ORAU Team

NIOSH Dose Reconstruction Project

Technical Basis Document for the Hanford Site -- Site 

Description

Document Number:

ORAUT-TKBS-0006-2 

Effective Date: 12/29/2004 

Revision No.: 00 PC-1 

Controlled Copy No.: 

Page 1 of 39

Subject Expert: Jack Selby

Document Owner:

Approval: Signature on File Date: 10/03/2003

Edward D. Scalsky, Document Owner

Approval: Signature on File Date: 10/03/2003 Judson L. Kenoyer, Task 3 Manager

Concurrence: Signature on File Date: 10/08/2003

Richard E. Toohey, Project Director

Approval: Signature on File Date: 10/03/2003

James W. Neton, OCAS Health Science Administrator

Supersedes:

None

TABLE OF CONTENTS

Section

Record of Issue/Revisions ...................................................................................................................

Page

5

Acronyms and Abbreviations ...............................................................................................................6

Hanford Site Description and Processes..............................................................................................7

2.1 Reactors .....................................................................................................................................7

2.1.1 105-B, C, D, DR, F, H, KW, and KE Production Reactors................................................ 8

2.1.2 105-N Production Reactor ...............................................................................................8

2.1.3 305 Hanford Test Reactor ...............................................................................................8

2.1.4 305-B Physