia National Labs.,

Carlsbad, NM (United States)); Mellegard, K.D. Sandia National Labs., Albuquerque, NM (United States). Mar 1998.

11p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC04-94AL85000. (CONF-980620–: 3. North American

Rock Mechanics Society conference, Cancun (Mexico), 3-5

Jun 1998). Order Number DE98004221. Source: OSTI;

NTIS; INIS; GPO Dep.

This paper discusses rock mechanics testing of surrogate

materials to provide failure criteria for compacted, degraded

nuclear waste. This daunting proposition was approached

by first assembling all known parameters such as the initial

waste inventory and rock mechanics response of the underground setting after the waste is stored. Conservative

assumptions allowing for extensive degradation processes

helped quantify the lowest possible strength conditions of

the future state of the waste. In the larger conceptual setting, computations involve degraded waste behavior in

transient pressure gradients as gas exits the waste horizon

into a wellbore. Therefore, a defensible evaluation of tensile

strength is paramount for successful analyses and intentionally provided maximal failed volumes. The very conservative

approach assumes rampant degradation to define waste

surrogate composition. Specimens prepared from derivative

degradation product were consolidated into simple geometries for rock mechanics testing. Tensile strength thus

derived helped convince a skeptical peer review panel that

drilling into the Waste Isolation Pilot Plant (WIPP) would not

likely expel appreciable solids via the drill string.

703

(SAND–98-0179C)

Constitutive behavior of reconsolidating crushed salt.

Callahan, G.D. (RE/SPEC, Inc., Rapid City, SD (United

States)); Mellegard, K.D.; Hansen, F.D. Sandia National

Labs., Albuquerque, NM (United States). Feb 1998. 15p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC04-94AL85000. (CONF-980620–: 3. North American

Rock Mechanics Society conference, Cancun (Mexico), 3-5

Jun 1998). Order Number DE98004224. Source: OSTI;

NTIS; INIS; GPO Dep.

The constitutive model used to describe deformation of

crushed salt is presented in this paper. Two mechanisms–

dislocation creep and grain boundary diffusional pressure

solutioning–are combined to form the basis for the constitutive model governing deformation of crushed salt. The

constitutive model is generalized to represent threedimensional states of stress. Recently completed creep

consolidation tests are combined with an existing database

that includes hydrostatic consolidation and shear consolidation tests conducted on Waste Isolation Pilot Plant (WIPP)

and southeastern New Mexico salt to determine material parameters for the constitutive model. Nonlinear least-squares

model fitting to data from shear consolidation tests and a

combination of shear and hydrostatic tests produces two

sets of material parameter values for the model. Changes in

material parameter values from test group to test group indicate the empirical nature of the model but show significant

improvement over earlier work. To demonstrate the predictive capability of the model, each parameter value set was

used to predict each of the tests in the database. Based on

fitting statistics and ability of the model to predict test data,

the model appears to capture the creep consolidation behavior of crushed salt quite well.

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

704

(SAND–98-0180/1)

Guidebook for performance assessment parameters

used in the Waste Isolation Pilot Plant compliance certification application. Volume 1: Main report. Howarth,

S.M. (Sandia National Labs., Albuquerque, NM (United

States)); Martell, M.A.; Weiner, R.; Lattier, C. Sandia National Labs., Albuquerque, NM (United States). Jun 1998.

76p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC04-94AL85000. Order Number DE98005942. Source:

OSTI; NTIS; INIS; GPO Dep.

The Waste Isolation Pilot Plant (WIPP) Compliance Certification Application (CCA) Performance Assessment (PA)

Parameter Database and its ties to supporting information

evolved over the course of two years. When the CCA was

submitted to the Environmental Protection Agency (EPA) in

October 1996, information such as identification of parameter value or distribution source was documented using

processes established by Sandia National Laboratories

WIPP Quality Assurance Procedures. Reviewers later

requested additional supporting documentation, links to supporting information, and/or clarification for many parameters.

This guidebook is designed to document a pathway through

the complex parameter process and help delineate flow

paths to supporting information for all WIPP CCA parameters. In addition, this report is an aid for understanding how

model parameters used in the WIPP CCA were developed

and qualified. To trace the source information for a particular

parameter, a dual-route system was established. The first

route uses information from the Parameter Records Package as it existed when the CCA calculations were run. The

second route leads from the EPA Parameter Database to

additional supporting information.

705

(SAND–98-0180/2)

Guidebook for performance assessment parameters

used in the Waste Isolation Pilot Plant compliance certification application. Volume 2: Appendices. Howarth,

S.M. (Sandia National Labs., Albuquerque, NM (United

States)); Martell, M.A.; Weiner, R.; Lattier, C. Sandia National Labs., Albuquerque, NM (United States). Jun 1998.

[600p.] Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC04-94AL85000. Order Number DE98005943. Source:

OSTI; NTIS; INIS; GPO Dep.

The Waste Isolation Pilot Plant (WIPP) Compliance Certification Application (CCA) Performance Assessment (PA)

Parameter Database and its ties to supporting information

evolved over the course of two years. When the CCA was

submitted to the Environmental Protection Agency (EPA) in

October 1996, information such as identification of parameter value or distribution source was documented using

processes established by Sandia National Laboratories

WIPP Quality Assurance Procedures. Reviewers later

requested additional supporting documentation, links to supporting information, and/or clarification for many parameters.

This guidebook is designed to document a pathway through

the complex parameter process and help delineate flow

paths to supporting information for all WIPP CCA parameters. In addition, this report is an aid for understanding how

model parameters used in the WIPP CCA were developed

and qualified. To trace the source information for a particular

parameter, a dual-route system was established. The first

route uses information from the Parameter Records package as it existed when the CCA calculations were run. The

second route leads from the EPA Parameter Database to

additional supporting information.

706

(SAND–98-0386C)

Representation of spatial variability for modelling of

flow and transport processes in the Culebra Dolomite at

the WIPP site. Meigs, L.C.; Beauheim, R.L. Sandia National

Labs., Albuquerque, NM (United States). 1997. 9p. Sponsored by USDOE Office of Environmental Management,

Washington, DC (United States). DOE Contract AC04-

94AL85000. (CONF-9706229–: GEOTRAP workshop, Paris

(France), 9-11 Jun 1997). Order Number DE98003377.

Source: OSTI; NTIS; INIS; GPO Dep.

The Waste Isolation Pilot Plant (WIPP) is a proposed

repository for transuranic wastes constructed in bedded

Permian-acre halite deposits in southeastern New Mexico,

USA. Site-characterization studies at the WIPP site identified groundwater flow in the Culebra Dolomite Member of

the Rustler Formation as the most likely Geologic pathway

for radio nuclide transport to the accessible environment in

the event of a breach of the WIPP repository through inadvertent human intrusion. The Culebra is a 7-m-thick, variably

fractured dolomite with massive and layers. Detailed studies

at all scales demonstrated that the Culebra is a heterogeneous medium. Heterogeneity in Culebra properties was

incorporated into numerical simulations used for data interpretation and PA calculations in different ways, depending

on the amount of data available, the certainty with which the

effects of a given approach could be evaluated, and the purpose of the study. When abundant, spatially distributed data

were available, the heterogeneity was explicitly included.

For example, a stochastic approach was used to generate

numerous, equally likely, heterogeneous transmissivity fields

conditioned on head and transmissivity data. In other cases,

constant parameter values were applied over the model domain. These constant values were selected and applied in

two different ways. In simple cases where a conservative

bounding value could be identified that would not lead to unrealistically conservative results, that value was used for all

calculations. In more complex cases, parameter distributions

were developed and single values of the parameters were

sampled from the distributions and applied across the entire

model domain for each of the PA Monte Carlo simulations.

We are currently working to refine our understanding of the

multiple rates of diffusion attributable to small-scale spatial

variability.

707

(SAND–98-0411C)

Experimental determination of the relationship between

permeability and microfracture-induced damage in bedded salt. Pfeifle, T.W. (RE/SPEC Inc., Rapid City, SD

(United States)); Brodsky, N.S.; Munson, D.E. Sandia National Labs., Albuquerque, NM (United States). Mar 1998.

12p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC04-94AL85000. (CONF-980670–: 12. international conference on computational methods in water resources,

Heraklion (Greece), 15-19 Jun 1998). Order Number

DE98004242. Source: OSTI; NTIS; INIS; GPO Dep.

The development of deep underground structures (e.g.,

shafts, mines, storage and disposal caverns) significantly

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

alters the stress state in the rock near the structure or opening. The effect of such an opening is to concentrate the

far-field stress near the free surface. For soft rock such as

salt, the concentrating effect of the opening induces deviatoric stresses in the salt that may be large enough to initiate

microcracks which then propagate with time. The volume of

rock susceptible to damage by microfracturing is often referred to as the disturbed rock zone and, by its nature, is

expected to exhibit high permeability relative to that of the

native, far-field rock. This paper presents laboratory data

that characterize microfracture-induced damage and the effect this damage has on permeability for bedded salt from

the Waste Isolation Pilot Plant located in southeastern New

Mexico. Damage is induced in the salt through a series of

tertiary creep experiments and quantified in terms of dilatant

volumetric strain. The permeability of damaged specimens

is then measured using nitrogen gas as the permeant. The

range in damage investigated included dilatant volumetric

strains from less than 0.03 percent to nearly 4.0 percent.

Permeability values corresponding to these damage levels

ranged from 1 1018 m2 to 1 1012 m2. Two simple

models were fitted to the data for use in predicting permeability from dilatant volumetric strain.

708

(SAND–98-0417C)

Permeability of natural rock salt from the Waste Isolation Pilot Plant (WIPP) during damage evolution and

healing. Pfeifle, T.W. (RE/SPEC Inc., Rapid City, SD

(United States)); Hurtado, L.D. Sandia National Labs., Albuquerque, NM (United States). Jun 1998. 12p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract AC04-94AL85000.

(CONF-980620–: 3. North American Rock Mechanics Society conference, Cancun (Mexico), 3-5 Jun 1998). Order

Number DE98002815. Source: OSTI; NTIS; INIS; GPO Dep.

The US Department of Energy has developed the Waste

Isolation Pilot Plant (WIPP) in the bedded salt of southeastern New Mexico to demonstrate the safe disposal of

radioactive transuranic wastes. Four vertical shafts provide

access to the underground workings located at a depth of

about 660 meters. These shafts connect the underground

facility to the surface and potentially provide communication

between lithologic units, so they will be sealed to limit both

the release of hazardous waste from and fluid flow into the

repository. The seal design must consider the potential for

fluid flow through a disturbed rock zone (DRZ) that develops

in the salt near the shafts. The DRZ, which forms initially

during excavation and then evolves with time, is expected to

have higher permeability than the native salt. The closure of

the shaft openings (i.e., through salt creep) will compress

the seals, thereby inducing a compressive back-stress on

the DRZ. This back-stress is expected to arrest the evolution of the DRZ, and with time will promote healing of

damage. This paper presents laboratory data from tertiary

creep and hydrostatic compression tests designed to characterize damage evolution and healing in WIPP salt.

Healing is quantified in terms of permanent reduction in permeability, and the data are used to estimate healing times

based on considerations of first-order kinetics.

709

(SAND–98-0450)

Evaluation of the capabilities of the Hanford Reservation

and Envirocare of Utah for disposal of potentially problematic mixed low-level waste streams. Waters, R.D.;

Pohl, P.I.; Cheng, W.C.; Gruebel, M.M.; Wheeler, T.A.;

Langkopf, B.S. Sandia National Labs., Albuquerque, NM

(United States). Mar 1998. 60p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States). DOE Contract AC04-94AL85000. Order Number

DE98004402. Source: OSTI; NTIS; INIS; GPO Dep.

The US Department of Energy’s (DOE) Mixed Waste Focus Area is developing a program to address and resolve

issues associated with final waste form performance in treating and disposing of DOE’s mixed low-level waste (MLLW)

inventory. A key issue for the program is identifying MLLW

streams that may be problematic for disposal. Previous reports have quantified and qualified the capabilities of fifteen

DOE sites for MLLW disposal and provided volume and radionuclide concentration estimates for treated MLLW based

on the DOE inventory. Scoping-level analyses indicated that

101 waste streams identified in this report (approximately

6,250 m3 of the estimated total treated MLLW) had radionuclide concentrations that may make their disposal

problematic. The radionuclide concentrations of these waste

streams were compared with the waste acceptance criteria

(WAC) for a DOE disposal facility at Hanford and for Envirocare’s commercial disposal facility for MLLW in Utah. Of the

treated MLLW volume identified as potentially problematic,

about 100 m3 exceeds the WAC for disposal at Hanford, and

about 4,500 m3 exceeds the WAC for disposal at Envirocare. Approximately 7% of DOE’s total MLLW inventory has

not been sufficiently characterized to identify a treatment

process for the waste and was not included in the analysis.

In addition, of the total treated MLLW volume, about 30%

was associated with waste streams that did not have radionuclide concentration data and could not be included in

the determination of potentially problematic waste streams.

710

(SAND–98-0457C)

Integration of US Department of Energy contractor installations for the purpose of optimizing treatment,

storage, and disposal of low-level radioactive waste

(LLW). Lucas, M.; Gnoose, J.; Coony, M.; Martin, E.;

Piscitella, R. Sandia National Labs., Albuquerque, NM

(United States). Feb 1998. 10p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States). DOE Contract AC04-94AL85000. (CONF-980307–:

Waste management ’98, Tucson, AZ (United States), 1-5

Mar 1998). Order Number DE98004133. Source: OSTI;

INIS; NTIS; GPO Dep.

The US Department of Energy (DOE) manages a multibillion dollar environmental management (EM) program. In

June 1996, the Assistant Secretary of Energy for EM issued

a memorandum with guidance and a vision for a ten year

planning process for the EM Program. The purpose of this

process, which became known as the Accelerated Cleanup:

Focus on 2006, is to make step changes within the DOE

complex regarding the approach for making meaningful environmental cleanup progress. To augment the process,

Assistant Secretary requested the site contractors to engage

in an effort to identify and evaluate integration alternatives

for EM waste stream treatment, storage, and disposal (TSD)

that would parallel the 2006 Plan. In October 1996, ten DOE

contractor installations began the task of identifying alternative opportunities for low level radioactive waste (LLW). Cost

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

effective, efficient solutions were necessary to meet all requirements associated with storing, characterizing, treating,

packaging, transporting, and disposing of LLW while protecting the workers’ health and safety, and minimizing impacts

to the environment. To develop these solutions, a systems

engineering approach was used to establish the baseline requirements, to develop alternatives, and to evaluate the

alternatives. Key assumptions were that unique disposal capabilities exist within the DOE that must be maintained;

private sector disposal capability for some LLW may not

continue to exist into the foreseeable future; and decisions

made by the LLW Team must be made on a system or complex wide basis to fully realize the potential cost and

schedule benefits. This integration effort promoted more accurate waste volume estimates and forecasts; enhanced

recognition of existing treatment, storage, and disposal capabilities and capacities; and improved identification of cost

savings across the complex.

711

(SAND–98-0466C)

Micromechanics and homogenization techniques for analyzing the continuum damage of rock salt. DeVries, K.L.

(RE/SPEC Inc., Rapid City, SD (United States)); Allen, D.H.;

Hurtado, L.D. Sandia National Labs., Albuquerque, NM

(United States). Mar 1998. 12p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States). DOE Contract AC04-94AL85000. (CONF-980620–:

3. North American Rock Mechanics Society conference,

Cancun (Mexico), 3-5 Jun 1998). Order Number

DE98004243. Source: OSTI; NTIS; GPO Dep.

This paper presents a model for evaluating microcrack development and dilatant behavior of crystalline rocks. The

model is developed within the concepts of continuum mechanics, with special emphasis on the development of

internal boundaries in the continuum by utilizing fracture mechanics based cohesive zone models. The model is capable

of describing the evolution from initial debonding through

complete separation and subsequent void growth of an

interface. An example problem of a rock salt specimen subjected to a high deviatoric load and low confinement is

presented that predicts preferential opening of fractures oriented parallel with the maximum compressive stress axis.

712

(SAND–98-0468C)

Assessing seal performance and parameter sensitivity

with a full-shaft model. Reeves, M. (Duke Engineering and

Services, Austin, TX (United States)); Fryar, D.G.; Statham,

W.H.; Knowles, M.K. Sandia National Labs., Albuquerque,

NM (United States). May 1998. 8p. Sponsored by USDOE

Office of Environmental Management, Washington, DC

(United States). DOE Contract AC04-94AL85000. (CONF980559–: TOUGH ’98 workshop, Berkeley, CA (United

States), 4-6 May 1998). Order Number DE98005536.

Source: OSTI; NTIS; INIS; GPO Dep.

The Waste Isolation Pilot Plant (WIPP) is a planned geologic repository for permanent disposal of transuranic waste

generated by US government defense programs. Located

near Carlsbad in southeastern New Mexico, the facility’s disposal regions are mined from the bedded salt of the Salado

Formation at a depth of approximately 652 m. Four shafts

service the operational needs of the facility for air intake, exhaust, waste handling and salt handling. These shafts range

in diameter from 3.5 to 6.1 m and extend from the ground

surface to the repository. During repository closure, following an operational life of approximately 50 years, these

shafts will be sealed in accordance with an acceptable design. Under contract to the US Department of Energy

(DOE), the Repository Isolation Systems Department (RISD)

of Sandia National Laboratories has developed a design for

the WIPP shaft sealing system. This design has been reviewed by the US Environmental Protection Agency (EPA)

as part of the 1996 WIPP Compliance Certification Application (CCA). An effective shaft sealing system for the WIPP

will limit liquid and gas flows, and permanently prevent the

migration of radiological or other hazardous constituents

through the sealed shafts from repository to accessible environment. Because of these performance objectives, a

significant effort has been directed toward evaluation of the

seal design. Whereas RISD (1996) provides a comprehensive discussion, this paper focuses on only one aspect of

the evaluation effort, namely a full shaft, fluid flow model.

713

(SAND–98-0476C)

Integration and evaluation of a position sensor with

continuous read-out for use with the Environmental

Measurement-While-Drilling Gamma Ray Spectrometer

system. Normann, R.A.; Lockwood, G.J.; Williams, C.V.;

Selph, M.M. Sandia National Labs., Albuquerque, NM

(United States). Feb 1998. 10p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States). DOE Contract AC04-94AL85000. (CONF-980418–:

North American no-dig ’98, Albuquerque, NM (United

States), 5-8 Apr 1998). Order Number DE98004136.

Source: OSTI; NTIS; INIS; GPO Dep.

The Environmental Measurement-While-Drilling-Gamma

Ray Spectrometer (EMWD-GRS) system represents an innovative blend of new and existing technology that provides

real-time environmental and drill bit data during drilling operations. The EMWD-GRS technology was demonstrated at

Savannah River Site (SRS) F-Area Retention Basin. The

EMWD-GRS technology demonstration consisted of

continuously monitoring for gamma-radiation-producing contamination while drilling two horizontal boreholes below the

backfilled waste retention basin. These boreholes passed

near previously sampled locations where concentrations of

contaminant levels of cesium had been measured. Contaminant levels continuously recorded by the EMWD-GRS

system during drilling were compared to contaminant levels

previously determined through quantitative laboratory analysis of soil samples. The results show general agreement

between the soil sampling and EMWD-GRS techniques for

Cs-137. The EMWD-GRS system has been improved by the

integration of an orientation sensor package for position

sensing (PS) (EMWD-GRS/PS). This added feature gives

the capability of calculating position, which is tied directly to

EMWD-GRS sensor data obtained while drilling. The

EMWD-GRS/PS system is described and the results of the

field tests are presented.

714

(SAND–98-0529C)

Waste reduction by separation of contaminated soils

during environmental restoration. Roybal, J.A. (Sandia

National Labs., Albuquerque, NM (United States)); Conway,

R.; Galloway, B.; Vinsant, E.; Slavin, P.; Guerin, D. Sandia

National Labs., Albuquerque, NM (United States). Jun 1998.

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

14p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC04-94AL85000. (CONF-980654–: 14. DOE pollution prevention conference, Seattle, WA (United States), 2-4 Jun

1998). Order Number DE98005532. Source: OSTI; NTIS;

INIS; GPO Dep.

During cleanup of contaminated sites, Sandia National

Laboratories, New Mexico (SNL/NM) frequently encounters

soils with low-level radioactive contamination. The contamination is not uniformly distributed, but occurs within areas of

clean soil. Because it is difficult to characterize heterogeneously contaminated soils in detail and to excavate such

soils precisely using heavy equipment, it is common for

large quantities of uncontaminated soil to be removed during excavation of contaminated sites. This practice results in

the commingling and disposal of clean and contaminated

material as low-level waste (LLW), or possibly low-level

mixed waste (LLMW). Until recently, volume reduction of radioactively contaminated soil depended on manual

screening and analysis of samples, which is a costly and

impractical approach and does not uphold As Low As Reasonably Achievable (ALARA) principles. To reduce the

amount of LLW and LLMW generated during the excavation

process, SNL/NM is evaluating two alternative technologies.

The first of these, the Segmented Gate System (SGS), is an

automated system that located and removes gamma-ray

emitting radionuclides from a host matrix (soil, sand, dry

sludge). The matrix materials is transported by a conveyor

to an analyzer/separation system, which segregates the

clean and contaminated material based on radionuclide activity level. The SGS was used to process radioactively

contaminated soil from the excavation of the Radioactive

Waste Landfill. The second technology, Large Area Gamma

Spectroscopy (LAGS), utilizes a gamma spec analyzer suspended over a slab upon which soil is spread out to a

uniform depth. A counting period of approximately 30 minutes is used to obtain a full-spectrum analysis for the

isotopes of interest. The LAGS is being tested on the soil

that is being excavated from the Classified Waste Landfill.

715

(SAND–98-1171/1)

Data and methods for the assessment of the risks associated with the maritime transport of radioactive

materials: Results of the SeaRAM program studies. Volume 1 – Main report. Sprung, J.L. (and others); Bespalko,

S.J.; Kanipe, F.L. Sandia National Labs., Albuquerque, NM

(United States). May 1998. 180p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States). DOE Contract AC04-94AL85000. (TTC–1525/1).

Order Number DE98005813. Source: OSTI; NTIS; INIS;

GPO Dep.

This report describes ship accident event trees, ship collision and ship fire frequencies, representative ships and

shipping practices, a model of ship penetration depths

during ship collisions, a ship fire spread model, cask to environment release fractions during ship collisions and fires,

and illustrative consequence calculations.

716

(SAND–98-1171/2)

Data and methods for the assessment of the risks associated with the maritime transport of radioactive

materials: Results of the SeaRAM program studies. Volume 2 – Appendices. Sprung, J.L. (and others); Bespalko,

S.J.; Kanipe, F.L. Sandia National Labs., Albuquerque, NM

(United States). May 1998. 319p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States). DOE Contract AC04-94AL85000. (TTC–1525/2).

Order Number DE98005814. Source: OSTI; NTIS; INIS;

GPO Dep.

This report describes ship accident event trees, ship collision and ship fire frequencies, representative ships and

shipping practices, a model of ship penetration depths

during ship collisions, a ship fire spread model, cask to environment release fractions during ship collisions and fires,

and illustrative consequence calculations. This report

contains the following appendices: Appendix 1 – Representative Ships and Shipping Practices; Appendix 2 – Input

Data for Minorsky Calculations; Appendix 3 – Port Ship

Speed Distribution; and Appendix 4 – Cask-to-Environment

Release Fractions.

717

(SAND–98-1192C)

Testing, expanding and implementing pollution

prevention tools for environmental restoration and decontamination and decommissioning. Roybal, J.A.

(Sandia National Lab., Albuquerque, NM (United States));

McInroy, D.; Watson, J.; Mizner, J. Sandia National Labs.,

Albuquerque, NM (United States). Jun 1998. 9p. Sponsored

by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract AC04-94AL85000.

(CONF-980654–: 14. DOE pollution prevention conference,

Seattle, WA (United States), 2-4 Jun 1998). Order Number

DE98005530. Source: OSTI; NTIS; INIS; GPO Dep.

Pollution Prevention (P2) programs and projects within the

DOE Environmental Restoration (ER) and Decontamination

and Decommissioning (D and D) Programs have been independently developed and implemented at various sites. As a

result, unique, innovative solutions used at one site may not

be known to other sites, and other sites may continue to duplicate efforts to develop and implement similar solutions.

Several DOE Program offices have funded the development

of tools to assist ER/D and D P2 projects. To realize the full

value of these tools, they need to be evaluated and publicized to field sites. To address these needs and concerns,

Sandia National Laboratory (SNL/NM), Los Alamos National

Laboratory (LANL), and the Oak Ridge Field Office (DOEOR) have teamed to pilot test DOE training and tracking

tools; transfer common P2 analyses between sites, and

evaluate and expand P2 tools and methodologies. The

project is supported by FY 98 DOE Pollution Prevention

Complex-Wide Project Funds. This paper presents the preliminary results for each of the following project modules:

Training, Waste Tracking Pilot, Information Exchange, Evaluate P2 Tools for ER/D and D, Field Test of P2 Tools; and

DOE Information Exchange.

718

(SAND–98-1193C)

Sandia bicycle commuters group – pollution prevention

at Sandia National Laboratories, New Mexico. Wrons, R.

Sandia National Labs., Albuquerque, NM (United States).

Jun 1998. 10p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE

Contract AC04-94AL85000. (CONF-980654–: 14. DOE pollution prevention conference, Seattle, WA (United States),

2-4 Jun 1998). Order Number DE98005531. Source: OSTI;

NTIS; GPO Dep.

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

The Sandia Bicycle Commuters Group (SBCG) formed

three years ago for the purpose of addressing issues that

impact the bicycle commuting option. The meeting that

launched the SBCG was scheduled in conjunction with National Bike-to-Work day in May 1995. Results from a survey

handed out at the meeting solidly confirmed the issues and

that an advocacy group was needed. The purpose statement for the Group headlines its web site and brochure:

“Existing to assist and educate the SNL workforce bicyclist

on issues regarding Kirtland Air Force Base (KAFB) access,

safety and bicycle-supporting facilities, in order to promote

bicycling as an effective and enjoyable means of commuting.” The SNL Pollution Prevention (P2) Team’s challenge to

the SNL workforce is to “prevent pollution, conserve natural

resources, and save money”. In the first winter of its existence, the SBCG sponsored a winter commute contest in

conjunction with the City’s Clean Air Campaign (CAC). The

intent of the CAC is to promote alternative (to the singleoccupant vehicle) commuting during the Winter Pollution

Advisory Period (October 1–February 28), when the City

runs the greatest risk of exceeding federal pollution limits.

719

(SAND–98-1200C)

Importance of energy efficiency in the design of the

Process and Environmental Technology Laboratory

(PETL) at Sandia National Laboratories, New Mexico

(NM). Wrons, R. Sandia National Labs., Albuquerque, NM

(United States). Jun 1998. 12p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States). DOE Contract AC04-94AL85000. (CONF-980654–:

14. DOE pollution prevention conference, Seattle, WA

(United States), 2-4 Jun 1998). Order Number DE98005533.

Source: OSTI; NTIS; GPO Dep.

As part of the design of the Process and Environmental

Technology Laboratory (PETL) in FY97, an energy conservation report (ECR) was completed. The original energy

baseline for the building, established in Title 1 design, was

595,000 BTU/sq. ft./yr, site energy use. Following the input

of several reviewers and the incorporation of the various

recommendations into the Title 2 design, the projected energy consumption was reduced to 341,000 BTU/sq. ft./yr. Of

this reduction, it is estimated that about 150,000 BTU/sq. ft./

yr resulted from inclusion of more energy efficient options

into the design. The remaining reductions resulted from better accounting of energy consumption between Title 1 ECR

and the final ECR. The energy efficient features selected by

the outcome of the ECR were: (1) Energy Recovery system,

with evaporative cooling assist, for the Exhaust/Make-up Air

System; (2) Chilled Water Thermal Storage system; (3) Premium efficiency motors for large, year-round applications;

(4) Variable frequency drives for all air handling fan motors;

(4) Premium efficiency multiple boiler system; and (5) Lighting control system. The annual energy cost savings due to

these measures will be about $165,000. The estimated annual energy savings are two million kWhrs electric, and

168,000 therms natural gas, the total of which is equivalent

to 23,000 million BTUs per year. Put into the perspective of

a typical office/light lab at SNL/NM, the annual energy savings is equal the consumption of a 125,000 square foot

building. The reduced air emissions are approximately 2,500

tons annually.

720

(SAND–98-1358C)

Field analytical technology verification: The ETV Site

Characterization Program. Einfeld, W. (Sandia National

Labs., Albuquerque, NM (United States)); Jenkins, R.A.;

Dindal, A.B. Sandia National Labs., Albuquerque, NM

(United States). Jun 1998. 15p. Sponsored by Environmental Protection Agency, Washington, DC (United

States);USDOE Office of Environmental Management,

Washington, DC (United States). DOE Contract AC05-

96OR22464. (CONF-980632–: 91. annual meeting and

exhibition of the Air and Waste Management Association,

San Diego, CA (United States), 14-19 Jun 1998). Order

Number DE98005924. Source: OSTI; NTIS; GPO Dep.

Innovative field characterization and monitoring technologies are often slow to be adopted by the environmental

engineering/consulting community because of concerns that

their performance has not been proven by an independent

testing body, and/or they have not received the EPA’s blessing on a regional or national level. The purpose of the EPA

Environmental Technology Verification (ETV) Site Characterization Pilot, a joint effort between EPA and DOE, is to

accelerate the acceptance of technologies that reduce the

cost and increase the speed of environmental clean-up and

monitoring. Technology verifications that have been completed or are underway include: in situ technologies for the

characterization of sub-surface hydrocarbon plumes, fieldportable GC/MS systems, field-portable X-ray fluorescence

analyzers, soil sampling technologies, field-portable PCB

analyzers, analyzers for VOC analysis at the wellhead, and

decision support software systems to aid site sample collection and contaminant plume definition. The verification

process follows a somewhat generic pathway. A usercommunity need is identified, the vendor community is

canvassed, and relevant, interested companies are selected. A demonstration plan is prepared by the verification

organization and circulated to participants prior to the field

activities. Field trials are normally held at two geologically or

environmentally different sites and typically require one

week at each site. Samples (soil, soil gas, water, surface

wipe etc.) provided to the vendor at the demonstration include site-specific samples and standards or performance

evaluation samples. Sample splits are sent to a pre-selected

laboratory for analysis using a reference method. Laboratory

data are used for comparison with field technology results

during the data analysis phase of the demonstration.

721

(SAND–98-1719)

Development of the SEAtrace barrier verification and

validation technology. Final report. Dunn, S.D. (Science

and Engineering Associates, Santa Fe, NM (United States));

Lowry, W.; Walsh, R.; Rao, D.V.; Williams, C. Sandia National Labs., Albuquerque, NM (United States). Aug 1998.

129p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC04-94AL85000. Order Number DE99000462. Source:

OSTI; NTIS; INIS; GPO Dep.

In-situ barrier emplacement techniques and materials for

the containment of high-risk contaminants in soils are currently being developed by the Department of Energy (DOE).

Because of their relatively high cost, the barriers are intended to be used in cases where the risk is too great to

remove the contaminants, the contaminants are too difficult

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

to remove with current technologies, or the potential movement of the contaminants to the water table is so high that

immediate action needs to be taken to reduce health risks.

Assessing the integrity of the barrier once it is emplaced, and

during its anticipated life, is a very difficult but necessary requirement. Science and Engineering Associates, Inc., (SEA)

and Sandia National Laboratories (SNL) have developed a

quantitative subsurface barrier assessment system using

gaseous tracers in support of the Subsurface Contaminants

Focus Area barrier technology program. Called SEAtrace,

this system integrates an autonomous, multi-point soil vapor

sampling and analysis system with a global optimization

modeling methodology to locate and size barrier breaches in

real time. The methodology for the global optimization code

was completed and a prototype code written using simplifying assumptions. Preliminary modeling work to validate the

code assumptions were performed using the T2VOC numerical code. A multi-point field sampling system was built to

take soil gas samples and analyze for tracer gas concentration. The tracer concentration histories were used in the

global optimization code to locate and size barrier breaches.

SEAtrace was consistently able to detect and locate leaks,

even under very adverse conditions. The system was able

to locate the leak to within 0.75 m of the actual value, and

was able to determine the size of the leak to within 0.15 m.

722

(SAND–98-1720)

Project report: Tritiated oil repackaging highlighting the

ISMS process. Historical radioactive and mixed waste

disposal request validation and waste disposal project.

Schriner, J.A. (Automated Solutions of Albuquerque, Inc.,

NM (United States)). Sandia National Labs., Albuquerque,

NM (United States);Automated Solutions of Albuquerque,

Inc., NM (United States). Aug 1998. 16p. Sponsored by USDOE Office of Environmental Management, Washington, DC

(United States). DOE Contract AC04-94AL85000. Order

Number DE98006274. Source: OSTI; NTIS; INIS; GPO Dep.

The Integrated Safety Management System (ISMS) was

established to define a framework for the essential functions

of managing work safely. There are five Safety Management

Functions in the model of the ISMS process: (1) work planning, (2) hazards analysis, (3) hazards control, (4) work

performance, and (5) feedback and improve. Recent activities at the Radioactive and Mixed Waste Management

Facility underscored the importance and effectiveness of integrating the ISMS process to safely manage high-hazard

work with a minimum of personnel in a timely and efficient

manner. This report describes how project personnel followed the framework of the ISMS process to successfully

repackage tritium-contaminated oils. The main objective was

to open the boxes without allowing the gaseous tritium oxide, which had built up inside the boxes, to release into the

sorting room. The boxes would be vented out the building

stack until tritium concentration levels were acceptable. The

carboys would be repackaged into 30-gallon drums and

caulked shut. Sealing the drums would decrease the tritium

off-gassing into the RMWMF.

723

(UCRL-ID–129837)

Destruction of 2,2’,3 - trichlorobiphenyl in aqueous solution by hydrous pyrolysis/oxidation (HPO). Leif, R.N.;

Knauss, K.G.; Mew, D.A.; Aines, R.D. Lawrence Livermore

National Lab., CA (United States). 25 Nov 1997. 21p. Sponsored by USDOE Office of Environmental Management,

Washington, DC (United States). DOE Contract W-7405-

ENG-48. Order Number DE98058335. Source: OSTI; NTIS;

INIS; GPO Dep.

Aqueous, low-temperature oxidation rates for the polychlorinated biphenyl (PCB) congener 2,2’,3-trichlorobiphenyl

have been measured in aqueous phosphate-buffered solutions using Dickson-type reaction vessels. Concentrations of

the target compounds were determined by gas chromatography and compound identification was verified by gas

chromatography - mass spectrometry. The reaction temperatures ranged from 131 C to 165C and the activation

energy for the destruction of 2,2’,3-trichlorobiphenyl was

estimated to be 134 kJ/mole. In a low concentration experiment (approximately 500 ng/g starting concentration),

2,2’,3-trichlorobiphenyl concentration reached non-detect in

two days at 135C. In a much higher concentration experiment (approximately 24,000 mg/g initial loading), nearly

40% of the initial 2,2’,3-trichlorobiphenyl concentration, or

about 10,000 ng/g was destroyed at 161C in 18 days. The

2,2’, 3-trichlorobiphenyl concentration of 24,000 ng/g measured at 131C represents a greater than 100 fold increase

in the aqueous solubility compared to the value of 200 ng/g

at 20C reported by Mackay et al. During the experiments

the reacted portion of the 2,2’, 3-trichlorobiphenyl was

completely mineralized, as indicated by a stoichiometric production of inorganic carbon and chloride ion, and no

intermediates amenable to gas chromatography were observed during the HPO experiments. These preliminary

experiments indicate that hydrous pyrolysis/oxidation (HPO)

may be a useful alternative method for remediating soil and

groundwater contaminated with PCBs.

724

(UCRL-JC–130449)

Alternate airborne release fraction determination for

hazardous waste management storage repository hazard categorization at the Lawrence Livermore National

Laboratory. Brumburgh, G.P. Lawrence Livermore National

Lab., CA (United States). 1 May 1998. 13p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract W-7405-ENG-48.

(CONF-980616–: Conference on integrating safety analysis

into safety management, Park City, UT (United States), 15-

19 Jun 1998). Order Number DE98054783. Source: OSTI;

NTIS; INIS; GPO Dep.

Hazardous Waste Management (HWM) facilities are used

in the handling and processing of solid and liquid radioactive, hazardous, mixed, and medical wastes generated at

Lawrence Livermore National Laboratory (LLNL). Waste

may be treated or stored in one of the HWM facility units

prior to shipment off site for treatment or disposal. Planned

facilities such as the Decontamination and Waste Treatment

Facility (DWTF) and the Building 280 Container Storage Unit

are expected to handle similar waste streams. A hazard

classification was preformed in each facility safety analysis

report (SAR) according to the DOE Standard 1027-92 ’Hazard Categorization and Accident Analysis Techniques for

Compliance with DOE Order 5480.23, Nuclear Safety Analysis Reports.’ The general methodology practiced by HWM to

determine alternate airborne release fractions (ARFs) in

those SARs was based upon a beyond evaluation basis

earthquake accident scenario characterized by the release

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

of the largest amount of respirable, airborne radioactive material. The alternate ARF was calculated using a three-factor

formula consisting of the fraction of failed waste containers,

fraction of material released from failed waste

containers,and the fraction of material entrained to the environment. Recently, in deliberation with DOE-Oakland

representatives, HWM decided to modify this methodology.

In place of the current detailed analysis, a more straightforward process was proposed based upon material form,

credible accident environments, and empirical data. This paper will discuss the methodology and derivation of ARFs

specific to HWM treatment and storage facilities that are alternative to those presented in DOE-STD-1027-92.

725

(UCRL-JC–131027)

Isotope hydrology of catchment basins: lithogenic and

cosmogenic isotopic systems. Nimz, G. J., LLNL.

Lawrence Livermore National Lab., CA (United States). 1

Jun 1998. 48p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE

Contract W-7405-ENG-48. (CONF-980736–: Environmental

management science program workshop, Chicago, IL

(United States), 27-30 Jul 1998). Order Number

DE98058641. Source: OSTI; NTIS; GPO Dep.

A variety of physical processes affect solute concentrations within catchment waters. The isotopic compositions of

the solutes can indicate which processes have determined

the observed concentrations. These processes together

constitute the physical history of the water. Many solutes in

natural waters are derived from the interaction between the

water and the rock and/or soil within the system - these are

termed ’lithogenic’ solutes. The isotopic compositions of

these solutes provide information regarding rock-water interactions. Many other solutes have their isotopic compositions

determined both within and outside of the catchment - i.e., in

addition to being derived from catchment rock and soil, they

are solutes that are also transported into the catchment. Important members of this group include solutes that have

isotopic compositions produced by atomic particle interactions with other nuclides. The source of the atomic particles

can be cosmic radiation (producing ’cosmogenic’ nuclides in

the atmosphere and land surface), anthropogenic nuclear reactions (producing ’thermonuclear’ nuclides), or radioactive

and fission decay of naturally-occurring elements, principally

238U (producing ’in-situ’ lithogenic nuclides in the deep subsurface). Current language usage often combines all of the

atomic particle-produced nuclides under the heading ’cosmogenic nuclides’, and for simplicity we will often follow that

usage here, although always indicating which variety is being discussed. This paper addresses the processes that

affect the lithogenic and cosmogenic solute concentrations

in catchment waters, and how the isotopic compositions of

the solutes can be used in integrative ways to identify these

processes, thereby revealing the physical history of the water within a catchment system. The concept of a ’system’ is

important in catchment hydrology. (Abstract truncated)

726

(USGS–97-4025)

Estimated ground-water discharge by evapotranspiration, Ash Meadows Area, Nye County, Nevada, 1994.

Nichols, W.D.; Laczniak, R.J.; DeMeo, G.A.; Rapp, T.R. Geological Survey, Carson City, NV (United States). 1997. 20p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AI08-91NV11040. Order Number DE97005308. Source:

OSTI; NTIS; U.S. Geological Survey, Branch of Information

Services, Box 25286, Denver, CO 80225-0286 (United

States); GPO Dep.

Ground water discharges from the regional ground-water

flow system that underlies the eastern part of the Nevada

Test Site through numerous springs and seeps in the Ash

Meadows National Wildlife Refuge in southern Nevada. The

total spring discharge was estimated to be about 17,000

acre-feet per year by earlier studies. Previous studies estimated that about 10,500 acre-feet of this discharge was lost

to evapotranspiration. The present study was undertaken to

develop a more rigorous approach to estimating groundwater discharge in the Ash Meadows area. Part of the study

involves detailed field investigation of evapotranspiration.

Data collection began in early 1994. The results of the first

year of study provide a basis for making preliminary estimates of ground-water discharge by evapotranspiration. An

estimated 13,100 acre-feet of ground water was evapotranspired from about 6,800 acres of marsh and salt-grass.

Additional 3,500 acre-feet may have been transpired from

the open water and from about 1,460 acres of other areas of

Ash Meadows in which field studies have not yet been made.

727

(USGS/OFR–97-476)

Geophysical interpretations west of and within the

northwestern part of the Nevada Test Site. Grauch, V.J.;

Sawyer, D.A.; Fridrich, C.J.; Hudson, M.R. Geological Survey, Denver, CO (United States). 1997. 57p. Sponsored by

Geological Survey, Reston, VA (United States);Department

of the Interior, Washington, DC (United States);USDOE Office of Environmental Management, Washington, DC (United

States). DOE Contract AI08-96NV11967. Order Number

DE98003404. Source: OSTI; NTIS; INIS; GPO Dep.

This report focuses on interpretation of gravity and new

magnetic data west of the Nevada Test Site (NTS) and

within the northwestern part of NTS. The interpretations

integrate the gravity and magnetic data with other geophysical, geological, and rock property data to put constraints on

tectonic and magmatic features not exposed at the surface.

West of NTS, where drill hole information is absent, these

geophysical data provide the best available information on

the subsurface. Interpreted subsurface features include

calderas, intrusions, basalt flows and volcanoes, Tertiary

basins, structurally high pre-Tertiary rocks, and fault zones.

New features revealed by this study include (1) a northsouth buried tectonic fault east of Oasis Mountain, which the

authors call the Hogback fault; (2) an east striking fault or

accommodation zone along the south side of Oasis Valley

basin, which they call the Hot Springs fault; (3) a NNE striking structural zone coinciding with the western margins of the

caldera complexes; (4) regional magnetic highs that probably represent a thick sequence of Tertiary volcanic rocks;

and (5) two probable buried calderas that may be related to

the tuffs of Tolicha Peak and of Sleeping Butte, respectively.

728

(WSRC-MS–96-0323)

Remote telerobotic replacement for master-slave manipulator. Heckendorn, F.M. (Westinghouse Savannah River

Company, Aiken, SC (United States)); Iverson, D.C.;

LaValle, D.R. Westinghouse Savannah River Co., Aiken, SC

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

(United States). 1997. 14p. Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract AC09-89SR18035. (CONF-970464–

15: 7. American Nuclear Society topical meeting on robotics

and remote systems, Augusta, GA (United States), 27 Apr -

1 May 1997). Order Number DE97004962. Source: OSTI;

NTIS; INIS; GPO Dep.

A remotely replaceable telerobotic manipulator (TRM) has

been developed and deployed at the Defense Waste

Processing Facility (DWPF) in support of its radioactive operation. The TRM replaces a Master-Slave Manipulator

(MSM). The TRM is in use for both routine and recovery operations for the radioactive waste vitrification melter, the

primary production device within the DWPF. The arm was

designed for deployment and operation using an existing

MSM penetration. This replacement of an existing MSM with

a high power robotic device demonstrates the capability to

perform similar replacement in other operating facilities. The

MSM’s were originally deployed in the DWPF to perform

routine light capacity tasks. During the testing phase of the

DWPF, prior to its radioactive startup in 5/96, the need to remove glass deposits that can form at the melter discharge

during filling of glass containment canisters was identified.

The combination of high radiation and contamination in the

DWPF melter cell during radioactive operation eliminated

personnel entry as a recovery option. Therefore remote

cleaning methods had to be devised. The MSM’s had neither

the reach nor the strength required for this task. It became

apparent that a robust manipulator arm would be required

for recovery from these potential melter discharge pluggage

events. The existing wall penetrations, used for the MSM’s,

could not be altered for seismic and radiological reasons.

The new manipulator was required to be of considerable

reach, due to existing physical layout, and strength, due to

the glass removal requirement. Additionally, the device

would have to compatible with high radiation and remote

crane installation. The physical size of the manipulator and

the weight of components must be consistent with the existing facilities. It was recognized early-on that a manipulator of

sufficient strength to recover from a pluggage event would

require robotic functions to constrain undesirable motions.

729

(WSRC-MS–96-0333)

The application of metal cutting technologies in tasks

performed in radioactive environments. Fogle, R.F.;

Younkins, R.M. Westinghouse Savannah River Co., Aiken,

SC (United States). [1997]. 11p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States). DOE Contract AC09-89SR18035. (CONF-9704105–

1: 7. Americal Nuclear Society (ANS) topical meeting on

robotics and remote systems, Agusta, GA (United States),

27 Apr - 1 May 1997). Order Number DE97060070. Source:

OSTI; NTIS; INIS; GPO Dep.

The design and use of equipment to perform work in radioactive environments is uniquely challenging. Some tasks

require that the equipment be operated by a person wearing

a plastic suit or full face respirator and donning several pairs

of rubber gloves. Other applications may require that the

equipment be remotely controlled. Other important, design

considerations include material compatibility, mixed waste

issues, tolerance to ionizing radiation, size constraints and

weight capacities. As always, there is the “We need it

ASAP” design criteria. This paper describes four applications where different types of metal cutting technologies

were used to successfully perform tasks in radioactive environments. The technologies include a plasma cutting torch,

a grinder with an abrasive disk, a hydraulic shear, and a

high pressure abrasive water jet cutter.

730

(WSRC-MS–96-0524)

Cross flow filtration of aqueous radioactive tank wastes.

McCabe, D.J. (Westinghouse Savannah River Co., Aiken,

SC (United States)); Reynolds, B.A.; Todd, T.A.; Wilson,

J.H. Oak Ridge National Lab., TN (United States). [1997].

6p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC05-96OR22464. (CONF-970321–1: National spring

meeting and petrochemical exposition of the American Institute of Chemical Engineers (AIChE) and 2. plant operations

and design conference, Houston, TX (United States), 10-13

Mar 1997). Order Number DE97003104. Source: OSTI;

NTIS; INIS; GPO Dep.

The Tank Focus Area (TFA) of the Department of Energy

(DOE) Office of Science and Technology addresses remediation of radioactive waste currently stored in underground

tanks. Baseline technologies for treatment of tank waste can

be categorized into three types of solid liquid separation: (a)

removal of radioactive species that have been absorbed or

precipitated, (b) pretreatment, and (c) volume reduction of

sludge and wash water. Solids formed from precipitation or

absorption of radioactive ions require separation from the

liquid phase to permit treatment of the liquid as Low Level

Waste. This basic process is used for decontamination of

tank waste at the Savannah River Site (SRS). Ion exchange

of radioactive ions has been proposed for other tank wastes,

requiring removal of insoluble solids to prevent bed fouling

and downstream contamination. Additionally, volume reduction of washed sludge solids would reduce the tank space

required for interim storage of High Level Wastes. The

scope of this multi-site task is to evaluate the solid/liquid

separations needed to permit treatment of tank wastes to

accomplish these goals. Testing has emphasized cross now

filtration with metal filters to pretreat tank wastes, due to tolerance of radiation and caustic.

731

(WSRC-MS–96-0670)

Coupon corrosion monitoring of a high level waste tank.

Mickalonis, J.I. Westinghouse Savannah River Co., Aiken,

SC (United States). [1997]. 12p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States). DOE Contract AC09-89SR18035. (CONF-970332–

2: Corrosion 97. 52. annual corrosion conference of the

National Association of Corrosion Engineers: economics

and performance - bridging the gap and NACExpo, New Orleans, LA (United States), 9-14 Mar 1997). Order Number

DE97060048. Source: OSTI; NTIS; INIS; GPO Dep.

Radioactive nuclear waste, which was generated during

the production of nuclear fuel, is safely stored in contained

underground tanks and is being processed for long-term

storage. A coupon corrosion rig (CCR) for monitoring was

designed and used in a preliminary trial on a tank containing

diluted low-level radioactive waste. Welded and standard flat

coupons were exposed for ten months. The coupons were

exposed in both the liquid waste and the air space above

the waste. The evaluation consisted of visual examination

and weight loss and pit depth measurements. Corrosion

degradation was not significant for coupons in the waste.

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

The corrosion in the air space was characterized by

variable-depth degradation under adherent corrosion products. The coupon areas exposed at the air-waste interface

had pits; the deepest measuring 6 mils. These results are

consistent with those from previous laboratory coupon tests

in simulated waste

732

(WSRC-MS–96-0743)

Automation in a material processing/storage facility. Peterson, K.; Gordon, J. Westinghouse Savannah River Co.,

Aiken, SC (United States). 1997. 8p. Sponsored by USDOE

Office of Environmental Management, Washington, DC

(United States). DOE Contract AC09-89SR18035. (CONF970464–16: 7. American Nuclear Society topical meeting on

robotics and remote systems, Augusta, GA (United States),

27 Apr - 1 May 1997). Order Number DE97004957. Source:

OSTI; NTIS; INIS; GPO Dep.

The Savannah River Site (SRS) is currently developing a

new facility, the Actinide Packaging and Storage Facility

(APSF), to process and store legacy materials from the

United States nuclear stockpile. A variety of materials, with

a variety of properties, packaging and handling/storage requirements, will be processed and stored at the facility.

Since these materials are hazardous and radioactive, automation will be used to minimize worker exposure. Other

benefits derived from automation of the facility include increased throughput capacity and enhanced security. The

diversity of materials and packaging geometries to be handled poses challenges to the automation of facility

processes. In addition, the nature of the materials to be processed underscores the need for safety, reliability and

serviceability. The application of automation in this facility

must, therefore, be accomplished in a rational and disciplined manner to satisfy the strict operational requirements

of the facility. Among the functions to be automated are the

transport of containers between process and storage areas

via an Automatic Guided Vehicle (AGV), and various processes in the Shipping Package Unpackaging (SPU) area,

the Accountability Measurements (AM) area, the Special

Isotope Storage (SIS) vault and the Special Nuclear Materials (SNM) vault. Other areas of the facility are also being

automated, but are outside the scope of this paper.

733

(WSRC-MS–97-0023)

Hydrological methods preferentially recover cesium

from nuclear waste salt cake. Brooke, J.N.; Hamm, L.L.

Westinghouse Savannah River Co., Aiken, SC (United

States). 1997. 7p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE

Contract AC09-96SR18500. (CONF-970607–17: ARS ’97:

American Nuclear Society (ANS) international meeting on

advanced reactors safety, Orlando, FL (United States), 1-5

Jun 1997). Order Number DE97004879. Source: OSTI;

NTIS; INIS; GPO Dep.

The Savannah River Site is treating high level radioactive

waste in the form of insoluble solids (sludge), crystallized

salt (salt cake), and salt solutions. High costs and operational concerns have prompted DOE to look for ways to

improve the salt cake treatment process. A numerical model

was developed to evaluate the feasibility of pump and treat

technology for extracting cesium from salt cake. A modified

version of the VAM3DCG code was used to first establish a

steady-state flow field, then to simulate 30 days of operation. Simulation results suggest that efficient cesium

extraction can be obtained with low displacement volumes.

The actual extraction process will probably be less impressive because of nonuniform properties. 2 refs., 2 figs.

734

(WSRC-MS–97-00041)

Glass formulation development and testing for the vitrification of cesium-loaded crystalline silicotitanate

(CST). Andrews, M.K. Westinghouse Savannah River Co.,

Aiken, SC (United States). 1997. 8p. Sponsored by USDOE

Office of Environmental Management, Washington, DC

(United States). DOE Contract AC09-89SR18035. (CONF970677–: 90. annual meeting and exhibition of the Air and

Waste Management Association, Toronto (Canada), 8-13

Jun 1997). Order Number DE98003418. Source: OSTI;

NTIS; INIS; GPO Dep.

Crystalline Silicotitanate (CST) is an inorganic ion exchange medium that was designed to sorb Cs-137, Sr-90

and several other radionuclides. CST exhibits high selectivity for the ion exchange of cesium from highly alkaline

solutions containing large quantities of sodium. Through the

Tanks Focus Area (TFA), Oak Ridge National Laboratory

(ORNL) was funded to demonstrate the effectiveness of

CST as an ion exchange material using supernate from the

Melton Valley Storage Tanks (MVST). After processing the

supernate through columns containing CST, the CST will be

sluiced into drums and dewatered. Some of the CST will be

shipped to the Savannah River Technology Center (SRTC)

to demonstrate vitrification of the cesium-loaded CST in the

shielded cells facility of SRTC. Vitrification is considered to

be the Best Demonstrated Available Technology for immobilization of high-level waste and is currently being

investigated for the treatment of low-level/mixed wastes. Vitrification of cesium-loaded CST offers a number of benefits.

Vitrification: (1) is less expensive than many of the technologies available; (2) offers a large volume reduction; (3)

produces a waste form that is very durable; (4) is an established technology; (5) can be used for a wide variety of

waste streams; and (6) produces a waste form that is resistant to radiation damage. Prior to a full-scale demonstration,

a glass formulation that will produce a glass that is both processable and durable must be developed. Crucible studies

using unloaded CST and reagent grade glass-forming

chemicals (or frit) were performed. Initially, scoping studies

were performed to determine the chemicals necessary to

form a glass. A screening experiment was then performed to

determine the quantity of chemicals required. Finally, tests

were conducted to determine the waste loading to be used

during processing in the melter.

735

(WSRC-MS–97-0048)

Counter current decantation washing of HLW sludge.

Brooke, J.N.; Peterson, R.A. Westinghouse Savannah River

Co., Aiken, SC (United States). 1997. 15p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract AC09-96SR18500.

(CONF-970321–7: National spring meeting and petrochemical exposition of the American Institute of Chemical

Engineers (AIChE) and 2. plant operations and design conference, Houston, TX (United States), 10-13 Mar 1997).

Order Number DE97004881. Source: OSTI; NTIS; INIS;

GPO Dep.

188
Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

The Savannah River Site (SRS) has 51 High Level Waste

(HLW) tanks with typical dimensions 25.9 meters (85 feet)

diameter and 10 meters (33 feet) high. Nearly 114 million

liters (30 M gallons) of HLW waste is stored in these tanks

in the form of insoluble solids called sludge, crystallized salt

called salt cake, and salt solutions. This waste is being converted to waste forms stable for long term storage. In one of

the processes, soluble salts are washed from HLW sludge in

preparation for vitrification. At present, sludge is batch

washed in a waste tank with one or no reuse of the wash

water. Sodium hydroxide and sodium nitrite are added to the

wash water for tank corrosion protection; the large volumes

of spent wash water are recycled to the evaporator system;

additional salt cake is produced; and sodium carbonate is

formed in the washed sludge during storage by reaction with

CO2 from the air. High costs and operational concerns with

the current washing process prompts DOE and WSRC to

seek an improved washing method. A new method should

take full advantage of the physical/chemical properties of

sludge, experience from other technical disciplines, processing rate requirements, inherent process safety, and use of

proven processes and equipment. Counter current solids

washing is a common process in the minerals processing

and chemical industries. Washing circuits can be designed

using thickeners, filters or centrifuges. Realizing the special

needs of nuclear work and the low processing rates required, a Counter Current Decantation (CCD) circuit is

proposed using small thickeners and fluidic pumps.

736

(WSRC-MS–97-00050)

Compliance with the Nevada Test Site’s waste acceptance criteria for vitrified cesium-loaded crystalline

silicotitanate (CST). Harbour, J.R.; Andrews, M.K. Westinghouse Savannah River Co., Aiken, SC (United States).

1997. 10p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract AC09-89SR18035. (CONF-970677–: 90. annual

meeting and exhibition of the Air and Waste Management

Association, Toronto (Canada), 8-13 Jun 1997). Order Number DE98003419. Source: OSTI; NTIS; INIS; GPO Dep.

Oak Ridge National Laboratory (ORNL) and Savannah

River Technology Center (SRTC) are involved in a joint

project for immobilization of radionuclides from the Melton

Valley Storage Tanks (MVST) at Oak Ridge (OR). The supernate from Tank W-29 of the MVST will be treated by

passage through a crystalline silicotitanate (CST) ion exchange medium. The CST was designed to sorb cesium,

the primary radio nuclide (Cs-137) in the supernate of

MVST’s. A smaller amount of strontium (Sr-90) will also be

sorbed. This demonstration will be performed by ORNL.

One column volume of cesium-loaded CST (10 gallons or

38 liters) will then be shipped to SRTC where it will be

mixed with glass formers and fed as an aqueous slurry to a

joule-heated melter within the SRTC Shielded Cells. A

borosilicate glass formulation which will incorporate the CST

has been developed as part oft SRTC’s role in this project.

The molten glass (1150C) will be poured into 500 ml

stainless steel beakers which in turn will be placed in 30 gallon drums for disposal. An import&f part of this project is to

demonstrate that the glass waste form produced will meet

the Waste Acceptance Criteria (WAC) for disposal at the

Nevada Test Site (NTS). If vitrification of the cesium-loaded

CST is implemented as the immobilization method for all of

the MVST supernate, then it is essential to demonstrate that

the waste can be disposed of at an acceptable disposal facility. NTS accepts low-level radioactive waste as long as it

is not TRU and not hazardous. This paper documents the

efforts in the development stage of this work to integrate the

requirements of NTS into the formulation and processing

efforts. This work is funded by the Tank Focus Area with additional funding for ORNL provided by EM-30 at OR.

737

(WSRC-MS–97-0214)

Joint EPA/DOE demonstration program for total mercury continuous emissions monitors. Burns, D.B.

(Westinghouse Savannah River Company, Aiken, SC

(United States). Savannah River Technology Center);

Rauenzahn, H.S.; Stevens, F.M. Westinghouse Savannah

River Co., Aiken, SC (United States). 1997. 16p. Sponsored

by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract AC09-96SR18500.

(CONF-970677–13: 90. annual meeting and exhibition of

the Air and Waste Management Association, Toronto

(Canada), 8-13 Jun 1997). Order Number DE97060158.

Source: OSTI; NTIS; INIS; GPO Dep.

Continuous emissions monitoring of mercury from hazardous waste thermal treatment processes is desired for

verification of emission compliance, process control, and

public safety perception. Continuous real-time monitoring of

mercury would permit actual measurement of mercury emissions and permit measurement of real-time (actual) mercury

emissions and allow accurate (realistic) human risk assessment from hazardous thermal treatment facility operation.

The U.S. Environmental Protection Agency (EPA) has proposed regulations that require the use of total mercury

continuous emissions monitors (CEMs) on incinerators, boilers, and industrial furnaces that burn hazardous waste.

These proposed regulations also include draft performance

specifications for mercury CEMs. This paper describes an

ongoing joint EPA/DOE program to identify and demonstrate

commercially available mercury CEMs that can meet the

proposed EPA performance specification and includes initial

instrument test results obtained. The complete demonstration consists of a six month performance test of several

commercially available total mercury CEMs at a commercial

cement kiln that co-fires hazardous waste. During the performance test, several indicators of CEM performance will

be evaluated (as required in the proposed performance

specification), including; zero and calibration drift, relative

accuracy through comparison to EPA manual Reference

Methods, calibration error through testing with calibration

standards, and specific interference tests. The results of this

extensive test program will be used to either confirm availability of mercury CEMs that meet the requirements in the

proposed EPA performance specification, provide the necessary data for revision of the proposed mercury CEM

performance specification, or reveal the need for further instrument development prior to deployment.

738

(WSRC-MS–97-0217)

Air pollution control system testing at the DOE offgas

components test facility. Burns, D.B.; Speed, D.; VanPelt,

W.; Burns, H.H. Westinghouse Savannah River Co., Aiken,

SC (United States). 1997. 12p. Sponsored by USDOE Office

of Environmental Management, Washington, DC (United

States). DOE Contract AC09-96SR18500. (CONF-970562–

4: International conference on incineration and thermal

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

treatment technologies, Oakland, CA (United States), 12-16

May 1997). Order Number DE97060159. Source: OSTI;

NTIS; INIS; GPO Dep.

In 1997, the Department of Energy (DOE) Savannah River

Site (SRS) plans to begin operation of the Consolidated

Incineration Facility (CIF) to treat solid and liquid RCRA hazardous and mixed wastes. The Savannah River Technology

Center (SRTC) leads an extensive technical support program designed to obtain incinerator and air pollution control

equipment performance data to support facility start-up and

operation. A key component of this technical support program includes the Offgas Components Test Facility (OCTF),

a pilot-scale offgas system test bed. The primary goal for this

test facility is to demonstrate and evaluate the performance

of the planned CIF Air Pollution Control System (APCS). To

accomplish this task, the OCTF has been equipped with a 1/

10 scale CIF offgas system equipment components and instrumentation. In addition, the OCTF design maximizes the

flexibility of APCS operation and facility instrumentation and

sampling capabilities permit accurate characterization of all

process streams throughout the facility. This allows APCS

equipment performance to be evaluated in an integrated

system under a wide range of possible operating conditions.

This paper summarizes the use of this DOE test facility to

successfully demonstrate APCS operability and maintainability, evaluate and optimize equipment and instrument

performance, and provide direct CIF start-up support. These

types of facilities are needed to permit resolution of technical issues associated with design and operation of systems

that treat and dispose combustible hazardous, mixed, and

low-level radioactive waste throughout and DOE complex.

739

(WSRC-MS–97-0220)

Investigation of water accumulation in an offgas test facility HEPA housing. Speed, D.L.; Burns, D.B.; Van Pelt,

W.B.; Burns, H.H. Westinghouse Savannah River Co.,

Aiken, SC (United States). 1997. 14p. Sponsored by USDOE Office of Environmental Management, Washington, DC

(United States). DOE Contract AC09-96SR18500. (CONF970562–4: International conference on incineration and

thermal treatment technologies, Oakland, CA (United

States), 12-16 May 1997). Order Number DE97060161.

Source: OSTI; NTIS; INIS; GPO Dep.

The Consolidated Incineration Facility, at the Department

of Energy’s Savannah River Site, is designed to treat solid

and liquid RCRA hazardous and mixed wastes generated by

site operations and clean-up activities. During CIF’s pretrial

burn campaigns in 1995, an appreciable amount of water

was recovered from the HEPA housings. Questions were

immediately raised as to the source of the water, and the

degree of wetness of the filters during operation. There are

two primary issues involved: Water could reduce the life expectancy and performance of the HEPA filters, housing, and

associated ducting, and wet HEPAs also present radiological concerns for personnel during filter change-out. A similar

phenomenon was noted at the Offgas Components Test Facility (OCTF), a 1/10 scale pilot of CIF’s air pollution control

system. Tests at OCTF indicated the water’s most likely origin to be vapor condensing out from the flue gas stream due

to excessive air in-leakage at housing door seals, ducting

flanges, and actual holes in the ducting. The rate of accumulation bears no statistical correlation to such process

parameters as steam flow, reheater outlet temperature and

offgas velocity in the duct. Test results also indicated that

the HEPA filter media is moistened by the initial process

flow while the facility is being brought on line. However,

even when the HEPA filters were manually drenched prior to

startup, they became completely dry within four hours of the

time steam was introduced to the reheater. Finally, no

demonstrable relationship was found between the degree of

filter media wetness and filter dP.

740

(WSRC-MS–97-0404)

Chemical inventory control program for mixed and hazardous waste facilities at SRS. Ades, M.J.; Vincent, A.M.

III. Westinghouse Savannah River Co., Aiken, SC (United

States). 1997. 9p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE

Contract AC09-96SR18500. (CONF-970661–4: 1997 safety

analysis workshop, Oakland, CA (United States), 9-13 Jun

1997). Order Number DE97060187. Source: INIS; OSTI;

NTIS; INIS; GPO Dep.

Mixed Waste (MW) and Hazardous Waste (HW) are being

stored at the Savannah River Site (SRS) pending onsite

and/or offsite treatment and disposal. The inventory control

for these wastes has recently been brought under Technical

Safety Requirements (TSR) in accordance with DOE Order

5480.22. With the TSRs was the question of the degree of

rigor with which the inventory is to be tracked, considering

that the variety of chemicals present, or that could be

present, numbers in the hundreds. This paper describes the

graded approach program to track Solid Waste (SW) inventories relative to TSRs. The approach uses a ratio of the

maximum anticipated chemical inventory to the permissible

inventory in accordance with Emergency Response Planning Guideline (ERPG) limits for on- and off-site receptors.

A specific threshold ratio can then be determined. The

chemicals above this threshold ratio are to be included in

the chemical inventory control program. The chemicals that

fall below the threshold ratio are managed in accordance

with existing practice per State and RCRA hazardous materials requirements. Additionally, the facilities are managed in

accordance with process safety management principles,

specifically using process hazards analyses, which provides

safety assurance for even the small quantities that may be

excluded from the formal inventory control program. The

method yields a practical approach to chemical inventory

control, while maintaining appropriate chemical safety margins. The resulting number of specific chemicals that require

inclusion in a rigorous inventory control program is greatly

reduced by about 80%, thereby resulting in significant reduction in chemical data management while preserving

appropriate safety margins.

741

(WSRC-MS–97-0574)

Feed Acceptance for the Defense Waste Processing

Facility at the Savannah River Site. Jacobs, R.A. (Westinghouse Savannah River Company, AIKEN, SC (United

States)); Elder, H.H. Westinghouse Savannah River Co.,

Aiken, SC (United States). Mar 1998. 28.p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract AC09-89SR18035.

(CONF-980318–: 1998 American Institute of Chemical Engineers (AIChE) spring meeting, New Orleans, LA (United

States), 8-12 Mar 1998). Order Number DE98051763.

Source: OSTI; NTIS; INIS; GPO Dep.

190
Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

The DWPF at the Department of Energy’s (DOE) Savannah River Site (SRS) began radioactive operations in

December of 1995. The High Level Waste Tank Farm at

SRS contains approximately thirty three million gallons of

salt, supernate, and insoluble sludge wastes accumulated

during more than three decades of weapons manufacture.

In the DWPF, the radioactive components from this waste

will ultimately be processed into a stable, borosilicate glass

for long-term storage in a geological repository.The feeds to

the DWPF are pretreated in a number of steps. Insoluble

sludges, primarily aluminum, iron and other transition metals, are combined from several tanks, treated by caustic

dissolution of aluminum and washed to remove soluble

salts; these materials are removed to increase waste loading

in the glass produced by the DWPF.The water soluble radioactive species in the salt and supernate, primarily cesium

and actinides, are precipitated by sodium tetraphenylborate

(NaTPB) or adsorbed onto sodium titanate. The resulting

solids are also washed to remove excessive soluble salts

before feeding to the DWPF. The soluble species removed

by washing are disposed of as low level radioactive waste in

a concrete form known as Saltstone. The presentation includes a brief overview of the High Level Waste system,

pretreatment, and disposition of the various streams.The

washed tetraphenylborate precipitates of cesium and potassium are hydrolyzed by copper catalyzed formic acid

hydrolysis in the Salt Processing Cell (SPC) to yield soluble

formates, boric acid, benzene and minor organic byproducts.The benzene and most of the organic byproducts are

then steam stripped. The resulting aqueous hydrolysis product, including the still insoluble actinides adsorbed onto

sodium titanate, is combined in the Chemical Processing

Cell (CPC) with the insoluble sludge which has been treated

with nitric acid and formic acid to remove mercury and to

adjust the glass redox. (Abstract truncated)

742

(WSRC-MS–97-0576)

Fractured rock aquifer tests in the Western Siberian

Basin, Ozyorsk, Russia. Nichols, R.L. (and others);

Looney, B.B.; Eddy-Dilek, C.A. Westinghouse Savannah

River Co., Aiken, SC (United States). 1997. 10p. Sponsored

by USDOE Office of Environmental Management, Washington, DC (United States);Russian Atomic Energy

Commission, Moscow (Russian Federation). DOE Contract

AC09-96SR18500. (CONF-971198–: 1997 American Institute of Hydrology annual meeting, Tampa, FL (United

States), 16-19 Nov 1997). Order Number DE97054318.

Source: OSTI; NTIS; INIS; GPO Dep.

A series of multi-zone pumping tests was conducted in a

contaminated fractured rock aquifer in the Western Siberian

Basin, Ozyorsk, Russia. The tests were conducted adjacent

to the Mishelyak River floodplain in fractured Paleozoic porphyrites, tufts, tuff breccia, and lava typical of the Ural

mountain complex. Geophysical logs, borehole photography,

core samples, and results from previous borehole contamination studies were used to identify the zones to be tested.

A network of three uncased wells was tested using a system

of inflatable packers, pressure transducers and data loggers. Seven zones were isolated and monitored in two of

the uncased wells. A straddle packer assembly was used to

isolate individual zones within the pumping well. Eight constant rate pumping tests were conducted. Results of the

testing indicate that shallow groundwater migrates primarily

in two intervals that are separated by an interval with low

lateral conductivity. The water bearing intervals have moderate to high specific capacities (1.3 and 30 L/min/m). Several

processes are responsible for fracturing present in the lower

interval. The network of compound fractures produced a

complex array of fracture intersections yielding a fractured

media with hydraulic behavior similar to porous media. Models used for the analysis of pumping tests in porous media

provide a good estimation of the hydraulic response of the

lower interval to pumping. Future work will include more

complex analysis of the data to determine hydraulic conductivity ellipses.

743

(WSRC-MS–97-00758)

Effect of nitrite concentration on pit depth in carbon

steel exposed to simulated radioactive waste. Zapp, P.E.

Westinghouse Savannah River Co., Aiken, SC (United

States). 21 Oct 1997. 13p. Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract AC09-96SR18500. (CONF-980316–:

Corrosion ’98, San Diego, CA (United States), 22-27 Mar

1998). Order Number DE98051096. Source: OSTI; NTIS;

INIS; GPO Dep.

The growth of pits in carbon steel exposed to dilute (0.055

M nitrate-bearing) alkaline salt solutions that simulate radioactive waste was investigated in coupon immersion tests.

Most coupons were tested in the as-received condition, with

the remainder having been heat treated to produce an oxide

film. Nitrite, which is an established pitting inhibitor in these

solutions, was present in concentrations from 0 to 0.031 M

to 0.16 M; the last concentration is known to prevent pitting

initiation in the test solution at the 50 degrees C test temperature. The depths of the deepest pits on coupons of

particular exposure conditions were measure microscopically and were analyzed as simple, type 1 extreme value

statistical distributions, to predict the deepest expected pit in

a radioactive waste tank subject to the test conditions. While

the growth rate of pits could not be established from these

tests, the absolute value of the deepest pits predicted is of

the order of 100 mils after 448 days of exposure. The data

indicate that even nitrite concentrations insufficient to prevent pitting have a beneficial effect on limiting the growth of

deepest pits.

744

(WSRC-MS–97-00790)

ICP-MS nebulizer performance for analysis of SRS high

salt simulated radioactive waste tank solutions (#3053).

Jones, V.D. Westinghouse Savannah River Co., Aiken, SC

(United States). [1997]. 10p. Sponsored by USDOE Office of

Environmental Management, Washington, DC (United

States). DOE Contract AC09-96SR18500. (CONF-980317–:

2. ASTM symposium on applications of ICP-MS to radionuclide determinations, New Orleans, LA (United States), 2-7

Mar 1998). Order Number DE98050691. Source: OSTI;

NTIS; INIS; GPO Dep.

High Level Radioactive Waste Tanks at the Savannah

River Site are high in salt content. The cross-flow nebulizer

provided the most stable signal for all salt matrices with the

smallest signal loss/suppression due to this matrix. The DIN

exhibited a serious lack of tolerance for TDS; possibly due

to physical de-tuning of the nebulizer efficiency.

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

745

(WSRC-MS–98-00013)

ITP Waste Tank Positive Pressure Inerting System. Blanchard, A. (Westinghouse Savannah River Company, AIKEN,

SC (United States)); Thomas, J.K. Westinghouse Savannah

River Company, Aiken, SC (United States);Westinghouse

Savannah River Co., Aiken, SC (United States). Jun 1998.

10p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC09-96SR18500. (CONF-980616–: Conference on integrating safety analysis into safety management, Park City,

UT (United States), 15-19 Jun 1998). Order Number

DE98054752. Source: OSTI; INIS; NTIS; GPO Dep.

This paper provides an overview of the methods used to

perform the first two evaluations along with the most relevant results.

746

(WSRC-MS–98-00018)

A Simple Method for Estimating Forced Convection

Mass Transfer in a Waste Tank. Kalinich, D.A. (Westinghouse Savannah River Company, AIKEN, SC (United

States)); Paddleford, D.F. Westinghouse Savannah River

Company, Aiken, SC (United States);Westinghouse Savannah River Co., Aiken, SC (United States). Jun 1998. 1p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC09-96SR18500. (CONF-980616–: Conference on integrating safety analysis into safety management, Park City,

UT (United States), 15-19 Jun 1998). Order Number

DE98054744. Source: OSTI; INIS; NTIS; GPO Dep.

Prevention of flammable vapor concentrations in a waste

tank can be accomplished by forced ventilation of the tank

vapor space.

747

(WSRC-MS–98-00022)

Preliminary Disposal Analysis for Selected Accelerator

Production of Tritium Waste Streams. Ades, M.J. (Westinghouse Savannah River Company, AIKEN, SC (United

States)); England, J.L. Westinghouse Savannah River Co.,

Aiken, SC (United States). Jun 1998. 7p. Sponsored by USDOE Office of Environmental Management, Washington, DC

(United States). DOE Contract AC09-89SR18035. (CONF980606–: Annual meeting of the American Nuclear Society,

Nashville, TN (United States), 7-12 Jun 1998). Order Number DE98051721. Source: OSTI; NTIS; INIS; GPO Dep.

A preliminary analysis was performed for two selected Accelerator Production of Tritium (APT) generated mixed and

low-level waste streams to determine if one mixed low-level

waste (MLLW) stream that includes the Mixed Waste Lead

(MWL) can be disposed of at the Nevada Test Site (NTS)

and at the Hanford Site and if one low-level radioactive

waste (LLW) stream, that includes the Tungsten waste

stream (TWS) generated by the Tungsten Neutron Source

modules and used in the Target/Blanket cavity vessel, can

be disposed of in the LLW Vaults at the Savannah River

Plant (SRP). The preliminary disposal analysis that the radionuclide concentrations of the two selected APT waste

streams are not in full compliance with the Waste Acceptance Criteria (WAC) and the Performance Assessment (PA)

radionuclide limits of the disposal sites considered.

748

(WSRC-MS–98-00023)

Accelerator Production of Tritium Waste Characterization and Certification Challenges. Ades, M.J.

(Westinghouse Savannah River Company, AIKEN, SC

(United States)); England, J.L.; Nowacki, P.L.; Hane, R.;

Tempel, K.L.; Pitcher, E.; Cohen, H.S. Westinghouse Savannah River Co., Aiken, SC (United States). Jun 1998. 6p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC09-89SR18035. (CONF-980606–: Annual meeting of the

American Nuclear Society, Nashville, TN (United States), 7-

12 Jun 1998). Order Number DE98051722. Source: OSTI;

NTIS; INIS; GPO Dep.

This paper summaries the processes and methods APT

used for the identification and classification of the waste

streams, the characterization and certification of the waste

streams, and waste minimization.

749

(WSRC-MS–98-00039)

Cross-Flow Filtration of Department of Energy Hanford

Waste Streams Using Sintered Metal Mott and Graver

Filters at the Savannah River Technology Center.

Walker, B.W. (Westinghouse Savannah River Company,

AIKEN, SC (United States)); McCabe, D.J. Westinghouse

Savannah River Co., Aiken, SC (United States). May 1998.

8p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC09-96SR18500. (CONF-980543–: 11. annual technical

conference of the American Filtration and Separations Society, St. Louis, MO (United States), 4-7 May 1998). Order

Number DE98052363. Source: OSTI; NTIS; INIS; GPO Dep.

Treatment processes have been proposed that will utilize

cross-flow filtration to filter supernate and concentrated

sludge waste streams at a Department of Energy plant in

Hanford, Washington. Two waste processing applications

have been identified as candidates for this technology. The

first of the Hanford applications involves filtration of the decanted supernate from sludge leaching and washing

operations. This process requires the concentration and removal of dilute fines from the bulk of the supernate. The

second application involves filtration to wash and concentrate the sludge during out-of-tank processing of a relatively

concentrated solids feed stream.

750

(WSRC-MS–98-00107)

On-Board Hydrogen Storage for a City Transit Bus. Heung, L.K. (Westinghouse Savannah River Company, AIKEN,

SC (United States)). Westinghouse Savannah River Co.,

Aiken, SC (United States). Mar 1998. 7p. Sponsored by USDOE Office of Environmental Management, Washington, DC

(United States). DOE Contract AC09-96SR18500. (CONF980350–: 9. annual U.S. hydrogen meeting, Vienna, VA

(United States), 3-5 Mar 1998). Order Number

DE98051917. Source: OSTI; NTIS; GPO Dep.

An electric bus was modified to use hydrogen fuel for

demonstration in the city of Augusta, Georgia, USA. The hydrogen fuel is stored in a solid form using an on-board metal

hydride storage system. The storage system performs better

than expected.

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

751

(WSRC-MS–98-00112)

Advanced Separations at SRS. Thompson, M.C. (Westinghouse Savannah River Company, AIKEN, SC (United

States)). Westinghouse Savannah River Co., Aiken, SC

(United States). Mar 1998. 3p. Sponsored by USDOE Office

of Environmental Management, Washington, DC (United

States). DOE Contract AC09-96SR18500. (CONF-980335–:

Efficient separations and processing crosscutting program

technical exchange meeting, Augusta, GA (United States),

17-19 Mar 1998). Order Number DE98052367. Source:

OSTI; NTIS; INIS; GPO Dep.

The Savannah River Site (SRS) has many waste streams

which are contaminated with radionuclides and/or hazardous materials which must be treated to remove the

radioactivity (Cs, Sr, tritium, actinides) and hazardous components (polychlorinated biphenyls, cyanide, metal ions).

This task provides test beds for ESP-developed separations

materials and technologies using actual SRS waste

streams. The work includes different SRS waste streams;

high level waste solutions presently stored in underground

tanks onsite, water recycled from the waste vitrification

plant, and reactor basin water in excess facilities.

752

(WSRC-MS–98-00316)

Implementation of ISO140001 at the Savannah River

Site. Marra, S.L. (Westinghouse Savannah River Company,

AIKEN, SC (United States)); Reeves, R.D. Westinghouse

Savannah River Co., Aiken, SC (United States). 20 Apr

1998. 8 p.p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract AC09-96SR18500. DE-AC09-96SR18500. Order

Number DE98052902. Source: OSTI; INIS; NTIS; GPO Dep.

The Department of Energy’s Savannah River Site (SRS)

in Aiken, SC recently received ISO14001 certification.

ISO14001 is an internationally recognized standard that

delineates the elements of an effective environmental management system (EMS) and enhances environmental

stewardship. SRS preparations for ISO14001 certification

involved a comparison of existing programs to the requirements of the standard. Gaps in the program were identified

and work initiated to fill those gaps. Primarily, these deficiencies were related to documentation of the SRS EMS and

employee training. Certification was granted after an extensive review by a team of independent auditors. The review

included personnel interviews, documentation reviews, and

work practice observations. An overview of the preparation

process as well as the independent review will be presented.

753

(WSRC-OS–97-00006)

Groundwater Flow Model for the R-Reactor Area Final

Report. Harris, M.K. (Westinghouse Savannah River Company, AIKEN, SC (United States)). Westinghouse Savannah

River Company, Aiken, SC (United States);Westinghouse

Savannah River Co., Aiken, SC (United States). Nov 1997.

200p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC09-96SR18500. Order Number DE98052998. Source:

OSTI; NTIS; INIS; GPO Dep.

A detailed numerical groundwater flow model has been

developed for the R-Area of the Savannah River Site in

Aiken, South Carolina. The three-dimensional, finite-element

groundwater modeling code Flow and Contaminant Transport (FACT) has been used for this study.

754

(WSRC-RP–97-25)

Report on bioventing of petroleum contaminated soils

at 108-3C: Active extraction and passive injection (barometric pumping) of a gaseous nutrient. Kastner, J.R.

(and others); Lombard, K.; Radway, J. Westinghouse Savannah River Co., Aiken, SC (United States). [1997]. 18p.

Sponsored by USDOE, Washington, DC (United States).

DOE Contract AC09-96SR18500. Order Number

DE97060080. Source: OSTI; NTIS; INIS; GPO Dep.

A bioventing system was constructed with horizontal extraction wells and vertical injection wells in an area which

had previously been excavated and then backfilled. Initial

in-situ respiration rates (air addition only) suggest that hydrocarbon degradation may be nutrient limited. The rate of

TPH degradation was maximum (0.8-1.2 mg/kg/day) between 10-15 ft (bgs), but dropped to essentially zero 30 ft

(bgs) within the contaminated zone (even though previous

analysis at this depth indicated a TPH concentration of 3800

ppm). Analysis of the soil at 17 ft showed that NO3 and PO4

were below detection limits (0.5 ppm), indicating that nutrient limitation may be occurring. Nitrate levels were highest

at 10 ft (bgs), correlating with the highest respiration rates.

However, phosphate levels were at/or below detection levels

throughout tile site (indicating possible PO4 limitation). Viable

cells increased from 3 x 106 cfu/g at 3 ft (bgs) to 1 x 107 cfu/

g at 10 ft (bgs) and remained relatively constant down to 17

ft. Cell numbers in the control area were significantly lower

than in the contaminated zone (4.5 x 103). Gas phase nutrients (triethlyphosphate and nitrous oxide) will be injected to

see if the hydrocarbon degradation rate can be increased.

755

(WSRC-RP–97-177-Rev.1-Final)

Removal site evaluation report L-area rubble pile (131-

3L) gas cylinder disposal facility (131-2L). Palmer, E.R.

(Westinghouse Savannah River Company, AIKEN, SC

(United States)); Mason, J.T. Westinghouse Savannah River

Co., Aiken, SC (United States). Oct 1997. 101p. Sponsored

by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract AC09-96SR18500.

Order Number DE98051299. Source: OSTI; NTIS; INIS;

GPO Dep.

This Removal Site Evaluation Report (RSER) is prepared

in accordance with Sections 300.410 and 300.415 of the National Contingency Plan and Section XIV of the Savannah

River Site (SRS) Federal Facility Agreement (FFA). The purpose of this investigation is to report information concerning

conditions at the L-Area Rubble Pile (LRP) (131-3L) and the

L-Area Gas Cylinder Disposal Facility (LGCDF) (131- 2L)

sufficient to assess the threat posed to human health and

the environment. This investigation also assesses the need

for additional Comprehensive Environmental Response,

Compensation and Liability Act (CERCLA) actions. The

scope of this investigation included a review of files, limited

sampling efforts, and visits to the area. An investigation of

the LRP (1131-3L) indicates the presence of semi volatile

organic compounds (SVOCs), volatile organic compounds

(VOCs), metals, and asbestos. Potential contaminants in the

waste piles could migrate into the secondary media (soils

and groundwater), and the presence of some of the contaminants in the piles poses an exposure threat to site works.

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

The Department of Energy (DOE), United States Environmental Protection Agency (EPA) and South Carolina

Department of Health and Environmental Control (SCDHEC)

discussed the need for a removal action at the Resource

Conservation and Recovery Act (RCRA) Facility Investigation/Remedial Investigation (RFI/RI) work plan scoping

meetings on the waste unit, and agreed that the presence of

the waste piles limits the access to secondary media for

sampling, and the removal of the piles would support future

characterization of the waste unit. In addition, the DOE, EPA,

and SCDHEC agreed that the proposed removal action for

the LRP (131-3L) would be documented in the RFI/RI work

plan. The LGCDF (131-2L) consists of a backfilled pit containing approximately 28 gas cylinders. (Abstract truncated)

756

(WSRC-RP–97-236)

Rheology of Savannah River site tank 42 HLW radioactive sludge. Ha, B.C. Westinghouse Savannah River Co.,

Aiken, SC (United States). 5 Nov 1997. 14p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract AC09-96SR18500. Order

Number DE98051871. Source: OSTI; NTIS; INIS; GPO Dep.

Knowledge of the rheology of the radioactive sludge slurries at the Savannah River Site is necessary in order to

ensure that they can be retrieved from waste tanks and processed for final disposal. At Savannah River Site, Tank 42

sludge represents on of the first HLW radioactive sludges to

be vitrified in the Defense Waste Processing Facility. The

rheological properties of unwashed Tank 42 sludge slurries

at various solids concentrations were measured remotely in

the Shielded Cells at the Savannah River Technology Center using a modified Haake Rotovisco viscometer.

757

(WSRC-RP–97-00937)

Analysis of cascade impactor and EPA method 29 data

from the americium/curium pilot melter system. Zamecnik, J.R. Westinghouse Savannah River Co., Aiken, SC

(United States). Nov 1997. 41p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States). DOE Contract AC09-96SR18500. Order Number

DE98051509. Source: OSTI; NTIS; INIS; GPO Dep.

The offgas system of the Am/Cm pilot melter at TNX was

characterized by measuring the particulate evolution using a

cascade impactor and EPA Method 29. This sampling work

was performed by John Harden of the Clemson Environmental Technologies Laboratory, under SCUREF Task SC0056.

Elemental analyses were performed by the SRTC Mobile

Laboratory.Operation of the Am/Cm melter with B2000 frit

has resulted in deposition of PbO and boron compounds in

the offgas system that has contributed to pluggage of the

High Efficiency Mist Eliminator (HEME). Sampling of the offgas system was performed to quantify the amount of

particulate in the offgas system under several sets of conditions. Particulate concentration and particle size distribution

were measured just downstream of the melter pressure

control air addition port and at the HEME inlet. At both locations, the particulate was measured with and without steam

to the film cooler while the melter was idled at about 1450

degrees Celsius. Additional determinations were made at

the melter location during feeding and during idling at 1150

degrees Celsius rather than 1450 degrees Celsius (both

with no steam to the film cooler). Deposition of particulates

upstream of the melter sample point may have, and most

likely did occur in each run, so the particulate concentrations

measured do no necessarily reflect the total particulate

emission at the melt surface. However, the data may be

used in a relative sense to judge the system performance.

758

(WSRC-RP–98-00032)

Characterization Plan and Dissolution Tests for Tank

16H Samples. Davis, P.L.; Hay, M.S. Westinghouse Savannah River Co., Aiken, SC (United States). 9 Feb 1998. 5p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC09-96SR18500. Order Number DE98052149. Source:

OSTI; NTIS; INIS; GPO Dep.

In support of the closure of Tank 16H, a sample of the

solids residue on the bottom of the tank interior and three

samples from the tank annulus will be sent to SRTC for

analysis. The results of the analysis of the samples from the

tank interior and the annulus will define the source term inventory used for fate and transport modeling. In addition, the

samples from the tank annulus will be used for dissolution

tests to evaluate the effectiveness of various cleaning alternatives.

759

(WSRC-RP–98-00034)

Characterization of Samples from the Effluent Treatment

Facility Evaporator Waste Concentrate Tank. Wilmarth,

W.R. (Westinghouse Savannah River Company, AIKEN, SC

(United States)). Westinghouse Savannah River Co., Aiken,

SC (United States). 31 Jan 1998. 10p. Sponsored by USDOE Office of Environmental Management, Washington, DC

(United States). DOE Contract AC09-89SR18035. Order

Number DE98052688. Source: OSTI; NTIS; INIS; GPO Dep.

During October 1997, the ETF Evaporator Waste Concentrate Tank No. 2 was discovered to contain a significant

accumulation of solid deposits. SRTC performed destructive

and nondestructive examination of solid samples from the

tank. The results of these tests indicate that the solids contain mixtures of sodium oxalate (65 percent), the sulfide

enclathrated sodium aluminosilicate (30 percent), and iron

oxide (5 percent).

760

(WSRC-RP–98-00311)

Porflow Capabilities, Usage, History, and Testing. Collard, L.B. (Westinghouse Savannah River Company, AIKEN,

SC (United States)). Westinghouse Savannah River Company, Aiken, SC (United States);Westinghouse Savannah

River Co., Aiken, SC (United States). May 1998. 14p. Sponsored by USDOE Office of Environmental Management,

Washington, DC (United States). DOE Contract AC09-

96SR18500. Order Number DE98057406. Source: OSTI;

INIS; NTIS; GPO Dep.

To support closure of the Savannah River Site High Level

Waste tanks, the PORFLOW computer program is being

applied to predict long term movement of residual contaminants from the tanks. The PORFLOW program has greater

capabilities than simpler programs that have been used previously, and PORFLOW results have been accepted by

state and federal regulators throughout the United States.

This document briefly discusses the PORFLOW capabilities

and presents lists of reports showing PORFLOW’s usage

history and testing.

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

761

(WSRC-TR–96-0294-Rev.1)

Commercial Light Water Reactor -Tritium Extraction Facility Process Waste Assessment (Project S-6091). Hsu,

R.H. (Westinghouse Savannah River Co., Aiken, SC (United

States)); Delley, A.O.; Alexander, G.J.; Clark, E.A.; Holder,

J.S.; Lutz, R.N.; Malstrom, R.A.; Nobles, B.R.; Carson, S.D.;

Peterson, P.K. Westinghouse Savannah River Co., Aiken,

SC (United States). 30 Nov 1997. 126p. Sponsored by USDOE Office of Environmental Management, Washington, DC

(United States). DOE Contract AC09-89SR18035. Order

Number DE98051912. Source: OSTI; NTIS; INIS; GPO Dep.

The Savannah River Site (SRS) has been tasked by the

Department of Energy (DOE) to design and construct a Tritium Extraction Facility (TEF) to process irradiated tritium

producing burnable absorber rods (TPBARs) from a Commercial Light Water Reactor (CLWR). The plan is for the

CLWR-TEF to provide tritium to the SRS Replacement Tritium Facility (RTF) in Building 233-H in support of DOE

requirements. The CLWR-TEF is being designed to provide

3 kg of new tritium per year, from TPBARS and other

sources of tritium (Ref. 1-4).The CLWR TPBAR concept is

being developed by Pacific Northwest National Laboratory

(PNNL). The TPBAR assemblies will be irradiated in a Commercial Utility light water nuclear reactor and transported to

the SRS for tritium extraction and processing at the CLWRTEF. A Conceptual Design Report for the CLWR-TEF

Project was issued in July 1997 (Ref. 4).The scope of this

Process Waste Assessment (PWA) will be limited to CLWRTEF processing of CLWR irradiated TPBARs. Although the

CLWR- TEF will also be designed to extract APT tritiumcontaining materials, they will be excluded at this time to

facilitate timely development of this PWA. As with any process, CLWR-TEF waste stream characteristics will depend

on process feedstock and contaminant sources. If irradiated

APT tritium-containing materials are to be processed in the

CLWR-TEF, this PWA should be revised to reflect the introduction of this contaminant source term.

762

(WSRC-TR–97-0285)

Tetraphenylborate Solids Stability Tests. Walker, D.D.

(Westinghouse Savannah River Company, AIKEN, SC

(United States)); Edwards, T.B. Westinghouse Savannah

River Company, Aiken, SC (United States). 19 Dec 1997.

44p. Sponsored by USDOE, Washington, DC (United

States);USDOE Office of Environmental Management,

Washington, DC (United States). DOE Contract AC09-

96SR18500. Order Number DE98058908. Source: OSTI;

NTIS; INIS; GPO Dep.

Tetraphenylborate solids provide a potentially large source

of benzene in the slurries produced in the In-Tank Precipitation process. The stability of the solids is an important

consideration in the safety analysis of the process and we

desire an understanding of the factors that influence the rate

of conversion of the solids to benzene.

763

(WSRC-TR–97-00323)

Savannah River Site environmental report for 1997 summary. Arnett, M. Westinghouse Savannah River Co.,

Savannah River Site, Aiken, SC (United States). [1997].

26p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC09-96SR18500. Order Number DE99001338. Source:

OSTI; NTIS; INIS; GPO Dep.

The Savannah River Site (SRS) publishes an environmental report each year to provide environmental monitoring

and surveillance results to the US Department of Energy

(DOE), the public, Congress, state and federal regulators,

universities, local governments, the news media, and environmental and civic groups. The Savannah River Site

Environmental Report for 1997 (WSRC-TR-97-00322) contains detailed information on site operations, environmental

monitoring and surveillance programs, environmental compliance activities, and special projects for calendar year

1997. The purpose of this document is to give a brief

overview of the site and its activities, to summarize the site

environmental report and the impact of 1997 SRS operations on the environment and the public, and to provide a

brief explanation of radiation and dose.

764

(WSRC-TR–97-00323-Summ.)

Savannah River Site Environmental Report for 1997

Summary. Arnett, M. (Westinghouse Savannah River Company, AIKEN, SC (United States)). Westinghouse Savannah

River Company, Aiken, SC (United States). 16 Jun 1998.

26p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC09-96SR18500. Order Number DE98058240. Source:

OSTI; NTIS; INIS; GPO Dep.

The Savannah River Site (SRS) publishes an environmental report each year to provide environmental monitoring

and surveillance results to the U. S. Department of Energy

(DOE), the public, Congress, state and federal regulators,

universities, local governments, the news media, and environmental and civic groups. The Savannah River Site

Environmental Report for 1997 (WSRC-TR-97-00322) contains detailed information on site operations, environmental

monitoring and surveillance programs, environmental compliance activities, and special projects for the calendar year

1997. The purpose of this documents is to give a brief

overview of the site and its activities, to summarize the site

environmental report and the impact of 1997 SRS operations on the environment and the public, and to provide a

brief explanation of radiation and dose.The data used to

compile the annual environmental report and this summary

can be found in Savannah River Site Environmental Data for

1997 (WSRC-TR-97-00324).

765

(WSRC-TR–97-00350)

Sampling plan to support HLW tank 16. Rodwell, P.O.;

Martin, B. Westinghouse Savannah River Co., Aiken, SC

(United States). 30 Oct 1997. 4p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States). DOE Contract AC09-96SR18500. Order Number

DE98051776. Source: OSTI; NTIS; INIS; GPO Dep.

Plans are to remove the residual waste from the annulus

of High-Level Waste Tank 16, located in the H-Area Tank

Farm, in 1998. The interior of the tank is virtually clean. In

the late 1970’s, the waste was removed from the interior of

the tank by several campaigns of waste removal with slurry

pumps, spray washing, and oxalic acid cleaning. The annulus of the tank at one time had several thousand gallons of

waste salt, which had leaked from the tank interior. Some of

this salt was removed by adding water to the annulus and

circulating, but much of the salt remains in the annulus. In

195
ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

order to confirm the source term used for fate and transport

modeling, samples of the tank interior and annulus will be

obtained and analyzed. If the results of the analyses indicate that the data used for the initial modeling is bounding

then no changes will be made to the model. However, if the

results indicate that the source term is higher than that assumed in the initial modeling, thus not bounding, additional

modeling will be performed. The purpose of this Plan is to

outline the approach to sampling the annulus and interior of

Tank 16 as a prerequisite to salt removal in the annulus and

closure of the entire tank system. The sampling and analysis

of this tank system must be robust to reasonably ensure the

actual tank residual is within the bounds of analysis error.

766

(WSRC-TR–97-00368)

Tritium Facilities Modernization and Consolidation

Project Process Waste Assessment (Project S-7726).

Hsu, R.H. (Westinghouse Savannah River Company,

AIKEN, SC (United States)); Oji, L.N. Westinghouse Savannah River Co., Aiken, SC (United States). 14 Nov 1997.

98p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC09-89SR18035. Order Number DE98052037. Source:

OSTI; NTIS; INIS; GPO Dep.

Under the Tritium Facility Modernization & Consolidation

(TFM&C) Project (S-7726) at the Savannah River Site (SS),

all tritium processing operations in Building 232-H, with the

exception of extraction and obsolete/abandoned systems,

will be reestablished in Building 233-H. These operations include hydrogen isotopic separation, loading and unloading of

tritium shipping and storage containers, tritium recovery from

zeolite beds, and stripping of nitrogen flush gas to remove

tritium prior to stack discharge. The scope of the TFM&C

Project also provides for a new replacement R&D tritium test

manifold in 233-H, upgrading of the 233- H Purge Stripper

and 233-H/234-H building HVAC, a new 234-H motor control

center equipment building and relocating 232-H Materials

Test Facility metallurgical laboratories (met labs), flow tester

and life storage program environment chambers to 234-H.

767

(WSRC-TR–97-00372)

Resolving Radiological Waste Classification and Release Issues Using Material Process Information and

Simple Measurements and Models. Hochel, R.C. (Westinghouse Savannah River Company, AIKEN, SC (United

States)). Westinghouse Savannah River Company, Aiken,

SC (United States);Westinghouse Savannah River Co.,

Aiken, SC (United States). Nov 1997. 18p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract AC09-96SR18500. Order

Number DE98054746. Source: OSTI; NTIS; INIS; GPO Dep.

This report was prepared as an account of work sponsored by an agency of the United States Government.

Neither the United States Government nor any agency

thereof, nor any of their employees, makes any warranty,

express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any

information, apparatus, product, or process disclosed, or

represents that its use would not infringe privately owned

rights. Reference herein to any specific commercial product,

process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply

its endorsement, recommendation, or favoring by United

States Government or any agency thereof. The views and

opinions of the author expressed herein do not necessarily

state or reflect those of the United States Government or

any agency thereof.

768

(WSRC-TR–97-00389)

Sodium Aluminosilicate Formation in Tank 43H Simulants. Wilmarth, W.R. (Westinghouse Savannah River

Company, AIKEN, SC (United States)); Walker, D.D.; Fink,

S.D. Westinghouse Savannah River Company, Aiken, SC

(United States);Westinghouse Savannah River Co., Aiken,

SC (United States). Nov 1997. 21 p.p. Sponsored by USDOE Office of Environmental Management, Washington, DC

(United States). DOE Contract AC09-89SR18035. Order

Number DE98054481. Source: OSTI; NTIS; INIS; GPO Dep.

This work studied the formation of a sodium aluminosilicate, Na8Al6Si6O24(NO3)2?4H2O, at 40 110 C in simulated

waste solutions with varied amounts of silicon and aluminum.

The data agree well with literature solubility data for sodalite, the analogous chloride salt. The following conclusions

result from this work: (1) The study shows, by calculation

and experiments, that evaporation of the September 1997

Tank 43H inventory will only form minor quantities of the aluminosilicate. (2) The data indicate that the rate of formation

of the nitrate enclathrated sodalite solid at these temperatures falls within the residence time (<; 4 h) of liquid in the

evaporator. (3) The silicon in entrained Frit 200 transferred

to the evaporator with the Tank 43H salt solution will quantitatively convert to the sodium aluminosilicate. One kilogram

of Frit 200 produces 2.1 kg of the sodium aluminosilicate.

769

(WSRC-TR–97-00394)

ESP’s Tank 42 washwater transfer to the 241-F/H tank

farms. Aponte, C.I. (Westinghouse Savannah River Company, Aiken, SC (United States)); Lee, E.D. Westinghouse

Savannah River Co., Aiken, SC (United States). Dec 1997.

29p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC09-96SR18500. Order Number DE98051771. Source:

OSTI; NTIS; INIS; GPO Dep.

As a result of the separation of the High-Level Liquid

Waste Department into three separate organizations (formerly there were two) (Concentration, Storage, and Transfer

(CST), Waste Pre-Treatment (WPT) and Waste Disposition

(WD)) process interface controls were required. One of these

controls is implementing the Waste the waste between CST

and WPT. At present, CST’s Waste Acceptance Criteria is

undergoing revision and WPT has not prepared the required

Waste Compliance Plan (WCP). The Waste Pre-Treatment

organization is making preparations for transferring spent

washwater in Tank 42 to Tank 43 and/or Tank 22. The washwater transfer is expected to complete the washing steps for

preparing ESP batch 1B sludge. This report is intended to

perform the function of a Waste Compliance Plan for the

proposed transfer. Previously, transfers between the Tank

Farm and ITP/ESP were controlled by requirements outlined

in the Tank Farm’s Technical Standards and ITP/ESP’s

Process Requirements. Additionally, these controls are implemented primarily in operating procedure 241-FH-7TSQ

and ITP Operations Manual SW16.1-SOP-WTS-1 which will

be completed prior to performing the waste transfers.

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

770

(WSRC-TR–97-0398)

Technology Status Report of the Applicability of SolidLiquid Separation Methods to Radioactive Tank Wastes.

McCabe, D.J. (Westinghouse Savannah River Company,

AIKEN, SC (United States)). Westinghouse Savannah River

Co., Aiken, SC (United States). 22 Dec 1997. 9p. Sponsored by USDOE Office of Environmental Management,

Washington, DC (United States). DOE Contract AC09-

96SR18500. Order Number DE98052362. Source: OSTI;

NTIS; INIS; GPO Dep.

Solid-Liquid separation of highly radioactive underground

storage tank wastes has been examined, and cross-flow filtration has been shown to be viable.

771

(WSRC-TR–98-00006)

Sanitary Landfill Groundwater Monitoring Report.

Fourth Quarter 1997 and 1997 Summary. Chase, J.

(Westinghouse Savannah River Company, AIKEN, SC

(United States)). Westinghouse Savannah River Co., Aiken,

SC (United States). Feb 1998. 400p. Sponsored by USDOE

Office of Environmental Management, Washington, DC

(United States). DOE Contract AC09-96SR18500. Order

Number DE98052690. Source: OSTI; NTIS; GPO Dep.

A maximum of forty-eight wells of the LFW series monitor

groundwater quality in the Steed Pond Aquifer (Water Table)

beneath the Sanitary Landfill at the Savannah River Site

(SRS). These wells are sampled quarterly to comply with

the South Carolina Department of Health and Environmental

Control Domestic Water Permit DWP-087A and as part of

the SRS Groundwater Monitoring Program. Chloroethene

(vinyl chloride) and trichloroethylene were the most

widespread constituents exceeding standards during 1997.

Lead (total recoverable), 1,4-dichlorobenzene, mercury,

benzene, dichloromethane (methylene chloride), a common laboratory contaminant, tetrachloroethylene,

1,2-dichloroethane, gross alpha, tritium, and 1.2-

dichloropropane also exceeded standards in one or more

wells. The groundwater flow direction in the Steed Pond

Aquifer (Water Table) beneath the Sanitary Landfill was to

the southeast (universal transverse Mercator coordinates).

The flow rate in this unit was approximately 139 ft/year during first quarter 1997 and 132 ft/year during fourth quarter.

772

(WSRC-TR–98-00011)

Glass Formulation Development for the Vitrification of

Oak Ridge Tank Waste. Andrews, M.K. (Westinghouse Savannah River Company, AIKEN, SC (United States));

Workman, P.J.; Harbour, J.R.; Edwards, T.B. Westinghouse

Savannah River Co., Aiken, SC (United States). Jul 1998.

6p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC09-89SR18035. (CONF-980712–: 18. international

congress on glass, San Francisco, CA (United States), 5-10

Jul 1998). Order Number DE98051873. Source: OSTI;

NTIS; INIS; GPO Dep.

Radioactive waste from four different Oak Ridge tank

farms will be immobilized. The sludges in these tanks contain transuranic radionuclides and RCRA metals at levels

which will make the final waste from both TRU and mixed.

The final waste form in the immobilization of these sludges

may be glass because of its ability to accept a wide variety of

components into its network structure. The results of these

tests indicate that sufficient waste loadings can be obtained

in the glass to significantly reduce the waste volume. This

paper will present the results of the glass formulation efforts.

773

(WSRC-TR–98-00047)

Trial Burn Activities for a Mixed Waste Incinerator. Birk,

M.B. (Westinghouse Savannah River Company, AIKEN, SC

(United States)). Westinghouse Savannah River Co., Aiken,

SC (United States). May 1998. 10p. Sponsored by USDOE,

Washington, DC (United States);USDOE Office of Environmental Management, Washington, DC (United States). DOE

Contract AC09-96SR18500. (CONF-980513–: International

conference on incineration and thermal treatment technologies, Salt Lake City, UT (United States), 11-15 May 1998).

Order Number DE98052550. Source: OSTI; NTIS; GPO

Dep.

The Consolidated Incineration Facility (CIF) is located on

the Savannah River Site (SRS), owned by the U. S. Department of Energy and managed by BNFL, Inc. for the

Westinghouse Savannah River Company. SRS received

permits from the South Carolina Department of Health and

Environmental Control (SCDHEC) and the U. S. Environmental Protection Agency (EPA), Region IV to construct and

operate the CIF, a hazardous, radioactive mixed waste incinerator. This paper presents the results of the trial burn

conducted on the CIF in April 1997 which is the initial

demonstration of compliance with the permits. The incinerator is currently operating under approved post-trial burn

conditions while the trial burn results are being evaluated. A

final operating permit is expected the fall of 1998.

774

(WSRC-TR–98-00070,Rev.0)

Radioactive Testing Results in Support of the In-Tank

Precipitation Facility. Hobbs, D.T. (Westinghouse Savannah River Company, AIKEN, SC (United States)); Barnes,

M.J.; Peterson, R.A.; Crawford, C.L. Westinghouse Savannah River Company, Aiken, SC (United

States);Westinghouse Savannah River Co., Aiken, SC

(United States). Apr 1998. 68p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States). DOE Contract AC09-96SR18500. Order Number

DE98054395. Source: OSTI; NTIS; INIS; GPO Dep.

A series of twelve tests examined benzene generation

rates with radioactive materials simulating the planned

Batches 2 through 4 that complete Cycle 1 for the In-Tank

Precipitation (ITP) facility.

775

(WSRC-TR–98-0083)

Annual Radioactive Waste Tank Inspection Program -

1997. McNatt, F.G. (Westinghouse Savannah River Company, AIKEN, SC (United States)). Westinghouse Savannah

River Company, Aiken, SC (United States);Westinghouse

Savannah River Co., Aiken, SC (United States). May 1998.

91 p.p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC09-96SR18500. Order Number DE98054393. Source:

OSTI; INIS; NTIS; GPO Dep.

Aqueous radioactive wastes from Savannah River Site

(SRS) separations processes are contained in large underground carbon steel tanks. Inspections made during 1997 to

evaluate these vessels, and evaluations based on data

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

accrued by inspections performed since the tanks were constructed are the subject of this report.

776

(WSRC-TR–98-00099)

Excess Sodium Tetraphenylborate and Intermediates

Decomposition Studies. Barnes, M.J. (Westinghouse

Savannah River Company, AIKEN, SC (United States)); Peterson , R.A. Westinghouse Savannah River Company,

Aiken, SC (United States);Westinghouse Savannah River

Co., Aiken, SC (United States). Apr 1998. 42p. Sponsored

by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract AC09-96SR18500.

Order Number DE98053169. Source: OSTI; INIS; NTIS;

GPO Dep.

The stability of excess amounts of sodium tetraphenylborate (NaTPB) in the In-Tank Precipitation (ITP) facility

depends on a number of variables. Concentration of palladium, initial benzene, and sodium ion as well as temperature

provide the best opportunities for controlling the decomposition rate. This study examined the influence of these four

variables on the reactivity of palladium-catalyzed sodium

tetraphenylborate decomposition. Also, single effects tests

investigated the reactivity of simulants with continuous

stirring and nitrogen ventilation, with very high benzene concentrations, under washed sodium concentrations, with very

high palladium concentrations, and with minimal quantities

of excess NaTPB. These tests showed the following.The

testing demonstrates that current facility configuration does

not provide assured safety of operations relative to the hazards of benzene (in particular to maintain the tank

headspace below 60 percent of the lower flammability limit

(lfl) for benzene generation rates of greater than 7 mg/(L.h))

from possible accelerated reaction of excess NaTPB. Current maximal operating temperatures of 40 degrees C and

the lack of protection against palladium entering Tank 48H

provide insufficient protection against the onset of the reaction. Similarly, control of the amount of excess NaTPB,

purification of the organic, or limiting the benzene content of

the slurry (via stirring) and ionic strength of the waste mixture prove inadequate to assure safe operation.

777

(WSRC-TR–98-00101)

Application of Epoxy Based Coating Instacote on Waste

Tank Tops. Pike, J.A. (Westinghouse Savannah River Company, AIKEN, SC (United States)). Westinghouse Savannah

River Company, Aiken, SC (United States);Westinghouse

Savannah River Co., Aiken, SC (United States). 18 Mar

1998. 7p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract AC09-96SR18500. Order Number DE98052911.

Source: OSTI; NTIS; INIS; GPO Dep.

This evaluation examines the compatibility of coating Instacote with existing High-Level Waste facilities and safety

practices. No significant incompatibilities are identified. The

following actions need to be completed as indicated when

applying Instacote on waste tank tops:(1) Prior to application

in ITP facilities, the final product should be tested for chemical resistance to sodium tetraphenylborate solutions or

sodium titanate slurries.(2) Any waste contaminated with

Part A or B that can not be removed by the vendor such as

for radiological contamination, HLW must hold the waste until HLW completes a formal assessment of the waste,

disposal criteria, and impact.(3) Prior to the start of any application of the coating, each riser needs to be evaluated for

masking and masking applied if needed.(4) At the conclusion of an application actual total weight of material applied

to a waste tank needs to documented and sent to the tank

top loading files for reference purposes.(5) Verify that the final product contains less than 250 ppm chloride.

778

(WSRC-TR–98-00129)

The Solubility of Phenylborate Compounds in Benzene.

Eibling, R.E. (Westinghouse Savannah River Company,

AIKEN, SC (United States)). Westinghouse Savannah River

Company, Aiken, SC (United States);Westinghouse Savannah River Co., Aiken, SC (United States). Apr 1998. 9p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC09-96SR18500. Order Number DE98057627. Source:

OSTI; INIS; NTIS; GPO Dep.

The original goal of this scoping study was to determine if

the solubility of sodium and potassium tetraphenylborates in

benzene was sufficiently large to justify designing and

performing kinetic studies on a benzene-phase catalytic reaction.

779

(WSRC-TR–98-00171-Rev.1)

Analysis of Steam Heating of a Two-Layer TBP/NParaffin/Nitric Acid Mixtures. Laurinat, J.E. (Westinghouse

Savannah River Company, AIKEN, SC (United States));

Hassan, N.M.; Rudisill, T.S.; Askew, N.M. Westinghouse

Savannah River Company, Aiken, SC (United States). 22

Jul 1998. 105p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE

Contract AC09-96SR18500. Order Number DE98058037.

Source: OSTI; NTIS; INIS; GPO Dep.

This report presents an analysis of steam heating of a

two-layer tri-n-butyl phosphate (TBP)/n-paraffin-nitric acid

mixture.The purpose of this study is to determine if the degree of mixing provided by the steam jet or by bubbles

generated by the TBP/nitric acid reaction is sufficient to prevent a runaway reaction.

780

(WSRC-TR–98-00186)

Summary of Tests to Determine Effectiveness of Gelatin

Strike on SS&C Dissolver Solutions. Murray, A.M. (Westinghouse Savannah River Company, AIKEN, SC (United

States)); Karraker, D.G. Westinghouse Savannah River

Company, Aiken, SC (United States);Westinghouse Savannah River Co., Aiken, SC (United States). May 1998. 13p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC09-96SR18500. Order Number DE98054751. Source:

OSTI; INIS; NTIS; GPO Dep.

The solutions from the dissolution of sand, slag, and crucible (SS&C) material are sufficiently different from previous

solutions processed via the F-Canyon Purex process that

the effectiveness of individual process steps needed to be

ascertained. In this study, the effectiveness of gelatin strike

was tested under a variety of conditions. Specifically, several concentrations of silica, fluoride, nitric acid (HNO3),

boric acid (H3BO3), and aluminium nitrate nonahydrate

(ANN) were studied. The disengagement times of surrogate

and plant SS&C dissolver solutions from plant solvent also

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

were measured. The results of the tests indicate that gelatin

strike does not coagulate the silica at the low concentration

of silica (30 ppm) expected in the SS&C dissolver solutions  ̃

because the silicon is complexed with fluoride ions (e.g.,

SiF6

2). The silicon fluoride complex is expected to remain

with the aqueous phase during solvent extraction. The disengagement times of the dissolver solutions from the plant

solvent were not affected by the presence of low concentrations of silica and no third phase formation was observed in

the disengagement phase with the low silica concentrations.

Tests of surrogate SS&C dissolver solutions with higher concentration of silica (less than 150 ppm) did show that gelatin

strike followed by centrifugation resulted in good phase disengagement of the surrogate SS&C dissolver solution from

the plant dissolver solution. At the higher silica concentrations, there is not sufficient fluoride to complex with the

silica, and the silica must be entrained by the gelatin and removed from the dissolver solution prior to solvent extraction.

781

(WSRC-TR–98-00188)

Solubility Limits of Dibutyl Phosphoric Acid in Uranium

Solutions at SRS. Thompson, M.C. (Westinghouse Savannah River Company, AIKEN, SC (United States)); Pierce,

R.A.; Ray, R.J. Westinghouse Savannah River Company,

Aiken, SC (United States);Westinghouse Savannah River

Co., Aiken, SC (United States). Jun 1998. 13p. Sponsored

by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract AC09-96SR18500.

Order Number DE98054753. Source: OSTI; INIS; NTIS;

GPO Dep.

The Savannah River Site has enriched uranium (EU) solution which has been stored for almost 10 years since being

purified in the second uranium cycle of the H area solvent

extraction process. The concentrations in solution are 6 g/L  ̃

U and about 0.1 M nitric acid. Residual tributylphosphate in

the solutions has slowly hydrolyzed to form dibutyl phosphoric acid (HDBP) at concentrations averaging 50 mg/L.

Uranium is known to form compounds with DBP which have

limited solubility. The potential to form uranium-DBP solids

raises a nuclear criticality safety issue. SRTC tests have

shown that U-DBP solids will precipitate at concentrations

potentially attainable during storage of enriched uranium solutions. Evaporation of the existing EUS solution without

additional acidification could result in the precipitation of UDBP solids if DBP concentration in the resulting solution

exceeds 110 ppm at ambient temperature. The same potential exists for evaporation of unwashed 1CU solutions. The

most important variables of interest for present plant operations are HNO3 and DBP concentrations. Temperature is

also an important variable controlling precipitation. The data

obtained in these tests can be used to set operating and

safety limits for the plant. It is recommended that the data

for 0 degrees C with 0.5 M HNO3 be used for setting the

limits. The limit would be 80 mg/L which is 3 standard deviations below the average of 86 observed in the tests. The

data shows that super-saturation can occur when the DBP

concentration is as much as 50 percent above the solubility

limit. However, super-saturation cannot be relied on for

maintaining nuclear criticality safety. The analytical method

for determining DBP concentration in U solutions was improved so that analyses for a solution are accurate to within

10 percent. However, the overall uncertainty of results for

periodic samples of the existing EUS solutions was only reduced slightly. (Abstract truncated)

782

(WSRC-TR–98-00202)

Commercial Light Water Reactor Irradiated Hardware

Waste Stream. Adamson, D.J. (Westinghouse Savannah

River Company, AIKEN, SC (United States)). Westinghouse

Savannah River Company, Aiken, SC (United States). Jun

1998. 15p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract AC09-96SR18500. Order Number DE98058683.

Source: OSTI; NTIS; INIS; GPO Dep.

The Commercial Light Water Reactor (CLWR) Production

of Tritium is one of two options being investigated by the

DOE for producing tritium, an essential element of our nation’s nuclear stockpile.

783

(WSRC-TR–98-00223)

High Level Waste Evaporator Analysis Results. Wilmarth,

W.R. (Westinghouse Savannah River Company, AIKEN, SC

(United States)). Westinghouse Savannah River Company,

Aiken, SC (United States). 16 Jun 1998. 24p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States). DOE Contract AC09-96SR18500. Order

Number DE98058320. Source: OSTI; NTIS; INIS; GPO Dep.

This report discusses analyses of samples from the Fand H-Area Evaporator Feed and Concentrate Tanks for the

period January of 1994 through January of 1997. Analyses

include measurements of density, Cs-137 radioactivity, and

concentration of actinide elements.. Statistical analysis of

the data also includes previous samples dating as early as

1991. This data helps understand the behavior of fissile actinides in the evaporator system.

784

(Y/ER–293)

Experimental bypass of Lake Reality, Oak Ridge Y-12

Plant, Oak Ridge, Tennessee. Oak Ridge Y-12 Plant, TN

(United States). Oct 1997. 17p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States). DOE Contract AC05-84OR21400. Order Number

DE98000607. Source: OSTI; NTIS; INIS; GPO Dep.

Studies conducted by the Y-12 Reduction of Mercury in

Plant Effluent (RMPE) Program and Y-12 Biological Monitoring and Abatement Program (BMAP) in 1995 and 1996 (Y/

ER-251, Y/ER-277) identified concerns regarding Lake Reality’s effect on the transport and transformation of mercury

in East Fork Poplar Creek (EFPC). The pond appeared to

have two potentially adverse effects on mercury transport.

First, it acted as a biochemical reactor, converting inorganic

mercury in inflowing water to methylmercury, a more toxic

substance with extremely high bioaccumulation potential in

aquatic environments. Second, the pond appeared to trap

mercury associated with suspended particulates during periods of stormflow, and slowly released that mercury via the

export of resuspended particles during periods of baseflow.

The net effect was to raise the day-to-day exposure of

aquatic life to mercury in the stream downstream from the

pond, and add to the calculated mercury loading of the

stream under baseflow conditions. Scientific investigations

thus indicated that diversion of the flow of EFPC around

Lake Reality had the potential to reduce time-averaged concentrations of methylmercury and total mercury in the creek

below its discharge, but that such diversion might also interfere with possible beneficial effects of the retention pond.

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ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

Therefore, an experimental bypass of the pond was undertaken in late 1996 to evaluate the consequences of such an

action before embarking on a more permanent change.

785

(Y/ER–301)

Bear Creek Valley Floodplain Hot Spot Removal Action

Project Plan, Oak Ridge Y-12 Plant, Oak Ridge, Tennessee. Oak Ridge Y-12 Plant, TN (United States). Jan

1998. 17p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract AC05-84OS21400. Order Number DE98001771.

Source: OSTI; NTIS; INIS; GPO Dep.

The Bear Creek Valley Floodplain Hot Spot Removal Action Project Plan, Oak Ridge Y-12 Plant, Oak Ridge,

Tennessee (Y/ER-301) was prepared (1) to safely, costeffectively, and efficiently evaluate the environmental impact

of solid material in the two debris areas in the context of industrial land uses (as defined in the Bear Creek Valley

Feasibility Study) to support the Engineering Evaluation/Cost

Assessment and (2) to evaluate, define, and implement the

actions to mitigate these impacts. This work was performed

under Work Breakdown Structure 1.x.01.20.01.08.

786

(Y/ER–305)

Phase 2 confirmatory sampling data report, Lower East

Fork Poplar Creek, Oak Ridge Y-12 Plant, Oak Ridge,

Tennessee. Oak Ridge Y-12 Plant, TN (United States); Science Applications International Corp., Oak Ridge, TN

(United States). Jan 1998. [300p.] Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States). DOE Contract AC05-84OS21400. Order Number

DE98003282. Source: OSTI; NTIS; INIS; GPO Dep.

A Remedial Investigation of East Fork Poplar Creek

(EFPC) concluded that mercury is the principal contaminant

of concern in the EFPC floodplain. The highest concentrations of mercury were found to be in a visually distinct black

layer of soil that typically lies 15 to 30 cm (6 to 12 in.) below

the surface. Mercury contamination was found to be situated

in distinct areas along the floodplain, and generally at

depths > 20 cm (8 in.) below the surface. In accordance

with Comprehensive, Environmental Response, Compensation, and Liability Act (CERCLA), a feasibility study was

prepared to assess alternatives for remediation, and a proposed plan was issued to the public in which a preferred

alternative was identified. In response to public input, the

plan was modified and US Department of Energy (DOE) issued a Record of Decision in 1995 committing to excavating

all soil in the EFPC floodplain exceeding a concentration of

400 parts per million (ppm) of mercury. The Lower East Fork

Poplar Creek (LEFPC) remedial action (RA) focuses on the

stretch of EFPC flowing from Lake Reality at the Y-12 Plant,

through the city of Oak Ridge, to Poplar Creek on the Oak

Ridge Reservation (ORR) and its associated floodplain.

Specific areas were identified that required remediation at

the National Oceanographic and Atmospheric Administration

(NOAA) Site along Illinois Avenue and at the Bruner Site

along the Oak Ridge Turnpike. The RA was conducted in

two separate phases. Phase 2, conducted from February to

October 1997, completed the remediation efforts at the

NOAA facility and fully remediated the Bruner Site. During

both phases, data were collected to show that the remedial

efforts performed at the NOAA and Bruner sites were successful in implementing the Record of Decision and had no

adverse impact on the creek water quality or the city of Oak

Ridge publicly owned treatment works.

787

(Y/ER–306)

Work plan for mercury treatability study in upper east

fork Popular Creek at DOE’s Y-12 Site in support of the

Reduction of Mercury in Plant Effluent program (RMPE).

Oak Ridge Y-12 Plant, TN (United States). Feb 1998. 14p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC05-84OS21400. Order Number DE98004069. Source:

OSTI; NTIS; INIS; GPO Dep.

Over the past ten years the Department of Energy Y-12

Site’s Reduction of Mercury in Plant Effluents (RMPE)

project has carried out an aggressive investigative program

of identifying sources of mercury which are influencing the

levels of mercury in Upper East Fork Popular Creek

(UEFPC) and exiting the site at Station 17. The driver for

these activities has been and continues to be the site’s National Pollution Discharge Elimination Permit (NPDES). This

permit establishes certain remedial actions, the schedule for

these actions and requires that the mercury in the creek be

equal to or less than 5 grams per day by December 31,

1998 and the concentration in the creek be equal to or less

than 0.12  grams per liter on the last day of the permit,

April 27, 2000.

788

(Y/ER–308)

Work plan for support to Upper East Fork Poplar Creek

east end VOC plumes well installation project at the Oak

Ridge Y-12 Plant, Oak Ridge, Tennessee. Oak Ridge Y-12

Plant, TN (United States);Science Applications International

Corp., Oak Ridge, TN (United States). Mar 1998. 32p.

Sponsored by USDOE Office of Environmental Management, Washington, DC (United States). DOE Contract

AC05-84OR21400. Order Number DE98004691. Source:

OSTI; NTIS; INIS; GPO Dep.

Under the Resource Conservation and Recovery Act of

1976 guidelines and requirements from the Tennessee Department of Environment and Conservation (TDEC), the

Y-12 Plant initiated investigation and monitoring of various

sites within its boundaries in the mid-1980s. The entire Oak

Ridge Reservation (ORR) was placed on the National Priorities List of the Comprehensive Environmental Response,

Compensation, and Liability Act of 1980 (CERCLA) sites in

November 1989. Following CERCLA guidelines, sites within

the ORR require a remedial investigation (RI) to define the

nature and extent of contamination, evaluate the risks to

public health and the environment, and determine the goals

for a feasibility study (FS) or an engineering evaluation/cost

analysis (EE/CA) of potential remedial actions. Data from

monitoring wells at the east end of the Y-12 Plant have

identified an area of groundwater contamination dominated

by the volatile organic compound (VOC) carbon tetrachloride; other VOCs include chloroform, tetrachloroethene, and

trichloroethene.

789

(Y/ER–310)

Field sampling and analysis plan for the removal action

at the former YS-860 Firing Ranges, Oak Ridge Y-12

Plant, Oak Ridge, Tennessee. Lockheed Martin Energy

Systems, Inc., Oak Ridge, TN (United States);ENTECH,

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Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

Inc., Oak Ridge, TN (United States). Mar 1998. 28p. Sponsored by USDOE Office of Environmental Management,

Washington, DC (United States);USDOE, Washington, DC

(United States). DOE Contract AC05-84OR21400. Order

Number DE98004548. Source: OSTI; NTIS; INIS; GPO Dep.

The former YS-860 Firing Ranges are located at the eastern end of the Oak Ridge Y-12 Plant outside the primary

facility fence line and west of Scarboro Road within the

Upper East Fork Poplar Creek watershed in Oak Ridge, Tennessee. A decision has been made by the US Department

of Energy to conduct a removal action of lead-contaminated

soils at this site as part of early source actions within the

Upper East Fork Poplar Creek watershed. This non-time

critical removal action of bullets and lead-contaminated soil

from the YS-860 Firing Ranges is being conducted as a

Comprehensive Environmental Response, Compensation,

and Liability Act of 1980 action. These actions are consistent with the Oak Ridge Reservation Environmental

Restoration Program. The removal action will focus on the

excavation of bullets and lead-contaminated soil from the

shooting range berms, transportation of the material to a

permitted treatment facility for disposal, demolition and land

filling of a concrete trench and asphalt pathways at the site,

and grading and revegetating of the entire site. This report

is the field sampling and analysis plan for the removal action

at the former YS-860 Firing Ranges. The field sampling and

analysis plan addresses environmental sampling for lead after the removal of lead-contaminated soil from the target

berm area. The objective of this sampling plan is to obtain

sufficient analytical data to confirm that the removal action

excavation has successfully reduced lead levels in soil to

below the action level of 1,400 micrograms/g.

790

(Y/ER–311)

Data management implementation plan for the removal

action at the former YS-860 Firing Ranges, Oak Ridge Y12 Plant, Oak Ridge, Tennessee. Lockheed Martin Energy

Systems, Inc., Oak Ridge, TN (United States);ENTECH,

Inc., Oak Ridge, TN (United States). Mar 1998. 36p. Sponsored by USDOE Office of Environmental Management,

Washington, DC (United States);USDOE, Washington, DC

(United States). DOE Contract AC05-84OR21400. Order

Number DE98004550. Source: OSTI; NTIS; INIS; GPO Dep.

The former YS-860 Firing Ranges are located outside the

primary facility fenceline at the Y-12 Plant within the Upper

East Fork Poplar Creek watershed. The lead-contaminated

soils at this site will be removed as part of early source actions of the Oak Ridge Reservation Environmental

Restoration Program. The removal action will focus on the

excavation of bullets and lead-contaminated soil from the

shooting range berms, transportation of the material to a

certified treatment and/or disposal facility, demolition and

landfilling of a concrete trench and asphalt pathways, and

grading and revegetating of the entire site. The primary purpose of environmental data management is to provide a

system for generating and maintaining technically defensible

data. To meet current regulatory requirements for the Environmental Restoration Program, complete documentation of

the information flow must be established. This necessitates

that each step in the data management process (collection,

management, storage, and analysis) be adequately planned

and documented. This document will serve to identify data

management procedures, expected data types and flow, and

roles and responsibilities for all data management activities

associated with the YS-860 Firing Ranges removal action.

791

(Y/ER–313)

Health and safety plan for the removal action at the former YS-860 Firing Ranges, Oak Ridge Y-12 Plant, Oak

Ridge, Tennessee. Lockheed Martin Energy Systems, Inc.,

Oak Ridge, TN (United States);ENTECH, Inc., Oak Ridge,

TN (United States). 24 Mar 1998. 42p. Sponsored by USDOE Office of Environmental Management, Washington, DC

(United States);USDOE, Washington, DC (United States).

DOE Contract AC05-84OR21400. Order Number

DE98004549. Source: OSTI; NTIS; INIS; GPO Dep.

This health and safety plan sets forth the requirements

and procedures to protect the personnel involved in the removal action project at the former YS-860 Firing Ranges.

This project will be conducted in a manner that ensures the

protection of the safety and health of workers, the public,

and the environment. The purpose of this removal action is

to address lead-contaminated soil and reduce a potential

risk to human health and the environment. This site is an

operable unit within the Upper East Fork Poplar Creek watershed. The removal action will contribute to early source

actions within the watershed. The project will accomplish

this through the removal of lead-contaminated soil in the target areas of the two small arms firing ranges. The primary

hazards include temperature extremes, equipment operation, noise, potential lead exposure, uneven and slippery

working surfaces, and insects.

792

(Y/ER–314)

Quality assurance project plan for the removal action at

the former YS-860 Firing Ranges, Oak Ridge Y-12 Plant,

Oak Ridge, Tennessee. Lockheed Martin Energy Systems,

Inc., Oak Ridge, TN (United States);ENTECH, Inc., Oak

Ridge, TN (United States). Mar 1998. 31p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States);USDOE, Washington, DC (United

States). DOE Contract AC05-84OR21400. Order Number

DE98004547. Source: OSTI; INIS; NTIS; GPO Dep.

This quality assurance project plan defines project organization and roles of responsibility, sampling and field

procedures, sample documentation and chain-of-custody

protocols, equipment calibration, analytical procedures, data

reduction and validation, and internal quality control procedures for the former YS-860 Firing Ranges removal action

at the Oak Ridge Y-12 Plant. The ENTECH Team will maintain the highest standards to ensure strict compliance with

this plan. Implementation of this plan will include consideration of the technical, as well as administrative, aspects of

activities affecting quality. Plan implementation is based on

the premise that quality controls selected for each element

of work are consistent with the risk, importance, and health

and safety considerations of performing the work. The purpose of this removal action is to address lead-contaminated

soil and reduce a potential risk to human health and the environment. This site is an operable unit within the Upper

East Fork Poplar Creek watershed. The removal action will

contribute to early source actions within the watershed. The

project will accomplish this through the removal of leadcontaminated soil in the target areas of two small arms firing

ranges. This plan covers the removal action at the former

201
ENVIRONMENTAL MANAGEMENT Environmental Management Technical Reports

YS-86O Firing Ranges. These actions involve the excavation of lead-contaminated soils, the removal of the concrete

trench and macadam (asphalt) paths, verification sampling,

grading, and revegetation.

793

(Y/ER–315)

Waste management plan for the removal action at the

former YS-860 Firing Ranges, Oak Ridge Y-12 Plant,

Oak Ridge, Tennessee. Lockheed Martin Energy Systems,

Inc., Oak Ridge, TN (United States);ENTECH, Inc., Oak

Ridge, TN (United States). Mar 1998. 24p. Sponsored by

USDOE Office of Environmental Management, Washington,

DC (United States);USDOE, Washington, DC (United

States). DOE Contract AC05-84OR21400. Order Number

DE98004546. Source: OSTI; INIS; NTIS; GPO Dep.

This waste management plan defines the procedures for

control and management of waste generated as a result of

the removal action of the YS-86O Firing Ranges site at the

Oak Ridge Y-12 Plant. This document includes plan

objectives; remediation activities; key personnel; waste generation activities; and waste treatment, storage,

transportation, and disposal. Methods of control and characterization of waste generated as a result of remediation

activities will be within the guidelines and procedures outlined herein. ENTECH personnel will make every effort

when conducting remediation and decontamination activities

to minimize the amount of generated waste.

794

(Y/ER–316)

Reduction of mercury in plant effluents data management implementation plan, FY 1998, Oak Ridge Y-12

Plant, Oak Ridge, Tennessee. Fischer, K.N.; Forsberg,

V.M. Lockheed Martin Energy Systems, Inc., Oak Ridge, TN

(United States). 26 Mar 1998. 110p. Sponsored by USDOE

Office of Environmental Management, Washington, DC

(United States);USDOE, Washington, DC (United States).

DOE Contract AC05-84OR21400. Order Number

DE98004552. Source: OSTI; NTIS; INIS; GPO Dep.

The purpose of the Data Management Implementation

Plan (DMIP) is to document the requirements and responsibilities for managing, using, and archiving data used for the

Reduction of Mercury in Plant Effluents (RMPE) project. The

DMIP was created for the RMPE project in accordance with

the guidance given in Environmental Data Management Implementation Handbook for the Environmental Restoration

Program (ES/ER/TM- 88/R 1) and in “Developing, implementing, and Maintaining Data Management Implementation

Plans” (EMEF/ER-P2216, Rev. 0). This document reflects

the state of the RMPE project and the types of environmental monitoring planned as they existed through March 16,

1998. The scope of this document is the management of the

RMPE project’s environmental information, which includes

electronic or hard copy records describing environmental

processes or conditions. The RMPE program was established as a best management practice to address sources in

the Y-12 Plant that contribute mercury to plant effluents being discharged to Upper East Fork Poplar Creek. The

strategy is multifaceted: reroute clean water through clean

conduits; clean, reline, and/or replace mercury-contaminated

water conduits; eliminate or reduce accumulations of mercury in tanks and sumps; isolate inaccessible mercury from

contact with water; and install treatment capability for

streams where the source(s) cannot be eliminated or mitigated to acceptable levels. The RMPE project database

consists of data from surface water monitoring and sediment

sampling at locations of interest within the Y-12 Plant. This

DMIP describes the types and sources of RMPE data, other

data systems relevant to the RMPE project, the different

data management interactions and flow of information involved in processing RMPE data, and the systems used in

data management.

795

(Y/ER–318)

Bear Creek Valley Floodplain hot spot removal early action characterization field data summary report, Oak

Ridge Y-12 Plant, Oak Ridge, Tennessee. Oak Ridge Y-12

Plant, TN (United States);ENTECH, Inc., Oak Ridge, TN

(United States). Apr 1998. 393p. Sponsored by USDOE Office of Environmental Management, Washington, DC (United

States). DOE Contract AC05-98OR22700. Order Number

DE98004590. Source: OSTI; NTIS; INIS; GPO Dep.

This report summarizes the field and laboratory efforts as

a result of the Bear Creek Floodplain Hot Spot Removal

Project Early Action. The purpose of this project was to collect data necessary to assess contaminant levels in the

Bear Creek Valley Floodplain and evaluate the risk posed by

the sites. This report provides information on the background of the site, characterization of site and field activities,

results of field and laboratory data collected, extent and distribution of contamination, and an assessment of the future

risk posed by the site.

796

(Y/ER–319)

Postremediation monitoring program baseline assessment report, Lower East Fork Poplar Creek, Oak Ridge

Y-12 Plant, Oak Ridge, Tennessee. Greeley, M.S. Jr. (Oak

Ridge National Lab., TN (United States)); Ashwood, T.L.;

Kszos, L.A.; Peterson, M.J.; Rash, C.D.; Southworth, G.R.;

Phipps, T.L. Oak Ridge Y-12 Plant, TN (United States). Apr

1998. 38p. Sponsored by USDOE Office of Financial Management and Controller, Washington, DC (United

States);USDOE Office of Environmental Management,

Washington, DC (United States). DOE Contract AC05-

98OR22700. Order Number DE98004587. Source: OSTI;

NTIS; INIS; GPO Dep.

Lower East Fork Poplar Creek (LEFPC) and its floodplain

are contaminated with mercury (Hg) from ongoing and historical releases from the US Department of Energy (DOE)

Oak Ridge Y-12 Plant. A remedial investigation and feasibility study of LEFPC resulted in the signing of a Record of

Decision (ROD) in August 1995. In response to the ROD,

soil contaminated with mercury above 400 mg/kg was removed from two sites in LEFPC and the floodplain during a

recently completed remedial action (RA). The Postremediation Monitoring Program (PMP) outlined in the LEFPC

Monitoring Plan was envisioned to occur in two phases: (1)

a baseline assessment prior to remediation and (2) postremediation monitoring. The current report summarizes the

results of the baseline assessment of soil, water, biota, and

groundwater usage in LEFPC and its floodplain conducted

in 1995 and 1996 by personnel of the Oak Ridge National

Laboratory Biological Monitoring and Abatement Program

(BMAP). This report also includes some 1997 data from

contaminated sites that did not undergo remediation during

the RA (i.e., sites where mercury is greater than 200 mg/kg

202
Environmental Management Technical Reports ENVIRONMENTAL MANAGEMENT

but less than 400 mg/kg). The baseline assessment described in this document is distinct and separate from both

the remedial investigation/feasibility study the confirmatory

sampling conducted by SAIC during the RA. The purpose of

the current assessment was to provide preremediation

baseline data for the LEFPC PMP outlined in the LEFPC

Monitoring Plan, using common approaches and techniques, as specified in that plan.

797

(Y/ER/MS–11-Rev.1)

Best management practices and work plan for installation of and monitoring at temporary weirs and flumes at

NT-3, NT-4, and NT-5 Oak Ridge Y-12 Plant, Oak Ridge,

Tennessee. Oak Ridge Y-12 Plant, TN (United States). Feb

1998. 12p. Sponsored by USDOE Office of Environmental

Management, Washington, DC (United States). DOE Contract AC05-84OS21400. Order Number DE98004148.

Source: OSTI; NTIS; INIS; GPO Dep.

This Best Management Practices (BMP) and Work Plan

has been developed in order to maintain compliance with

applicable regulatory requirements by documenting the

practices that are required during the installation and maintenance of temporary weirs and flumes at the NT-3, NT-4,

and NT-5 tributaries, subsequent collection of water discharge data, and removal of the weirs and flumes. The

practices included in this BMP comply with the Clean Water

Act and the intent of Sect. 70-8-104(b) of the Tennessee

Code Annotated: Tennessee Wildlife Resources Commission Proclamation 94-16 to prevent the destruction of the

habitat of state-listed wildlife species that are designated as

“in need of management.”

203
Corporate Author Index

This index lists the corporate authors responsible for issuing the documents in this publication which are identified primarily

by report number. The corporate names are entered in standardized forms as defined in ETDE/PUB–3 (Rev.1), International Energy: Research Organizations 1988–1992. Each entry under a corporate name includes the document title and

citation number. Three items of information may appear in parentheses: (1) an abbreviation to identify the document type,

such as a report; (2) the country of publication, indicated by International Organization for Standardization (ISO) country

code; and (3) the language of the document if non-English (R;CA;In French). Author affiliations are not listed in this index.

A

Advent Engineering Services, Inc., San Ramon, CA (United

States)

241-SY-101 strain concentration factor development via nonlinear

analysis. Volume 1 of 1, 98:422 (R;US)

Afton Associates, Inc., Washington, DC (United States)

LLW (Low-Level Waste) Notes, Volume 13, Number 1, February

1998, 98:206 (R;US)

LLW Forum meeting report, May 7–9, 1997, 98:202 (R;US)

LLW Forum meeting report, October 20–22, 1997, 98:203 (R;US)

LLW Notes, Volume 12, Number 8, 98:204 (R;US)

LLW Notes, Volume 12, Number 9, 98:205 (R;US)

Allied Technology Group, Inc., Oak Ridge, TN (United States)

Dismantlement and removal of Old Hydrofracture Facility bulk

storage bins and water tank, Oak Ridge National Laboratory,

Oak Ridge, Tennessee, 98:521 (R;US)

Ames Lab., IA (United States)

Performance testing of multi-metal continuous emissions monitors, 98:407 (R;US)

Performance testing of multi-metal continuous emissions monitors. Appendix Volume 1, 98:408 (R;US)

Performance testing of multi-metal continuous emissions monitors. Appendix Volume 2, 98:409 (R;US)

Argonne National Lab., Chemical Technology Div., IL (United

States)

A data base and a standard material for use in acceptance testing

of low-activity waste products, 98:2 (R;US)

Formulation of a candidate glass for use as an acceptance test

standard material, 98:3 (R;US)

Argonne National Lab., Energy Technology Div., IL (United

States)

Ultrasonic viscometer and methods of measuring solids concentration, 98:4 (R;US)

Argonne National Lab., Environmental Assessment Div., IL

(United States)

Evaluation of the area factor used in the RESRAD code for the estimation of airborne contaminant concentrations of finite area

sources, 98:25 (R;US)

Argonne National Lab., Idaho Falls, ID (United States)

Statistical signal processing and artificial intelligence applications in

the nondestructive assay of U/Pu bearing materials, 98:26 (R;US)

Argonne National Lab., IL (United States)

A comparative review of accident studies from recent assessments of emergency planning zone boundaries, 98:17 (R;US)

An AEM study of glass-palagonite interfaces formed in Hawaiian

basalt glasses, 98:7 (R;US)

An ultrasonic instrument for measuring density and viscosity of

tank waste, 98:37 (R;US)

Analysis of disposition alternatives for radioactively contaminated

scrap metal, 98:16 (R;US)

Argonne National Laboratory puts alternative-fuel vehicles to the

test, 98:32 (R;US)

Argonne National Laboratory’s photo-oxidation organic mixed waste

treatment system - installation and startup testing, 98:30 (R;US)

Characterization report for Building 301 Hot Cell Facility, 98:31

(R;US)

Chemistry, radiation, and interfaces in suspensions of nuclear

waste simulants, 98:5 (R;US)

Conceptual framework and technical basis for clearance of materials with residual radioactivity, 98:18 (R;US)

Consistency in accident analyses in DOE safety, environmental,

and emergency planning documents, 98:21 (R;US)

Deactivation of the EBR-II complex, 98:27 (R;US)

Decontamination and Decommissioning activities photobriefing

book FY 1997, 98:15 (R;US)

Decontamination and dismantlement of the JANUS Reactor at Argonne National Laboratory-East. Project final report, 98:14

(R;US)

Deployment of remote dismantlement systems at the CP-5 reactor, 98:41 (R;US)

D&D of a reactor, hot cells and gloveboxes - an integrated experience, 98:43 (R;US)

Effect of alteration phase formation on the glass dissolution rate,

98:12 (R;US)

Environmental risk assessment, 98:23 (R;US)

Evaluation of gamma radiation shielding for nuclear waste shipping casks, 98:38 (R;US)

Fission product solvent extraction, 98:484 (R;US)

Gas evolution during vitrification of sodium sulfate and silica,

98:13 (R;US)

Immobilization of fission products in phosphate ceramic waste

forms, 98:36 (R;US)

In-situ mineralization of actinides for groundwater cleanup: Laboratory demonstration with soil from the Fernald Environmental

Management Project, 98:6 (R;US)

Incorporation of pollution prevention and waste minimization practices during the decommissioning of Building 310 at Argonne

National Laboratory-East, 98:44 (R;US)

Large-scale demonstration of D&D technologies, 98:42 (R;US)

Leakage testing of packagings with three-O-ring closure seals,

98:35 (R;US)

Legal precedents regarding use and defensibility of risk assessment in Federal transportation of SNF and HLW, 98:19 (R;US)

Method of estimating the leakage of multiple barriers in a radioactive materials shipping package, 98:34 (R;US)

Microscopic analysis of Pu-contaminated incinerator ash: Implications for immobilization, 98:10 (R;US)

Nevada Risk Assessment/Management Program scientific peer

review, 98:22 (R;US)

Plutonium alteration phases from lanthanide borosilicate glass,

98:9 (R;US)

Production-scale LLW and RMW solidification system operational

testing at Argonne National Laboratory-East (ANL-E), 98:28

(R;US)

Pu and Gd chemistry of zirconolite polytypes in a titanate ceramic,

98:11 (R;US)

Reduction of Np(VI) and Pu(VI) by organic chelating agents,

98:689 (R;US)

Regulatory concerns for leakage testing of packagings with three

O-ring closure seals, 98:33 (R;US)

Release process for non-real property containing residual radioactive material, 98:20 (R;US)

Review of processes for the release of DOE real and non-real

property for reuse and recycle, 98:24 (R;US)

Short-term consistency testing vs. long-term behavior, 98:8 (R;US)

Surveillance of Site A and Plot M report for 1997, 98:1 (R;US)

204 Environmental Management Technical Reports
CDM Federal Programs Corp., Oak Ridge, TN (United States)

Systems engineering based planning for DOE D&D projects,

98:40 (R;US)

The restoration of an Argonne National Laboratory foundry, 98:29

(R;US)

VIM: Initial ENDF/B-VI experience, 98:39 (R;US)

Automated Solutions of Albuquerque, Inc., NM (United States)

Project report: Tritiated oil repackaging highlighting the ISMS process. Historical radioactive and mixed waste disposal request

validation and waste disposal project, 98:722 (R;US)

B

Battelle Memorial Inst., Columbus, OH (United States)

Chemistry, radiation, and interfaces in suspensions of nuclear

waste simulants, 98:5 (R;US)

Battelle, Columbus, OH (United States)

Field evaluation of recycled plastic lumber (RPL) pallets. Final

project report, 98:134 (R;US)

Bechtel Hanford, Inc., Richland, WA (United States)

105-DR Large Sodium Fire Facility Supplemental Information to the

Hanford Facility Contingency Plan (DOE/RL-93-75), 98:76 (R;US)

105-DR Large Sodium Fire Facility Inspection Plan, 98:77 (R;US)

105-F and DR Phase 1 Sampling and Analysis Plan, 98:277 (R;US)

111-B Metal Examination Facility Concrete Tank Interim Characterization Report, 98:73 (R;US)

1301-N Liquid Waste Disposal Facility Supplemental Information

to the Hanford Facility Contingency Plan, 98:48 (R;US)

1325-N Liquid Waste Disposal Facility Supplemental Information

to the Hanford Facility Contingency Plan (DOE/RL-93-75),

98:49 (R;US)

300 Area Process Trenches Postclosure Plan, 98:275 (R;US)

ALARA Review for the 202-S Plutonium Loadout Hood Sampling,

98:80 (R;US)

ALARA Review for the Decontamination, Deactivation and Housekeeping of the 233-S Viewing Room, 98:78 (R;US)

ALARA Review of the Activation/Repair of Fire Detectors in Zone

Three at the 233-S Facility, 98:79 (R;US)

Annular Kinetic Impactor Air Sampler, 98:67 (R;US)

Bechtel Hanford, Inc., RCRA Permit Implementation Plan, 98:46

(R;US)

Borehole Summary Report for the 216-B-2-2 Ditch, 98:75 (R;US)

Chemical Hygiene Plan for Onsite Measurement and Sample

Shipping Facility Activities, 98:50 (R;US)

Code of accounts. Management overview volume: Environmental

restoration, 98:56 (R;US)

Data Quality Objectives Report for the 115-B Gas Tunnel, 98:60

(R;US)

Description of Work for a Vadose Zone Characterization Borehole

at the 216-B-2-2 Ditch, 98:62 (R;US)

Environmental Monitoring Plan United States Department of Energy Richland Operations Office. Revision 2, 98:272 (R;US)

Environmental Restoration Disposal Facility Waste Acceptance

Criteria, 98:45 (R;US)

Environmental Restoration Project - Systems Engineering Management Plan, 98:53 (R;US)

Final Hazard Classification and Auditable Safety Analysis for the N

Basin Segment, 98:57 (R;US)

Final Hazard Classification and Auditable Safety Analysis for the

105-F Building Interim Safe Storage Project, 98:68 (R;US)

Hazard Classification and Auditable Safety Analysis for the 1300-

N Emergency Dump Basin, 98:52 (R;US)

Inspection, Monitoring, and Maintenance Plan for the 300 Area

Process Trenches, 98:72 (R;US)

N Area Final Project Program Plan, 98:66 (R;US)

Operations and Maintenance Manual for the Temporary Septic

Holding Tank at the 100-C Remedial Action Support Facility,

98:54 (R;US)

Operations and Maintenance Manual for the Temporary Septic

Holding Tank at the 100-C Remedial Action Restroom Facility,

98:55 (R;US)

RCRA corrective measure study for the 200-PO-1 operable unit,

98:273 (R;US)

Sampling and Analysis Instruction for the 120-F-1 Glass Dump

Site, 98:61 (R;US)

Sampling and Analysis Plan for the 216-A-29 Ditch, 98:64 (R;US)

Sampling and Analysis Plan for the REDOX Plutonium Loadout

Hood, 98:274 (R;US)

Site-Specific Health and Safety Plan, 233-S Decontamination and

Decommissioning, 98:51 (R;US)

Site-Specific Waste Management Instruction - 100-DR-1 Group 2

Sites, 98:65 (R;US)

Surveillance and Maintenance Plan for the Plutonium Uranium Extraction (PUREX) Facility, 98:276 (R;US)

Survey Method for Radiological Surveys of 300-FF-1 Operable

Unit Soils and Material, 98:59 (R;US)

Technical Basis to Describe the Use of the Eberline E-600, 98:63

(R;US)

The Necessary and Sufficient Closure Process Completion Report

for Purex FacilitySurveillance and Maintenance, 98:58 (R;US)

Unit-Specific Contingency Plan for the 183-H Solar Evaporation

Basins, 98:47 (R;US)

Vadose Zone Clean Closure Report for the 300 Area Process

Trenches, 98:74 (R;US)

Bechtel Jacobs Co. LLC, Oak Ridge, TN (United States)

Contingency plan for the Old Hydrofracture Facility Tanks Sluicing

Project at Oak Ridge National Laboratory, Oak Ridge, Tennessee, 98:84 (R;US)

Bechtel Jacobs Co., Environmental Compliance Div., Piketon,

OH (United States)

Portsmouth annual environmental report for 1997, 98:262 (R;US)

Bechtel Jacobs Co., Oak Ridge, TN (United States)

Evaluation of the Molten Salt Reactor Experiment drain tanks for

reuse in salt disposal, Oak Ridge National Laboratory, Oak

Ridge, Tennessee, 98:83 (R;US)

Guidance for treatment of variability and uncertainty in ecological

risk assessments of contaminated sites, 98:86 (R;US)

In-Process Analysis Program for the Isolock sampler at the Gunite

and Associated Tanks, Oak Ridge National Laboratory, Oak

Ridge, Tennessee, 98:81 (R;US)

Bechtel Nevada Inc., Las Vegas, NV (United States)

Establishment of a facility for intrusive characterization of transuranic waste at the Nevada Test Site, 98:259 (R;US)

Remedial actions of nuclear safety shot sites: Double Tracks and

Clean Slates, 98:260 (R;US)

Benchmark Environmental Corp., Albuquerque, NM (United

States)

Draft test plan for hydrogen getters project, 98:461 (R;US)

Test plan for headspace gas sampling of remote-handled transuranic waste containers at Los Alamos National Laboratory,

98:460 (R;US)

Test plan for hydrogen getters project, 98:458 (R;US)

Brookhaven National Lab., Upton, NY (United States)

Commercialization of the polyethylene macroencapsulation process, 98:89 (R;US)

Northeast Waste Management Enterprise (NEWME) 1996 annual/final report, 98:87 (R;US)

Overview of environmental decision support software, 98:88 (R;US)

C

Cal Poly Pomona Foundation, Pomona, CA (United States)

Greenhouse of the future. Final report, 98:197 (R;US)

CDM Federal Programs Corp., Oak Ridge, TN (United States)

ALARA plan for the Old Hydrofracture Facility tanks contents removal project at Oak Ridge National Laboratory, Oak Ridge,

Tennessee, 98:518 (R;US)

ALARA plan for the Old Hydrofracture Facility tanks contents removal project at Oak Ridge National Laboratory, Oak Ridge,

Tennessee. Amendment 1 for Appendix B: Install flex-pipe on

tank riser spools, 98:519 (R;US)

Old hydrofracture facility tanks contents removal action operations

plan at the Oak Ridge National Laboratory, Oak Ridge, Tennessee. Volume 2: Checklists and work instructions, 98:175

(R;US)

Environmental Management Technical Reports 205
CDM Federal Programs Corp., Oak Ridge, TN (United States)

Old hydrofracture facility tanks contents removal action operations

plan at the Oak Ridge National Laboratory, Oak Ridge,

Tennessee. Volume 1: Text. Volume 2: Checklists and work instructions, 98:520 (R;US)

Project management plan for Waste Area Grouping 5 Old

Hydrofracture Facility tanks contents removal at Oak Ridge National Laboratory, Oak Ridge, Tennessee, 98:85 (R;US)

Project management plan for Waste Area Grouping 5 Old

Hydrofracture Facility tanks contents removal at Oak Ridge National Laboratory, Oak Ridge, Tennessee, 98:509 (R;US)

CDM Federal Programs Corp., Oak Ridge, TN 37830 (United

States)

Cold test plan for the Old Hydrofracture Facility tank contents removal project, Oak Ridge National Laboratory, Oak Ridge,

Tennessee, 98:514 (R;US)

Coleman Research Corp., Springfield, VA (United States)

Base program interim phase test procedure - Coherent Laser Vision System (CLVS). Final report, September 27, 1994–January

30, 1997, 98:227 (R;US)

Crownpoint Inst. of Tech. (United States)

Tribal Colleges Initiative project. Quarterly report, April 1–June 30,

1998, 98:281 (R;US)

Crownpoint Inst. of Tech., NM (United States)

Tribal Colleges Initiative project. Quarterly report, April 1–June 30,

1998, 98:280 (R;US)

D

Department of Agriculture, Washington, DC (United States)

Precision agriculture in the 21st Century: Geospatial and information technologies in crop management, 98:194 (R;US)

Department of Energy, Office of Environmental Management,

Washington, DC (United States)

Report to Congress on the U.S. Department of Energy’s Environmental Management Science Program: Research funded and

its linkages to environmental cleanup problems. Volume 1 of 3 –

Report and Appendix A, 98:159 (R;US)

Report to Congress on the U.S. Department of Energy’s Environmental Management Science Program: Research funded and

its linkages to environmental cleanup problems, and Environmental Management Science Program research award

abstracts. Volume 2 of 3 – Appendix B, 98:160 (R;US)

Report to Congress on the U.S. Department of Energy’s Environmental Management Science Program: Research funded and

its linkages to environmental cleanup problems, and high outyear cost environmental management project descriptions.

Volume 3 of 3 – Appendix C, 98:161 (R;US)

Dept. of Energy Assistant Secretary for Environmental Management, Office of the Deputy Assistant Secretary for Science

and Technology, Washington, DC (United States)

Proceedings of a workshop on uses of depleted uranium in storage, transportation and repository facilities, 98:151 (R;US)

Dept. of Energy, Albuquerque Operations Office, NM (United

States)

Annual report of waste generation and pollution prevention

progress 1997, 98:165 (R;US)

Dept. of Energy, Environmental Measurement Lab., New York,

NY (United States)

Semi-annual report of the Department of Energy, Office of Environmental Management, Quality Assessment Program, 98:293

(R;US)

Dept. of Energy, Environmental Measurements Lab., New York,

NY (United States)

A portable battery-powered continuous airborne 222Rn sampler,

98:290 (R;US)

ISD97, a computer program to analyze data from a series of in situ

measurements on a grid and identify potential localized areas of

elevated activity, 98:288 (R;US)

MAXED, a computer code for the deconvolution of multisphere

neutron spectrometer data using the maximum entropy method,

98:292 (R;US)

Preparation and validation of gross alpha/beta samples used in

EML’s quality assessment program, 98:289 (R;US)

Dept. of Energy, Environmental Measurements Laboratory, New

York, NY (United States)

Semi-annual report of the Department of Energy, Office of Environmental Management, Quality Assessment Program, 98:291

(R;US)

Dept. of Energy, Office of Environmental Management, Washington, DC (United States)

Accelerating cleanup: Paths to closure, 98:164 (R;US)

EM international activities: May 1998 highlights, 98:173 (R;US)

Innovative technology summary report: Houdini I and II remotely

operated vehicle, 98:166 (R;US)

Innovative technology summary report: Transportable vitrification

system, 98:167 (R;US)

Innovative technology summary report: Confined sluicing end effector, 98:168 (R;US)

Innovative technology summary report: Concrete grinder, 98:169

(R;US)

Innovative technology summary report: High-speed clamshell pipe

cutter, 98:170 (R;US)

Innovative technology summary report: System for Tracking Remediation, Exposure, Activities and Materials, 98:171 (R;US)

Innovative technology summary report: Sealed-seam sack suits,

98:172 (R;US)

Uranium Mill Tailings Remedial Action Project fiscal year 1997 annual report to stakeholders, 98:132 (R;US)

Dept. of Energy, Office of Science and Technology, Washington, DC (United States)

Integrated process analyses studies on mixed low level and transuranic wastes. Summary report, 98:152 (R;US)

Dept. of Energy, Office of Scientific and Technical Information,

Oak Ridge, TN (United States)

The Office of Environmental Management technical reports: A bibliography, 98:270 (R;US)

Dept. of Energy, Office of Spent Fuel Management and Special

Projects, Washington, DC (United States)

Deployment evaluation methodology for the electrometallurgical

treatment of DOE-EM spent nuclear fuel, 98:284 (R;US)

Dept. of Energy, Washington, DC (United States)

Centrifugal shot blast system, 98:149 (R;US)

GammaCam radiation imaging system, 98:148 (R;US)

Rotary peening with captive shot, 98:147 (R;US)

ROTO PEEN Scalar and VAC-PAC system, 98:146 (R;US)

Surface Contamination Monitor and Survey Information Management System, 98:150 (R;US)

Dine Coll., Tsaile, AZ (United States)

Tribal Colleges Initiative project. Quarterly report, April 1–June 30,

1998, 98:280 (R;US)

Dine’ Coll., Tsaile, AZ (United States)

Tribal Colleges Initiative project. Quarterly report, April 1–June 30,

1998, 98:281 (R;US)

E

EG and G Idaho, Inc., Idaho Falls, ID (United States)

High performance APCS conceptual design and evaluation scoping study, 98:340 (R;US)

EG and G Rocky Flats, Inc., Golden, CO (United States)

Basis of Estimate Software Tool (BEST) - a practical solution to

part of the cost and schedule integration puzzle, 98:613 (R;US)

Workforce mobilization for D&D at the Rocky Flats Environmental

Technology Site (RFETS), 98:615 (R;US)

EG and G Rocky Flats, Inc., Golden, CO (United States). Rocky

Flats Plant

Natural succession impeded by smooth brome (Bromus inermis)

and intermediate wheatgrass (Agropyron intermedium) in an

abandoned agricultural field, 98:617 (R;US)

ENTECH, Inc., Oak Ridge, TN (United States)

Bear Creek Valley Floodplain hot spot removal early action characterization field data summary report, Oak Ridge Y-12 Plant,

Oak Ridge, Tennessee, 98:795 (R;US)

Data management implementation plan for the removal action at

the former YS-860 Firing Ranges, Oak Ridge Y-12 Plant, Oak

Ridge, Tennessee, 98:790 (R;US)

206 Environmental Management Technical Reports
Idaho National Engineering Lab., Idaho Falls, ID (United States)

Field sampling and analysis plan for the removal action at the former YS-860 Firing Ranges, Oak Ridge Y-12 Plant, Oak Ridge,

Tennessee, 98:789 (R;US)

Health and safety plan for the removal action at the former YS-860

Firing Ranges, Oak Ridge Y-12 Plant, Oak Ridge, Tennessee,

98:791 (R;US)

Quality assurance project plan for the removal action at the former

YS-860 Firing Ranges, Oak Ridge Y-12 Plant, Oak Ridge, Tennessee, 98:792 (R;US)

Removal action work plan for the YS-860 Firing Ranges, Oak

Ridge Y-12 Plant, Oak Ridge, Tennessee, 98:261 (R;US)

Waste management plan for the removal action at the former

YS-860 Firing Ranges, Oak Ridge Y-12 Plant, Oak Ridge, Tennessee, 98:793 (R;US)

Environmental Evaluation Group, Albuquerque, NM (United

States)

Evaluation of the WIPP Project’s compliance with the EPA radiation protection standards for disposal of transuranic waste,

98:125 (R;US)

Mine stability evaluation of panel 1 during waste emplacement operations at WIPP, 98:287 (R;US)

Probability of failure of the waste hoist brake system at the Waste

Isolation Pilot Plant (WIPP), 98:286 (R;US)

Environmental Evaluation Group, Carlsbad, NM (United States)

Evaluation of the WIPP Project’s compliance with the EPA radiation protection standards for disposal of transuranic waste,

98:125 (R;US)

Mine stability evaluation of panel 1 during waste emplacement operations at WIPP, 98:287 (R;US)

Environmental Science and Research Foundation Inc., Idaho

Falls, ID (United States)

Landowner and permit-holder perceptions of wildlife damage

around the Idaho National Engineering and Environmental Laboratory. A survey of INEEL neighbors about elk, mule deer,

pronghorn antelope, and depredation, 98:294 (R;US)

Environmental Science and Research Foundation, Inc., Idaho

Falls, ID (United States)

Environmental Science and Research Foundation, Inc. annual

technical report: Calendar year 1997, 98:295 (R;US)

F

F2 Associates, Inc., Albuquerque, NM (United States)

Commercialization plan laser-based decoating systems, 98:216

(R;US)

Fermi National Accelerator Lab., Batavia, IL (United States)

118-C-4 Horizontal Rod Cave Characterization Report, 98:69

(R;US)

ALARA Review for the Sediment Relocation and Removal from

the 105-N Fuel Storage Basin, 98:71 (R;US)

Cleanup Verification Package for the 107-D5 Trench, 98:70 (R;US)

Florida International Univ., Miami, FL (United States)

Assessment of strippable coatings for decontamination and decommissioning, 98:184 (R;US)

Investigation of waste glass pouring behavior over a knife edge,

98:180 (R;US)

Large-bore pipe decontamination, 98:186 (R;US)

Melting, solidification, remelting, and separation of glass and

metal, 98:182 (R;US)

Microwave combustion and sintering without isostatic pressure,

98:185 (R;US)

Plant stress analysis technology deployment, 98:183 (R;US)

Sensor for viscosity and shear strength measurement, 98:181

(R;US)

Fluor Daniel Fernald, Inc., Cincinnati, OH (United States)

Presidential Rapid Commercialization Initiative for mixed waste

solvent extraction, 98:296 (R;US)

Fluor Daniel Hanford, Inc., Richland, WA (United States)

Environmental Monitoring Plan United States Department of Energy Richland Operations Office. Revision 2, 98:272 (R;US)

G

General Electric Co., Schenectady, NY (United States). Corporate Research and Development Center

Rapid Surface Sampling and Archival Record (RSSAR) System.

Topical report, October 1, 1993–December 31, 1994, 98:214

(R;US)

Rapid surface sampling and archival record system (RSSAR),

98:213 (R;US)

Geological Survey, Carson City, NV (United States)

Estimated ground-water discharge by evapotranspiration, Ash

Meadows Area, Nye County, Nevada, 1994, 98:726 (R;US)

Geological Survey, Denver, CO (United States)

Geophysical interpretations west of and within the northwestern

part of the Nevada Test Site, 98:727 (R;US)

Geological Survey, Lincoln, NE (United States)

Description of the U.S. Geological Survey’s water-quality sampling

and water-level monitoring program at the Hallam Nuclear Facility, June through September 1996, 98:135 (R;US)

Geological Survey, Rolla, MO (United States)

Ground-water flow and ground- and surface-water interaction at

the Weldon Spring quarry, St. Charles County, Missouri, 98:265

(R;US)

Geological Survey, Water Resources Div., Lincoln, NE (United

States)

Description of the U.S. Geological Survey’s water-quality sampling

and water-level monitoring program at the Hallam Nuclear Facility, August through September 1997, 98:136 (R;US)

Global Environment and Technology Foundation, Annandale,

VA (United States)

Environmental management technology leveraging initiative. Topical report, October 1994–September 1995, 98:217 (R;US)

I

Idaho National Engineering Lab., Idaho Falls, ID (United States)

A graded approach to safety analysis for Rover Processing Facility

deactivation, 98:393 (R;US)

Actinide partitioning from actual Idaho chemical processing plant

acidic tank waste using centrifugal contactors, 98:402 (R;US)

An engineering and economic analysis: Inductively coupled

plasma mobile treatment of hazardous waste, 98:337 (R;US)

Assessment of the RELAP5 multi-dimensional component model

using data from LOFT test L2-5, 98:352 (R;US)

Calcined solids storage facility closure study, 98:357 (R;US)

Clean-up criteria for remediation of contaminated soils, 98:396

(R;US)

Demonstration of the SREX process for the removal of 90Sr from

actual highly radioactive solutions in centrifugal contactors,

98:403 (R;US)

Demonstration of the TRUEX process for the treatment of actual

high activity tank waste at the INEEL using centrifugal contactors, 98:312 (R;US)

Design and operation of the Rover vacuum system, 98:392 (R;US)

Developmental assessment of the SCDAP/RELAP5 code, 98:321

(R;US)

Direct cementitious waste option study report, 98:360 (R;US)

Evaluation of emplacement sensors for detecting radiation and

volatile organic compounds and for long-term monitoring access

tubes for the BWCS, 98:338 (R;US)

Gamma-ray pulse height spectrum analysis on systems with multiple Ge detectors using a spectrum summing, 98:382 (R;US)

Gravity gradiometry difference measurement as a tool for monitoring

pumping and injection; forward modeling results, 98:395 (R;US)

High resolution gamma spectroscopy well logging system, 98:394

(R;US)

ICPP calcined solids storage facility closure study. Volume II: Cost

estimates, planning schedules, yearly cost flowcharts, and lifecycle cost estimates, 98:358 (R;US)

ICPP calcined solids storage facility closure study. Volume III: Engineering design files, 98:359 (R;US)

Environmental Management Technical Reports 207
Idaho National Engineering Lab., Idaho Falls, ID (United States)

Optimization of hydraulic cement admixture waste forms for

sodium-bearing, high aluminum, and high zirconium wastes,

98:397 (R;US)

Public participation in a DOE national program: The mixed waste

focus area’s approach, 98:388 (R;US)

Results from five years of treatability studies using hydraulic binders

to stabilize low-level mixed waste at the INEL, 98:381 (R;US)

System for decision analysis support on complex waste management issues, 98:405 (R;US)

The development of a new edition of the gamma-ray spectrum catalogues designed for presentation in electronic format, 98:386

(R;US)

The VirtualwindoW for nuclear applications, 98:398 (R;US)

Thermal denitration and mineralization of waste constituents,

98:399 (R;US)

Tribal and stakeholder involvement in systems analysis, 98:404

(R;US)

Vitrified waste option study report, 98:354 (R;US)

Where has the public gone and will communications technology

bring them back?, 98:379 (R;US)

Idaho Univ., Moscow, ID (United States)

Magnetically controlled deposition of metals using gas plasma.

Quarterly progress report, January 1997–March 1997, 98:190

(R;US)

Magnetically controlled deposition of metals using gas plasma.

Quarterly progress report, October–December 1996, 98:189

(R;US)

Idaho Univ., Moscow, ID (United States). Coll. of Engineering

Magnetically controlled deposition of metals using gas plasma.

Quarterly progress report, April–June 1997, 98:191 (R;US)

Magnetically controlled deposition of metals using gas plasma. Final report, 98:192 (R;US)

International Lead Zinc Research Organization, Research Triangle Park, NC (United States)

Task 7: Die soldering during host site testing. Final report,

January1–December 31, 1997, 98:193 (R;US)

J

Jacobs Engineering Group Inc., Albuquerque, NM (United States)

Long-term surveillance plan for the Burro Canyon disposal cell,

Slick Rock, Colorado, 98:127 (R;US)

Jacobs Engineering Group, Inc., Albuquerque, NM (United

States)

1997 Monitoring report for the Gunnison, Colorado Wetlands Mitigation Plan, 98:129 (R;US)

Addendum to the 1996 Gunnison Monitoring Report for the Gunnison, Colorado Wetlands Mitigation Plan, 98:131 (R;US)

Long-term surveillance plan for the Maybell, Colorado Disposal

Site, 98:128 (R;US)

Long-term surveillance plan for the Green River, Utah disposal

site. Revision 2, 98:126 (R;US)

Remedial action plan for the inactive uranium processing site at

Naturita, Colorado. Remedial action selection report: Attachment 2, geology report; Attachment 3, ground water hydrology

report; Attachment 4, supplemental information, 98:130 (R;US)

Joint Inst. for Energy and Environment, Knoxville, TN (United

States)

DOE-EM privatization and the 2006 Plan: Principles for procurement policies and risk management, 98:410 (R;US)

K

Keystone Center, Keystone, CO (United States)

The Keystone Center final technical report, 98:90 (R;US)

L

Lawrence Berkeley National Lab., CA (United States)

Literature search on the use of resins for treatment of radioactive

wastes, 98:466 (R;US)

Susceptibility of polysiloxane and colloidal silica to degradation by

soil microorganisms, 98:465 (R;US)

What does a tensiometer measure in fractured rock?, 98:468 (R;US)

Lawrence Berkeley National Lab., Earth Sciences Div., Berkeley, CA (United States)

Numerical modeling of field tests in unsaturated fractured basalt at

the Box Canyon site, 98:469 (R;US)

Lawrence Berkeley National Lab.,Berkeley, CA (United States)

Environmental Management Science Program awards. Fiscal year

1997 annual progress report, 98:467 (R;US)

Lawrence Livermore National Lab., CA (United States)

Alternate airborne release fraction determination for hazardous

waste management storage repository hazard categorization at

the Lawrence Livermore National Laboratory, 98:724 (R;US)

Destruction of 2,2’,3 - trichlorobiphenyl in aqueous solution by hydrous pyrolysis/oxidation (HPO), 98:723 (R;US)

Isotope hydrology of catchment basins: lithogenic and cosmogenic isotopic systems, 98:725 (R;US)

Lockheed Idaho Technologies Co., Idaho Falls, ID (United States)

Applying programmatic risk assessment to nuclear materials stabilization R and D planning, 98:300 (R;US)

Buried waste containment system materials. Final Report, 98:336

(R;US)

Cask crush pad analysis using detailed and simplified analysis

methods, 98:311 (R;US)

Cementitious waste option scoping study report, 98:361 (R;US)

Demonstration of an optimized TRUEX flowsheet for partitioning of

actinides from actual ICPP sodium-bearing waste using centrifugal contactors in a shielded cell facility, 98:364 (R;US)

Department of Energy environmental management complex-wide

integration using systems engineering, 98:301 (R;US)

Design and operational considerations of United States commercial near-surface low-level radioactive waste disposal facilities,

98:314 (R;US)

Development of the environmental management integrated baseline at the Idaho National Engineering Laboratory using systems

engineering, 98:302 (R;US)

Development of the SREX process for the treatment of ICPP liquid

wastes, 98:334 (R;US)

Evaluation and testing of HUMASORB-CS for the removal of radionuclides from groundwater, 98:366 (R;US)

Evaluation of SAFT America, Inc. electrochemical capacitors,

98:362 (R;US)

Field screening of soils contaminated with explosives using ion

mobility spectrometry, 98:387 (R;US)

Fusion safety program annual report fiscal year 1997, 98:363 (R;US)

FY-97 operations of the pilot-scale glass melter to vitrify simulated

ICPP high activity sodium-bearing waste, 98:351 (R;US)

Hot isostatic press waste option study report, 98:355 (R;US)

ICPP tank farm closure study. Volume 1, 98:345 (R;US)

ICPP tank farm closure study. Volume 2: Engineering design files,

98:346 (R;US)

ICPP tank farm closure study. Volume 3: Cost estimates, planning

schedules, yearly cost flowcharts, and life-cycle cost estimates,

98:347 (R;US)

Integration of project management and systems engineering:

Tools for a total-cycle environmental management system,

98:406 (R;US)

Interim storage study report, 98:356 (R;US)

Mapping of contamination at Savannah River Site FBWU by INEEL trolley, 98:365 (R;US)

Performance assessment and licensing issues for United States

commercial near-surface low-level radioactive waste disposal

facilities, 98:320 (R;US)

Proceedings for the nondestructive assay and nondestructive examination waste characterization conference. No. 5, 98:91 (R;US)

SWEPP PAN assay system uncertainty analysis: Active mode measurements of solidified aqueous sludge waste, 98:350 (R;US)

208 Environmental Management Technical Reports
Lockheed Martin Idaho Technologies Co., Idaho National Engineering and

Systems engineering identification and control of mixed waste

technology development, 98:400 (R;US)

The Mixed Waste Focus Area: Status and accomplishments,

98:390 (R;US)

The proposed combustion standards and DOE thermal treatment

systems, 98:389 (R;US)

TRUEX flowsheet testing for the removal of the actinides from dissolved ICPP zirconium calcine using centrifugal contactors,

98:335 (R;US)

Waste disposal options report. Volume 1, 98:342 (R;US)

Waste disposal options report. Volume 2, 98:343 (R;US)

Lockheed Idaho Technologies Co., Idaho National Engineering

and Environmental Lab., Idaho Falls, ID (United States)

Idaho Chemical Processing Plant low-activity waste grout stabilization development program FY-97 status report, 98:368 (R;US)

National Low-Level Waste Management Program final summary

report of key activities and accomplishments for fiscal year

1997, 98:371 (R;US)

Lockheed Martin Astronautics, Littleton, CO (United States)

Intelligent mobile sensor system for drum inspection and monitoring:

Topical report, October 1, 1993–April 22, 1995, 98:207 (R;US)

Lockheed Martin Energy Systems, Inc., Oak Ridge, TN (United

States)

Data management implementation plan for the removal action at

the former YS-860 Firing Ranges, Oak Ridge Y-12 Plant, Oak

Ridge, Tennessee, 98:790 (R;US)

Field sampling and analysis plan for the removal action at the former YS-860 Firing Ranges, Oak Ridge Y-12 Plant, Oak Ridge,

Tennessee, 98:789 (R;US)

Health and safety plan for the removal action at the former YS-860

Firing Ranges, Oak Ridge Y-12 Plant, Oak Ridge, Tennessee,

98:791 (R;US)

Quality assurance project plan for the removal action at the former

YS-860 Firing Ranges, Oak Ridge Y-12 Plant, Oak Ridge, Tennessee, 98:792 (R;US)

Reduction of mercury in plant effluents data management implementation plan, FY 1998, Oak Ridge Y-12 Plant, Oak Ridge,

Tennessee, 98:794 (R;US)

Waste management plan for the removal action at the former

YS-860 Firing Ranges, Oak Ridge Y-12 Plant, Oak Ridge, Tennessee, 98:793 (R;US)

Lockheed Martin Energy Systems, Inc., Toxic Substances Control Act/Health Issues Team, Oak Ridge, TN (United States)

Review of organic nitrile incineration at the Toxic Substances Control Act Incinerator, 98:411 (R;US)

Lockheed Martin Idaho Technologies Co., Idaho Falls, ID

(United States)

Corrosion Resistance of Various High Chromium Alloys in Simulated Chemical Processing Nuclear Plant Waste Solutions,

98:324 (R;US)

Passive active neutron radioassay measurement uncertainty for

combustible and glass waste matrices, 98:383 (R;US)

Plutonium stabilization and disposition focus area, FY 1999 and

FY 2000 multi-year program plan, 98:188 (R;US)

Sampling and verification methods for the uncertainty analysis of

NDA and NDE waste characterization systems, 98:384 (R;US)

SWEPP assay system software: An update, 98:385 (R;US)

The basics in transportation of low-level radioactive waste, 98:198

(R;US)

Lockheed Martin Idaho Technologies Co., Idaho National Engineering and Environmental Lab., Idaho Falls, ID (United

States)

An alternative test for verifying electronic balance linearity, 98:331

(R;US)

An evaluation of the cost/benefits of concrete biodecontamination,

98:378 (R;US)

Analysis of a hypothetical dropped spent nuclear fuel shipping

cask impacting a floor mounted crush pad, 98:313 (R;US)

Assessment results of the Indonesian TRIGA SNF to be shipped

to INEEL, 98:319 (R;US)

Assessment results of the South Korea TRIGA SNF to be shipped

to INEEL, 98:317 (R;US)

Characterization of environmental samples using ion trapsecondary ion mass spectrometry, 98:303 (R;US)

Complex-Wide Waste Flow Analysis V1.0 verification and validation report, 98:353 (R;US)

Corral Monitoring System assessment results, 98:373 (R;US)

Degradation of hazardous chemicals in liquid radioactive wastes

from biomedical research using a mixed microbial population,

98:299 (R;US)

Developing a dependable approach for evaluating waste treatment data, 98:330 (R;US)

Development, calibration, and predictive results of a simulator for

subsurface pathway fate and transport of aqueous- and

gaseous-phase contaminants in the Subsurface Disposal Area

at the Idaho National Engineering and Environmental Laboratory, 98:332 (R;US)

DPC loading feasibility study report, 98:348 (R;US)

Evaluation of engineered barriers at the Idaho National Engineering and Environmental Laboratory, 98:310 (R;US)

Fission product solvent extraction, 98:484 (R;US)

High level waste facilities – Continuing operation or orderly shutdown, 98:367 (R;US)

High-level waste program integration within the DOE complex,

98:305 (R;US)

Human health risk comparisons for environmental management

baseline program and integration opportunities (discussion

draft), 98:349 (R;US)

ICPP Tank Farm planning through 2012, 98:374 (R;US)

Idaho Nuclear Technology and Engineering Center (INTEC) (formerly ICPP) ash reutilization study, 98:375 (R;US)

Incineration of DOE offsite mixed waste at the Idaho National Engineering and Environmental Laboratory, 98:309 (R;US)

Integrated process analysis of treatment systems for mixed low

level waste, 98:306 (R;US)

Legacy sample disposition project. Volume 2: Final report, 98:369

(R;US)

Low-level radioactive waste form qualification testing, 98:341

(R;US)

Mercury emissions control technologies for mixed waste thermal

treatment, 98:322 (R;US)

Parameter selection for Department of Energy spent nuclear fuel

to be used in the Yucca Mountain Viability Assessment, 98:376

(R;US)

Performance test results of noninvasive characterization of RCRA

surrogate waste by prompt gamma neutron activation analysis,

98:344 (R;US)

Pinhole corrosion of CH-TRU waste containers by volatile organic

compounds, 98:308 (R;US)

Predicting flammability of gas mixtures containing volatile organic

compounds, 98:327 (R;US)

Preliminary design report for SCDAP/RELAP5 lower core plate

model, 98:377 (R;US)

Preliminary design specification for Department of Energy standardized spent nuclear fuel canisters. Volume 1: Design

specification, 98:282 (R;US)

Preliminary design specification for Department of Energy standardized spent nuclear fuel canisters. Volume 2: Rationale

document, 98:283 (R;US)

Radioactive waste management complex low-level waste radiological composite analysis, 98:339 (R;US)

Security preparation for receipt of SNF from the FRR to the INEEL, 98:315 (R;US)

Spreadsheet application to classify radioactive material for shipment, 98:325 (R;US)

Status of the TRIGA shipments to the INEEL from Europe, 98:316

(R;US)

Status of the TRIGA shipments to the INEEL from Asia, 98:318

(R;US)

To retrieve or not to retrieve: These are the issues, 98:401 (R;US)

Volatilization of heavy metals and radionuclides from soil heated in

an induction “cold” crucible melter, 98:323 (R;US)

Waste generator services implementation plan, 98:372 (R;US)

Workshop proceedings: Developing the scientific basis for longterm land management of the Idaho National Engineering and

Environmental Laboratory, 98:370 (R;US)

Environmental Management Technical Reports 209
Lockheed Martin Idaho Technologies Co., Idaho National Engineering and

Lockheed Martin Idaho Technologies Co., Idaho National Engineering and Environmental Laboratory, Idaho Falls, ID

(United States)

Development of a comprehensive source term model for the Subsurface Disposal Area at the Idaho National Engineering and

Environmental Laboratory, 98:307 (R;US)

Lockheed Martin Idaho Technologies Co., Idaho National Engineering Lab., Idaho Falls, ID (United States)

Development of a techno-economic model to optimization DOE

spent nuclear fuel disposition, 98:304 (R;US)

Lockheed Martin Idaho Technologies Co., Inc., Idaho National

Engineering and Environmental Lab., Idaho Falls, ID

(United States)

Alternative calcination development status report, 98:333 (R;US)

Lockheed Martin Idaho Technologies Co., National Spent Nuclear Fuel Program, Idaho Falls, ID (United States)

Overview of the United States spent nuclear fuel program, 98:326

(R;US)

Lockheed Martin Idaho Technologies, Idaho National Engineering and Environmental Lab., Idaho Falls, ID (United States)

Position for determining gas-phase volatile organic compound

concentrations in transuranic waste containers. Revision 2,

98:298 (R;US)

Lockheed Martin Idaho Technologies, Inc., Idaho National Engineering and Environmental Lab., Idaho Falls, ID (United

States)

Removal of strontium-90 from calcined wastes with the SREX process, 98:328 (R;US)

Treatment of acidic INEEL waste using a countercurrent cobalt

dicarbollide-based universal solvent extraction process, 98:329

(R;US)

Los Alamos National Lab., NM (United States)

241-SY-101 strain concentration factor development via nonlinear

analysis. Volume 1 of 1, 98:422 (R;US)

A model for the effective diffusion of gas or the vapor phase in a

fractured media unsaturated zone driven by periodic atmospheric pressure fluctuations, 98:432 (R;US)

A new waste minimization method for the determination of total

nonhalogenated volatile organic compounds in TRU wastes,

98:436 (R;US)

A Standard Analysis Method (SAM) for the automated analysis of

polychlorinated biphenyls (PCBs) in soils using the chemical

analysis automation (CAA) paradigm: Validation and performance, 98:417 (R;US)

A standard analysis method (SAM) for the automated analysis of

polychlorinated biphenyls (PCBs) in soils using the chemical

analysis automation (CAA) paradigm: validation and performance, 98:448 (R;US)

A successful waste stream analysis on a large construction project

in a radiologically controlled facility, 98:446 (R;US)

An analysis of background noise in selected canyons of Los

Alamos County, 98:415 (R;US)

Atmospheric transport in complex terrain at Los Alamos, Area G,

98:431 (R;US)

Automating the analytical laboratory via the Chemical Analysis Automation paradigm, 98:447 (R;US)

Chemical gel barriers as low-cost alternative to containment and in

situ cleanup of hazardous wastes to protect groundwater,

98:424 (R;US)

CID-based ICP-AES instrumentation for continuous on-line analysis of aqueous industrial waste streams, 98:434 (R;US)

Comparison of General Purpose Heat Source testing with the ANSI

N43.6-1977 (R1989) sealed source standard, 98:462 (R;US)

Comparison of silver(II), cobalt(III), and cerium(IV) as electron

transfer mediators in the MEO mixed waste treatment process,

98:442 (R;US)

Correction to the MCNP perturbation feature for cross-section

dependent tallies, 98:416 (R;US)

Draft test plan for hydrogen getters project, 98:461 (R;US)

Effects on the long term storage container by thermal cycling alpha plutonium, 98:450 (R;US)

Experience operating LANL’s passive/active neutron (PAN) assay

system, 98:430 (R;US)

Gas generation matrix depletion quality assurance project plan,

98:464 (R;US)

Hazardous waste systems analysis at Los Alamos National Laboratory, 98:444 (R;US)

Hazards associated with retrieval and storage of legacy waste at the

Transuranic Waste Inspectable Storage Project, 98:451 (R;US)

HEPA filter jointer, 98:418 (R;US)

Key regulatory drivers affecting shipments of mixed transuranic

waste from Los Alamos National Laboratory to the Waste Isolation Pilot Plant, 98:428 (R;US)

Laboratory and field studies related to radionuclide migration at

the Nevada Test Site. Progress report, October 1, 1996–

September 30, 1997, 98:419 (R;US)

Los Alamos National Laboratory’s Mobile Real Time Radiography

System, 98:429 (R;US)

Low-level radioactive waste disposal operations at Los Alamos

National Laboratory, 98:427 (R;US)

Measurement of surface emission flux rates for volatile organic

compounds at Technical Area 54, 98:413 (R;US)

Metal recycling experience at Los Alamos National Laboratory.

Reuse, release, and recycle of metals from radiological control

areas”, 98:445 (R;US)

New bifunctional anion-exchange resins for nuclear waste treatment: Part 2, 98:437 (R;US)

New probability table treatment in MCNP for unresolved resonances, 98:457 (R;US)

New spectroscopic studies of plutonium (IV) nitrate complex formation in solution, 98:435 (R;US)

Old-field plant succession on the Pajarito Plateau, 98:414 (R;US)

Oxidation kinetics of plutonium in air: Consequences for environmental dispersal, 98:440 (R;US)

Performance of NDA techniques on a vitrified waste form, 98:441

(R;US)

Plutonium (IV) complexation by nitrate in acid solutions of ionic

strengths from 2 to 19 molal, 98:438 (R;US)

Prediction of heat capacities of solid inorganic salts from group

contributions, 98:423 (R;US)

Quality management in environmental programs: Los Alamos National Laboratory’s approach, 98:453 (R;US)

Radionuclide concentrations in honey bees from Area G at TA-54

during 1997. Progress report, 98:421 (R;US)

Real-time alpha emitter assay of large volumes, 98:426 (R;US)

Recovery of 241Am/Be neutron sources, Wooster, Ohio, 98:420

(R;US)

Report on the GC-MBS method for correcting NaI spectra for

transmission loss in hand-held instruments, 98:449 (R;US)

Speciation and surface interactions of actinides on aged ionexchange resins, 98:439 (R;US)

Standard data report. 1997 annual report on waste generation and

waste minimization progress, 98:463 (R;US)

Synopsis of hydrologic data collected by waste management for

characterization of unsaturated transport at Area G, 98:454

(R;US)

Synopsis of moisture monitoring by neutron probe in the unsaturated zone at Area G, 98:455 (R;US)

Synopsis of recent moisture flux analyses relevant to the unsaturated zone at Area G, 98:456 (R;US)

Systematic evaluation of options to avoid generation of noncertifiable transuranic (TRU) waste at Los Alamos National

Laboratory, 98:452 (R;US)

Test plan for headspace gas sampling of remote-handled transuranic waste containers at Los Alamos National Laboratory,

98:460 (R;US)

Test plan for hydrogen getters project, 98:458 (R;US)

Treatability study Number PDC-1-O-T. Final report, 98:425 (R;US)

TRU waste transportation – The flammable gas generation problem, 98:443 (R;US)

Use of data fusion to optimize contaminant transport predictions,

98:459 (R;US)

Visualizing data for environmental analysis, 98:433 (R;US)

Lovelace Biomedical and Environmental Research Inst., Albuquerque, NM (United States)

Improved risk estimates for carbon tetrachloride. Project status report and technical progress report, 98:133 (R;US)

210 Environmental Management Technical Reports
Oak Ridge National Lab., Energy Div., TN (United States)

M

Mechanical Technology, Inc., Latham, NY (United States)

Interactive Computer-Enhanced Remote Viewing System

(ICERVS): Final report, November 1994–September 1996,

98:208 (R;US)

Medical Univ. of South Carolina, Charleston, SC (United States)

Environmental hazards assessment program. Quarterly report (extended quarter), April 1997–September 1997, 98:176 (R;US)

Environmental hazards assessment program (extended year). Annual report, July 1, 1996–September 30, 1997, 98:177 (R;US)

Environmental hazards assessment program. Summary report,

June 23, 1992–September 30, 1997, 98:178 (R;US)

Environmental Hazards Assessment Program summary report,

June 23, 1992–September 30, 1997, 98:179 (R;US)

Molten Metal Technology, Inc., Waltham, MA (United States)

Recycle of contaminated scrap metal, comprehensive executive

summary. Final report, September 30, 1993–March 31, 1996,

98:211 (R;US)

Monsanto Co., St. Louis, MO (United States)

Development of an integrated in-situ remediation technology. Topical report for task No. 12 and 13 entitled: Large scale field test

of the Lasagna process, September 26, 1994–May 25, 1996,

98:221 (R;US)

Development of an integrated in-situ remediation technology. Topical report for task No. 7 entitled: Development of degradation

processes, September 26, 1994–May 25, 1996, 98:225 (R;US)

Development of an integrated in-situ remediation technology.

Topical report for task No. 11 entitled: Evaluation of TCE contamination before and after the field experiment, September 26,

1994–May 25, 1996, 98:226 (R;US)

Development of an integrated in-situ remediation technology. Topical report for Task #3.2 entitled, “Modeling and iron dechlorination

studies” (September 26, 1994–August 31, 1997), 98:266 (R;US)

Development of an integrated in-situ remediation technology. Draft

topical report for Task #3.3 entitled, “Iron dechlorination studies”

(September 26, 1994–August 31, 1997), 98:267 (R;US)

Development of an integrated in-situ remediation technology. Draft

topical report for Task #7.2 entitled “Field scale test” (January

10, 1996–December 31, 1997), 98:268 (R;US)

Development of an integrated, in-situ remediation technology.

Topical report for task No. 6: lab-scale development of microbial

degradation process, September 26, 1994–May 25, 1996,

98:219 (R;US)

Development of an integrated, in-situ remediation technology.

Topical report for task No. 5: Cost analysis, September 26,

1994–May 25, 1996, 98:220 (R;US)

Development of an integrated, in-situ remediation technology:

Task 2–4, electrokinetic modeling. Topical report, September

26–May 25, 1996, 98:222 (R;US)

Development of an integrated, in-situ remediation technology.

Topical report for task No. 9. Part I. TCE degradation using nonbiological methods, September 26, 1994–May 25, 1996, 98:223

(R;US)

Development of an integrated, in-situ remediation technology.

Draft topical report for task No. 9. Part II. Entitled: TCE degradation using non-biological methods, September 26, 1994–May

25, 1996, 98:224 (R;US)

Development of the integrated, in-situ remediation technology.

Topical report for tasks No. 8 and No. 10 entitled: Laboratory

and pilot scale experiments of Lasagna process, September

26, 1994–May 25, 1996, 98:218 (R;US)

Montana State Univ., Bozeman, MT (United States)

The greenhouse of the future: Using a sponsored competition in a

capstone course, 98:195 (R;US)

Morgan, Lewis and Bockius, Washington, DC (United States)

Licensing an assured isolation facility for low-level radioactive

waste. Volume 1: Licensing strategy and issues, 98:200 (R;US)

Licensing an assured isolation facility for low-level radioactive

waste. Volume 2: Recommendations on the content and review

of an application, 98:201 (R;US)

N

National Governors’ Association, Center for Best Practices,

Washington, DC (United States)

The NGA-DOE grant to examine critical issues related to radioactive waste and materials disposition involving DOE facilities.

Quarterly report, October 1–December 31, 1997, 98:187 (R;US)

Nevada Univ., Las Vegas, NV (United States). Water Resources

Center

Numerical evaluation of monofil and subtle-layered evapotranspiration (ET) landfill caps, 98:256 (R;US)

New Jersey Public Utilities Board, Newark, NJ (United States)

NICE-3. Technical progress report, March 1, 1995–October 31,

1995, 98:271 (R;US)

New Mexico State Univ., Las Cruces, NM (United States). Dept.

of Chemical Engineering

Prediction of heat capacities of solid inorganic salts from group

contributions, 98:423 (R;US)

North Carolina Agricultural and Technical State Univ., Greensboro, NC (United States)

Infrastructure support for a waste management institute. Final

project report, September 12, 1994–September 11, 1997,

98:285 (R;US)

North Dakota Univ. Grand Forks Energy And Environmental Research Center (United States)

Cone Penetrometer for Subsurface Heavy Metals Detection. Semiannual report, November 1, 1996–March 31, 1997, 98:249 (R;US)

Laser Cleaning of Contaminated Painted Surfaces. Semiannual

report, November 1, 1996–March 31, 1997, 98:248 (R;US)

Task 14 - Bubbleless Gas Transfer Technology for the In Situ Remediation of Chlorinated Hydrocarbons. Semiannual report,

November 1, 1996–March 31, 1997, 98:244 (R;US)

Task 9- Centrifugal Membrane Filtration. Semiannual report,

November 1, 1996–March 31, 1997, 98:246 (R;US)

North Dakota Univ., Grand Forks, ND (United States)

Task 15 - Remediation of Organically Contaminated Soil Using

Hot/Liquid (Subcritical) Water. Semiannual report, November 1,

1996– March 31,1997, 98:243 (R;US)

Task 3 - Pyrolysis of Plastic Waste. Semiannual report, November

1, 1996–March 31, 1997, 98:247 (R;US)

North Dakota Univ., Grand Forks, ND (United States). Energy

and Environmental Research Center

Task 10 - technology development integration. Semi-annual report, April 1–September 30, 1996, 98:240 (R;US)

Task 11: Technology development integration. Semi-annual report, April 1, 1996–September 30, 1996, 98:241 (R;US)

Task 12: Laser cleaning of contaminated painted surfaces. Semiannual report, April 1, 1996–September 30, 1996, 98:242 (R;US)

Task 2: Extraction and analysis of pollutant organics from contaminated solids using off-line Supercritical Fluid Extraction (SFE)

and on-line SFE-infrared spectroscopy. Semi-annual report,

April 1, 1996–September 30, 1996, 98:236 (R;US)

Task 3 - pyrolysis of plastic waste. Semi-annual report, April 1–

September 30, 1996, 98:237 (R;US)

Task 8 - management and reporting. Semi-annual report April 1–

September 30, 1996, 98:238 (R;US)

Task 9 - centrifugal membrane filtration. Semi-annual report April

1–September 30, 1996, 98:239 (R;US)

O

Oak Ridge National Lab., Chemical Technology Div., TN (United

States)

Progress report and technology status development of an EG and

G Berthold LB-150 alpha/beta particulate monitor for use on the

East Tennessee Technology Park Toxic Substances Control Act

Incinerator, 98:542 (R;US)

Oak Ridge National Lab., Chemistry Div., TN (United States)

Technological and economic update on the nitrate to ammonia and

ceramic process, 98:479 (R;US)

Oak Ridge National Lab., Energy Div., TN (United States)

Temperature inversions in the vicinity of Oak Ridge, Tennessee,

as characterized by tethersonde data, 98:544 (R;US)

Environmental Management Technical Reports 211
Oak Ridge National Lab., Grand Junction, CO (United States)

Oak Ridge National Lab., Grand Junction, CO (United States)

Implementation of passive samplers for monitoring volatile organic

compounds in ground water at the Kansas City Plant, 98:554

(R;US)

Introduction to naturally occurring radioactive material, 98:114

(R;US)

Real-time, automated characterization of surfaces for alpha and

beta radiation, 98:478 (R;US)

Oak Ridge National Lab., Oak Ridge, TN 37831 (United States)

Cold test plan for the Old Hydrofracture Facility tank contents removal project, Oak Ridge National Laboratory, Oak Ridge,

Tennessee, 98:514 (R;US)

Oak Ridge National Lab., TN (United States)

A case study: using a multi-grout barrier to control 90Sr release at

ORNL, 98:94 (R;US)

A field trial of novel bifunctional resins for removing pertechnetate

(TcO4

) from contaminated groundwater, 98:553 (R;US)

A life cycle analysis approach to D and D decision-making, 98:497

(R;US)

A retrospective study of the chemical analysis cost for the remediation of Lower East Fork Poplar Creek, Oak Ridge, Tennessee,

98:556 (R;US)

A simplified ALARA approach to demonstration of compliance with

surface contaminated object regulatory requirements, 98:488

(R;US)

Active Sites Environmental Monitoring Program FY 1994 annual

report, 98:524 (R;US)

Active Sites Environmental Monitoring Program FY 1996 annual

report, 98:525 (R;US)

Active sites environmental monitoring program FY 1997 annual report, 98:526 (R;US)

Adaptive controller for hyperthermia robot, 98:106 (R;US)

Admixture enhanced controlled low-strength material for direct underwater injection with minimal cross-contamination, 98:112

(R;US)

Advanced hydraulic fracturing methods to create in situ reactive

barriers, 98:477 (R;US)

ALARA plan for the Old Hydrofracture Facility tanks contents removal project at Oak Ridge National Laboratory, Oak Ridge,

Tennessee, 98:518 (R;US)

ALARA plan for the Old Hydrofracture Facility tanks contents removal project at Oak Ridge National Laboratory, Oak Ridge,

Tennessee. Amendment 1 for Appendix B: Install flex-pipe on

tank riser spools, 98:519 (R;US)

Alternative methods to determine headwater benefits, 98:533

(R;US)

An investigation of a passively controlled haptic interface, 98:109

(R;US)

Basic and Acidic Leaching of Sludge from Melton Valley Storage

Tank W-25, 98:472 (R;US)

Bear Creek Valley characterization area mixed wastes passive in

situ treatment technology demonstration project - status report,

98:95 (R;US)

Caustic leaching of high-level radioactive tank sludge: A critical literature review, 98:505 (R;US)

Caustic leaching of high-level radioactive tank sludge: A critical literature review, 98:560 (R;US)

Certification testing for the ES-2 shipping package, 98:487 (R;US)

Cesium removal demonstration utilizing crystalline silicotitanate

sorbent for processing Melton Valley Storage Tank supernate:

Final report, 98:536 (R;US)

Cesium removal flow studies using ion exchange, 98:97 (R;US)

Cesium removal from high-pH, high-salt wastwater using crystalline silicotitanate sorbent, 98:473 (R;US)

Characterization of the C1 and C2 waste tanks located in the

BVEST system at ORNL, 98:543 (R;US)

Characterizing, for packaging and transport, large objects contaminated by radioactive material having a limited A2 value, 98:489

(R;US)

Comparative testing of slurry monitors, 98:121 (R;US)

Comparative testing of slurry monitors, 98:551 (R;US)

Completion of the Radioactive Materials Packaging Handbook,

98:485 (R;US)

Completion report for the isolation and remediation of inactive liquid low-level radioactive waste tanks WC-5, WC-6, WC-8,

WC-19, 3002-A, 7560, and 7562 at Oak Ridge National Laboratory Oak Ridge, Tennessee, 98:517 (R;US)

Control of flexible robots with prismatic joints and hydraulic drives,

98:104 (R;US)

Criticality safety considerations for MSRE fuel drain tank uranium

aggregation, 98:116 (R;US)

Cross flow filtration of aqueous radioactive tank wastes, 98:730

(R;US)

Current and projected liquid low-level waste generation at ORNL,

98:538 (R;US)

Degradation of trichloroethylene (TCE) and polychlorinated

biphenyls (PCBs) by Fe and Fe-Pd bimetals in the presence of

surfactants and cosolvents, 98:93 (R;US)

Demonstration of fluidic pulse jet mixing for a horizontal waste

storage tank, 98:548 (R;US)

Demonstration of Mixed Waste Debris Macroencapsulation Using

Sulfur Polymer Cement, 98:546 (R;US)

Development and testing of spheroidal inorganic sorbents, 98:482

(R;US)

Development of a path forward for special-case wastes at the Oak

Ridge Reservation, 98:529 (R;US)

Development of nuclear analysis capabilities for DOE waste management activities, 98:527 (R;US)

Development testing of the chemical analysis automation polychlorinated biphenyl standard analysis method during surface soils

sampling at the David Witherspoon 1630 site, 98:552 (R;US)

Dismantlement and removal of Old Hydrofracture Facility bulk

storage bins and water tank, Oak Ridge National Laboratory,

Oak Ridge, Tennessee, 98:521 (R;US)

Distillation under electric fields, 98:475 (R;US)

Distribution of Fatty Acids and Triethanolamine in Synthetic Metalworking Fluid Aerosols Generated in the Laboratory and Field,

98:471 (R;US)

Dry well conductivity monitoring report for Tanks W-8, W-9, and

W-10, Oak Ridge National Laboratory, Oak Ridge, Tennessee,

98:513 (R;US)

Dual Arm Work Package performance estimates and telerobot

task network simulation, 98:102 (R;US)

Environmental health and safety plan for the Molten Salt Reactor

Experiment Remediation Project at Oak Ridge National Laboratory, Oak Ridge, Tennessee, 98:507 (R;US)

Evaluation of improved techniques for the removal of fission products from process wastewater and groundwater: FY 1997

status, 98:534 (R;US)

Evaluation of operating characteristics for a chabazite zeolite system for treatment of process wastewater at Oak Ridge National

Laboratory, 98:532 (R;US)

Field technologies for the measurement of PCBs, 98:124 (R;US)

Fission product solvent extraction, 98:484 (R;US)

GAAT dry well conductivity monitoring report, July 1997 through

January 1998, Oak Ridge National Laboratory, Oak Ridge, Tennessee, 98:523 (R;US)

Global transportation cost modeling for long-range planning,

98:491 (R;US)

Groundwater quality assessment report for Solid Waste Storage

Area 6 at Oak Ridge National Laboratory, Oak Ridge, Tennessee – 1997, 98:522 (R;US)

Grout and glass performance in support of stabilization/solidification of ORNL tank sludges, 98:557 (R;US)

Grout and vitrification formula development for immobilization of

hazardous radioactive tank sludges at ORNL, 98:495 (R;US)

Guidance and methods for satisfying low specific activity material

and surface contaminated object regulatory requirements,

98:492 (R;US)

Gunite and associated tanks remediation project recycling and

waste minimization effort, 98:502 (R;US)

Heterogeneous reactivity effects in medium- and high-enriched

uranium metal-water systems, 98:117 (R;US)

Homogeneous Reactor Experiment (HRE) Pond cryogenic barrier

technology demonstration: Pre-barrier subsurface hydrology

and contaminant transport investigation, 98:545 (R;US)

212 Environmental Management Technical Reports
Oak Ridge Y-12 Plant, TN (United States)

Hot demonstration of proposed commercial cesium removal technology, 98:528 (R;US)

Hot demonstration of proposed commercial cesium removal technology: Progress report, 98:531 (R;US)

Hydraulic manipulator research at ORNL, 98:108 (R;US)

HYDROBIOGEOCHEM: A coupled model of HYDROlogic transport and mixed BIOGEOCHEMical kinetic/equilibrium reactions

in saturated-unsaturated media, 98:561 (R;US)

Impact analysis of stainless steel spent fuel canisters, 98:504 (R;US)

Implications of electron attachment to highly-excited states in

pulsed-power discharges, 98:113 (R;US)

In situ global method for measurement of oxygen demand and

mass transfer, 98:110 (R;US)

In situ vitrification demonstration at Pit 1, Oak Ridge National Laboratory. Volume 1: Results of treatability study, 98:515 (R;US)

In situ vitrification demonstration at Pit 1, Oak Ridge National Laboratory. Volume 2: Site characterization report of the Pit 1 area,

98:516 (R;US)

Inactive tanks remediation program strategy and plans for Oak

Ridge National Laboratory, Oak Ridge, Tennessee, 98:506

(R;US)

Integrated data base report–1996: US spent nuclear fuel and radioactive waste inventories, projections, and characteristics,

98:278 (R;US)

Isotopes facilities deactivation project at Oak Ridge National Laboratory, 98:118 (R;US)

Laboratory stabilization/solidification of surrogate and actual

mixed-waste sludge in glass and grout, 98:470 (R;US)

Large underground radioactive waste storage tanks successfully

cleaned at Oak Ridge National Laboratory, 98:503 (R;US)

Large-scale treatment of high-salt, high-pH wastewater for 137Cs

and 90Sr removal, using crystalline silicotitanate resin, 98:494

(R;US)

Liquid and gaseous waste operations section. Annual operating

report CY 1997, 98:549 (R;US)

Magnetic-seeding filtration, 98:474 (R;US)

Measuring the accomplishments of public participation programs:

Overview of a methodological study performed for DOE’s Office

of Environmental Management, 98:119 (R;US)

Mixed Waste Focus Area Mercury Working Group: An integrated approach to mercury waste treatment and disposal, 98:480 (R;US)

Multi-weight isotherm results for mercury removal in upper East

Fork Popular Creek water, 98:550 (R;US)

North Tank Farm data report for the Gunite and Associated Tanks

at Oak Ridge National Laboratory, 98:555 (R;US)

Nuclear criticality safety controls for uranium deposits during D

and D at the Oak Ridge Gaseous Diffusion Plant, 98:115 (R;US)

Out-of-tank evaporator demonstration. Final report, 98:535 (R;US)

Passivation of fluorinated activated charcoal, 98:537 (R;US)

Performance of in situ chemical oxidation field demonstrations at

DOE sites, 98:123 (R;US)

Predictive mathematical modeling of trickling bed biofilters for elucidating mass transfer and kinetic effects, 98:486 (R;US)

Process waste treatment system upgrades: Clarifier startup at the

nonradiological wastewater treatment plant, 98:558 (R;US)

Process wastewater treatment with hydrogen-form CST and

chabazite zeolite, 98:499 (R;US)

Programmatic and technical requirements for the FMDP fresh

MOX fuel transport package, 98:540 (R;US)

Project management plan for Waste Area Grouping 5 Old

Hydrofracture Facility tanks contents removal at Oak Ridge National Laboratory, Oak Ridge, Tennessee, 98:85 (R;US)

Project management plan for Waste Area Grouping 5 Old

Hydrofracture Facility tanks contents removal at Oak Ridge National Laboratory, Oak Ridge, Tennessee, 98:509 (R;US)

Quality assurance plan for the molten salt reactor experiment Remediation Project at Oak Ridge National Laboratory, Oak Ridge,

Tennessee, 98:508 (R;US)

R-matrix analysis of 235U neutron transmission and cross sections

in the energy range 0 to 2.25 keV, 98:539 (R;US)

Recent experience in planning, packaging and preparing noncommercial spent fuel for shipment in the United States, 98:493

(R;US)

Removal action work plan for the YS-860 Firing Ranges, Oak

Ridge Y-12 Plant, Oak Ridge, Tennessee, 98:261 (R;US)

Removal of chlorinated and non-chlorinated alkanes in a tricklebed biofilter, 98:481 (R;US)

Reprocessing of Shallow Seismic Reflection Data to Image Faults

Near a Hazardous Waste Site on the Oak Ridge Reservation,

Tennessee, 98:483 (R;US)

RoboCon: A general purpose telerobotic control center, 98:101

(R;US)

Sampling and analysis plan for the gunite and associated tanks interim remedial action, wall coring and scraping at Oak Ridge

National Laboratory, Oak Ridge, Tennessee, 98:512 (R;US)

Seismic reflection processing for characterization of a hazardous

waste site, 98:100 (R;US)

Separations/pretreatment considerations for Hanford privatization

phase 2, 98:500 (R;US)

Simulation tools for hazardous waste removal, 98:107 (R;US)

Solids Control in Sludge Pretreatment, 98:122 (R;US)

Solvent extraction of radionuclides from aqueous tank waste,

98:92 (R;US)

Statistical description of liquid low-level waste system supernatant

liquids at Oak Ridge National Laboratory, Oak Ridge, Tennessee, 98:530 (R;US)

Status report on solid control in leachates, 98:559 (R;US)

Strategies for redundancy resolution of dual-arm systems with

passive elements for tank waste removal, 98:103 (R;US)

Strategies for the cost effective treatment of Oak Ridge legacy

wastes, 98:547 (R;US)

Tank Focus Area pretreatment activities, 98:98 (R;US)

Technical safety requirements for the South Tank Farm remediation project, Oak Ridge National Laboratory, Oak Ridge,

Tennessee, 98:511 (R;US)

Technical safety requirments for the South Tank Farm Remediation Project, Oak Ridge National Laboratory, Oak Ridge,

Tennessee, 98:510 (R;US)

Testing of low-temperature stabilization alternatives for salt containing mixed wastes – Approach and results to date, 98:496 (R;US)

The independent verification process in decommissioning, decontamination, and reutilization activities - description, benefits, and

lessons learned, 98:120 (R;US)

The mixed waste focus area mercury working group: an integrated

approach for mercury treatment and disposal, 98:99 (R;US)

The use of carbonate lixiviants to remove uranium from uraniumcontaminated soils, 98:111 (R;US)

The Virtual Robotics Laboratory, 98:105 (R;US)

Topographical mapping system for radiological and hazardous environments acceptance testing, 98:476 (R;US)

Transportation Routing Analysis Geographic Information System –

TRAGIS, progress on improving a routing tool, 98:490 (R;US)

U.S. Department of Energy National Center of Excellence for Metals Recycle, 98:498 (R;US)

U.S. Department of Energy National Center of Excellence for Metals Recycle, 98:501 (R;US)

Work plan for denaturing waste in the Old Hydrofracture Tanks at

Oak Ridge National Laboratory, Oak Ridge, Tennessee, 98:82

(R;US)

X-231A demonstration of in-situ remediation of DNAPL compounds in low permeability media by soil fracturing with

thermally enhanced mass recovery or reactive barrier destruction, 98:541 (R;US)

Oak Ridge Research Inst., TN (United States)

Developing biological and chemical methods for environmental

monitoring of DOE waste disposal and storage facilities.

Progress report, April 1, 1985–October 30, 1985, 98:263 (R;US)

Removal of dissolved heavy metals and radionuclides by microbial

spores, 98:264 (R;US)

Oak Ridge Y-12 Plant, TN (United States)

Bear Creek Valley Floodplain Hot Spot Removal Action Project Plan,

Oak Ridge Y-12 Plant, Oak Ridge, Tennessee, 98:785 (R;US)

Bear Creek Valley Floodplain hot spot removal early action characterization field data summary report, Oak Ridge Y-12 Plant,

Oak Ridge, Tennessee, 98:795 (R;US)

Environmental Management Technical Reports 213
Oak Ridge Y-12 Plant, TN (United States)

Best management practices and work plan for installation of and

monitoring at temporary weirs and flumes at NT-3, NT-4, and NT5 Oak Ridge Y-12 Plant, Oak Ridge, Tennessee, 98:797 (R;US)

Experimental bypass of Lake Reality, Oak Ridge Y-12 Plant, Oak

Ridge, Tennessee, 98:784 (R;US)

Phase 2 confirmatory sampling data report, Lower East Fork

Poplar Creek, Oak Ridge Y-12 Plant, Oak Ridge, Tennessee,

98:786 (R;US)

Postremediation monitoring program baseline assessment report,

Lower East Fork Poplar Creek, Oak Ridge Y-12 Plant, Oak

Ridge, Tennessee, 98:796 (R;US)

Work plan for mercury treatability study in upper east fork Popular

Creek at DOE’s Y-12 Site in support of the Reduction of Mercury in Plant Effluent program (RMPE), 98:787 (R;US)

Work plan for support to Upper East Fork Poplar Creek east end

VOC plumes well installation project at the Oak Ridge Y-12

Plant, Oak Ridge, Tennessee, 98:788 (R;US)

Office of Science and Technology, International Program Office,

Washington, DC (United States)

United States-Russia: Environmental management activities,

Summer 1998, 98:174 (R;US)

Operating Engineers National HAZMAT Program, Beaver, WV

(United States)

A robotic inspection experimental system (ARIES) and BOA,

98:254 (R;US)

Pegasus International, Inc. coating removal systems, 98:253 (R;US)

PTC-6 vacuum system: WallWalker and Blastrac shot blast

cleaning system, 98:252 (R;US)

P

Pacific Northwest Lab., Richland, WA (United States)

Atmospheric dispersion of ammonia accidentally released from

the 242-A Evaporator, Hanford Site, Richland, Washington,

98:577 (R;US)

Chemical information on tank supernatants, Cs adsorption from

tank liquids onto Hanford sediments, and field observations of

Cs migration from past tank leaks, 98:563 (R;US)

Comparison of inorganic ion exchange materials for removing cesium, strontium, and transuranic elements from K-basin water,

98:574 (R;US)

Composite analysis for low-level waste disposal in the 200 area

plateau of the Hanford Site, 98:581 (R;US)

Crystalline silicotitanate gate review analysis, 98:576 (R;US)

Gas treatment of Cr(VI)-contaminated sediment samples from the

North 60’s pits of the chemical waste landfill, 98:565 (R;US)

International waste management fact book, 98:567 (R;US)

Mercury separation from concentrated potassium iodide/iodine

leachate using Self-Assembled Mesoporous Mercaptan Support

(SAMMS) technology, 98:572 (R;US)

Risk based requirements for long term stewardship: A proof-ofprinciple analysis of an analytic method tested on selected

Hanford locations, 98:585 (R;US)

STOMP Subsurface Transport Over Multiple Phases: User’s

guide, 98:562 (R;US)

Three-dimensional analysis of future groundwater flow conditions

and contaminant plume transport in the Hanford Site unconfined

aquifer system: FY 1996 and 1997 status report, 98:582 (R;US)

Waste behavior during horizontal extrusion: Effect of waste

strength for bentonite and kaolin/ludox simulants and strength

estimates for wastes from Hanford waste tanks 241-SY-103,

AW-101, AN-103, and S-102, 98:571 (R;US)

Pacific Northwest National Lab., Richland, WA (United States)

Application of the risk-based strategy to the Hanford tank waste

organic-nitrate safety issue, 98:580 (R;US)

Baseline estimate of the retained gas volume in Tank 241-C-106,

98:587 (R;US)

Calculation of combustible waste fraction (CWF) estimates used in

organics safety issue screening, 98:597 (R;US)

Chemical pathways for the formation of ammonia in Hanford

wastes, 98:569 (R;US)

Composition and quantities of retained gas measured in Hanford

waste tanks 241-U-103, S-106, BY-101, and BY-109, 98:578

(R;US)

Demonstration of strontium removal from Hanford N-Area well water, 98:608 (R;US)

Descriptive models for single-jet sluicing of sludge waste, 98:570

(R;US)

Dryout modeling in support of the organic tank safety project,

98:599 (R;US)

Environmental Monitoring Plan United States Department of Energy Richland Operations Office. Revision 2, 98:272 (R;US)

Fabrication and testing of engineered forms of self-assembled

monolayers on mesoporous silica (SAMMS) material, 98:611

(R;US)

Fission product solvent extraction, 98:484 (R;US)

Flammable gas issues in double-contained receiver tanks. Revision 1, 98:583 (R;US)

Flammable gas issues in double-contained receiver tanks. Revision 2, 98:584 (R;US)

Groundwater monitoring plan for the Hanford Site 216-B-3 pond

RCRA facility, 98:590 (R;US)

Hanford annual first quarter seismic report, fiscal year 1998: Seismicity on and near the Hanford Site, Pasco Basin, Washington,

98:564 (R;US)

Integrated monitoring plan for the Hanford groundwater monitoring

project, 98:606 (R;US)

Integrating pretreatment and retrieval: Results from the July 1997

Tanks Focus Area workshop, 98:592 (R;US)

Interaction of Pu(IV,VI) hydroxides/oxides with metal hydroxides/oxides in alkaline media, 98:588 (R;US)

Investigation of flammable gas and thermal safety issues for retrieval of waste from Tank 241-AN-105, 98:607 (R;US)

Low-pressure, single-point grout injection for tank heel sludge mixing and in-situ immobilization, 98:609 (R;US)

Mechanisms of gas retention and release: Experimental results

for Hanford single-shell waste tanks 241-A-101, 241-S-106, and

241-U-103, 98:604 (R;US)

Monitoring bank erosion at the Locke Island Archaeological National Register District: Summary of 1996/1997 field activities,

98:603 (R;US)

Nuclear magnetic resonance measurement of ammonia diffusion

in dense solid-liquid slurries. Revision 1, 98:568 (R;US)

Organic speciation of AX-102, BX-104, C-104, C-201, and C-202

tank wastes, 98:601 (R;US)

Organic tank safety project: Equilibrium moisture determination

task, FY 1998 annual progress report, 98:600 (R;US)

Organic tanks safety program waste aging studies. Final report,

Revision 1, 98:591 (R;US)

Organic tanks safety program, FY97 waste aging studies. Revision 1, 98:566 (R;US)

Performance evaluation of rotating pump jet mixing of radioactive

wastes in Hanford Tanks 241-AP-102 and -104, 98:593 (R;US)

Plutonium(IV) precipitates formed in alkaline media in the presence of various anions, 98:589 (R;US)

Purification of alkaline solutions and wastes from actinides and

technetium by coprecipitation with some carriers using the

method of appearing reagents: Final Report, 98:605 (R;US)

Retained gas sampler extractor mixing and mass transfer rate

study: Experimental and simulation results, 98:575 (R;US)

Sampling and analysis plan for the former Atomic Energy Commission bus lot property, 98:594 (R;US)

Summary of uncertainty estimation results for Hanford tank chemical and radionuclide inventories, 98:610 (R;US)

Survey of radiological contaminants in the near-shore environment

at the Hanford Site 100-N Area reactor, 98:598 (R;US)

Tank Focus Area pretreatment activities, 98:98 (R;US)

TEMPEST code modifications and testing for erosion-resisting

sludge simulations, 98:579 (R;US)

TWRS privatization phase 1 monitoring wells engineering study,

98:586 (R;US)

Ventilation rates calculated from hydrogen release data in tanks

equipped with standard hydrogen monitoring systems (SHMS),

98:596 (R;US)

214 Environmental Management Technical Reports
Sandia National Labs., Albuquerque, NM (United States)

Waste tank ventilation rates measured with a tracer gas method,

98:595 (R;US)

Pacific Northwest National Lab., TN (United States)

Performance evaluation of the PITBULL pump for the removal of

hazardous waste, 98:602 (R;US)

Pacific Northwest National Labs., Richland, WA (United States)

Organic analysis progress report FY 1997, 98:573 (R;US)

Paducah Gaseous Diffusion Plant, KY (United States)

Paducah site annual environmental for 1996, 98:412 (R;US)

Parsons Infrastructure and Technology Group, Inc., Idaho Falls,

ID (United States)

Construction safety: Can management prevent all accidents or

are workers responsible for their own actions?, 98:391 (R;US)

Perma-Fix Environmental Services, Gainesville, FL (United

States)

Treatability study Number PDC-1-O-T. Final report, 98:425 (R;US)

Physical Sciences, Inc., Andover, MA (United States)

Portable sensor for hazardous waste. Topical report, October 1,

1993–September 30, 1994, 98:215 (R;US)

Providence Group, Inc., Knoxville, TN (United States)

In-Process Analysis Program for the Isolock sampler at the Gunite

and Associated Tanks, Oak Ridge National Laboratory, Oak

Ridge, Tennessee, 98:81 (R;US)

R

RAHCO International, Inc., Spokane, WA (United States)

Report for slot cutter proof-of-principle test, Buried Waste Containment System project. Revision 1, 98:196 (R;US)

Rockwell International, Rocky Flats Plant, Golden, CO (United

States)

Status and use of the Rocky Flats Environmental Technology Site

Pipe Overpack Container for TRU waste storage and shipments, 98:618 (R;US)

Rocky Flats Environmental Technology Site, Golden, CO

(United States)

NRC regulation of DOE facilities, 98:616 (R;US)

Safety Analysis and Risk Assessment Handbook, new guidance to

the safety analyst, 98:614 (R;US)

Rogers and Associates Engineering Corp., Salt Lake City, UT

(United States)

Licensing an assured isolation facility for low-level radioactive

waste. Volume 1: Licensing strategy and issues, 98:200 (R;US)

Licensing an assured isolation facility for low-level radioactive

waste. Volume 2: Recommendations on the content and review

of an application, 98:201 (R;US)

Life cycle costs for disposal and assured isolation of low-level radioactive waste in Connecticut, 98:199 (R;US)

S

Safe Sites of Colorado, Golden, CO (United States)

Cementation of residue ion exchange resins at Rocky Flats,

98:620 (R;US)

Progress in stabilization of plutonium and residues since DNFSB

recommendation 94-1, 98:621 (R;US)

The use of filtered bags to increase waste payload capacity,

98:619 (R;US)

Safe Sites of Colorado, Rocky Flats Environmental Technology

Site, Golden, CO (United States)

Panasonic dosimetry system performance testing and results at nuclear accident dose levels 500 rad to 10,000 rad, 98:623 (R;US)

Year 2000 compliance concerns with the ISA Thermoluminescent

Dosimetry Data Processing (TL-DP) software system, 98:622

(R;US)

Sandia National Labs., Albuquerque, NM (United States)

3D electromagnetic inversion for environmental site characterization, 98:640 (R;US)

A comparison of regulatory impacts to real target impacts, 98:666

(R;US)

A method of modeling time-dependent rock damage surrounding

underground excavations in multiphase groundwater flow,

98:663 (R;US)

A model for predicting damage dependent response of inelastic

media with microstructure, 98:677 (R;US)

A Modular Approach to Redundant Robot Control, 98:694 (R;US)

A new and superior ultrafine cementitious grout, 98:627 (R;US)

A risk-based decision-aiding tool for waste disposal, 98:674 (R;US)

A testing program to evaluate the effects of simulant mixed wastes

on plastic transportation packaging components, 98:659 (R;US)

An effective waste management process for segregation and

disposal of legacy mixed waste at Sandia National Laboratories/New Mexico, 98:700 (R;US)

An Effective Waste Management Process for Segregation and

Disposal of Legacy Mixed Waste at Sandia National Laboratories/New Mexico, 98:701 (R;US)

An overview of performance assessment for the Waste Isolation

Pilot Plant, 98:690 (R;US)

Analysis of hydraulic tests of the Culebra and Magenta Dolomites

and Dewey Lake Redbeds conducted at the Waste Isolation Pilot Plant Site, 98:697 (R;US)

Anticipating Potential Waste Acceptance Criteria for Defense

Spent Nuclear Fuel, 98:687 (R;US)

Application of the RADTRAN 5 stop model, 98:673 (R;US)

Assessing seal performance and parameter sensitivity with a fullshaft model, 98:712 (R;US)

Balancing compliance and cost when implementing a Quality Assurance program, 98:688 (R;US)

Beyond pretty pictures: Quantifying porous media properties and

transport processes using transmission and emission CT,

98:665 (R;US)

Calculation of density and permeability of compacted crushed salt

within an engineered shaft sealing system, 98:664 (R;US)

Calculation of population doses with RADTRAN for route segments

that have an unpopulated near-field region, 98:652 (R;US)

Characterization of septic and drain system releases at Sandia

National Laboratories, New Mexico, 98:643 (R;US)

Comparison of lumped-element and transmission-line models for

thickness-shear-mode quartz resonator sensors, 98:630 (R;US)

Comparison of Ross’ capillary barrier diversion formula with detailed numerical simulations, 98:655 (R;US)

Computer-assisted comparison of analysis and test results in

transportation experiments, 98:660 (R;US)

Condensed summary of the systems prioritization method as a

decision-aiding approach for the Waste Isolation Pilot Plant,

98:626 (R;US)

Constitutive behavior of reconsolidating crushed salt, 98:703 (R;US)

Cost comparisons of alternative landfill final covers, 98:633 (R;US)

Critical scientific issues in the demonstration of WIPP compliance

with EPA repository standards, 98:691 (R;US)

Data and methods for the assessment of the risks associated with

the maritime transport of radioactive materials: Results of the

SeaRAM program studies. Volume 1 – Main report, 98:715 (R;US)

Data and methods for the assessment of the risks associated with

the maritime transport of radioactive materials: Results of the

SeaRAM program studies. Volume 2 – Appendices, 98:716

(R;US)

Design of an experiment to measure the fire exposure of radioactive

materials packages aboard container cargo ships, 98:648 (R;US)

Designing a database for performance assessment: Lessons

learned from WIPP, 98:683 (R;US)

Developing the Sandia National Laboratories transportation infrastructure for isotope products and wastes, 98:644 (R;US)

Development of a cement-polymer close-coupled subsurface barrier technology, 98:636 (R;US)

Development of a container for the transportation and storage of

plutonium bearing materials, 98:668 (R;US)

Development of the SEAtrace barrier verification and validation

technology. Final report, 98:721 (R;US)

Effects of simulant mixed waste on EPDM and butyl rubber,

98:650 (R;US)

Electrokinetic demonstration at Sandia National Laboratories: Use

of transference numbers for site characterization and process

evaluation, 98:632 (R;US)

Environmental Management Technical Reports 215
Sandia National Labs., Albuquerque, NM (United States)

Electrokinetic demonstration at the unlined chromic acid pit,

98:676 (R;US)

Evaluation of the capabilities of the Hanford Reservation and Envirocare of Utah for disposal of potentially problematic mixed

low-level waste streams, 98:709 (R;US)

Examples of technical innovations in rock property measurements

prompted by the Waste Isolation Pilot Plant, 98:658 (R;US)

Experimental determination of the relationship between permeability and microfracture-induced damage in bedded salt, 98:707

(R;US)

Experimental ship fire measurements with simulated radioactive

cargo, 98:653 (R;US)

Extension of ship accident analysis to multiple-package shipments, 98:682 (R;US)

Field analytical technology verification: The ETV Site Characterization Program, 98:720 (R;US)

Gas generation phenomena in radioactive waste transportation

packaging, 98:647 (R;US)

Geothermal drilling technology update, 98:657 (R;US)

Graphical programming of telerobotic tasks, 98:631 (R;US)

Guidebook for performance assessment parameters used in the

Waste Isolation Pilot Plant compliance certification application.

Volume 1: Main report, 98:704 (R;US)

Guidebook for performance assessment parameters used in the

Waste Isolation Pilot Plant compliance certification application.

Volume 2: Appendices, 98:705 (R;US)

Hydraulic Characterization Activities in Support of the Shaft-Seals

Fluid-Flow Modeling Integration into the WIPP EPA Compliance

Certification Application, 98:695 (R;US)

Implementation of a fully automated process purge-and-trap gas

chromatograph at an environmental remediation site, 98:639

(R;US)

Implementation of chemical controls through a backfill system for

the Waste Isolation Pilot Plant (WIPP), 98:624 (R;US)

Importance of energy efficiency in the design of the Process and

Environmental Technology Laboratory (PETL) at Sandia National Laboratories, New Mexico (NM), 98:719 (R;US)

In situ remediation of uranium contaminated groundwater, 98:635

(R;US)

Integration and evaluation of a position sensor with continuous

read-out for use with the Environmental Measurement-WhileDrilling Gamma Ray Spectrometer system, 98:713 (R;US)

Integration of US Department of Energy contractor installations for

the purpose of optimizing treatment, storage, and disposal of

low-level radioactive waste (LLW), 98:710 (R;US)

Long-term brine migration through an engineered shaft seal system, 98:662 (R;US)

Low-level radioactive waste transportation safety history, 98:672

(R;US)

Metal sorption on kaolinite, 98:642 (R;US)

Micromechanics and homogenization techniques for analyzing the

continuum damage of rock salt, 98:711 (R;US)

Milestones for disposal of radioactive waste at the Waste Isolation

Pilot Plant (WIPP) in the United States, 98:699 (R;US)

Mixed low-level waste form evaluation, 98:638 (R;US)

Modeling fires in adjacent ship compartments with computational

fluid dynamics, 98:698 (R;US)

PASS: a component of Desk Top PA for the WIPP, 98:693 (R;US)

Performance assessment in support of compliance certification

application for the WIPP project, 98:675 (R;US)

Permeability of natural rock salt from the Waste Isolation Pilot Plant

(WIPP) during damage evolution and healing, 98:708 (R;US)

Physical and mechanical properties of degraded waste surrogate

material, 98:702 (R;US)

Planning and scheduling for agile manufacturers: The Pantex Process Model, 98:696 (R;US)

Pollution prevention and waste minimization opportunity assessment in environmental restoration, 98:670 (R;US)

Prediction of packaging seal life using thermoanalytical techniques, 98:649 (R;US)

Prediction of tilted capillary barrier performance, 98:656 (R;US)

Principles and objectives of containment verification and performance monitoring and technology selection, 98:629 (R;US)

Project report: Tritiated oil repackaging highlighting the ISMS process. Historical radioactive and mixed waste disposal request

validation and waste disposal project, 98:722 (R;US)

QA lessons learned for parameter control from the WIPP Project,

98:686 (R;US)

Radioactive material (RAM) transportation accident and incident

experience in the U.S.A. (1971–1997), 98:692 (R;US)

Radioactive material package closures with the use of shape

memory alloys, 98:646 (R;US)

Rapid world modelling from a mobile platform, 98:645 (R;US)

Reduction of Np(VI) and Pu(VI) by organic chelating agents,

98:689 (R;US)

Regulatory and extra-regulatory testing to demonstrate radioactive

material packaging safety, 98:661 (R;US)

Representation of spatial variability for modelling of flow and transport processes in the Culebra Dolomite at the WIPP site, 98:706

(R;US)

Sandia bicycle commuters group – pollution prevention at Sandia

National Laboratories, New Mexico, 98:718 (R;US)

Science to compliance: The WIPP success story, 98:678 (R;US)

SeaRAM: A DOE evaluation of maritime accident risk assessment

data and methods, 98:651 (R;US)

Studies of photoredox reactions on nanosize semiconductors,

98:625 (R;US)

Studies of photoredox reactions on nanosize semiconductors,

98:671 (R;US)

Study of the components of evacuation times, 98:681 (R;US)

Testing and analysis to determine the shell thickness required to

prevent puncture, 98:669 (R;US)

Testing, expanding and implementing pollution prevention tools for

environmental restoration and decontamination and decommissioning, 98:717 (R;US)

The effect of cargo on the crush loading of RAM transportation

packages in ship collisions, 98:667 (R;US)

The effects of heterogeneities on the performance of capillary barriers for waste isolation, 98:628 (R;US)

The electromagnetic integrated demonstration at the Idaho National Engineering Laboratory cold test pit, 98:654 (R;US)

The residuals analysis project: Evaluating disposal options for

treated mixed low-level waste, 98:634 (R;US)

Traceability and retrievability: Documentation, the bridge from science to compliance, 98:641 (R;US)

Truck transport of RAM: Risk effects of avoiding metropolitan areas, 98:680 (R;US)

United States of America activities relative to the International

Atomic Energy Agency (IAEA) initiative: Records management

for deep geologic repositories, 98:637 (R;US)

Waste reduction by separation of contaminated soils during environmental restoration, 98:714 (R;US)

WIPP Compliance Certification Application calculations parameters. Part 1: Parameter development, 98:679 (R;US)

WIPP Compliance Certification Application calculations parameters. Part 2: Parameter documentation, 98:685 (R;US)

“We crash, burn, and crush”: A history of packaging at Sandia National Laboratories, 1978–1997, 98:684 (R;US)

Science and Engineering Associates, Inc., Albuquerque, NM

(United States)

Characterization of pipes, drain lines, and ducts using the pipe explorer system, 98:212 (R;US)

Science Applications International Corp., Oak Ridge, TN (United

States)

Phase 2 confirmatory sampling data report, Lower East Fork

Poplar Creek, Oak Ridge Y-12 Plant, Oak Ridge, Tennessee,

98:786 (R;US)

Work plan for support to Upper East Fork Poplar Creek east end

VOC plumes well installation project at the Oak Ridge Y-12

Plant, Oak Ridge, Tennessee, 98:788 (R;US)

Science, Inc., Anaheim, CA (United States)

Proceedings of the efficient separations and processing crosscutting program 1997 technical exchange meeting, 98:612 (R;US)

South Carolina Universities Research and Education Foundation, Clemson, SC (United States). Strom Thurman Inst.

Measurement of radionuclides using ion chromatography and

flow-call scintillation counting with pulse shape discrimination:

216 Environmental Management Technical Reports
Waste Management Federal Services of Hanford, Inc., Richland, WA

Topical report, September 15, 1996–October 3, 1996, Tasks

1.11, 1.12 and 1.13, 98:251 (R;US)

Southwestern Indian Polytechnic Inst., Albuquerque, NM

(United States)

Tribal Colleges Initiative project. Quarterly report, April 1–June 30,

1998, 98:280 (R;US)

Tribal Colleges Initiative project. Quarterly report, April 1–June 30,

1998, 98:281 (R;US)

STEP, Inc., Oak Ridge, TN (United States)

Inactive tanks remediation program strategy and plans for Oak

Ridge National Laboratory, Oak Ridge, Tennessee, 98:506

(R;US)

T

Tennessee Dept. of Environment and Conservation, Oak Ridge,

TN (United States)

Tennessee Department of Environment and Conservation Department of Energy Oversight Division - status report to the public,

98:269 (R;US)

Textron, Inc., Wilmington, MA (United States)

Progress of electro-hydraulic scabbling technology for concrete

decontamination, 98:210 (R;US)

ThermoChem, Inc., Baltimore, MD (United States)

Steam reforming of low-level mixed waste. Final report, 98:250

(R;US)

Tribal College Initiative Program Office (United States)

Tribal Colleges Initiative project. Quarterly report, April 1–June 30,

1998, 98:281 (R;US)

U

Univ. of North Dakota Energy and Environmental Research Center, Grand Forks (United States)

Task 10 - Technology Development Integration. Semiannual report, November 1, 1996–March 31, 1997, 98:245 (R;US)

Univ. of North Dakota, Energy and Environmental Research

Center, Grand Forks, ND (United States)

EM Task 12 – Laser cleaning of contaminated painted surfaces.

Semi-annual report, April 1–September 30, 1997, 98:232 (R;US)

EM Task 13 – Cone penetrometer for subsurface heavy metals detection. Semi-annual report, April 1–September 30, 1997,

98:233 (R;US)

EM14 – Bubbleless gas transfer technology for the in situ remediation of chlorinated hydrocarbons. Semi-annual report, April

1–September 30, 1997, 98:234 (R;US)

Task 10 – Technology development integration. Semi-annual report, April 1–September 30, 1997, 98:231 (R;US)

Task 15 – Remediation of organically contaminated soil using

hot/liquid (subcritical) water. Semi-annual report, April 1–

September 30, 1997, 98:235 (R;US)

Task 2 – Extraction and analysis of pollutant organics from contaminated solids using off-line supercritical fluid extraction (SFE)

and on-line SFE-infrared spectroscopy. Semi-annual report,

April 1–September 30, 1997, 98:228 (R;US)

Task 8 – Management and reporting. Semi-annual report, April 1–

September 30, 1997, 98:229 (R;US)

Task 9 – Centrifugal membrane filtration. Semi-annual report, April

1–September 30, 1997, 98:230 (R;US)

University and Community College System of Nevada, Desert

Research Inst., Las Vegas, NV (United States)

Evaluation of groundwater flow and transport at the Shoal underground nuclear test: An interim report, 98:258 (R;US)

University and Community College System of Nevada, Desert

Research Inst., Quaternary Sciences Center, Reno, NV

(United States)

Hunter-gatherer adaptations and environmental change in the

southern Great Basin: The evidence from Pahute and Rainier

mesas, 98:257 (R;US)

USDOE Assistant Secretary for Environmental Management,

Washington, DC (United States)

1996 annual report on low-level radioactive waste management

progress. Report to Congress, 98:144 (R;US)

Equity of commercial low-level radioactive waste disposal fees.

Report to Congress, 98:145 (R;US)

Final waste management programmatic environmental impact

statement for managing treatment, storage, and disposl of radioactive and hazardous waste. Volume II, 98:137 (R;US)

Final waste management programmatic environmental impact

statement for managing treatment, storage, and disposal of radioactive and hazardous waste. Volume III of V, 98:138 (R;US)

Final waste management programmatic environmental impact

statement for managing treatment, storage, and disposal of radioactive and hazardous waste. Volume IV of V, 98:139 (R;US)

Final waste management programmatic environmental impact

statement for managing treatment, storage, and disposal of radioactive and hazardous waste. Volume V of V, 98:140 (R;US)

USDOE Idaho Operations Office, Office of Environmental Management, Idaho Falls, ID (United States)

Advanced mixed waste treatment project draft environmental impact statement, 98:141 (R;US)

USDOE Office of Environmental Management, Subsurface Contaminants Focus Area, Washington, DC (United States)

Subsurface Contaminants Focus Area annual report 1997, 98:163

(R;US)

USDOE Office of Environmental Management, Washington, DC

(United States)

Cyanide destruction/immobilization of residual sludge - mixed

waste focus area. Innovative Technology Summary Report,

98:154 (R;US)

Environmental management activities, 98:142 (R;US)

Pipe Crawler internal piping characterization system - deactivation and decommissioning focus area. Innovative Technology

Summary Report, 98:157 (R;US)

Tanks focus area. Annual report, 98:162 (R;US)

USDOE Office of Science and Technology, Washington, DC

(United States). Office of Program Analysis

FRHAM-TEX cool suit - OST reference No. 1854. Deactivation

and decommissioning focus area, 98:155 (R;US)

In situ permeable flow sensor - OST reference No. 99. Subsurface

contaminants focus area, 98:158 (R;US)

NuFab anti-contamination suit - OST reference No. 1855. Deactivation and decommissioning focus area, 98:156 (R;US)

USDOE Office of Science and Technology, Washington, DC

(United States). Research and Technical Assessment Div.

Polyethylene macroencapsulation - mixed waste focus area. OST

reference No. 30, 98:153 (R;US)

USDOE, Washington, DC (United States)

Fiscal year 1996 progress in implementing Section 120 of the

Comprehensive Environmental Response, Compensation, and

Liability Act. Tenth annual report to Congress, 98:143 (R;US)

International Containment Technology Conference: proceedings,

98:96 (R;US)

V

Vista Research, Inc., Mountain View, CA (United States)

Dry well conductivity monitoring report for Tanks W-8, W-9, and

W-10, Oak Ridge National Laboratory, Oak Ridge, Tennessee,

98:513 (R;US)

Vista Research, Inc., Oak Ridge, TN (United States)

GAAT dry well conductivity monitoring report, July 1997 through

January 1998, Oak Ridge National Laboratory, Oak Ridge, Tennessee, 98:523 (R;US)

W

Waste Management Federal Services of Hanford, Inc., Richland,

WA (United States)

Environmental Monitoring Plan United States Department of Energy Richland Operations Office. Revision 2, 98:272 (R;US)

Environmental Management Technical Reports 217
WASTREN, Inc., Westminster, CO (United States)

WASTREN, Inc., Westminster, CO (United States)

Acceptable knowledge document for INEEL stored transuranic

waste – Rocky Flats Plant waste. Revision 2, 98:380 (R;US)

Weiss Associates, Emeryville, CA (United States)

Final annual site environmental report, calendar year 1997, for the

Laboratory for Energy-Related Health Research (LEHR), University of California at Davis, California, 98:279 (R;US)

West Valley Nuclear Services Co., Inc., NY (United States)

Integrated radwaste treatment system. Final report, 98:255 (R;US)

West Virginia Univ. Research Corp., Morgantown, WV (United

States)

Decontamination systems information and research programs.

Quarterly report, July 1–August 31, 1996, 98:209 (R;US)

Westinghouse Hanford Co., Richland, WA (United States)

Cesium removal flow studies using ion exchange, 98:97 (R;US)

Westinghouse Savannah River Co., Aiken, SC (United States)

A Simple Method for Estimating Forced Convection Mass Transfer

in a Waste Tank, 98:746 (R;US)

Accelerator Production of Tritium Waste Characterization and Certification Challenges, 98:748 (R;US)

Advanced Separations at SRS, 98:751 (R;US)

Air pollution control system testing at the DOE offgas components

test facility, 98:738 (R;US)

Analysis of cascade impactor and EPA method 29 data from the

americium/curium pilot melter system, 98:757 (R;US)

Annual Radioactive Waste Tank Inspection Program - 1997,

98:775 (R;US)

Application of Epoxy Based Coating Instacote on Waste Tank

Tops, 98:777 (R;US)

Automation in a material processing/storage facility, 98:732 (R;US)

Characterization of Samples from the Effluent Treatment Facility

Evaporator Waste Concentrate Tank, 98:759 (R;US)

Characterization Plan and Dissolution Tests for Tank 16H Samples, 98:758 (R;US)

Chemical inventory control program for mixed and hazardous

waste facilities at SRS, 98:740 (R;US)

Commercial Light Water Reactor -Tritium Extraction Facility Process Waste Assessment (Project S-6091), 98:761 (R;US)

Compliance with the Nevada Test Site’s waste acceptance criteria

for vitrified cesium-loaded crystalline silicotitanate (CST),

98:736 (R;US)

Counter current decantation washing of HLW sludge, 98:735 (R;US)

Coupon corrosion monitoring of a high level waste tank, 98:731

(R;US)

Cross-Flow Filtration of Department of Energy Hanford Waste

Streams Using Sintered Metal Mott and Graver Filters at the Savannah River Technology Center, 98:749 (R;US)

Effect of nitrite concentration on pit depth in carbon steel exposed

to simulated radioactive waste, 98:743 (R;US)

ESP’s Tank 42 washwater transfer to the 241-F/H tank farms,

98:769 (R;US)

Excess Sodium Tetraphenylborate and Intermediates Decomposition Studies, 98:776 (R;US)

Feed Acceptance for the Defense Waste Processing Facility at the

Savannah River Site, 98:741 (R;US)

Fractured rock aquifer tests in the Western Siberian Basin, Ozyorsk, Russia, 98:742 (R;US)

Glass formulation development and testing for the vitrification of

cesium-loaded crystalline silicotitanate (CST), 98:734 (R;US)

Glass Formulation Development for the Vitrification of Oak Ridge

Tank Waste, 98:772 (R;US)

Groundwater Flow Model for the R-Reactor Area Final Report,

98:753 (R;US)

Hydrological methods preferentially recover cesium from nuclear

waste salt cake, 98:733 (R;US)

ICP-MS nebulizer performance for analysis of SRS high salt simulated radioactive waste tank solutions (#3053), 98:744 (R;US)

Implementation of ISO140001 at the Savannah River Site, 98:752

(R;US)

Investigation of water accumulation in an offgas test facility HEPA

housing, 98:739 (R;US)

ITP Waste Tank Positive Pressure Inerting System, 98:745 (R;US)

Joint EPA/DOE demonstration program for total mercury continuous emissions monitors, 98:737 (R;US)

On-Board Hydrogen Storage for a City Transit Bus, 98:750 (R;US)

Porflow Capabilities, Usage, History, and Testing, 98:760 (R;US)

Preliminary Disposal Analysis for Selected Accelerator Production

of Tritium Waste Streams, 98:747 (R;US)

Radioactive Testing Results in Support of the In-Tank Precipitation

Facility, 98:774 (R;US)

Remote telerobotic replacement for master-slave manipulator,

98:728 (R;US)

Removal site evaluation report L-area rubble pile (131-3L) gas

cylinder disposal facility (131-2L), 98:755 (R;US)

Report on bioventing of petroleum contaminated soils at 108-3C:

Active extraction and passive injection (barometric pumping) of

a gaseous nutrient, 98:754 (R;US)

Resolving Radiological Waste Classification and Release Issues

Using Material Process Information and Simple Measurements

and Models, 98:767 (R;US)

Rheology of Savannah River site tank 42 HLW radioactive sludge,

98:756 (R;US)

Sampling plan to support HLW tank 16, 98:765 (R;US)

Sanitary Landfill Groundwater Monitoring Report. Fourth Quarter

1997 and 1997 Summary, 98:771 (R;US)

Sodium Aluminosilicate Formation in Tank 43H Simulants, 98:768

(R;US)

Solubility Limits of Dibutyl Phosphoric Acid in Uranium Solutions at

SRS, 98:781 (R;US)

Summary of Tests to Determine Effectiveness of Gelatin Strike on

SS&C Dissolver Solutions, 98:780 (R;US)

Technology Status Report of the Applicability of Solid-Liquid Separation Methods to Radioactive Tank Wastes, 98:770 (R;US)

The application of metal cutting technologies in tasks performed in

radioactive environments, 98:729 (R;US)

The Solubility of Phenylborate Compounds in Benzene, 98:778

(R;US)

Trial Burn Activities for a Mixed Waste Incinerator, 98:773 (R;US)

Tritium Facilities Modernization and Consolidation Project Process

Waste Assessment (Project S-7726), 98:766 (R;US)

Westinghouse Savannah River Co., Savannah River Site, Aiken,

SC (United States)

Savannah River Site environmental report for 1997 summary,

98:763 (R;US)

Westinghouse Savannah River Company, Aiken, SC (United

States)

A Simple Method for Estimating Forced Convection Mass Transfer

in a Waste Tank, 98:746 (R;US)

Analysis of Steam Heating of a Two-Layer TBP/N-Paraffin/Nitric

Acid Mixtures, 98:779 (R;US)

Annual Radioactive Waste Tank Inspection Program - 1997,

98:775 (R;US)

Application of Epoxy Based Coating Instacote on Waste Tank

Tops, 98:777 (R;US)

Commercial Light Water Reactor Irradiated Hardware Waste

Stream, 98:782 (R;US)

Excess Sodium Tetraphenylborate and Intermediates Decomposition Studies, 98:776 (R;US)

Groundwater Flow Model for the R-Reactor Area Final Report,

98:753 (R;US)

High Level Waste Evaporator Analysis Results, 98:783 (R;US)

High Level Waste System Plan Revision 9, 98:297 (R;US)

ITP Waste Tank Positive Pressure Inerting System, 98:745 (R;US)

Porflow Capabilities, Usage, History, and Testing, 98:760 (R;US)

Radioactive Testing Results in Support of the In-Tank Precipitation

Facility, 98:774 (R;US)

Resolving Radiological Waste Classification and Release Issues

Using Material Process Information and Simple Measurements

and Models, 98:767 (R;US)

Savannah River Site Environmental Report for 1997 Summary,

98:764 (R;US)

Sodium Aluminosilicate Formation in Tank 43H Simulants, 98:768

(R;US)

Solubility Limits of Dibutyl Phosphoric Acid in Uranium Solutions at

SRS, 98:781 (R;US)

Summary of Tests to Determine Effectiveness of Gelatin Strike on

SS&C Dissolver Solutions, 98:780 (R;US)

Tetraphenylborate Solids Stability Tests, 98:762 (R;US)

218 Environmental Management Technical Reports
XL Associates, Inc., Oak Ridge, TN (United States)

The Solubility of Phenylborate Compounds in Benzene, 98:778

(R;US)

X

XL Associates, Inc., Oak Ridge, TN (United States)

North Tank Farm data report for the Gunite and Associated Tanks

at Oak Ridge National Laboratory, 98:555 (R;US)

Environmental Management Technical Reports 219
Personal Author Index

Authors’ surnames are indexed in the form appearing in the publication cited; given names generally have been reduced

to initials. For documents with multiple authors, each author name is indexed. The entry for a primary author (first author

listed on an abstracted document) includes the full document title and citation number. Entries for other authors provide

a cross-reference to the primary author. Also included is information on the document type, country of publication, and

the document language listed in parentheses in the format (J;FR;In French and English). Accent marks are not input because of computer alphabetization. Spelling and transliteration follow standard conventions.

A

Aase, S.B., See Reed, D.T., 98:689

Adams, J.P., See Dahl, C.A., 98:284

See Ramer, R.J., 98:304

Adams, V., U.S. Department of Energy National Center of Excellence for Metals Recycle, 98:498 (R;US)

U.S. Department of Energy National Center of Excellence for Metals Recycle, 98:501 (R;US)

Adamson, D.J., Commercial Light Water Reactor Irradiated Hardware Waste Stream, 98:782 (R;US)

Ades, M.J., Accelerator Production of Tritium Waste Characterization and Certification Challenges, 98:748 (R;US)

Chemical inventory control program for mixed and hazardous

waste facilities at SRS, 98:740 (R;US)

Preliminary Disposal Analysis for Selected Accelerator Production

of Tritium Waste Streams, 98:747 (R;US)

Agarwal, D.C., See Anderson, P.A., 98:324

Ahrens, E.H., A new and superior ultrafine cementitious grout,

98:627 (R;US)

Aikin, J.T., See Gauglitz, P.A., 98:571

Aines, R.D., See Leif, R.N., 98:723

Akers, D.W., See Sohal, M.S., 98:341

Albin, C.L., See Van Verst, S.P., 98:598

Alexander, G.J., See Hsu, R.H., 98:761

Alexandratos, S.D., See Gu, B., 98:553

Alfa, T., See Jefimoff, J., 98:319

Allan, S.E., See Grisanti, A.A., 98:232

Allen, D.H., A model for predicting damage dependent response of

inelastic media with microstructure, 98:677 (R;US)

See DeVries, K.L., 98:711

Allen, T.H., See Haschke, J.M., 98:440

Allred, W.E., The basics in transportation of low-level radioactive

waste, 98:198 (R;US)

AlMahamid, I., Literature search on the use of resins for treatment

of radioactive wastes, 98:466 (R;US)

Aloy, A.S., Volatilization of heavy metals and radionuclides from soil

heated in an induction “cold” crucible melter, 98:323 (R;US)

Alumbaugh, D.L., 3D electromagnetic inversion for environmental

site characterization, 98:640 (R;US)

See Pellerin, L., 98:654

Amaya, J.P., International waste management fact book, 98:567

(R;US)

Amidan, B.G., See Ferryman, T.A., 98:610

Ammerman, D., Development of a container for the transportation

and storage of plutonium bearing materials, 98:668 (R;US)

Ammerman, D.J., A comparison of regulatory impacts to real target

impacts, 98:666 (R;US)

Regulatory and extra-regulatory testing to demonstrate radioactive

material packaging safety, 98:661 (R;US)

Testing and analysis to determine the shell thickness required to

prevent puncture, 98:669 (R;US)

See Knight, R.D., 98:660

See Radloff, H.D., 98:667

See Sprung, J.L., 98:651

Amonette, J.E., See Thornton, E.C., 98:565

Anderl, R.A., See Longhurst, G.R., 98:363

Anderson, D.R., See Jow, H.N., 98:675

See Jow, Hong-Nian, 98:690

Anderson, G., See Soelberg, N., 98:340

Anderson, H.L., See Westrich, H.R., 98:642

Anderson, K.K., See Collins, J.L., 98:482

Anderson, M.O., The VirtualwindoW for nuclear applications,

98:398 (R;US)

Anderson, M.S., See Hylton, T.D., 98:121, 98:551

Anderson, P.A., Corrosion Resistance of Various High Chromium

Alloys in Simulated Chemical Processing Nuclear Plant Waste

Solutions, 98:324 (R;US)

Anderson, R.J., A Modular Approach to Redundant Robot Control,

98:694 (R;US)

Anderson, T.D., Environmental Restoration Project - Systems Engineering Management Plan, 98:53 (R;US)

Andrews, M.K., Glass formulation development and testing for the

vitrification of cesium-loaded crystalline silicotitanate (CST),

98:734 (R;US)

Glass Formulation Development for the Vitrification of Oak Ridge

Tank Waste, 98:772 (R;US)

See Harbour, J.R., 98:736

Andrews, W.B., See Jarvis, T.T., 98:585

Andricevic, R., See Pohll, G., 98:258

Antoniak, Z.I., See Caley, S.M., 98:607

See Mahoney, L.A., 98:578

Antonio, E.J., See Van Verst, S.P., 98:598

Aponte, C.I., ESP’s Tank 42 washwater transfer to the 241-F/H tank

farms, 98:769 (R;US)

Appelhans, A.D., See Groenewold, G.S., 98:303

Aramayo, G.A., Impact analysis of stainless steel spent fuel canisters, 98:504 (R;US)

See Shappert, L.B., 98:493

Armstrong, G.A., Topographical mapping system for radiological

and hazardous environments acceptance testing, 98:476 (R;US)

Arnett, M., Savannah River Site environmental report for 1997 summary, 98:763 (R;US)

Savannah River Site Environmental Report for 1997 Summary,

98:764 (R;US)

Arrington, T., See Federici, C., 98:434

Arviso, M., See Koski, J.A., 98:653

Ashwood, T.L., See Greeley, M.S. Jr., 98:796

Askew, N.M., See Laurinat, J.E., 98:779

Astafurova, L.N., See Fedoseev, A.M., 98:588

See Krot, N.N., 98:589

Athmer, C., Development of an integrated in-situ remediation technology. Draft topical report for Task #7.2 entitled “Field scale

test” (January 10, 1996–December 31, 1997), 98:268 (R;US)

Athmer, C.J., Development of an integrated in-situ remediation

technology. Topical report for task No. 12 and 13 entitled: Large

scale field test of the Lasagna process, September 26, 1994–

May 25, 1996, 98:221 (R;US)

See Ho, Sa V., 98:218

See Hughes, B.M., 98:226

Atkinson, D.A., Field screening of soils contaminated with explosives using ion mobility spectrometry, 98:387 (R;US)

Aulich, Ted R., See Ness, Robert O., 98:247

Aumeier, S.E., Statistical signal processing and artificial intelligence

applications in the nondestructive assay of U/Pu bearing materials, 98:26 (R;US)

Averill, R.H., See Lord, D.L., 98:338

220 Environmental Management Technical Reports
Blankenship

B

Babain, V.A., See Todd, T.A., 98:329

Bacigalupa, G.A., See Schumann, P.B., 98:428

Badden, J.W., 300 Area Process Trenches Postclosure Plan,

98:275 (R;US)

Baghel, S.S., See Shapiro, A.P., 98:223

Bain, P., See Murphy, L., 98:613

Baird, R.D., See Chau, B., 98:199

See Silverman, D.J., 98:200, 98:201

Bakel, A.J., Pu and Gd chemistry of zirconolite polytypes in a titanate ceramic, 98:11 (R;US)

See Ebert, W.L., 98:8, 98:13

Baker, J.L., See Gardner, F.G., 98:554

Baker, M.N., Integrated radwaste treatment system. Final report,

98:255 (R;US)

Ball, J.M., Progress in stabilization of plutonium and residues since

DNFSB recommendation 94-1, 98:621 (R;US)

Banaee, J., See Russell, N.E., 98:342, 98:343

Banaszak, J.E., See Reed, D.T., 98:689

Bao, Y.S., Alternative methods to determine headwater benefits,

98:533 (R;US)

Barnes, C.M., See Russell, N.E., 98:342, 98:343

Barnes, M.J., Excess Sodium Tetraphenylborate and Intermediates

Decomposition Studies, 98:776 (R;US)

See Hobbs, D.T., 98:774

Barnett, D.B., Groundwater monitoring plan for the Hanford Site

216-B-3 pond RCRA facility, 98:590 (R;US)

Barr, E.B., See Benson, J.M., 98:133

Barr, M.E., See Marsh, S.F., 98:437

Barren, E., Rapid surface sampling and archival record system

(RSSAR), 98:213 (R;US)

Barry, R.E., Rapid world modelling from a mobile platform, 98:645

(R;US)

Barton, J.W., Predictive mathematical modeling of trickling bed

biofilters for elucidating mass transfer and kinetic effects, 98:486

(R;US)

See Klasson, K.T., 98:481

Bartsch, R.A., See Marsh, S.F., 98:437

Basabilvazo, G., See Jow, H.N., 98:675

Baskaran, S., See Mattigod, S.V., 98:611

Bates, J.K., See Fortner, J.A., 98:9

See Luo, J.S., 98:7

Bates, J.M., See Mahoney, L.A., 98:578

See Recknagle, K.P., 98:575

Bates, R.M., The greenhouse of the future: Using a sponsored competition in a capstone course, 98:195 (R;US)

Bauer, R.G., Data Quality Objectives Report for the 115-B Gas Tunnel, 98:60 (R;US)

Baumbauer, D., See Bates, R.M., 98:195

Bauser, M.A., See Silverman, D.J., 98:200, 98:201

Bayne, C.K., See Dindal, A.B., 98:124

See Hylton, T.D., 98:121, 98:551

Beach, J.A., See Fryar, D.G., 98:662

Beahm, E.C., Status report on solid control in leachates, 98:559

(R;US)

Beahm, E.C., Weber, C.F., Solids Control in Sludge Pretreatment,

98:122 (R;US)

Beauchesne, A.M., The NGA-DOE grant to examine critical issues

related to radioactive waste and materials disposition involving

DOE facilities. Quarterly report, October 1–December 31, 1997,

98:187 (R;US)

Beauheim, R.L., Analysis of hydraulic tests of the Culebra and Magenta Dolomites and Dewey Lake Redbeds conducted at the

Waste Isolation Pilot Plant Site, 98:697 (R;US)

See Meigs, L.C., 98:706

Beaver, D.E., See Roush, D.E. Jr., 98:294

Bechtold, T.E., See Cooley, C.R., 98:306

Becker, B.H., See McCarthy, J.M., 98:339

Beckman, T.D., See Dustin, D.F., 98:620

Beene, D.E. Jr., See Koski, J.A., 98:653

Beitel, G.A., Systems engineering identification and control of mixed

waste technology development, 98:400 (R;US)

Belcher, G., Paducah site annual environmental for 1996, 98:412

(R;US)

Bellofatto, D., See Clauss, S.A., 98:573

Bellofatto, D.L., See Campbell, J.A., 98:601

Belov, V.Z., See Aloy, A.S., 98:323

Bennett, M., See Adams, V., 98:498, 98:501

Benson, J., Visualizing data for environmental analysis, 98:433

(R;US)

Benson, J.M., Improved risk estimates for carbon tetrachloride.

Project status report and technical progress report, 98:133 (R;US)

Bentz, C.B., See Bentz, E.J. Jr., 98:19, 98:22

Bentz, E.J. Jr., Legal precedents regarding use and defensibility of

risk assessment in Federal transportation of SNF and HLW,

98:19 (R;US)

Nevada Risk Assessment/Management Program scientific peer

review, 98:22 (R;US)

Berg, J.M., New spectroscopic studies of plutonium (IV) nitrate complex formation in solution, 98:435 (R;US)

Plutonium (IV) complexation by nitrate in acid solutions of ionic

strengths from 2 to 19 molal, 98:438 (R;US)

Bergeron, M.P., See Cole, C.R., 98:582

See Kincaid, C.T., 98:581

Bespalko, S.J., See Sprung, J.L., 98:715, 98:716

Bessonov, A.A., See Fedoseev, A.M., 98:588

Best, R.E., See Pope, R.B., 98:489

Betsill, J.D., See Reichhardt, D.K., 98:629

Betts, S., See Vigil, J., 98:429

Betts, S.E., See Taggart, D.P., 98:430

Bhatt, R.N., Evaluation of engineered barriers at the Idaho National

Engineering and Environmental Laboratory, 98:310 (R;US)

Bhattacharyya, S.K., Large-scale demonstration of D&D technologies, 98:42 (R;US)

See Yule, T.J., 98:43

Billets, S., See Dindal, A.B., 98:124

Billingsley, K., Large underground radioactive waste storage tanks

successfully cleaned at Oak Ridge National Laboratory, 98:503

(R;US)

Billingsley, K.M., See Kent, T.E., 98:548

Bills, K.C., Simulation tools for hazardous waste removal, 98:107

(R;US)

Birk, M.B., Trial Burn Activities for a Mixed Waste Incinerator,

98:773 (R;US)

Birk, S.M., Design and operational considerations of United States

commercial near-surface low-level radioactive waste disposal

facilities, 98:314 (R;US)

Performance assessment and licensing issues for United States

commercial near-surface low-level radioactive waste disposal

facilities, 98:320 (R;US)

Birkholz, H.L., See Fox, M.B., 98:56

Bishop, L., See Adams, V., 98:498, 98:501

Biyani, R.K., See Maio, V., 98:496

Bjornstad, D.J., DOE-EM privatization and the 2006 Plan: Principles

for procurement policies and risk management, 98:410 (R;US)

Black, D.B., Deployment of remote dismantlement systems at the

CP-5 reactor, 98:41 (R;US)

See Bhattacharyya, S.K., 98:42

Blacker, P.B., Integration of project management and systems engineering: Tools for a total-cycle environmental management

system, 98:406 (R;US)

Blackwood, L.G., Passive active neutron radioassay measurement

uncertainty for combustible and glass waste matrices, 98:383

(R;US)

Sampling and verification methods for the uncertainty analysis of

NDA and NDE waste characterization systems, 98:384 (R;US)

SWEPP PAN assay system uncertainty analysis: Active mode measurements of solidified aqueous sludge waste, 98:350 (R;US)

Blair, D.S., Implementation of a fully automated process purge-andtrap gas chromatograph at an environmental remediation site,

98:639 (R;US)

Blair, L.M., See Draper, J.V., 98:101, 98:102

Blair, M.S., See Egidi, P.V., 98:478

Blanchard, A., ITP Waste Tank Positive Pressure Inerting System,

98:745 (R;US)

Blankenship, K.D., See Shah, V.M., 98:475

Environmental Management Technical Reports 221
Blanton

Blanton, M.L., See Van Verst, S.P., 98:598

Blasing, T.J., Temperature inversions in the vicinity of Oak Ridge,

Tennessee, as characterized by tethersonde data, 98:544 (R;US)

Blomquist, R.N., VIM: Initial ENDF/B-VI experience, 98:39 (R;US)

Blumenkranz, D.B., See Corpuz, F.M., 98:70

Blunt, D., See Ranek, N.L., 98:24

Boak, D.M., Condensed summary of the systems prioritization

method as a decision-aiding approach for the Waste Isolation

Pilot Plant, 98:626 (R;US)

Boak, J.M., Systematic evaluation of options to avoid generation of

noncertifiable transuranic (TRU) waste at Los Alamos National

Laboratory, 98:452 (R;US)

Boardman, R.D., Alternative calcination development status report,

98:333 (R;US)

See Nenni, J.A., 98:399

Bobbe, J.G., See Koski, J.A., 98:653

Bobroff, S., Nuclear magnetic resonance measurement of ammonia

diffusion in dense solid-liquid slurries. Revision 1, 98:568 (R;US)

Bogle, M.A., See Spalding, B.P., 98:515, 98:516

Bond, S.L., See Rodovsky, T.J., 98:68

Bonnesen, P.V., See Gu, B., 98:553

See Moyer, B.A., 98:92, 98:484

Bontha, J.R., See Brown, G.N., 98:574

Book, W.J., See Davis, J.T., 98:109

Bostick, D.A., Multi-weight isotherm results for mercury removal in

upper East Fork Popular Creek water, 98:550 (R;US)

Bostick, D.T., Evaluation of improved techniques for the removal of

fission products from process wastewater and groundwater: FY

1997 status, 98:534 (R;US)

See DePaoli, S.M., 98:499

Bourgeois, T.G., See Coles, G.W., 98:615

Boyle, R.W., See Pope, R.B., 98:488, 98:492

Bracco, A., See Barren, E., 98:213

Brackin, M.J., Development of an integrated in-situ remediation

technology. Topical report for task No. 7 entitled: Development

of degradation processes, September 26, 1994–May 25, 1996,

98:225 (R;US)

Brady, P.V., See Westrich, H.R., 98:642

Bredt, P.R., See Rassat, S.D., 98:604

See Scheele, R.D., 98:600

Brehm, D.M., Survey Method for Radiological Surveys of 300-FF-1

Operable Unit Soils and Material, 98:59 (R;US)

Technical Basis to Describe the Use of the Eberline E-600, 98:63

(R;US)

Brewer, K.N., See Herbst, R.S., 98:335

See Law, J.D., 98:312, 98:364, 98:402

See Todd, T.A., 98:329

Broadhead, B.L., See Parks, C.V., 98:527

Broderick, T., See Chambers, A., 98:322

Brodsky, N.S., See Pfeifle, T.W., 98:707

Bronowski, D.R., See Koski, J.A., 98:646

Brooke, J.N., Counter current decantation washing of HLW sludge,

98:735 (R;US)

Hydrological methods preferentially recover cesium from nuclear

waste salt cake, 98:733 (R;US)

Brown, A.N., Spreadsheet application to classify radioactive material for shipment, 98:325 (R;US)

Brown, C.H., See Haas, W.J., 98:407

See Haas, W.J. Jr., 98:408, 98:409

Brown, G.M., See Gu, B., 98:553

Brown, G.N., Comparison of inorganic ion exchange materials for

removing cesium, strontium, and transuranic elements from Kbasin water, 98:574 (R;US)

Brown, H., See Norris, C., 98:202, 98:203, 98:204, 98:205

Brown, T.M., Sampling and Analysis Instruction for the 120-F-1

Glass Dump Site, 98:61 (R;US)

Brown-van Hoozer, S.A., See Kenley, C.R., 98:300

Brumburgh, G.P., Alternate airborne release fraction determination

for hazardous waste management storage repository hazard

categorization at the Lawrence Livermore National Laboratory,

98:724 (R;US)

Bryan, S.A., See Peurrung, L.M., 98:583, 98:584

Buck, E.C., Microscopic analysis of Pu-contaminated incinerator

ash: Implications for immobilization, 98:10 (R;US)

See Bakel, A.J., 98:11

Buck, J.W., See Jarvis, T.T., 98:585

Buckmaster, M.A., Inspection, Monitoring, and Maintenance Plan

for the 300 Area Process Trenches, 98:72 (R;US)

Budantseva, N.A., See Fedoseev, A.M., 98:588

Buhl, A.R., NRC regulation of DOE facilities, 98:616 (R;US)

Burke, D.S., See Serne, R.J., 98:563

Burks, B.L., See Billingsley, K., 98:503

See Rule, V.A., 98:555

Burman, S.N., Environmental health and safety plan for the Molten

Salt Reactor Experiment Remediation Project at Oak Ridge National Laboratory, Oak Ridge, Tennessee, 98:507 (R;US)

Burns, D., See Ranek, N.L., 98:20

Burns, D.B., Air pollution control system testing at the DOE offgas

components test facility, 98:738 (R;US)

Joint EPA/DOE demonstration program for total mercury continuous emissions monitors, 98:737 (R;US)

See Haas, W.J., 98:407

See Haas, W.J. Jr., 98:408, 98:409

See Speed, D.L., 98:739

Burns, H.H., See Burns, D.B., 98:738

See Speed, D.L., 98:739

Buscher, C.T., See Morris, D.E., 98:439

Byington, G.A., See Feldman, M.R., 98:487

Bynum, R.V., Implementation of chemical controls through a backfill

system for the Waste Isolation Pilot Plant (WIPP), 98:624 (R;US)

C

Cadwallader, L.C., See Longhurst, G.R., 98:363

Caley, S.M., Investigation of flammable gas and thermal safety issues for retrieval of waste from Tank 241-AN-105, 98:607 (R;US)

See Rassat, S.D., 98:604

Caliva, R.M., See Murphy, J.A., 98:302

Callahan, G.D., Constitutive behavior of reconsolidating crushed

salt, 98:703 (R;US)

Camaioni, D., See Meisel, D., 98:5

Camaioni, D.M., Organic tanks safety program waste aging studies.

Final report, Revision 1, 98:591 (R;US)

Organic tanks safety program, FY97 waste aging studies. Revision 1, 98:566 (R;US)

Cameron, P., See Gu, B., 98:93

Campbell, J.A., Organic speciation of AX-102, BX-104, C-104, C201, and C-202 tank wastes, 98:601 (R;US)

See Camaioni, D.M., 98:566

Carden, D.M., See Dindal, A.B., 98:124

Carlson, C.D., Demonstration of strontium removal from Hanford NArea well water, 98:608 (R;US)

Carlson, R.D., See Liu, Y.Y., 98:38

Carnes, S.A., See Schweitzer, M., 98:119

Carpenter, M.V., Mapping of contamination at Savannah River Site

FBWU by INEEL trolley, 98:365 (R;US)

Carreon, R., See Schlahta, S.N., 98:576

Carson, K.J., See Brown, G.N., 98:574

Carson, S.D., See Hsu, R.H., 98:761

Carter, L.L., New probability table treatment in MCNP for unresolved resonances, 98:457 (R;US)

Case, J.T., See Waters, R.D., 98:634

Cash, J.M., See Pope, R.B., 98:489

Cavin, B. III, Greenhouse of the future. Final report, 98:197 (R;US)

Cernosek, R.W., Comparison of lumped-element and transmissionline models for thickness-shear-mode quartz resonator sensors,

98:630 (R;US)

Chamberlain, D.C., See Fortner, J.A., 98:9

Chambers, A., Mercury emissions control technologies for mixed

waste thermal treatment, 98:322 (R;US)

See Soelberg, N., 98:340

Chang, Y.S., Evaluation of the area factor used in the RESRAD

code for the estimation of airborne contaminant concentrations

of finite area sources, 98:25 (R;US)

Channell, J.K., See Neill, R.H., 98:125

Chapman, J., See Pohll, G., 98:258

222 Environmental Management Technical Reports
Davidson

Chase, J., Sanitary Landfill Groundwater Monitoring Report. Fourth

Quarter 1997 and 1997 Summary, 98:771 (R;US)

Chaturvedi, L., See Neill, R.H., 98:125

Chau, B., Life cycle costs for disposal and assured isolation of lowlevel radioactive waste in Connecticut, 98:199 (R;US)

Chen, G., See Ferryman, T.A., 98:610

See Stewart, C.W., 98:587

Chen, S.Y., Conceptual framework and technical basis for clearance

of materials with residual radioactivity, 98:18 (R;US)

See Bentz, E.J. Jr., 98:19, 98:22

See Nieves, L.A., 98:16

See Ranek, N.L., 98:20, 98:24

Cheng, W.C., See Waters, R.D., 98:709

Cheng, Wu-Ching, See Pohl, P.I., 98:638

Chien, H.T., See Sheen, S.H., 98:4, 98:37

Chin, C.J., See Ying, T.Y., 98:474

Choi, A.S., See Davis, N.R., 98:297

Chou, C.J., See Barnett, D.B., 98:590

Christian-Frear, T., A method of modeling time-dependent rock

damage surrounding underground excavations in multiphase

groundwater flow, 98:663 (R;US)

Christian-Frear, T.L., Examples of technical innovations in rock

property measurements prompted by the Waste Isolation Pilot

Plant, 98:658 (R;US)

Chu, M.S., See Howarth, S.M., 98:678

Chu, M.S.Y., See Bynum, R.V., 98:624

See Weart, W.D., 98:691

Cisneros, M.A., See Berg, J.M., 98:438

Clark, E.A., See Hsu, R.H., 98:761

Clark, F.R., See Fellhauer, C.R., 98:14

Clausen, E.C., See Klasson, K.T., 98:110

Clauss, S.A., Organic analysis progress report FY 1997, 98:573

(R;US)

See Camaioni, D.M., 98:566

See Campbell, J.A., 98:601

Clemo, T.M., See Neill, R.H., 98:125

Cline, S.R., Performance of in situ chemical oxidation field demonstrations at DOE sites, 98:123 (R;US)

See Spalding, B.P., 98:515, 98:516

Cohen, H.S., See Ades, M.J., 98:748

Cole, C.M., Assessment results of the South Korea TRIGA SNF to

be shipped to INEEL, 98:317 (R;US)

Cole, C.R., Three-dimensional analysis of future groundwater flow

conditions and contaminant plume transport in the Hanford Site

unconfined aquifer system: FY 1996 and 1997 status report,

98:582 (R;US)

See Kincaid, C.T., 98:581

Cole, J.K., See Koski, J.A., 98:653

See Wix, S.D., 98:698

Coles, G.W., Workforce mobilization for D&D at the Rocky Flats Environmental Technology Site (RFETS), 98:615 (R;US)

Collard, L.B., Porflow Capabilities, Usage, History, and Testing,

98:760 (R;US)

Collings, M.E., See Stepan, D.J., 98:239

Collins, J.L., Development and testing of spheroidal inorganic sorbents, 98:482 (R;US)

Collins, J.L., Egan, B.Z, Basic and Acidic Leaching of Sludge from

Melton Valley Storage Tank W-25, 98:472 (R;US)

Colson, S.D., See Hunter, V.L., 98:580

Combs, W.H., See Hatchell, B.K., 98:602

Compere, A.L., Strategies for the cost effective treatment of Oak

Ridge legacy wastes, 98:547 (R;US)

Conley, T.B., Mixed Waste Focus Area Mercury Working Group: An

integrated approach to mercury waste treatment and disposal,

98:480 (R;US)

The mixed waste focus area mercury working group: an integrated

approach for mercury treatment and disposal, 98:99 (R;US)

Conner, C., See Shearer, T.L., 98:30

Conner, J.E., The Mixed Waste Focus Area: Status and accomplishments, 98:390 (R;US)

Connolly, M.J., Position for determining gas-phase volatile organic

compound concentrations in transuranic waste containers. Revision 2, 98:298 (R;US)

TRU waste transportation – The flammable gas generation problem, 98:443 (R;US)

Conway, R., See Roybal, J.A., 98:714

Cook, A., See Meisel, D., 98:5

Cook, D., See Honigford, L., 98:296

Cook, J., See Kerr, P.L., 98:426

Cook, J.C., See Pope, R.B., 98:488

Cook, J.R., See Pope, R.B., 98:492

Cooley, C., See McClure, L., 98:404

Cooley, C.R., Integrated process analysis of treatment systems for

mixed low level waste, 98:306 (R;US)

Coony, M., See Lucas, M., 98:710

Cooper, A.T., See Van Verst, S.P., 98:598

Corneillie, T.M., See Carlson, C.D., 98:608

Corpuz, F.M., Cleanup Verification Package for the 107-D5 Trench,

98:70 (R;US)

Coryell, E.W., Preliminary design report for SCDAP/RELAP5 lower

core plate model, 98:377 (R;US)

See Harvego, E.A., 98:321

Cottam, R.E., See Cole, C.M., 98:317

Cotten, G.B., Construction safety: Can management prevent all accidents or are workers responsible for their own actions?,

98:391 (R;US)

Cotton, J., See Bynum, R.V., 98:624

Cowley, J.L., See Foster, B.D., 98:259

Craig, K.A., Systems engineering based planning for DOE D&D projects, 98:40 (R;US)

Cramer, E., See Cremer, C.D., 98:212

Crawford, C.L., See Hobbs, D.T., 98:774

Crawford, M.B., PASS: a component of Desk Top PA for the WIPP,

98:693 (R;US)

Creed, R., Gravity gradiometry difference measurement as a tool for

monitoring pumping and injection; forward modeling results,

98:395 (R;US)

Cremer, C.D., Characterization of pipes, drain lines, and ducts using

the pipe explorer system, 98:212 (R;US)

Crocker, C.R., See Grisanti, A.A., 98:233

Crocker, Charlene R., See Grisanti, Ames A., 98:249

Crockett, A.B., See Atkinson, D.A., 98:387

Cummins, R.L., See Walker, J.F. Jr., 98:536

Cunningham, G.R., See Morrissey, C.M., 98:524, 98:525, 98:526

Curry, L.R., 105-F and DR Phase 1 Sampling and Analysis Plan,

98:277 (R;US)

Cuta, J.M., See Caley, S.M., 98:607

Cygan, R.T., See Westrich, H.R., 98:642

D

Dafoe, R.E., Direct cementitious waste option study report, 98:360

(R;US)

DPC loading feasibility study report, 98:348 (R;US)

Dahl, C.A., Deployment evaluation methodology for the electrometallurgical treatment of DOE-EM spent nuclear fuel, 98:284 (R;US)

See Ramer, R.J., 98:304

Dahl, T.L., See Haire, M.J., 98:115

Dahlmeir, M.M., Calcined solids storage facility closure study,

98:357 (R;US)

See Hyde, R.A., 98:401

See Spaulding, B.C., 98:345

Dahlquist, R.L., Security preparation for receipt of SNF from the

FRR to the INEEL, 98:315 (R;US)

Dale, Tim, See Knowles, M.K., 98:695

Daling, P.M., Atmospheric dispersion of ammonia accidentally released from the 242-A Evaporator, Hanford Site, Richland,

Washington, 98:577 (R;US)

Daly, D.J., Task 8 – Management and reporting. Semi-annual report,

April 1–September 30, 1997, 98:229 (R;US)

See Erickson, T.A., 98:231

See Hendrikson, J.G., 98:240

Daly, Daniel J., See Erickson, Thomas A., 98:245

Dauda, T., See Orth, R., 98:267

Davenport, D., See Gu, B., 98:93

Davidson, J.S., See Hepworth, H.K., 98:112

Environmental Management Technical Reports 223
Davis

Davis, C.B., Assessment of the RELAP5 multi-dimensional component model using data from LOFT test L2-5, 98:352 (R;US)

Davis, J.T., An investigation of a passively controlled haptic interface, 98:109 (R;US)

Davis, N.R., High Level Waste System Plan Revision 9, 98:297 (R;US)

See Valentine, J.H., 98:305

Davis, P.L., Characterization Plan and Dissolution Tests for Tank

16H Samples, 98:758 (R;US)

Davison, B.H., See Barton, J.W., 98:486

See Klasson, K.T., 98:481

Day, J.L., See Maassen, L., 98:453

Day, R.S., N Area Final Project Program Plan, 98:66 (R;US)

Decker, L.A., High level waste facilities – Continuing operation or orderly shutdown, 98:367 (R;US)

DeHart, M.D., See Parks, C.V., 98:527

Del Cul, G.D., Passivation of fluorinated activated charcoal, 98:537

(R;US)

Delley, A.O., See Hsu, R.H., 98:761

DeMeo, G.A., See Nichols, W.D., 98:726

Demers, J.W., ALARA Review for the Sediment Relocation and Removal from the 105-N Fuel Storage Basin, 98:71 (R;US)

Densmore, J.D., Correction to the MCNP perturbation feature for

cross-section dependent tallies, 98:416 (R;US)

DePaoli, S.M., Current and projected liquid low-level waste generation at ORNL, 98:538 (R;US)

Process wastewater treatment with hydrogen-form CST and

chabazite zeolite, 98:499 (R;US)

See Bostick, D.T., 98:534

Derrien, H., See Leal, L.C., 98:539

DesChane, J.R., See Brown, G.N., 98:574

See Carlson, C.D., 98:608

Detering, B.A., An engineering and economic analysis: Inductively

coupled plasma mobile treatment of hazardous waste, 98:337

(R;US)

DeVore, J.R., Statistical description of liquid low-level waste system

supernatant liquids at Oak Ridge National Laboratory, Oak

Ridge, Tennessee, 98:530 (R;US)

DeVries, K.L., Micromechanics and homogenization techniques for

analyzing the continuum damage of rock salt, 98:711 (R;US)

See Allen, D.H., 98:677

Dickens, T.G., See Nigrey, P.J., 98:650, 98:659

Dickman, P.T., See Nigrey, P.J., 98:659

Dietz, N.L., See Luo, J.S., 98:7

Dilday, D., See Honigford, L., 98:296

Dillion, J., See Ebadian, M.A., 98:181

Dillow, T.A., See Beahm, E.C., 98:559

Dindal, A.B., Field technologies for the measurement of PCBs,

98:124 (R;US)

See Einfeld, W., 98:720

Dirk, W.J., See Cole, C.M., 98:317

Ditch, R.W., See Black, D.B., 98:41

Djordjevic, S., See Liekhus, K., 98:327

Djordjevic, S.M., See Connolly, M.J., 98:298

Dmitriev, S.A., See Aloy, A.S., 98:323

Dochat, G.R., See Armstrong, G.A., 98:476

Doll, W.E., Reprocessing of Shallow Seismic Reflection Data to Image Faults Near a Hazardous Waste Site on the Oak Ridge

Reservation, Tennessee, 98:483 (R;US)

See Liu, Z.-M., 98:100

Donohoe, R.J., See Morris, D.E., 98:439

Dooley, K.J., See Giles, J.R., 98:394

Doorn, S., See Federici, C., 98:434

Dorn, S.B., See Barren, E., 98:213

Doughty, C., Numerical modeling of field tests in unsaturated fractured basalt at the Box Canyon site, 98:469 (R;US)

Draper, J.V., Dual Arm Work Package performance estimates and

telerobot task network simulation, 98:102 (R;US)

RoboCon: A general purpose telerobotic control center, 98:101

(R;US)

Dresel, P.E., See Hartman, M.J., 98:606

Dronen, V.R., Environmental Restoration Disposal Facility Waste

Acceptance Criteria, 98:45 (R;US)

Dubey, R., Strategies for redundancy resolution of dual-arm systems

with passive elements for tank waste removal, 98:103 (R;US)

Duda, P.M., See Lindgren, E.R., 98:676

Duemmer, C.L., See Bjornstad, D.J., 98:410

Duncan, G.M, See Day, R.S., 98:66

Dunn, S.D., Development of the SEAtrace barrier verification and

validation technology. Final report, 98:721 (R;US)

Durrer, R., See Kennicott, M., 98:446

Dustin, D.F., Cementation of residue ion exchange resins at Rocky

Flats, 98:620 (R;US)

The use of filtered bags to increase waste payload capacity,

98:619 (R;US)

See Ball, J.M., 98:621

Dwyer, B.P., Development of a cement-polymer close-coupled subsurface barrier technology, 98:636 (R;US)

In situ remediation of uranium contaminated groundwater, 98:635

(R;US)

Dwyer, S.F., Cost comparisons of alternative landfill final covers,

98:633 (R;US)

See Webb, S.W., 98:656

E

Eakman, J.M., See Mostafa, A.T.M.G., 98:423

Earle, O.K., See Michelbacher, J.A., 98:27

Easdon, R.C., See Coles, G.W., 98:615

East, L.V., SWEPP assay system software: An update, 98:385 (R;US)

Easton, E.P., See Pope, R.B., 98:492

Eaton, D., See Chambers, A., 98:322

See McFee, J., 98:389

Ebadian, M.A., Assessment of strippable coatings for decontamination and decommissioning, 98:184 (R;US)

Investigation of waste glass pouring behavior over a knife edge,

98:180 (R;US)

Large-bore pipe decontamination, 98:186 (R;US)

Melting, solidification, remelting, and separation of glass and

metal, 98:182 (R;US)

Microwave combustion and sintering without isostatic pressure,

98:185 (R;US)

Plant stress analysis technology deployment, 98:183 (R;US)

Sensor for viscosity and shear strength measurement, 98:181

(R;US)

Ebbinghaus, B., See Bakel, A.J., 98:11

Ebert, W.L., Effect of alteration phase formation on the glass dissolution rate, 98:12 (R;US)

Formulation of a candidate glass for use as an acceptance test

standard material, 98:3 (R;US)

Gas evolution during vitrification of sodium sulfate and silica,

98:13 (R;US)

Short-term consistency testing vs. long-term behavior, 98:8 (R;US)

See Luo, J.S., 98:7

See Wolf, S.F., 98:2

Eddy-Dilek, C.A., See Nichols, R.L., 98:742

Edenborn, H., See Revis, N.W., 98:264

Edens, V.G., 105-DR Large Sodium Fire Facility Supplemental

Information to the Hanford Facility Contingency Plan (DOE/RL93-75), 98:76 (R;US)

1301-N Liquid Waste Disposal Facility Supplemental Information

to the Hanford Facility Contingency Plan, 98:48 (R;US)

1325-N Liquid Waste Disposal Facility Supplemental Information

to the Hanford Facility Contingency Plan (DOE/RL-93-75),

98:49 (R;US)

Unit-Specific Contingency Plan for the 183-H Solar Evaporation

Basins, 98:47 (R;US)

Edgar, G., See Buhl, A.R., 98:616

Edwards, A., See Creed, R., 98:395

Edwards, T.B., See Andrews, M.K., 98:772

See Walker, D.D., 98:762

Eeckhout, E. van, Use of data fusion to optimize contaminant transport predictions, 98:459 (R;US)

Egidi, P., Introduction to naturally occurring radioactive material,

98:114 (R;US)

Egidi, P.V., Real-time, automated characterization of surfaces for alpha and beta radiation, 98:478 (R;US)

224 Environmental Management Technical Reports
Gavalya

The independent verification process in decommissioning, decontamination, and reutilization activities - description, benefits, and

lessons learned, 98:120 (R;US)

Eibling, R.E., The Solubility of Phenylborate Compounds in Benzene, 98:778 (R;US)

Eide, S.A., Human health risk comparisons for environmental management baseline program and integration opportunities

(discussion draft), 98:349 (R;US)

Eifert, E.J., See Ammerman, D.J., 98:669

Einfeld, W., Field analytical technology verification: The ETV Site

Characterization Program, 98:720 (R;US)

Elcock, C.G., See Weiner, R.F., 98:674

Elder, H.H., See Jacobs, R.A., 98:741

Elless, M.P., See Francis, C.W., 98:111

Elovich, R.J., See Brown, G.N., 98:574

Encke, B.D., 118-C-4 Horizontal Rod Cave Characterization Report,

98:69 (R;US)

Encke, D.B., 111-B Metal Examination Facility Concrete Tank Interim Characterization Report, 98:73 (R;US)

Sampling and Analysis Plan for the REDOX Plutonium Loadout

Hood, 98:274 (R;US)

England, J.L., See Ades, M.J., 98:747, 98:748

Erian, F.F., Descriptive models for single-jet sluicing of sludge

waste, 98:570 (R;US)

Erickson, T.A., Task 10 – Technology development integration.

Semi-annual report, April 1–September 30, 1997, 98:231 (R;US)

See Daly, D.J., 98:229

Erickson, Thomas A., Task 10 - Technology Development Integration. Semiannual report, November 1, 1996–March 31, 1997,

98:245 (R;US)

Esimantovskiy, V.M., See Todd, T.A., 98:329

Evans, J.C., See Huckaby, J.L., 98:595

Eversole, R.E., Isotopes facilities deactivation project at Oak Ridge

National Laboratory, 98:118 (R;US)

Eylands, K.E., See Grisanti, A.A., 98:233

Eylands, Kurt E., See Grisanti, Ames A., 98:249

F

Fagan, H.F., See McClure, J.D., 98:692

Fairbourn, P., Department of Energy environmental management

complex-wide integration using systems engineering, 98:301

(R;US)

Fancher, J.D., See Corpuz, F.M., 98:70

Faurote, J.M., Description of Work for a Vadose Zone Characterization Borehole at the 216-B-2-2 Ditch, 98:62 (R;US)

Faybishenko, B., See Finsterle, S., 98:468

Federici, C., CID-based ICP-AES instrumentation for continuous online analysis of aqueous industrial waste streams, 98:434 (R;US)

Fedoseev, A.M., Interaction of Pu(IV,VI) hydroxides/oxides with

metal hydroxides/oxides in alkaline media, 98:588 (R;US)

Feldman, M.R., Certification testing for the ES-2 shipping package,

98:487 (R;US)

Fellhauer, C.R., Decontamination and dismantlement of the JANUS

Reactor at Argonne National Laboratory-East. Project final report, 98:14 (R;US)

See Yule, T.J., 98:43

Feng, X., See Mattigod, S.V., 98:572, 98:611

Ferryman, T., See Hunter, V.L., 98:580

Ferryman, T.A., Summary of uncertainty estimation results for Hanford tank chemical and radionuclide inventories, 98:610 (R;US)

Fewell, M.E., See Crawford, M.B., 98:693

Field, L.R., Test plan for headspace gas sampling of remotehandled transuranic waste containers at Los Alamos National

Laboratory, 98:460 (R;US)

Filby, E.E., Corral Monitoring System assessment results, 98:373

(R;US)

Fillmore, D.L., Parameter selection for Department of Energy spent

nuclear fuel to be used in the Yucca Mountain Viability Assessment, 98:376 (R;US)

Fink, S.D., See Wilmarth, W.R., 98:768

Finsterle, S., What does a tensiometer measure in fractured rock?,

98:468 (R;US)

Firsova, E.V., See Peretrukhin, V.F., 98:605

Fischer, K.N., Reduction of mercury in plant effluents data management implementation plan, FY 1998, Oak Ridge Y-12 Plant, Oak

Ridge, Tennessee, 98:794 (R;US)

Fish, L.W., See Russell, N.E., 98:342, 98:343

Flamm, B.F., Effects on the long term storage container by thermal

cycling alpha plutonium, 98:450 (R;US)

Fleming, R., See Ranek, N.L., 98:20

Flora, J., See Yuracko, K.L., 98:497

Flynn, C.R., See Egidi, P.V., 98:478

Fogle, R.F., The application of metal cutting technologies in tasks

performed in radioactive environments, 98:729 (R;US)

Folga, S., See Mueller, C., 98:21

Folga, S.M., See Mueller, C.J., 98:17

Forbes, S.V., See Rassat, S.D., 98:604

Forsberg, V.M., See Fischer, K.N., 98:794

Forsmann, J.H., See Aumeier, S.E., 98:26

Fortner, J.A., Plutonium alteration phases from lanthanide borosilicate glass, 98:9 (R;US)

Foster, B.D., Establishment of a facility for intrusive characterization

of transuranic waste at the Nevada Test Site, 98:259 (R;US)

Foster, H.J., See Grisanti, A.A., 98:233

See Grisanti, Ames A., 98:249

Fox, M.B., Code of accounts. Management overview volume: Environmental restoration, 98:56 (R;US)

Foxx, T., Old-field plant succession on the Pajarito Plateau, 98:414

(R;US)

Francini, R.B., See Krishnaswamy, P., 98:134

Francis, C.W., The use of carbonate lixiviants to remove uranium

from uranium-contaminated soils, 98:111 (R;US)

Freeze, G., See Christian-Frear, T., 98:663

Freiwald, D.A., See Freiwald, J., 98:216

Freiwald, J., Commercialization plan laser-based decoating systems, 98:216 (R;US)

French, N.B., See Haas, W.J., 98:407

See Haas, W.J. Jr., 98:408, 98:409

Fresquez, P.R., See Haarmann, T.K., 98:421

Frey, J., Tanks focus area. Annual report, 98:162 (R;US)

Fridrich, C.J., See Grauch, V.J., 98:727

Fryar, D.G., Long-term brine migration through an engineered shaft

seal system, 98:662 (R;US)

See Reeves, M., 98:712

Fryxell, G.E., See Mattigod, S.V., 98:572, 98:611

G

Gaddy, J.L., See Klasson, K.T., 98:110

Gallagher, J.R., EM14 – Bubbleless gas transfer technology for the

in situ remediation of chlorinated hydrocarbons. Semi-annual report, April 1–September 30, 1997, 98:234 (R;US)

Task 14 - Bubbleless Gas Transfer Technology for the In Situ Remediation of Chlorinated Hydrocarbons. Semiannual report,

November 1, 1996–March 31, 1997, 98:244 (R;US)

Galloway, B., See Roybal, J.A., 98:714

Galloway, R.B., See Sanders, M.R., 98:643

Galson, D.A., See Crawford, M.B., 98:693

Gannon, R., See Goldfarb, V., 98:210

Gao, F., See Heasler, P.G., 98:597

Gardner, F.G., Implementation of passive samplers for monitoring

volatile organic compounds in ground water at the Kansas City

Plant, 98:554 (R;US)

Garlock, G.A., See Fellhauer, C.R., 98:14

Garn, T.G., See Wood, D.J., 98:334

Garnov, A.Y., See Fedoseev, A.M., 98:588

Garnov, A.Yu., See Krot, N.N., 98:589

Gauglitz, P.A., Waste behavior during horizontal extrusion: Effect of

waste strength for bentonite and kaolin/ludox simulants and

strength estimates for wastes from Hanford waste tanks 241-

SY-103, AW-101, AN-103, and S-102, 98:571 (R;US)

See Peurrung, L.M., 98:583, 98:584

See Rassat, S.D., 98:604

Gavalya, R.A., See Spaulding, B.C., 98:345

Environmental Management Technical Reports 225
Gehrke

Gehrke, R.J., Performance test results of noninvasive characterization of RCRA surrogate waste by prompt gamma neutron

activation analysis, 98:344 (R;US)

See Carpenter, M.V., 98:365

Geinitz, R., See Ammerman, D., 98:668

Geinitz, R.R., See Thorp, D.T., 98:618

Gelis, A.V., See Peretrukhin, V.F., 98:605

Gentilucci, J.A., See Schlahta, S.N., 98:576

George, W., See Tyacke, M., 98:318

Gephart, J.M., Proceedings of the efficient separations and processing crosscutting program 1997 technical exchange meeting,

98:612 (R;US)

Gephart, R.E., See Hunter, V.L., 98:580

Gerald, J.W., The Necessary and Sufficient Closure Process Completion Report for Purex FacilitySurveillance and Maintenance,

98:58 (R;US)

Gering, K.L., Developing a dependable approach for evaluating

waste treatment data, 98:330 (R;US)

Results from five years of treatability studies using hydraulic binders

to stabilize low-level mixed waste at the INEL, 98:381 (R;US)

German, K.E., See Peretrukhin, V.F., 98:605

Gerrick, D., See Yuracko, K.L., 98:497

Giaquinto, J.M., See Keller, J.M., 98:543

Gibson, L.V. Jr., See Shor, J.T., 98:542

Gibson, M.R., See Lee, D.D., 98:528, 98:531

Giles, J.R., High resolution gamma spectroscopy well logging system, 98:394 (R;US)

Gilkeson, R., See Trujillo, V., 98:413

Gilliam, T.M., Grout and vitrification formula development for immobilization of hazardous radioactive tank sludges at ORNL,

98:495 (R;US)

See Spence, R.D., 98:470

Gitten, M., See Sullivan, T.M., 98:88

Glowka, D.A., Geothermal drilling technology update, 98:657 (R;US)

Gnoose, J., See Lucas, M., 98:710

Gogol, S., Metal recycling experience at Los Alamos National Laboratory. Reuse, release, and recycle of metals from radiological

control areas”, 98:445 (R;US)

Goland, A., Northeast Waste Management Enterprise (NEWME)

1996 annual/final report, 98:87 (R;US)

Golchert, N.M., Surveillance of Site A and Plot M report for 1997,

98:1 (R;US)

Goldfarb, V., Progress of electro-hydraulic scabbling technology for

concrete decontamination, 98:210 (R;US)

Goldhagen, P., See Reginatto, M., 98:292

Gombert, D., See Aloy, A.S., 98:323

Gong, M., See Mattigod, S.V., 98:611

Goodwin, F.E., Task 7: Die soldering during host site testing. Final

report, January1–December 31, 1997, 98:193 (R;US)

Gordon, J., See Peterson, K., 98:732

Gorschboth, F.F., An evaluation of the cost/benefits of concrete

biodecontamination, 98:378 (R;US)

Gosslee, R.C., See Burman, S.N., 98:507

Grafsgaard, M.E., See Stepan, D.J., 98:230

Grafsgaard, Michael E., See Stephan, Daniel J., 98:246

Grant, K.E., See Clauss, S.A., 98:573

Grauch, V.J., Geophysical interpretations west of and within the

northwestern part of the Nevada Test Site, 98:727 (R;US)

Greeley, M.S. Jr., Postremediation monitoring program baseline assessment report, Lower East Fork Poplar Creek, Oak Ridge

Y-12 Plant, Oak Ridge, Tennessee, 98:796 (R;US)

Greenfield, M.A., Probability of failure of the waste hoist brake system at the Waste Isolation Pilot Plant (WIPP), 98:286 (R;US)

Greenlaw, P.D., Semi-annual report of the Department of Energy,

Office of Environmental Management, Quality Assessment Program, 98:291 (R;US)

Semi-annual report of the Department of Energy, Office of Environmental Management, Quality Assessment Program, 98:293

(R;US)

Gresalfi, M., See Yuracko, K.L., 98:497

Gresalfi, M.J., See Mezaraups, J., 98:44

Griffin, F.P., See Coryell, E.W., 98:377

Griffith, D.L., See Wagner, E.P. Jr., 98:392

Griffith, W.L., See Compere, A.L., 98:547

Grigoriev, M.S., See Fedoseev, A.M., 98:588

See Krot, N.N., 98:589

Grigsby, C.O., Comparison of General Purpose Heat Source testing

with the ANSI N43.6-1977 (R1989) sealed source standard,

98:462 (R;US)

Grisanti, A.A., EM Task 12 – Laser cleaning of contaminated

painted surfaces. Semi-annual report, April 1–September 30,

1997, 98:232 (R;US)

EM Task 13 – Cone penetrometer for subsurface heavy metals detection. Semi-annual report, April 1–September 30, 1997,

98:233 (R;US)

Task 12: Laser cleaning of contaminated painted surfaces. Semiannual report, April 1, 1996–September 30, 1996, 98:242 (R;US)

Grisanti, Ames A., Cone Penetrometer for Subsurface Heavy Metals Detection. Semiannual report, November 1, 1996–March 31,

1997, 98:249 (R;US)

Laser Cleaning of Contaminated Painted Surfaces. Semiannual

report, November 1, 1996–March 31, 1997, 98:248 (R;US)

Groenewold, G.S., Characterization of environmental samples using ion trap-secondary ion mass spectrometry, 98:303 (R;US)

Grogin, P.W., See Pannell, M.A., 98:451

Gruebel, M.M., See Waters, R.D., 98:634, 98:709

Gruetzmacher, K., See Boak, J.M., 98:452

Gu, B., A field trial of novel bifunctional resins for removing pertechnetate (TcO4

) from contaminated groundwater, 98:553 (R;US)

Degradation of trichloroethylene (TCE) and polychlorinated

biphenyls (PCBs) by Fe and Fe-Pd bimetals in the presence of

surfactants and cosolvents, 98:93 (R;US)

See Spalding, B.P., 98:516

Guerin, D., See Roybal, J.A., 98:714

Guo, B., See Bostick, D.T., 98:534

Gurley, R.N., Legacy sample disposition project. Volume 2: Final report, 98:369 (R;US)

Gwo, J.P., See Yeh, G.T., 98:561

H

Ha, B.C., Rheology of Savannah River site tank 42 HLW radioactive

sludge, 98:756 (R;US)

Haarmann, T.K., Radionuclide concentrations in honey bees from

Area G at TA-54 during 1997. Progress report, 98:421 (R;US)

Haas, W.J., Performance testing of multi-metal continuous emissions monitors, 98:407 (R;US)

Haas, W.J. Jr., Performance testing of multi-metal continuous emissions monitors. Appendix Volume 1, 98:408 (R;US)

Performance testing of multi-metal continuous emissions monitors. Appendix Volume 2, 98:409 (R;US)

Hadden, C.T., See Revis, N.W., 98:264

Haire, M.J., Nuclear criticality safety controls for uranium deposits

during D and D at the Oak Ridge Gaseous Diffusion Plant,

98:115 (R;US)

Hallman, A.K., An effective waste management process for segregation and disposal of legacy mixed waste at Sandia National

Laboratories/New Mexico, 98:700 (R;US)

Hallman, Anne K., An Effective Waste Management Process for

Segregation and Disposal of Legacy Mixed Waste at Sandia

National Laboratories/New Mexico, 98:701 (R;US)

Hamilton, M.A., See Gorschboth, F.F., 98:378

Hamm, L.L., See Brooke, J.N., 98:733

Handy, K.D., See , 98:487

See Feldman, M.R., 98:487

Hane, R., See Ades, M.J., 98:748

Hankins, M.G., See Lindgren, E.R., 98:676

Hansen, F.D., Physical and mechanical properties of degraded

waste surrogate material, 98:702 (R;US)

See Callahan, G.D., 98:703

Harbour, J.R., Compliance with the Nevada Test Site’s waste

acceptance criteria for vitrified cesium-loaded crystalline silicotitanate (CST), 98:736 (R;US)

See Andrews, M.K., 98:772

Harker, Y.D., See Blackwood, L.G., 98:350, 98:383

Harris, J.D., Incineration of DOE offsite mixed waste at the Idaho National Engineering and Environmental Laboratory, 98:309 (R;US)

226 Environmental Management Technical Reports
Hunt

Harris, M.K., Groundwater Flow Model for the R-Reactor Area Final

Report, 98:753 (R;US)

Hart, A.T., See Reichhardt, D.K., 98:629

Hartman, M.J., Integrated monitoring plan for the Hanford groundwater monitoring project, 98:606 (R;US)

Hartshorn, D.C., Hanford annual first quarter seismic report, fiscal

year 1998: Seismicity on and near the Hanford Site, Pasco

Basin, Washington, 98:564 (R;US)

Harvego, E.A., Developmental assessment of the SCDAP/RELAP5

code, 98:321 (R;US)

Harvego, L.A., See Harris, J.D., 98:309

Haschke, J.M., Oxidation kinetics of plutonium in air: Consequences for environmental dispersal, 98:440 (R;US)

Haskel, K.J., See Filby, E.E., 98:373

Hassan, A., See Pohll, G., 98:258

Hassan, N.M., See Laurinat, J.E., 98:779

Hassett, D.J., See Grisanti, A.A., 98:242

Hatchell, B.K., Performance evaluation of the PITBULL pump for

the removal of hazardous waste, 98:602 (R;US)

Hatler, V., See Tompkins, J.A., 98:420

Hawkes, B.D., Analysis of a hypothetical dropped spent nuclear fuel

shipping cask impacting a floor mounted crush pad, 98:313

(R;US)

See Uldrich, E.D., 98:311

Hawthorne, S.B., Task 15 – Remediation of organically contaminated soil using hot/liquid (subcritical) water. Semi-annual

report, April 1–September 30, 1997, 98:235 (R;US)

Task 2 – Extraction and analysis of pollutant organics from contaminated solids using off-line supercritical fluid extraction (SFE)

and on-line SFE-infrared spectroscopy. Semi-annual report,

April 1–September 30, 1997, 98:228 (R;US)

Hawthorne, Steven B., Task 15 - Remediation of Organically Contaminated Soil Using Hot/Liquid (Subcritical) Water. Semiannual

report, November 1, 1996– March 31,1997, 98:243 (R;US)

Hay, M.S., See Davis, P.L., 98:758

Heasler, P., See Hunter, V.L., 98:580

Heasler, P.G., Calculation of combustible waste fraction (CWF) estimates used in organics safety issue screening, 98:597 (R;US)

Heath, R.L., The development of a new edition of the gamma-ray

spectrum catalogues designed for presentation in electronic format, 98:386 (R;US)

Heckendorn, F.M., Remote telerobotic replacement for masterslave manipulator, 98:728 (R;US)

Heiser, J., See Dwyer, B.P., 98:636

Heitkamp, M.A., See Brackin, M.J., 98:225

Hellstrom, G.W., See Lageraaen, P.R., 98:89

Helmer, R.G., See Carpenter, M.V., 98:365

Helton, J., See Jow, H.N., 98:675

Hendricks, J.S., See Carter, L.L., 98:457

See Densmore, J.D., 98:416

Hendrikson, J.G., Task 10 - technology development integration.

Semi-annual report, April 1–September 30, 1996, 98:240 (R;US)

Henley, D.R., See Black, D.B., 98:41

Henley, M., See Wilson, G.V., 98:256

Henrikson, D.J., A graded approach to safety analysis for Rover

Processing Facility deactivation, 98:393 (R;US)

Henslee, S.P., See Michelbacher, J.A., 98:27

Hensley, J., See Ranek, N.L., 98:20, 98:24

Hepworth, H.K., Admixture enhanced controlled low-strength

material for direct underwater injection with minimal crosscontamination, 98:112 (R;US)

Herbst, A.K., Idaho Chemical Processing Plant low-activity waste

grout stabilization development program FY-97 status report,

98:368 (R;US)

Optimization of hydraulic cement admixture waste forms for

sodium-bearing, high aluminum, and high zirconium wastes,

98:397 (R;US)

Herbst, R.S., TRUEX flowsheet testing for the removal of the actinides from dissolved ICPP zirconium calcine using centrifugal

contactors, 98:335 (R;US)

See Law, J.D., 98:364

See Todd, T.A., 98:329

Heung, L.K., On-Board Hydrogen Storage for a City Transit Bus,

98:750 (R;US)

Hill, D., HEPA filter jointer, 98:418 (R;US)

Hill, D.D., See Flamm, B.F., 98:450

Hillman, A.R., See Cernosek, R.W., 98:630

Hinman, M.B., See McFee, J., 98:389

Ho, C.K., The effects of heterogeneities on the performance of capillary barriers for waste isolation, 98:628 (R;US)

Ho, S.V., See Athmer, C., 98:268

Ho, Sa V., Development of the integrated, in-situ remediation technology. Topical report for tasks No. 8 and No. 10 entitled:

Laboratory and pilot scale experiments of Lasagna process,

September 26, 1994–May 25, 1996, 98:218 (R;US)

See Athmer, C.J., 98:221

See Brackin, M.J., 98:225

Hobbs, B.J., Site-Specific Health and Safety Plan, 233-S Decontamination and Decommissioning, 98:51 (R;US)

Hobbs, D.T., Radioactive Testing Results in Support of the In-Tank

Precipitation Facility, 98:774 (R;US)

Hochel, R.C., Resolving Radiological Waste Classification and Release Issues Using Material Process Information and Simple

Measurements and Models, 98:767 (R;US)

Hoesen, D. van, See Billingsley, K., 98:503

Hoesen, S.D. van, See Rule, V.A., 98:555

Hogan, M.O., See Camaioni, D.M., 98:566

Hohnstreiter, G.F., See Koski, J.A., 98:653

Holden, W.L., See Cline, S.R., 98:123

Holder, J.S., See Hsu, R.H., 98:761

Hollen, R., Automating the analytical laboratory via the Chemical

Analysis Automation paradigm, 98:447 (R;US)

Hollenbach, D.F., Criticality safety considerations for MSRE fuel

drain tank uranium aggregation, 98:116 (R;US)

Holmes-Burns, H., See Conley, T.B., 98:99

Honeycutt, T.K., See McCarthy, J.M., 98:339

Honigford, L., Presidential Rapid Commercialization Initiative for

mixed waste solvent extraction, 98:296 (R;US)

Hoopes, V., See Clauss, S.A., 98:573

Hooyman, J.L., See Hepworth, H.K., 98:112

Hopper, C.M., See Hollenbach, D.F., 98:116

See Parks, C.V., 98:527

Houk, T.C., See Siegrist, R.L., 98:541

Houston, H.M., See Baker, M.N., 98:255

Howarth, S.M., Guidebook for performance assessment parameters

used in the Waste Isolation Pilot Plant compliance certification

application. Volume 1: Main report, 98:704 (R;US)

Guidebook for performance assessment parameters used in the

Waste Isolation Pilot Plant compliance certification application.

Volume 2: Appendices, 98:705 (R;US)

Science to compliance: The WIPP success story, 98:678 (R;US)

WIPP Compliance Certification Application calculations parameters. Part 1: Parameter development, 98:679 (R;US)

WIPP Compliance Certification Application calculations parameters. Part 2: Parameter documentation, 98:685 (R;US)

Hsu, K.M., Complex-Wide Waste Flow Analysis V1.0 verification

and validation report, 98:353 (R;US)

Hsu, R.H., Commercial Light Water Reactor -Tritium Extraction Facility Process Waste Assessment (Project S-6091), 98:761 (R;US)

Tritium Facilities Modernization and Consolidation Project Process

Waste Assessment (Project S-7726), 98:766 (R;US)

Huchton, K., An analysis of background noise in selected canyons

of Los Alamos County, 98:415 (R;US)

Huckaby, J.L., Waste tank ventilation rates measured with a tracer

gas method, 98:595 (R;US)

See Sklarew, D.S., 98:596

Hudson, M.R., See Grauch, V.J., 98:727

Huff, D.D., See Long, J.D., 98:94

Hughes, B.M., Development of an integrated in-situ remediation

technology. Topical report for task No. 11 entitled: Evaluation of

TCE contamination before and after the field experiment,

September 26, 1994–May 25, 1996, 98:226 (R;US)

See Athmer, C., 98:268

See Athmer, C.J., 98:221

Hunt, M.A., Development testing of the chemical analysis automation polychlorinated biphenyl standard analysis method during

surface soils sampling at the David Witherspoon 1630 site,

98:552 (R;US)

Environmental Management Technical Reports 227
Hunt

Hunt, R.D., Separations/pretreatment considerations for Hanford privatization phase 2, 98:500 (R;US)

See Beahm, E.C., 98:559

See McGinnis, C.P., 98:505, 98:560

Hunter, V.L., Application of the risk-based strategy to the Hanford

tank waste organic-nitrate safety issue, 98:580 (R;US)

Hunter-Cevera, J.C., See Lundy, D.Z., 98:465

Hurd, J.R., Performance of NDA techniques on a vitrified waste

form, 98:441 (R;US)

Hurt, W.L., Overview of the United States spent nuclear fuel program, 98:326 (R;US)

Hurtado, L.D., See Allen, D.H., 98:677

See DeVries, K.L., 98:711

See Knowles, M.K., 98:695

See Pfeifle, T.W., 98:708

Hutterman, L., Where has the public gone and will communications

technology bring them back?, 98:379 (R;US)

Huxtable, W.P., See Compere, A.L., 98:547

Hyde, R.A., To retrieve or not to retrieve: These are the issues,

98:401 (R;US)

Hylton, T.D., Comparative testing of slurry monitors, 98:121 (R;US)

Comparative testing of slurry monitors, 98:551 (R;US)

Hymas, C.R., See Hatchell, B.K., 98:602

See Whyatt, G.A., 98:609

I

Ilgner, R.H., Palausky,, Distribution of Fatty Acids and

Triethanolamine in Synthetic Metalworking Fluid Aerosols Generated in the Laboratory and Field, 98:471 (R;US)

Imes, J.L., Ground-water flow and ground- and surface-water interaction at the Weldon Spring quarry, St. Charles County,

Missouri, 98:265 (R;US)

Ingram, J.C., See Groenewold, G.S., 98:303

Isom, G.M., See Flamm, B.F., 98:450

Iverson, D.C., See Heckendorn, F.M., 98:728

J

Jackson, R.W., Site-Specific Waste Management Instruction - 100-

DR-1 Group 2 Sites, 98:65 (R;US)

Jacobs, A.M., See Harris, J.D., 98:309

Jacobs, J.E., See Klasson, K.T., 98:481

Jacobs, R.A., Feed Acceptance for the Defense Waste Processing

Facility at the Savannah River Site, 98:741 (R;US)

Jansen, J.F., See Kress, R.L., 98:108

See Love, L.J., 98:104

Jarvinen, G.D., See Marsh, S.F., 98:437

Jarvis, T.T., Risk based requirements for long term stewardship: A

proof-of-principle analysis of an analytic method tested on selected Hanford locations, 98:585 (R;US)

Jefimoff, J., Assessment results of the Indonesian TRIGA SNF to

be shipped to INEEL, 98:319 (R;US)

Jenkins, R.A., See Dindal, A.B., 98:124

See Einfeld, W., 98:720

Jenkins, S.L., See Cotten, G.B., 98:391

Jenkins, T.F., See Atkinson, D.A., 98:387

Jennings, H.L., See Kent, T.E., 98:532

See Lucero, A.J., 98:535

Jensen, M.P., See Nash, K.L., 98:6

Jensen, Robert R., See Grisanti, Ames A., 98:248

Jensen, S., See Langenwalter, T., 98:375

Jenson, R.R., See Grisanti, A.A., 98:232

Johnson, C.R., See Rzeszutko, C., 98:417, 98:448

Johnson, M., See Billingsley, K., 98:503

Johnson, P.E., Transportation Routing Analysis Geographic Information System – TRAGIS, progress on improving a routing tool,

98:490 (R;US)

Jollay, L.J. III, See Haire, M.J., 98:115

Jones, D.A., See Kjeldgaard, E.A., 98:696

Jones, D.W., See Bjornstad, D.J., 98:410

Jones, J.L., See Eide, S.A., 98:349

Jones, J.P., See Barry, R.E., 98:645

Jones, K., See Ebadian, M.A., 98:181

Jones, M.L., See Erickson, T.A., 98:231

Jones, V.D., ICP-MS nebulizer performance for analysis of SRS

high salt simulated radioactive waste tank solutions (#3053),

98:744 (R;US)

Jordan, W.C., See Haire, M.J., 98:115

Josten, N., See Carpenter, M.V., 98:365

Jow, H.N., Performance assessment in support of compliance certification application for the WIPP project, 98:675 (R;US)

Jow, Hong-Nian, An overview of performance assessment for the

Waste Isolation Pilot Plant, 98:690 (R;US)

K

Kadnar, M., See Scarpitta, S., 98:290

Kalb, P.D., See Lageraaen, P.R., 98:89

Kalinich, D.A., A Simple Method for Estimating Forced Convection

Mass Transfer in a Waste Tank, 98:746 (R;US)

Kamboj, S., See Ranek, N.L., 98:20, 98:24

Kanipe, F.L., Calculation of population doses with RADTRAN for

route segments that have an unpopulated near-field region,

98:652 (R;US)

See Sprung, J.L., 98:715, 98:716

Kanipe, R.L., See Neuhauser, K.S., 98:673

Kaplan, E., See Goland, A., 98:87

Kapoor, A., See Towell, R.H., 98:34

Kareta, A.V., See Peretrukhin, V.F., 98:605

Karney, C.C., See Foster, B.D., 98:259

Karraker, D.G., See Murray, A.M., 98:780

Kastner, J.R., Report on bioventing of petroleum contaminated soils

at 108-3C: Active extraction and passive injection (barometric

pumping) of a gaseous nutrient, 98:754 (R;US)

Keane, M.P., See Koski, J.A., 98:653

Keck, K.N., See McCarthy, J.M., 98:339

Keller, J.M., Characterization of the C1 and C2 waste tanks located

in the BVEST system at ORNL, 98:543 (R;US)

Kelley, D.F., See Wilcoxon, J.P., 98:671

Kelley, V.A., See Fryar, D.G., 98:662

Kelly, D.F., See Wilcoxon, J.P., 98:625

Kendrick, D.T., See Cremer, C.D., 98:212

Kenley, C.R., Applying programmatic risk assessment to nuclear

materials stabilization R and D planning, 98:300 (R;US)

Kennicott, M., A successful waste stream analysis on a large construction project in a radiologically controlled facility, 98:446

(R;US)

Kent, T.E., Demonstration of fluidic pulse jet mixing for a horizontal

waste storage tank, 98:548 (R;US)

Evaluation of operating characteristics for a chabazite zeolite system for treatment of process wastewater at Oak Ridge National

Laboratory, 98:532 (R;US)

See Lucero, A.J., 98:558

Kerr, P.L., Real-time alpha emitter assay of large volumes, 98:426

(R;US)

Keswa, C.M., See Beahm, E.C., 98:559

Kier, P., See Mueller, C., 98:21

Kier, P.H., See Mueller, C.J., 98:17

Killian, E.W., Gamma-ray pulse height spectrum analysis on systems with multiple Ge detectors using a spectrum summing,

98:382 (R;US)

Kimmitt, R.R., See Lopez, D.A., 98:354

Kincaid, C.T., Composite analysis for low-level waste disposal in the

200 area plateau of the Hanford Site, 98:581 (R;US)

Kjeldgaard, E.A., Planning and scheduling for agile manufacturers:

The Pantex Process Model, 98:696 (R;US)

Klasson, K.T., In situ global method for measurement of oxygen demand and mass transfer, 98:110 (R;US)

Removal of chlorinated and non-chlorinated alkanes in a tricklebed biofilter, 98:481 (R;US)

See Barton, J.W., 98:486

See Bostick, D.A., 98:550

See Mattigod, S.V., 98:611

228 Environmental Management Technical Reports
Loehr

Klatt, L.N., A retrospective study of the chemical analysis cost for

the remediation of Lower East Fork Poplar Creek, Oak Ridge,

Tennessee, 98:556 (R;US)

See Hunt, M.A., 98:552

See Rzeszutko, C., 98:417, 98:448

Kleeschulte, M.J., See Imes, J.L., 98:265

Kloster, G.L., Final Hazard Classification and Auditable Safety

Analysis for the N Basin Segment, 98:57 (R;US)

Kloster, G.L., Bechtel H, Hazard Classification and Auditable Safety

Analysis for the 1300-N Emergency Dump Basin, 98:52 (R;US)

Klueber, M.R., Panasonic dosimetry system performance testing

and results at nuclear accident dose levels 500 rad to 10,000

rad, 98:623 (R;US)

Knauss, K.G., See Leif, R.N., 98:723

Knecht, D.A., See Aloy, A.S., 98:323

Knecht, M., See Chambers, A., 98:322

Knight, R.D., Computer-assisted comparison of analysis and test

results in transportation experiments, 98:660 (R;US)

Knowles, M.K., Hydraulic Characterization Activities in Support of

the Shaft-Seals Fluid-Flow Modeling Integration into the WIPP

EPA Compliance Certification Application, 98:695 (R;US)

See Fryar, D.G., 98:662

See Reeves, M., 98:712

Koch, S.W., See Huchton, K., 98:415

Kohout, E.J., See Nieves, L.A., 98:16

Kornish, M.J., ALARA Review for the Decontamination, Deactivation

and Housekeeping of the 233-S Viewing Room, 98:78 (R;US)

ALARA Review of the Activation/Repair of Fire Detectors in Zone

Three at the 233-S Facility, 98:79 (R;US)

Korte, N.E., See Gardner, F.G., 98:554

Kosiewicz, S.T., See Boak, J.M., 98:452

See Connolly, M.J., 98:443

See Schumann, P.B., 98:428

Koski, J.A., Design of an experiment to measure the fire exposure

of radioactive materials packages aboard container cargo ships,

98:648 (R;US)

Experimental ship fire measurements with simulated radioactive

cargo, 98:653 (R;US)

Radioactive material package closures with the use of shape

memory alloys, 98:646 (R;US)

See Knight, R.D., 98:660

See Sprung, J.L., 98:651

See Wix, S.D., 98:698

Koster, J.E., See Kerr, P.L., 98:426

Kremer, J.L., See Foster, B.D., 98:259

Kress, R.L., Adaptive controller for hyperthermia robot, 98:106 (R;US)

Hydraulic manipulator research at ORNL, 98:108 (R;US)

The Virtual Robotics Laboratory, 98:105 (R;US)

See Love, L.J., 98:104

Krier, D., See Trujillo, V., 98:413

Krishnaswamy, P., Field evaluation of recycled plastic lumber

(RPL) pallets. Final project report, 98:134 (R;US)

Krot, N.N., Plutonium(IV) precipitates formed in alkaline media in the

presence of various anions, 98:589 (R;US)

See Fedoseev, A.M., 98:588

Krstich, M., See Yuracko, K.L., 98:497

Krstich, M.A., See Mezaraups, J., 98:44

Krumhansl, J., See Bynum, R.V., 98:624

Kszos, L.A., See Greeley, M.S. Jr., 98:796

L

Laczniak, R.J., See Nichols, W.D., 98:726

Lageraaen, P.R., Commercialization of the polyethylene macroencapsulation process, 98:89 (R;US)

LaMarche, M.N., See Amaya, J.P., 98:567

Landis, R., See Quinton, G., 98:220

Langenwalter, T., Idaho Nuclear Technology and Engineering Center

(INTEC) (formerly ICPP) ash reutilization study, 98:375 (R;US)

Langford, R.R., See Pannell, M.A., 98:451

Langkopf, B.S., See Waters, R.D., 98:709

Larson, N.M., See Leal, L.C., 98:539

Lattier, C., See Howarth, S.M., 98:704, 98:705

Laurinat, J.E., Analysis of Steam Heating of a Two-Layer TBP/NParaffin/Nitric Acid Mixtures, 98:779 (R;US)

LaValle, D.R., See Heckendorn, F.M., 98:728

Lavender, J.C., See Daling, P.M., 98:577

Law, J.D., Actinide partitioning from actual Idaho chemical processing plant acidic tank waste using centrifugal contactors, 98:402

(R;US)

Demonstration of an optimized TRUEX flowsheet for partitioning of

actinides from actual ICPP sodium-bearing waste using centrifugal contactors in a shielded cell facility, 98:364 (R;US)

Demonstration of the SREX process for the removal of 90Sr from

actual highly radioactive solutions in centrifugal contactors,

98:403 (R;US)

Demonstration of the TRUEX process for the treatment of actual

high activity tank waste at the INEEL using centrifugal contactors, 98:312 (R;US)

See Herbst, R.S., 98:335

See Todd, T.A., 98:329

See Wood, D.J., 98:334

Leal, L.C., R-matrix analysis of 235U neutron transmission and cross

sections in the energy range 0 to 2.25 keV, 98:539 (R;US)

Leavitt, M., See Watson, D., 98:95

Lee, A.E., Cementitious waste option scoping study report, 98:361

(R;US)

Lee, D.D., Cesium removal flow studies using ion exchange, 98:97

(R;US)

Hot demonstration of proposed commercial cesium removal technology, 98:528 (R;US)

Hot demonstration of proposed commercial cesium removal technology: Progress report, 98:531 (R;US)

See Beahm, E.C., 98:559

See Taylor, P.A., 98:494

See Walker, J.F. Jr., 98:473

Lee, E.D., See Aponte, C.I., 98:769

Lee, S.Y., See Francis, C.W., 98:111

Leif, R.N., Destruction of 2,2’,3 - trichlorobiphenyl in aqueous solution by hydrous pyrolysis/oxidation (HPO), 98:723 (R;US)

Lemieux, P.M., See Haas, W.J., 98:407

See Haas, W.J. Jr., 98:408, 98:409

Leonard, R.A., See Moyer, B.A., 98:92

Lerch, J.A., Vadose Zone Clean Closure Report for the 300 Area

Process Trenches, 98:74 (R;US)

Lester, P.B., See Johnson, P.E., 98:490

See Pope, R.B., 98:491

Letourneau, M.J., See Waters, R.D., 98:634

Liang, L., See Gu, B., 98:93, 98:553

Lichtenwalter, J.J., Heterogeneous reactivity effects in mediumand high-enriched uranium metal-water systems, 98:117 (R;US)

Liekhus, K., Predicting flammability of gas mixtures containing

volatile organic compounds, 98:327 (R;US)

See Soelberg, N., 98:340

Liekhus, K.J., See Connolly, M.J., 98:298

Lilga, M.A., See Camaioni, D.M., 98:566

Lincoln, R., See Boak, D.M., 98:626

Lindgren, E.R., Electrokinetic demonstration at Sandia National

Laboratories: Use of transference numbers for site characterization and process evaluation, 98:632 (R;US)

Electrokinetic demonstration at the unlined chromic acid pit,

98:676 (R;US)

Linehan, J.C., See Camaioni, D.M., 98:566, 98:591

List, G.F., See Kjeldgaard, E.A., 98:696

Little, C.Q., See Barry, R.E., 98:645

Little, R.C., See Carter, L.L., 98:457

Litus, M., See Mousseau, J., 98:372

Liu, J., See Mattigod, S.V., 98:611

Liu, Y.Y., Evaluation of gamma radiation shielding for nuclear waste

shipping casks, 98:38 (R;US)

Liu, Y.Z., See Ebadian, M.A., 98:182

Liu, Z.-M., Seismic reflection processing for characterization of a

hazardous waste site, 98:100 (R;US)

Lockwood, G.J., See Normann, R.A., 98:713

Loehr, C., See Liekhus, K., 98:327

Loehr, C.A., See Connolly, M.J., 98:298

Environmental Management Technical Reports 229
Loken

Loken, M., Calculation of density and permeability of compacted

crushed salt within an engineered shaft sealing system, 98:664

(R;US)

Lombard, K., See Kastner, J.R., 98:754

Lombardi, D.A., See Blasing, T.J., 98:544

Long, J.D., A case study: using a multi-grout barrier to control 90Sr

release at ORNL, 98:94 (R;US)

Longhurst, G.R., Fusion safety program annual report fiscal year

1997, 98:363 (R;US)

Loomis, G., See Maio, V., 98:496

Looney, B.B., See Nichols, R.L., 98:742

Lopez, D.A., Vitrified waste option study report, 98:354 (R;US)

See Dafoe, R.E., 98:348

Lord, D.L., Evaluation of emplacement sensors for detecting radiation and volatile organic compounds and for long-term

monitoring access tubes for the BWCS, 98:338 (R;US)

Lord, M.E., See Rechard, R.P., 98:687

Losinski, S.J., See Dafoe, R.E., 98:360

See Russell, N.E., 98:342, 98:343

Lotts, A.L., See Osborne-Lee, I.W., 98:529

Love, L.J., Control of flexible robots with prismatic joints and hydraulic drives, 98:104 (R;US)

See Bills, K.C., 98:107

See Dubey, R., 98:103

See Kress, R.L., 98:105, 98:108

Lowe, K.S., See Siegrist, R.L., 98:541

Lowry, W., See Dunn, S.D., 98:721

Lu, S.C., See Ying, T.Y., 98:474

Lucas, M., Integration of US Department of Energy contractor installations for the purpose of optimizing treatment, storage, and

disposal of low-level radioactive waste (LLW), 98:710 (R;US)

Lucero, A.J., Out-of-tank evaporator demonstration. Final report,

98:535 (R;US)

Process waste treatment system upgrades: Clarifier startup at the

nonradiological wastewater treatment plant, 98:558 (R;US)

See Kent, T.E., 98:532

Ludwig, S.B., Programmatic and technical requirements for the

FMDP fresh MOX fuel transport package, 98:540 (R;US)

Lumetta, G.J., See Moyer, B.A., 98:92

Lundbaeck, K.M.O., See Klasson, K.T., 98:110

Lundeen, A.S., See Hsu, K.M., 98:353

Lundy, D.Z., Susceptibility of polysiloxane and colloidal silica to

degradation by soil microorganisms, 98:465 (R;US)

Luo, J.S., An AEM study of glass-palagonite interfaces formed in

Hawaiian basalt glasses, 98:7 (R;US)

See Wolf, S.F., 98:2

Lutz, R.N., See Hsu, R.H., 98:761

Lyons, C., See Sanchez, M., 98:260

M

Maassen, L., Quality management in environmental programs: Los

Alamos National Laboratory’s approach, 98:453 (R;US)

MacDonell, M.M., Environmental risk assessment, 98:23 (R;US)

MacFarlane, R.E., See Carter, L.L., 98:457

Macy, K., See Kerr, P.L., 98:426

Maddox, J.J., Liquid and gaseous waste operations section. Annual

operating report CY 1997, 98:549 (R;US)

Madore, C.M., See Dustin, D.F., 98:620

Magleby, M., See Mousseau, J., 98:372

Magnuson, S.O., Development, calibration, and predictive results of

a simulator for subsurface pathway fate and transport of

aqueous- and gaseous-phase contaminants in the Subsurface

Disposal Area at the Idaho National Engineering and Environmental Laboratory, 98:332 (R;US)

See McCarthy, J.M., 98:339

Mahoney, L.A., Composition and quantities of retained gas measured in Hanford waste tanks 241-U-103, S-106, BY-101, and

BY-109, 98:578 (R;US)

See Caley, S.M., 98:607

See Erian, F.F., 98:570

See Peurrung, L.M., 98:583, 98:584

Maio, V., Testing of low-temperature stabilization alternatives for salt

containing mixed wastes – Approach and results to date, 98:496

(R;US)

Maleki, H., Mine stability evaluation of panel 1 during waste emplacement operations at WIPP, 98:287 (R;US)

Malone, K., See Valentine, J.H., 98:305

Malstrom, R.A., See Hsu, R.H., 98:761

Manke, K.L., See McGinnis, C.P., 98:98

Mann, N.R., Evaluation and testing of HUMASORB-CS for the removal of radionuclides from groundwater, 98:366 (R;US)

See Wood, D.J., 98:328

Marietta, M., See Jow, H.N., 98:675

See Jow, Hong-Nian, 98:690

Marozas, D.C., See Dwyer, B.P., 98:635

Marra, S.L., Implementation of ISO140001 at the Savannah River

Site, 98:752 (R;US)

Marsh, S.F., New bifunctional anion-exchange resins for nuclear

waste treatment: Part 2, 98:437 (R;US)

Marshall, D.S., See Morrissey, C.M., 98:525, 98:526

Marshall, D.W., See Herbst, A.K., 98:368

Martell, M.A., Designing a database for performance assessment:

Lessons learned from WIPP, 98:683 (R;US)

See Howarth, S.M., 98:704, 98:705

Martin, B., See Rodwell, P.O., 98:765

Martin, E., See Lucas, M., 98:710

Martin, S.J., See Cernosek, R.W., 98:630

Martinez, E.F., See Taggart, D.P., 98:430

Martinez, F., See Vigil, J., 98:429

Martinez, H.E., See Hill, D., 98:418

Martz, J.C., See Haschke, J.M., 98:440

Maslennikov, A.G., See Peretrukhin, V.F., 98:605

Mason, J.T., See Palmer, E.R., 98:755

Mattigod, S.V., Fabrication and testing of engineered forms of selfassembled monolayers on mesoporous silica (SAMMS)

material, 98:611 (R;US)

Mercury separation from concentrated potassium iodide/iodine

leachate using Self-Assembled Mesoporous Mercaptan Support

(SAMMS) technology, 98:572 (R;US)

Mattson, E.D., See Lindgren, E.R., 98:632, 98:676

Mattus, A.J., Technological and economic update on the nitrate to

ammonia and ceramic process, 98:479 (R;US)

See Spence, R.D., 98:470, 98:557

Mattus, C.H., Demonstration of Mixed Waste Debris Macroencapsulation Using Sulfur Polymer Cement, 98:546 (R;US)

See Spence, R.D., 98:470, 98:557

McCabe, D.J., Cross flow filtration of aqueous radioactive tank

wastes, 98:730 (R;US)

Technology Status Report of the Applicability of Solid-Liquid Separation Methods to Radioactive Tank Wastes, 98:770 (R;US)

See Walker, B.W., 98:749

McCarthy, J.M., Radioactive waste management complex low-level

waste radiological composite analysis, 98:339 (R;US)

McClure, J.D., Low-level radioactive waste transportation safety history, 98:672 (R;US)

Radioactive material (RAM) transportation accident and incident

experience in the U.S.A. (1971–1997), 98:692 (R;US)

McClure, L., Tribal and stakeholder involvement in systems analysis, 98:404 (R;US)

McConnell, P., See Mora, C.J., 98:684

McCord, J.T., See Webb, S.W., 98:656

McCray, J.A., See Herbst, A.K., 98:368

McCurley, R.D., See Rechard, R.P., 98:687

McDonald, J.P., See Hartman, M.J., 98:606

McDonald, M.J., See Small, D.E., 98:631

McDonald, T.G., See Russell, N.E., 98:342, 98:343

McFee, J., The proposed combustion standards and DOE thermal

treatment systems, 98:389 (R;US)

McGinnis, C.P., Caustic leaching of high-level radioactive tank

sludge: A critical literature review, 98:505 (R;US)

Caustic leaching of high-level radioactive tank sludge: A critical literature review, 98:560 (R;US)

Tank Focus Area pretreatment activities, 98:98 (R;US)

See Hunt, R.D., 98:500

McInroy, D., See Roybal, J.A., 98:717

230 Environmental Management Technical Reports
Nguyen

McKay, M.D., See Anderson, M.O., 98:398

McKee, S.D., See Smith, W.H., 98:442

McKenzie, D.E., See Orth, R., 98:267

See Orth, R.G., 98:224

McKinney, G.W., See Densmore, J.D., 98:416

McLlwain, M.E., See Detering, B.A., 98:337

McNatt, F.G., Annual Radioactive Waste Tank Inspection Program -

1997, 98:775 (R;US)

McTaggart, D.R., See Lucero, A.J., 98:558

Meachum, T.R., See Blackwood, L.G., 98:350, 98:383

Meiggs, T., See Murdoch, L., 98:477

Meigs, L.C., Representation of spatial variability for modelling of

flow and transport processes in the Culebra Dolomite at the

WIPP site, 98:706 (R;US)

Meisel, D., Chemistry, radiation, and interfaces in suspensions of

nuclear waste simulants, 98:5 (R;US)

Mellegard, K.D., See Callahan, G.D., 98:703

See Hansen, F.D., 98:702

Mendez, J., See Vigil, J., 98:429

Mendez, J.L., See Taggart, D.P., 98:430

Mercer, D.J., See Hurd, J.R., 98:441

Mercer, R.B., See Hartman, M.J., 98:606

Mertz, C.J., See Fortner, J.A., 98:9

Mew, D.A., See Leif, R.N., 98:723

Meyer, D., See Hallman, A.K., 98:700

Meyer, Dann, See Hallman, Anne K., 98:701

Mezaraups, J., Incorporation of pollution prevention and waste minimization practices during the decommissioning of Building 310

at Argonne National Laboratory-East, 98:44 (R;US)

Michelbacher, J.A., Deactivation of the EBR-II complex, 98:27 (R;US)

Michelhaugh, R.D., See Ludwig, S.B., 98:540

See Pope, R.B., 98:488, 98:489, 98:491, 98:492

Mickalonis, J.I., Coupon corrosion monitoring of a high level waste

tank, 98:731 (R;US)

Miele, C.R., See Krishnaswamy, P., 98:134

Miller, K.M., See Reginatto, M., 98:288

Millet, C.B., See Palmer, W.B., 98:374

Mills, G.S., Extension of ship accident analysis to multiple-package

shipments, 98:682 (R;US)

Study of the components of evacuation times, 98:681 (R;US)

Truck transport of RAM: Risk effects of avoiding metropolitan areas, 98:680 (R;US)

Mims, C., See Billingsley, K., 98:503

Minick, S.K., See Greenlaw, P.D., 98:293

Mitroshkov, A.V., See Huckaby, J.L., 98:595

Mizner, J., See Roybal, J.A., 98:717

Moe, T.A., See Stepan, D.J., 98:239

Moline, G.R., Homogeneous Reactor Experiment (HRE) Pond cryogenic barrier technology demonstration: Pre-barrier subsurface

hydrology and contaminant transport investigation, 98:545 (R;US)

Monagle, M., See Rzeszutko, C., 98:417, 98:448

Mong, G.M., See Campbell, J.A., 98:601

See Clauss, S.A., 98:573

Montoya, A., See Boak, J.M., 98:452

Moore, J., See Ebadian, M.A., 98:181

Moore, J.W., See Kent, T.E., 98:548

Mora, C.J., “We crash, burn, and crush”: A history of packaging at

Sandia National Laboratories, 1978–1997, 98:684 (R;US)

Morgenstern, M., See Trujillo, V., 98:413

Moridis, G.J., See Lundy, D.Z., 98:465

Moroney, J.D., Annular Kinetic Impactor Air Sampler, 98:67 (R;US)

Morris, D.E., Speciation and surface interactions of actinides on

aged ion-exchange resins, 98:439 (R;US)

Morris, M.I., See Conley, T.B., 98:99, 98:480

Morrison, D.J., See Blair, D.S., 98:639

Morrissey, C.M., Active Sites Environmental Monitoring Program

FY 1994 annual report, 98:524 (R;US)

Active Sites Environmental Monitoring Program FY 1996 annual

report, 98:525 (R;US)

Active sites environmental monitoring program FY 1997 annual report, 98:526 (R;US)

Moses, S.B., See Towell, R.H., 98:34

Moskowitz, P.D., See Sullivan, T.M., 98:88

Moss, D., See Watson, D., 98:95

Mostafa, A.T.M.G., Prediction of heat capacities of solid inorganic

salts from group contributions, 98:423 (R;US)

Mousseau, J., Waste generator services implementation plan,

98:372 (R;US)

Moyer, B.A., Fission product solvent extraction, 98:484 (R;US)

Solvent extraction of radionuclides from aqueous tank waste,

98:92 (R;US)

See Gu, B., 98:553

Mroz, G., Draft test plan for hydrogen getters project, 98:461 (R;US)

Test plan for hydrogen getters project, 98:458 (R;US)

Mueller, C., Consistency in accident analyses in DOE safety, environmental, and emergency planning documents, 98:21 (R;US)

Mueller, C.J., A comparative review of accident studies from recent

assessments of emergency planning zone boundaries, 98:17

(R;US)

Mullen, M., See Foxx, T., 98:414

Munson, D.E., See Pfeifle, T.W., 98:707

Murdoch, L., Advanced hydraulic fracturing methods to create in

situ reactive barriers, 98:477 (R;US)

Murdoch, L.D., See Siegrist, R.L., 98:541

Murley, T., See Buhl, A.R., 98:616

Murphy, J.A., Development of the environmental management integrated baseline at the Idaho National Engineering Laboratory

using systems engineering, 98:302 (R;US)

Murphy, L., Basis of Estimate Software Tool (BEST) - a practical solution to part of the cost and schedule integration puzzle, 98:613

(R;US)

Murphy, T.C., See Wright, R.B., 98:362

Murray, A.M., Summary of Tests to Determine Effectiveness of

Gelatin Strike on SS&C Dissolver Solutions, 98:780 (R;US)

Musich, M.A., Task 11: Technology development integration. Semiannual report, April 1, 1996–September 30, 1996, 98:241 (R;US)

Musick, C.A., FY-97 operations of the pilot-scale glass melter to vitrify simulated ICPP high activity sodium-bearing waste, 98:351

(R;US)

Musick, R.G., See Foster, B.D., 98:259

Mustin, T., Status of the TRIGA shipments to the INEEL from Europe, 98:316 (R;US)

N

Nabelssi, B., See Nieves, L.A., 98:16

Nagy, K.L., See Westrich, H.R., 98:642

Nakaoka, R.K., See Hurd, J.R., 98:441

Naney, M.T., See Spalding, B.P., 98:515, 98:516

Nash, K.L., In-situ mineralization of actinides for groundwater

cleanup: Laboratory demonstration with soil from the Fernald

Environmental Management Project, 98:6 (R;US)

Naudts, A.A., See Long, J.D., 98:94

NcNeel, K., See McFee, J., 98:389

Neill, R.H., Evaluation of the WIPP Project’s compliance with the

EPA radiation protection standards for disposal of transuranic

waste, 98:125 (R;US)

Nelson, J.K., Natural succession impeded by smooth brome

(Bromus inermis) and intermediate wheatgrass (Agropyron intermedium) in an abandoned agricultural field, 98:617 (R;US)

Nelson, R., See Wescott, J., 98:28

Nelson, R.A., See Shearer, T.L., 98:30

Nenni, J.A., Thermal denitration and mineralization of waste constituents, 98:399 (R;US)

Ness, Robert O., Task 3 - Pyrolysis of Plastic Waste. Semiannual

report, November 1, 1996–March 31, 1997, 98:247 (R;US)

Neuhauser, K.S., Application of the RADTRAN 5 stop model,

98:673 (R;US)

See Mills, G.S., 98:680, 98:681, 98:682

Neuhauser, S., See Kanipe, F.L., 98:652

Nevins, S., See Weiner, R.F., 98:674

Newcomer, D.R., See Hartman, M.J., 98:606

See Williams, B.A., 98:586

Newman, G.A., See Alumbaugh, D.L., 98:640

Nguyen, H.D., Clean-up criteria for remediation of contaminated

soils, 98:396 (R;US)

Environmental Management Technical Reports 231
Nichols

Nichols, R.L., Fractured rock aquifer tests in the Western Siberian

Basin, Ozyorsk, Russia, 98:742 (R;US)

Nichols, W.D., Estimated ground-water discharge by evapotranspiration, Ash Meadows Area, Nye County, Nevada, 1994, 98:726

(R;US)

Nickelson, D.F., See Hyde, R.A., 98:401

Nickens, P.R., Monitoring bank erosion at the Locke Island Archaeological National Register District: Summary of 1996/1997 field

activities, 98:603 (R;US)

Nie, Z., See Mattigod, S.V., 98:611

Nielson, R.R., Sampling and analysis plan for the former Atomic Energy Commission bus lot property, 98:594 (R;US)

Nieves, L.A., Analysis of disposition alternatives for radioactively

contaminated scrap metal, 98:16 (R;US)

Nigrey, P.J., A testing program to evaluate the effects of simulant

mixed wastes on plastic transportation packaging components,

98:659 (R;US)

Effects of simulant mixed waste on EPDM and butyl rubber,

98:650 (R;US)

Gas generation phenomena in radioactive waste transportation

packaging, 98:647 (R;US)

Prediction of packaging seal life using thermoanalytical techniques, 98:649 (R;US)

Nikonov, M.V., See Fedoseev, A.M., 98:588

Nikula, K.J., See Benson, J.M., 98:133

Nimz, G. J., LLNL, Isotope hydrology of catchment basins:

lithogenic and cosmogenic isotopic systems, 98:725 (R;US)

No, H., See Wescott, J., 98:28

Noakes, M.W., See Draper, J.V., 98:101

Nobles, B.R., See Hsu, R.H., 98:761

Normann, R.A., Integration and evaluation of a position sensor with

continuous read-out for use with the Environmental

Measurement-While-Drilling Gamma Ray Spectrometer system,

98:713 (R;US)

Norris, C., LLW Forum meeting report, May 7–9, 1997, 98:202 (R;US)

LLW Forum meeting report, October 20–22, 1997, 98:203 (R;US)

LLW Notes, Volume 12, Number 8, 98:204 (R;US)

LLW Notes, Volume 12, Number 9, 98:205 (R;US)

Nowacki, P.L., See Ades, M.J., 98:748

Nowak, J., See Bynum, R.V., 98:624

O

O’Hora, T.D., See Bentz, E.J. Jr., 98:19, 98:22

Oaks, R.E. Jr., See Feldman, M.R., 98:487

Ober, R., See Gu, B., 98:553

Ochoa, R., See Langenwalter, T., 98:375

Odom, J.M., Development of an integrated, in-situ remediation technology. Topical report for task No. 6: lab-scale development of

microbial degradation process, September 26, 1994–May 25,

1996, 98:219 (R;US)

Oji, L.N., See Hsu, R.H., 98:766

Olson, L.G., See Law, J.D., 98:312, 98:364, 98:403

Onishi, Y., Performance evaluation of rotating pump jet mixing of radioactive wastes in Hanford Tanks 241-AP-102 and -104,

98:593 (R;US)

TEMPEST code modifications and testing for erosion-resisting

sludge simulations, 98:579 (R;US)

Oostrom, M., See White, M.D., 98:562

Oras, J.J., Leakage testing of packagings with three-O-ring closure

seals, 98:35 (R;US)

Regulatory concerns for leakage testing of packagings with three

O-ring closure seals, 98:33 (R;US)

See Towell, R.H., 98:34

Orlando, T., See Meisel, D., 98:5

Ortega, L., See Sandoval, W., 98:436

Orth, R., Development of an integrated in-situ remediation technology. Draft topical report for Task #3.3 entitled, “Iron dechlorination

studies” (September 26, 1994–August 31, 1997), 98:267 (R;US)

Orth, R.G., Development of an integrated, in-situ remediation technology. Draft topical report for task No. 9. Part II. Entitled: TCE

degradation using non-biological methods, September 26,

1994–May 25, 1996, 98:224 (R;US)

Osborne-Lee, I.W., Development of a path forward for special-case

wastes at the Oak Ridge Reservation, 98:529 (R;US)

See Conley, T.B., 98:480

Osseo-Asare, K., See Beahm, E.C., 98:559

Oswald, K.B., See Hsu, K.M., 98:353

P

Paddleford, D.F., See Kalinich, D.A., 98:746

Paik, S.T., See Cole, C.M., 98:317

Palmedo, P. Wortman, J., See Goland, A., 98:87

Palmer, E.R., Removal site evaluation report L-area rubble pile

(131-3L) gas cylinder disposal facility (131-2L), 98:755 (R;US)

Palmer, W.B., ICPP Tank Farm planning through 2012, 98:374 (R;US)

Palmquist, C.A., Operations and Maintenance Manual for the Temporary Septic Holding Tank at the 100-C Remedial Action

Support Facility, 98:54 (R;US)

Operations and Maintenance Manual for the Temporary Septic

Holding Tank at the 100-C Remedial Action Restroom Facility,

98:55 (R;US)

Pancake, D., See Shearer, T., 98:29

Panisko, F.E., See Caley, S.M., 98:607

Pannell, M.A., Hazards associated with retrieval and storage of

legacy waste at the Transuranic Waste Inspectable Storage

Project, 98:451 (R;US)

Papelis, C., See Pohll, G., 98:258

Parks, C.V., Development of nuclear analysis capabilities for DOE

waste management activities, 98:527 (R;US)

See Shappert, L.B., 98:493

Parsapour, F., See Wilcoxon, J.P., 98:625, 98:671

Patchet, S.J., See Bynum, R.V., 98:624

Patterson, J., See Tyacke, M., 98:318

Patton, G.W., See Van Verst, S.P., 98:598

Paul, P., See Davis, N.R., 98:297

Pedalino, J.P., See Foster, B.D., 98:259

Pederson, L.R., See Peurrung, L.M., 98:583, 98:584

See Stock, L.M., 98:569

Peelle, E.B., See Schweitzer, M., 98:119

Pellerin, L., The electromagnetic integrated demonstration at the

Idaho National Engineering Laboratory cold test pit, 98:654

(R;US)

Peretrukhin, V.F., Purification of alkaline solutions and wastes from

actinides and technetium by coprecipitation with some carriers

using the method of appearing reagents: Final Report, 98:605

(R;US)

Perlack, R.D., See Bao, Y.S., 98:533

Perminov, V.P., See Fedoseev, A.M., 98:588

See Krot, N.N., 98:589

Perona, J.J., See Kent, T.E., 98:532

Petersell, J., See Conley, T.B., 98:99

Petersen, S.W., Sampling and Analysis Plan for the 216-A-29 Ditch,

98:64 (R;US)

Peterson , R.A., See Barnes, M.J., 98:776

Peterson, A., See Bynum, R.V., 98:624

Peterson, H.K., See Russell, N.E., 98:342, 98:343

Peterson, K., Automation in a material processing/storage facility,

98:732 (R;US)

Peterson, M.J., See Greeley, M.S. Jr., 98:796

Peterson, P.K., See Hsu, R.H., 98:761

Peterson, R.A., See Brooke, J.N., 98:735

See Hobbs, D.T., 98:774

Peterson, V.L., Safety Analysis and Risk Assessment Handbook,

new guidance to the safety analyst, 98:614 (R;US)

Petrasek, A., See Tyacke, M., 98:318

Petrie, L.M., See Parks, C.V., 98:527

Pettet, M., See Langenwalter, T., 98:375

Peurrung, L.M., Flammable gas issues in double-contained receiver

tanks. Revision 1, 98:583 (R;US)

Flammable gas issues in double-contained receiver tanks. Revision 2, 98:584 (R;US)

Pfeifer, M.C., See Pellerin, L., 98:654

232 Environmental Management Technical Reports
Robinson

Pfeifle, T.W., Experimental determination of the relationship between permeability and microfracture-induced damage in

bedded salt, 98:707 (R;US)

Permeability of natural rock salt from the Waste Isolation Pilot Plant

(WIPP) during damage evolution and healing, 98:708 (R;US)

Phillips, R.J., See Bobroff, S., 98:568

Phillips, S., See Dwyer, B.P., 98:636

Phipps, T.L., See Greeley, M.S. Jr., 98:796

Pickering, S.Y., Balancing compliance and cost when implementing

a Quality Assurance program, 98:688 (R;US)

Pierce, R.A., See Thompson, M.C., 98:781

Pike, J.A., Application of Epoxy Based Coating Instacote on Waste

Tank Tops, 98:777 (R;US)

Pinnaduwage, L.A., Implications of electron attachment to highlyexcited states in pulsed-power discharges, 98:113 (R;US)

Pippin, L.C., Hunter-gatherer adaptations and environmental

change in the southern Great Basin: The evidence from Pahute

and Rainier mesas, 98:257 (R;US)

Piscitella, R., See Lucas, M., 98:710

Pitcher, E., See Ades, M.J., 98:748

Platfoot, J.H., Technical safety requirments for the South Tank Farm

Remediation Project, Oak Ridge National Laboratory, Oak

Ridge, Tennessee, 98:510 (R;US)

Plum, M.M., See Ramer, R.J., 98:304

Pohl, P.I., Mixed low-level waste form evaluation, 98:638 (R;US)

See Waters, R.D., 98:709

Pohll, G., Evaluation of groundwater flow and transport at the Shoal

underground nuclear test: An interim report, 98:258 (R;US)

Pope, R.B., A simplified ALARA approach to demonstration of

compliance with surface contaminated object regulatory requirements, 98:488 (R;US)

Characterizing, for packaging and transport, large objects contaminated by radioactive material having a limited A2 value, 98:489

(R;US)

Global transportation cost modeling for long-range planning,

98:491 (R;US)

Guidance and methods for satisfying low specific activity material

and surface contaminated object regulatory requirements,

98:492 (R;US)

See Ludwig, S.B., 98:540

Porro, I., See Bhatt, R.N., 98:310

Poston, T.M., See Van Verst, S.P., 98:598

Powell, J., See Billingsley, K., 98:503

Powell, M.R., See Hatchell, B.K., 98:602

Prenger, F.C., See Flamm, B.F., 98:450

Prettyman, T.H., See Hurd, J.R., 98:441

Price, W.H., Chemical Hygiene Plan for Onsite Measurement and

Sample Shipping Facility Activities, 98:50 (R;US)

Priebe, S.J., See Haas, W.J., 98:407

See Haas, W.J. Jr., 98:408, 98:409

Primeau, S.J., See Liu, Y.Y., 98:38

Principe, J.M., See Shapiro, A.P., 98:266

Prindle, N.H., See Boak, D.M., 98:626

Propp, W.A., See Gehrke, R.J., 98:344

Purdy, G.M., See Smith, W.H., 98:442

Q

Quintana, B.D., See Sandoval, W., 98:436

Quinton, G., Development of an integrated, in-situ remediation technology. Topical report for task No. 5: Cost analysis, September

26, 1994–May 25, 1996, 98:220 (R;US)

R

Radloff, H.D., The effect of cargo on the crush loading of RAM

transportation packages in ship collisions, 98:667 (R;US)

See Ammerman, D.J., 98:669

Radtke, M., See Wolfram, J.H., 98:299

Radway, J., See Kastner, J.R., 98:754

Rael, C., See Vigil, J., 98:429

Rael, C.D., See Taggart, D.P., 98:430

Ramer, R.J., Development of a techno-economic model to optimization DOE spent nuclear fuel disposition, 98:304 (R;US)

See Dahl, C.A., 98:284

Ramm, S.G., See Gardner, F.G., 98:554

Ranek, N.L., Release process for non-real property containing residual radioactive material, 98:20 (R;US)

Review of processes for the release of DOE real and non-real

property for reuse and recycle, 98:24 (R;US)

Rao, D.V., See Dunn, S.D., 98:721

Rapp, T.R., See Nichols, W.D., 98:726

Raptis, A.C., See Sheen, S.H., 98:37

Rash, C.D., See Greeley, M.S. Jr., 98:796

Rassat, S.D., Mechanisms of gas retention and release: Experimental results for Hanford single-shell waste tanks 241-A-101,

241-S-106, and 241-U-103, 98:604 (R;US)

Rau, E.H., See Wolfram, J.H., 98:299

Rauenzahn, H.S., See Burns, D.B., 98:737

Rawlins, J.K., Interim storage study report, 98:356 (R;US)

Rawool-Sullivan, M., Report on the GC-MBS method for correcting

NaI spectra for transmission loss in hand-held instruments,

98:449 (R;US)

Ray, R.J., See Thompson, M.C., 98:781

Rechard, R.P., Anticipating Potential Waste Acceptance Criteria for

Defense Spent Nuclear Fuel, 98:687 (R;US)

Milestones for disposal of radioactive waste at the Waste Isolation

Pilot Plant (WIPP) in the United States, 98:699 (R;US)

Recknagle, K.P., Retained gas sampler extractor mixing and mass

transfer rate study: Experimental and simulation results, 98:575

(R;US)

See Onishi, Y., 98:593

Reed, D.T., Reduction of Np(VI) and Pu(VI) by organic chelating

agents, 98:689 (R;US)

Reeves, M., Assessing seal performance and parameter sensitivity

with a full-shaft model, 98:712 (R;US)

Reeves, R.D., See Marra, S.L., 98:752

Reginatto, M., ISD97, a computer program to analyze data from a

series of in situ measurements on a grid and identify potential

localized areas of elevated activity, 98:288 (R;US)

MAXED, a computer code for the deconvolution of multisphere

neutron spectrometer data using the maximum entropy method,

98:292 (R;US)

Reichhardt, D.K., Principles and objectives of containment verification and performance monitoring and technology selection,

98:629 (R;US)

Reidel, S.P., See Hartshorn, D.C., 98:564

Reiser, A.S., See Weiner, R.F., 98:674

Rellergert, C.A., See Hallman, A.K., 98:700

Rellergert, Carla A., See Hallman, Anne K., 98:701

Revis, N.W., Removal of dissolved heavy metals and radionuclides

by microbial spores, 98:264 (R;US)

Reynolds, B.A., See McCabe, D.J., 98:730

Reynolds, R.D., Environmental Science and Research Foundation,

Inc. annual technical report: Calendar year 1997, 98:295 (R;US)

Reynolds, T.D., See Sperber, T.D., 98:370

Richards, R.R., QA lessons learned for parameter control from the

WIPP Project, 98:686 (R;US)

Richardson, D., See Kennicott, M., 98:446

Ricketts, T.E., See Hurd, J.R., 98:441

Rinehart, D.E., See Rassat, S.D., 98:604

Rinker, M.W., See Hatchell, B.K., 98:602

Rittenberg, R.B., National Low-Level Waste Management Program

final summary report of key activities and accomplishments for

fiscal year 1997, 98:371 (R;US)

Rivera, J.M., See Wagner, E.P. Jr., 98:392

Rivera, M., See Ammerman, D., 98:668

Rivera, M.A., See Dustin, D.F., 98:619

See Thorp, D.T., 98:618

Robb, A.K., See Jefimoff, J., 98:319

Roberts, D., See Chambers, A., 98:322

Robinette, R.J., See Osborne-Lee, I.W., 98:529

Robinson, G.S., Bechtel Hanford, Inc., RCRA Permit Implementation Plan, 98:46 (R;US)

Robinson, J.M., See Hsu, K.M., 98:353

Robinson, R., See Huchton, K., 98:415

Environmental Management Technical Reports 233
Rodovsky

Rodovsky, T.J., Final Hazard Classification and Auditable Safety

Analysis for the 105-F Building Interim Safe Storage Project,

98:68 (R;US)

Rodwell, P.O., Sampling plan to support HLW tank 16, 98:765 (R;US)

Rogers, R.D., See Wolfram, J.H., 98:299

Rohay, A.C., See Hartshorn, D.C., 98:564

Rohay, V.J., Borehole Summary Report for the 216-B-2-2 Ditch,

98:75 (R;US)

Romanovskiy, V.N., See Todd, T.A., 98:329

Rose, R.W., See Bhattacharyya, S.K., 98:42

See Craig, K.A., 98:40

See Yule, T.J., 98:43

Rosine, S.D., See Ebert, W.L., 98:13

Roush, D.E. Jr., Landowner and permit-holder perceptions of

wildlife damage around the Idaho National Engineering and Environmental Laboratory. A survey of INEEL neighbors about elk,

mule deer, pronghorn antelope, and depredation, 98:294 (R;US)

Roybal, J.A., Pollution prevention and waste minimization opportunity assessment in environmental restoration, 98:670 (R;US)

Testing, expanding and implementing pollution prevention tools for

environmental restoration and decontamination and decommissioning, 98:717 (R;US)

Waste reduction by separation of contaminated soils during environmental restoration, 98:714 (R;US)

Rucker, D.F., See Neill, R.H., 98:125

Rudisill, T.S., See Laurinat, J.E., 98:779

Rule, V.A., North Tank Farm data report for the Gunite and Associated Tanks at Oak Ridge National Laboratory, 98:555 (R;US)

Ruskauff, G.J., See Beauheim, R.L., 98:697

Russell, N.E., Hot isostatic press waste option study report, 98:355

(R;US)

Waste disposal options report. Volume 1, 98:342 (R;US)

Waste disposal options report. Volume 2, 98:343 (R;US)

Ryan, J.V., See Haas, W.J., 98:407

See Haas, W.J. Jr., 98:408, 98:409

Rzeszutko, C., A Standard Analysis Method (SAM) for the automated analysis of polychlorinated biphenyls (PCBs) in soils

using the chemical analysis automation (CAA) paradigm: Validation and performance, 98:417 (R;US)

A standard analysis method (SAM) for the automated analysis of

polychlorinated biphenyls (PCBs) in soils using the chemical

analysis automation (CAA) paradigm: validation and performance, 98:448 (R;US)

See Hollen, R., 98:447

S

Sachleben, R.A., See Moyer, B.A., 98:92, 98:484

Sale, M.J., See Bao, Y.S., 98:533

Salisbury, M., See Foxx, T., 98:414

Salvage, K.M., See Yeh, G.T., 98:561

Samuels, W.D., See Camaioni, D.M., 98:566, 98:591

Sanchez, M., Remedial actions of nuclear safety shot sites: Double

Tracks and Clean Slates, 98:260 (R;US)

Sanders, M.R., Characterization of septic and drain system releases

at Sandia National Laboratories, New Mexico, 98:643 (R;US)

Sandoval, W., A new waste minimization method for the determination of total nonhalogenated volatile organic compounds in TRU

wastes, 98:436 (R;US)

Sargent, T.J., See Greenfield, M.A., 98:286

Sato, Chikashi, See Nguyen, H.D., 98:396

Sattler, J., See Honigford, L., 98:296

Saunders, A.D., See Van Hoesen, S.D., 98:502

Saviz, K., Year 2000 compliance concerns with the ISA Thermoluminescent Dosimetry Data Processing (TL-DP) software system,

98:622 (R;US)

Sawyer, D.A., See Grauch, V.J., 98:727

Scarpitta, S., A portable battery-powered continuous airborne 222Rn

sampler, 98:290 (R;US)

Scarpitta, S.C., Preparation and validation of gross alpha/beta samples used in EML’s quality assessment program, 98:289 (R;US)

Schaus, P.S., See Valentine, J.H., 98:305

Scheele, R.D., Organic tank safety project: Equilibrium moisture determination task, FY 1998 annual progress report, 98:600 (R;US)

See Hunter, V.L., 98:580

Schempf, H., See Draper, J.V., 98:101

Schenker, A., See Martell, M.A., 98:683

Schlahta, S.N., Crystalline silicotitanate gate review analysis,

98:576 (R;US)

Schmidt, M.A., See Nash, K.L., 98:6

Schriner, J.A., Project report: Tritiated oil repackaging highlighting

the ISMS process. Historical radioactive and mixed waste disposal request validation and waste disposal project, 98:722

(R;US)

See Hallman, A.K., 98:700

Schriner, Joseph A., See Hallman, Anne K., 98:701

Schultz, D., See Quinton, G., 98:220

Schumann, P.B., Key regulatory drivers affecting shipments of

mixed transuranic waste from Los Alamos National Laboratory

to the Waste Isolation Pilot Plant, 98:428 (R;US)

Schweitzer, M., Measuring the accomplishments of public participation programs: Overview of a methodological study performed

for DOE’s Office of Environmental Management, 98:119 (R;US)

Schwendiman, G.L., See Gering, K.L., 98:381

Schwendiman, L., See Conley, T.B., 98:99

Schwinkendorf, W.E., See Cooley, C.R., 98:306

Scott, C.B., See Maddox, J.J., 98:549

Seifert, L.S., See Black, D.B., 98:41

Selfridge, R.J., See Egidi, P.V., 98:478

Sell, R.L., See Scheele, R.D., 98:600

Selph, M.M., See Normann, R.A., 98:713

Serne, R.J., Chemical information on tank supernatants, Cs adsorption from tank liquids onto Hanford sediments, and field

observations of Cs migration from past tank leaks, 98:563 (R;US)

Shah, V.M., Distillation under electric fields, 98:475 (R;US)

Shapiro, A.P., Development of an integrated in-situ remediation

technology. Topical report for Task #3.2 entitled, “Modeling and

iron dechlorination studies” (September 26, 1994–August 31,

1997), 98:266 (R;US)

Development of an integrated, in-situ remediation technology.

Topical report for task No. 9. Part I. TCE degradation using nonbiological methods, September 26, 1994–May 25, 1996, 98:223

(R;US)

Shappert, L.B., Completion of the Radioactive Materials Packaging

Handbook, 98:485 (R;US)

Recent experience in planning, packaging and preparing noncommercial spent fuel for shipment in the United States, 98:493

(R;US)

See Feldman, M.R., 98:487

See Pope, R.B., 98:488, 98:489, 98:492

Sharma, A., See Clauss, S.A., 98:573

Sharma, A.K., See Camaioni, D.M., 98:566

See Campbell, J.A., 98:601

Shaw, P.G., See Weidner, J.R., 98:336

Shearer, T., The restoration of an Argonne National Laboratory

foundry, 98:29 (R;US)

Shearer, T.L., Argonne National Laboratory’s photo-oxidation organic mixed waste treatment system - installation and startup

testing, 98:30 (R;US)

Shebell, P., See Reginatto, M., 98:288

Sheen, S.H., An ultrasonic instrument for measuring density and viscosity of tank waste, 98:37 (R;US)

Ultrasonic viscometer and methods of measuring solids concentration, 98:4 (R;US)

Shekarriz, A., See Bobroff, S., 98:568

See Recknagle, K.P., 98:575

Shelton, B., See Shearer, T., 98:29

Shepard, C.L., See Peurrung, L.M., 98:583, 98:584

Shephard, L.E., See Howarth, S.M., 98:678

Sheridan, P.W., See Ho, Sa V., 98:218

See Hughes, B.M., 98:226

Shifty, K.L., See Gurley, R.N., 98:369

Shilov, V.P., See Krot, N.N., 98:589

See Peretrukhin, V.F., 98:605

Shirley, C., See Pohll, G., 98:258

234 Environmental Management Technical Reports
Taylor

Shor, J.T., Progress report and technology status development of

an EG and G Berthold LB-150 alpha/beta particulate monitor for

use on the East Tennessee Technology Park Toxic Substances

Control Act Incinerator, 98:542 (R;US)

Shotton, M., See Sanchez, M., 98:260

Shropshire, D.E., System for decision analysis support on complex

waste management issues, 98:405 (R;US)

See Hsu, K.M., 98:353

Siegrist, B., See Murdoch, L., 98:477

Siegrist, R.L., X-231A demonstration of in-situ remediation of

DNAPL compounds in low permeability media by soil fracturing

with thermally enhanced mass recovery or reactive barrier destruction, 98:541 (R;US)

See Cline, S.R., 98:123

Silin, V.I., See Peretrukhin, V.F., 98:605

Silva, M.K., See Neill, R.H., 98:125

Silverman, D., See Buhl, A.R., 98:616

Silverman, D.J., Licensing an assured isolation facility for low-level

radioactive waste. Volume 1: Licensing strategy and issues,

98:200 (R;US)

Licensing an assured isolation facility for low-level radioactive

waste. Volume 2: Recommendations on the content and review

of an application, 98:201 (R;US)

Simmons, A., Environmental Management Science Program

awards. Fiscal year 1997 annual progress report, 98:467 (R;US)

Simmons, C.S., Dryout modeling in support of the organic tank

safety project, 98:599 (R;US)

Simmons, D.W., See Del Cul, G.D., 98:537

Singh, D., Immobilization of fission products in phosphate ceramic

waste forms, 98:36 (R;US)

See Wescott, J., 98:28

Singh, S.P.N., See Shor, J.T., 98:542

Singley, P.T., See Pope, R.B., 98:491

Sinkule, B.J., See Schumann, P.B., 98:428

Sivavec, T.M., See Shapiro, A.P., 98:223, 98:266

Sklarew, D.S., Ventilation rates calculated from hydrogen release

data in tanks equipped with standard hydrogen monitoring systems (SHMS), 98:596 (R;US)

See Huckaby, J.L., 98:595

Slack, W.W., See Siegrist, R.L., 98:541

Slavin, P., See Roybal, J.A., 98:714

Slefken, L.J., See Harvego, E.A., 98:321

Small, D.E., Graphical programming of telerobotic tasks, 98:631

(R;US)

Smirnov, I.V., See Todd, T.A., 98:329

Smith, B.M., See AlMahamid, I., 98:466

Smith, C.A., See Berg, J.M., 98:438

Smith, G., See Maio, V., 98:496

Smith, J.D., See Mills, G.S., 98:681

Smith, R., See Hutterman, L., 98:379

Smith, W.H., Comparison of silver(II), cobalt(III), and cerium(IV) as

electron transfer mediators in the MEO mixed waste treatment

process, 98:442 (R;US)

Soelberg, N., High performance APCS conceptual design and evaluation scoping study, 98:340 (R;US)

See Chambers, A., 98:322

Sohal, M.S., Low-level radioactive waste form qualification testing,

98:341 (R;US)

Sondrup, A.J., See Magnuson, S.O., 98:332

Southworth, G.R., See Greeley, M.S. Jr., 98:796

Spalding, B.P., In situ vitrification demonstration at Pit 1, Oak Ridge

National Laboratory. Volume 1: Results of treatability study,

98:515 (R;US)

In situ vitrification demonstration at Pit 1, Oak Ridge National Laboratory. Volume 2: Site characterization report of the Pit 1 area,

98:516 (R;US)

Spangler, L.R., See Connolly, M.J., 98:298

Spaulding, B.C., ICPP tank farm closure study. Volume 1, 98:345

(R;US)

See Dahlmeir, M.M., 98:357

Spear, K.E., See Beahm, E.C., 98:559

Speed, D., See Burns, D.B., 98:738

Speed, D.L., Investigation of water accumulation in an offgas test facility HEPA housing, 98:739 (R;US)

Spence, R.D., Grout and glass performance in support of stabilization/solidification of ORNL tank sludges, 98:557 (R;US)

Laboratory stabilization/solidification of surrogate and actual

mixed-waste sludge in glass and grout, 98:470 (R;US)

See Gilliam, T.M., 98:495

See Maio, V., 98:496

Sperber, T.D., Workshop proceedings: Developing the scientific

basis for long-term land management of the Idaho National Engineering and Environmental Laboratory, 98:370 (R;US)

Springer, D.L., See Benson, J.M., 98:133

Sprung, J.L., Data and methods for the assessment of the risks associated with the maritime transport of radioactive materials:

Results of the SeaRAM program studies. Volume 1 – Main report, 98:715 (R;US)

Data and methods for the assessment of the risks associated with

the maritime transport of radioactive materials: Results of the

SeaRAM program studies. Volume 2 – Appendices, 98:716

(R;US)

SeaRAM: A DOE evaluation of maritime accident risk assessment

data and methods, 98:651 (R;US)

See Kanipe, F.L., 98:652

Staiger, M.D., See Palmer, W.B., 98:374

Stanford, A.R., Low-level radioactive waste disposal operations at

Los Alamos National Laboratory, 98:427 (R;US)

Starke, T.P., See Kennicott, M., 98:446

Statham, W., See Loken, M., 98:664

Statham, W.H., See Reeves, M., 98:712

Steele, R., See Clauss, S.A., 98:573

Stefanovsky, S.V., See Aloy, A.S., 98:323

Stellern, J.L., See Kent, T.E., 98:548

Stepan, D.J., Task 9 - centrifugal membrane filtration. Semi-annual

report April 1–September 30, 1996, 98:239 (R;US)

Task 9 – Centrifugal membrane filtration. Semi-annual report, April

1–September 30, 1997, 98:230 (R;US)

Stephan, Daniel J., Task 9- Centrifugal Membrane Filtration. Semiannual report, November 1, 1996–March 31, 1997, 98:246 (R;US)

Sterbentz, J.W., See Russell, N.E., 98:342, 98:343

Stevens, F.M., See Burns, D.B., 98:737

Stewart, C.W., Baseline estimate of the retained gas volume in Tank

241-C-106, 98:587 (R;US)

See Caley, S.M., 98:607

See Peurrung, L.M., 98:583, 98:584

Stewart, W., See Dwyer, B.P., 98:636

Stock, L.M., Chemical pathways for the formation of ammonia in

Hanford wastes, 98:569 (R;US)

Stockman, C., See Bynum, R.V., 98:624

Stockman, C.T., See Rechard, R.P., 98:687

Strachan, D.M., See Ebert, W.L., 98:3, 98:8

See Wolf, S.F., 98:2

Stump, R.C., See Mustin, T., 98:316

See Tyacke, M., 98:318

Stumpfl, E., See Feldman, M.R., 98:487

Sullivan, T.M., Overview of environmental decision support software, 98:88 (R;US)

Sutherland, A.A., See Chau, B., 98:199

Swanson, S.P., See Hyde, R.A., 98:401

Swartz, G., See McClure, L., 98:404

Swift, P.N., See Crawford, M.B., 98:693

Syarip, I., See Jefimoff, J., 98:319

Szecsody, J.E., See Yeh, G.T., 98:561

T

Taggart, D., See Vigil, J., 98:429

Taggart, D.P., Experience operating LANL’s passive/active neutron

(PAN) assay system, 98:430 (R;US)

Tananaev, I.G., See Krot, N.N., 98:589

Taylor, D.D., See Lee, A.E., 98:361

See Russell, N.E., 98:355

Taylor, P.A., Large-scale treatment of high-salt, high-pH wastewater

for 137Cs and 90Sr removal, using crystalline silicotitanate resin,

98:494 (R;US)

See Kent, T.E., 98:532

Environmental Management Technical Reports 235
Taylor

See Lee, D.D., 98:97

See Lucero, A.J., 98:558

See Walker, J.F. Jr., 98:473, 98:536

Taylor, S.A., See Kent, T.E., 98:548

Tempel, K.L., See Ades, M.J., 98:748

Terrones, G., See Erian, F.F., 98:570

Thomas, I.R., An alternative test for verifying electronic balance linearity, 98:331 (R;US)

Thomas, J.K., See Blanchard, A., 98:745

Thomas, T., See McClure, J.D., 98:692

Thompson, D.H., See Hunt, M.A., 98:552

Thompson, J.L., Laboratory and field studies related to radionuclide

migration at the Nevada Test Site. Progress report, October 1,

1996–September 30, 1997, 98:419 (R;US)

Thompson, M.C., Advanced Separations at SRS, 98:751 (R;US)

Solubility Limits of Dibutyl Phosphoric Acid in Uranium Solutions at

SRS, 98:781 (R;US)

Thoren, R.A., See Encke, B.D., 98:69

See Encke, D.B., 98:73

Thorne, P.D., See Cole, C.R., 98:582

Thornton, E.C., Gas treatment of Cr(VI)-contaminated sediment

samples from the North 60’s pits of the chemical waste landfill,

98:565 (R;US)

See Hartman, M.J., 98:606

Thorp, D., See Ammerman, D., 98:668

Thorp, D.T., Status and use of the Rocky Flats Environmental Technology Site Pipe Overpack Container for TRU waste storage

and shipments, 98:618 (R;US)

See Dustin, D.F., 98:619

Thrall, K.D., See Benson, J.M., 98:133

Tierney, G., See Foxx, T., 98:414

Tilbrook, R.W., See Nieves, L.A., 98:16

Tillotson, R., See Wood, D.J., 98:328

Tillotson, R.D., See Wood, D.J., 98:334

Timpe, R.C., See Grisanti, A.A., 98:233

Timpe, Ronald C., See Grisanti, Ames A., 98:249

Timpson, M.E., See Francis, C.W., 98:111

Tiner, P.F., See Burman, S.N., 98:507

Tixier, J.S., See Spalding, B.P., 98:515

Todd, T.A., Treatment of acidic INEEL waste using a countercurrent

cobalt dicarbollide-based universal solvent extraction process,

98:329 (R;US)

See Herbst, R.S., 98:335

See Law, J.D., 98:312, 98:364, 98:402, 98:403

See Mann, N.R., 98:366

See McCabe, D.J., 98:730

See Wood, D.J., 98:328, 98:334

Tompkins, J.A., Recovery of 241Am/Be neutron sources, Wooster,

Ohio, 98:420 (R;US)

Torres, T., See Shearer, T.L., 98:30

Toth, J.J., See Heasler, P.G., 98:597

Toth, L.M., See Del Cul, G.D., 98:537

Towell, R.H., Method of estimating the leakage of multiple barriers in

a radioactive materials shipping package, 98:34 (R;US)

See Oras, J.J., 98:33, 98:35

Travis, J.R., See Lee, D.D., 98:528, 98:531

Trennel, A.J., Developing the Sandia National Laboratories transportation infrastructure for isotope products and wastes, 98:644

(R;US)

Trent, D.S., See Onishi, Y., 98:579

Trent, S.J., See Day, R.S., 98:66

Triay, I., See Boak, J.M., 98:452

Trofimenko, A.S., See Aloy, A.S., 98:323

Trowbridge, L.D., See Del Cul, G.D., 98:537

Trujillo, V., Measurement of surface emission flux rates for volatile

organic compounds at Technical Area 54, 98:413 (R;US)

Trushina, V.E., See Peretrukhin, V.F., 98:605

Tsouris, C., See Shah, V.M., 98:475

Tullock, P.A., See Wood, D.J., 98:328, 98:334

Tumquist, M.A., See Kjeldgaard, E.A., 98:696

Tuott, L.C., See Dahlmeir, M.M., 98:357

Turner, D.W., See Aramayo, G.A., 98:504

See Shappert, L.B., 98:493

Tyacke, M., Status of the TRIGA shipments to the INEEL from Asia,

98:318 (R;US)

Tyacke, M.J., See Mustin, T., 98:316

U

Uldrich, E.D., Cask crush pad analysis using detailed and simplified

analysis methods, 98:311 (R;US)

See Hawkes, B.D., 98:313

Upton, J.F., See Amaya, J.P., 98:567

Urioste, J., Hazardous waste systems analysis at Los Alamos National Laboratory, 98:444 (R;US)

V

Valceschini, R., See Wilson, G.V., 98:256

Valentine, J.H., High-level waste program integration within the

DOE complex, 98:305 (R;US)

Van Essen, D.C., See Hylton, T.D., 98:121, 98:551

See Lucero, A.J., 98:558

Van Hoesen, S.D., Gunite and associated tanks remediation project

recycling and waste minimization effort, 98:502 (R;US)

Van Pelt, W.B., See Speed, D.L., 98:739

Van Verst, S.P., Survey of radiological contaminants in the nearshore environment at the Hanford Site 100-N Area reactor,

98:598 (R;US)

Vance, J.K., See Lageraaen, P.R., 98:89

VanEssen, D.C., See Lucero, A.J., 98:535

VanPelt, W., See Burns, D.B., 98:738

Vaughn, R.B., See Berg, J.M., 98:435, 98:438

Veazey, G.W., See Hurd, J.R., 98:441

Veirs, D.K., See Berg, J.M., 98:435, 98:438

See Flamm, B.F., 98:450

Vigil, J., Los Alamos National Laboratory’s Mobile Real Time Radiography System, 98:429 (R;US)

Vigil, J.J., See Taggart, D.P., 98:430

Villanueva, D., See Federici, C., 98:434

Villarreal, R., See Field, L.R., 98:460

Vincent, A.M. III, See Ades, M.J., 98:740

Vinsant, E., See Roybal, J.A., 98:714

Vold, E., Synopsis of hydrologic data collected by waste management for characterization of unsaturated transport at Area G,

98:454 (R;US)

Synopsis of moisture monitoring by neutron probe in the unsaturated zone at Area G, 98:455 (R;US)

Synopsis of recent moisture flux analyses relevant to the unsaturated zone at Area G, 98:456 (R;US)

Vold, E.L., A model for the effective diffusion of gas or the vapor

phase in a fractured media unsaturated zone driven by periodic

atmospheric pressure fluctuations, 98:432 (R;US)

Atmospheric transport in complex terrain at Los Alamos, Area G,

98:431 (R;US)

W

Wagh, A., See Maio, V., 98:496

See Singh, D., 98:36

See Wescott, J., 98:28

Wagner, E.P. Jr., Design and operation of the Rover vacuum system, 98:392 (R;US)

Wahl, K.L., See Camaioni, D.M., 98:566

Walker, A.B., See DePaoli, S.M., 98:538

Walker, B.A., See Neill, R.H., 98:125

Walker, B.W., Cross-Flow Filtration of Department of Energy Hanford Waste Streams Using Sintered Metal Mott and Graver

Filters at the Savannah River Technology Center, 98:749 (R;US)

Walker, D.D., Tetraphenylborate Solids Stability Tests, 98:762 (R;US)

See Wilmarth, W.R., 98:768

Walker, J.F., See Taylor, P.A., 98:494

236 Environmental Management Technical Reports
Xin

Walker, J.F. Jr., Cesium removal demonstration utilizing crystalline

silicotitanate sorbent for processing Melton Valley Storage Tank

supernate: Final report, 98:536 (R;US)

Cesium removal from high-pH, high-salt wastwater using crystalline silicotitanate sorbent, 98:473 (R;US)

See Lee, D.D., 98:97

Walkington, W.G., See Goodwin, F.E., 98:193

Wallo, A., See Ranek, N.L., 98:20

Walsh, R., See Dunn, S.D., 98:721

Wang, J.C., See Blasing, T.J., 98:544

Wang, S.K., See Chang, Y.S., 98:25

Wang, Yifeng, See Bynum, R.V., 98:624

Wangler, M.E., See Liu, Y.Y., 98:38

See Oras, J.J., 98:33, 98:35

Wannigman, D., See Tompkins, J.A., 98:420

Ward, F.S., See Palmer, W.B., 98:374

Warner, P.J., Traceability and retrievability: Documentation, the

bridge from science to compliance, 98:641 (R;US)

United States of America activities relative to the International

Atomic Energy Agency (IAEA) initiative: Records management

for deep geologic repositories, 98:637 (R;US)

Warren, R.W., See Reynolds, R.D., 98:295

Warren, S., See Ranek, N.L., 98:20

Waterland, L.R., See Haas, W.J., 98:407

Waters, R.D., Evaluation of the capabilities of the Hanford Reservation and Envirocare of Utah for disposal of potentially

problematic mixed low-level waste streams, 98:709 (R;US)

The residuals analysis project: Evaluating disposal options for

treated mixed low-level waste, 98:634 (R;US)

See Pohl, P.I., 98:638

Watson, D., Bear Creek Valley characterization area mixed wastes

passive in situ treatment technology demonstration project - status report, 98:95 (R;US)

Watson, J., See Roybal, J.A., 98:717

Weart, W.D., Critical scientific issues in the demonstration of WIPP

compliance with EPA repository standards, 98:691 (R;US)

Webb, S.W., Comparison of Ross’ capillary barrier diversion formula

with detailed numerical simulations, 98:655 (R;US)

Prediction of tilted capillary barrier performance, 98:656 (R;US)

See Ho, C.K., 98:628

Weber, C.F., See Beahm, E.C., 98:559

Weekes, D.C., See Rohay, V.J., 98:75

Weidner, J.R., Buried waste containment system materials. Final

Report, 98:336 (R;US)

Weiner, R., See Howarth, S.M., 98:704, 98:705

Weiner, R.F., A risk-based decision-aiding tool for waste disposal,

98:674 (R;US)

See Neuhauser, K.S., 98:673

Weinrach, J., See Mroz, G., 98:458, 98:461

Welch, T.D., See Hunt, R.D., 98:500

See McGinnis, C.P., 98:98, 98:505, 98:560

Wells, M.N., See Davis, N.R., 98:297

Wendt, K.M., See Jefimoff, J., 98:319

Wenzel, D.R., See Russell, N.E., 98:342, 98:343

Wescott, J., Production-scale LLW and RMW solidification system

operational testing at Argonne National Laboratory-East (ANLE), 98:28 (R;US)

West, G.D., See Lucero, A.J., 98:558

West, O.R., See Cline, S.R., 98:123

See Gu, B., 98:93

West, W.H., See Hsu, K.M., 98:353

Westrich, H.R., Metal sorption on kaolinite, 98:642 (R;US)

Wey, J.E., See Wolfram, J.H., 98:299

Wheeler, T., See Pohl, P.I., 98:638

Wheeler, T.A., See Waters, R.D., 98:709

White, M., See Hatchell, B.K., 98:602

White, M.D., STOMP Subsurface Transport Over Multiple Phases:

User’s guide, 98:562 (R;US)

Whyatt, G.A., Low-pressure, single-point grout injection for tank

heel sludge mixing and in-situ immobilization, 98:609 (R;US)

Wierman, T.E., See Eide, S.A., 98:349

Wilburn, D., Standard data report. 1997 annual report on waste

generation and waste minimization progress, 98:463 (R;US)

Wilcoxon, J.P., Studies of photoredox reactions on nanosize semiconductors, 98:625 (R;US)

Studies of photoredox reactions on nanosize semiconductors,

98:671 (R;US)

Willcox, M.V., See Harris, J.D., 98:309

Williams, B.A., TWRS privatization phase 1 monitoring wells engineering study, 98:586 (R;US)

Williams, C., See Dunn, S.D., 98:721

Williams, C.V., See Normann, R.A., 98:713

Williams, D.F., See Del Cul, G.D., 98:537

Williams, K.L., See Dafoe, R.E., 98:348

Williams, M.D., See Cole, C.R., 98:582

Williams, R.E., See Conner, J.E., 98:390

Willis, W.D., See Anderson, M.O., 98:398

Willison, C.P., See Roybal, J.A., 98:670

Wilmarth, W.R., Characterization of Samples from the Effluent Treatment Facility Evaporator Waste Concentrate Tank, 98:759 (R;US)

High Level Waste Evaporator Analysis Results, 98:783 (R;US)

Sodium Aluminosilicate Formation in Tank 43H Simulants, 98:768

(R;US)

Wilmot, R.D., See Crawford, M.B., 98:693

Wilson, C.W., See Barry, R.E., 98:645

Wilson, D.F., See Compere, A.L., 98:547

Wilson, G.V., Numerical evaluation of monofil and subtle-layered

evapotranspiration (ET) landfill caps, 98:256 (R;US)

Wilson, J.H., See Francis, C.W., 98:111

See McCabe, D.J., 98:730

Wilson, J.R., See Nguyen, H.D., 98:396

Wilson, S.E., See Nieves, L.A., 98:16

Wilson-Nichols, M.J., See Gardner, F.G., 98:554

Winslow, R.C., ALARA Review for the 202-S Plutonium Loadout

Hood Sampling, 98:80 (R;US)

Winston, R., See Blacker, P.B., 98:406

Wise, F.E., See Davis, N.R., 98:297

Wittreich, C.D., See Faurote, J.M., 98:62

Wix, S.D., Modeling fires in adjacent ship compartments with computational fluid dynamics, 98:698 (R;US)

See Koski, J.A., 98:653

Wixson, J.R., See Murphy, J.A., 98:302

Wolf, S.F., A data base and a standard material for use in acceptance testing of low-activity waste products, 98:2 (R;US)

See Ebert, W.L., 98:3, 98:8

Wolfe, A.K., See Schweitzer, M., 98:119

Wolfram, J.H., Degradation of hazardous chemicals in liquid

radioactive wastes from biomedical research using a mixed microbial population, 98:299 (R;US)

Wood, D.J., Development of the SREX process for the treatment of

ICPP liquid wastes, 98:334 (R;US)

Removal of strontium-90 from calcined wastes with the SREX process, 98:328 (R;US)

See Law, J.D., 98:403

See Mann, N.R., 98:366

Woods, P.J., Surveillance and Maintenance Plan for the Plutonium

Uranium Extraction (PUREX) Facility, 98:276 (R;US)

Workman, P.J., See Andrews, M.K., 98:772

Wright, R.B., Evaluation of SAFT America, Inc. electrochemical capacitors, 98:362 (R;US)

Wright, R.Q., See Leal, L.C., 98:539

Wrons, R., Importance of energy efficiency in the design of the Process and Environmental Technology Laboratory (PETL) at

Sandia National Laboratories, New Mexico (NM), 98:719 (R;US)

Sandia bicycle commuters group – pollution prevention at Sandia

National Laboratories, New Mexico, 98:718 (R;US)

Wurstner, S.K., See Cole, C.R., 98:582

Wygmans, D., See Shearer, T.L., 98:30

Wygmans, D.G., See Reed, D.T., 98:689

X

Xin, R.C., See Ebadian, M.A., 98:182

Environmental Management Technical Reports 237
Yarbro

Y

Yarbro, S.L., See Mostafa, A.T.M.G., 98:423

Yeh, G.T., HYDROBIOGEOCHEM: A coupled model of HYDROlogic

transport and mixed BIOGEOCHEMical kinetic/equilibrium reactions in saturated-unsaturated media, 98:561 (R;US)

Yerace, P., See Krishnaswamy, P., 98:134

See Yuracko, K.L., 98:497

Yerace, P.J., See Mezaraups, J., 98:44

Yiacoumi, S., See Ying, T.Y., 98:474

Ying, T.Y., Magnetic-seeding filtration, 98:474 (R;US)

Yoon, Woo Y., See Blackwood, L.G., 98:383

Yoshimura, H.R., See McClure, J.D., 98:692

Younkins, R.M., See Fogle, R.F., 98:729

Yu, C., See Chang, Y.S., 98:25

Yule, T.J., D&D of a reactor, hot cells and gloveboxes - an integrated experience, 98:43 (R;US)

Yuracko, K., See Krishnaswamy, P., 98:134

Yuracko, K.L., A life cycle analysis approach to D and D decisionmaking, 98:497 (R;US)

Yusov, A.B., See Krot, N.N., 98:589

Z

Zachara, J.M., See Serne, R.J., 98:563

See Yeh, G.T., 98:561

Zaitsev, B.N., See Todd, T.A., 98:329

Zamecnik, J.R., Analysis of cascade impactor and EPA method 29

data from the americium/curium pilot melter system, 98:757

(R;US)

Zapp, P.E., Effect of nitrite concentration on pit depth in carbon steel

exposed to simulated radioactive waste, 98:743 (R;US)

Zeek, D.P., Pinhole corrosion of CH-TRU waste containers by

volatile organic compounds, 98:308 (R;US)

Zhang, X.S., See Barton, J.W., 98:486

Zlochower, I., See Liekhus, K., 98:327

Zoric, J.P., 105-DR Large Sodium Fire Facility Inspection Plan,

98:77 (R;US)

238 Environmental Management Technical Reports
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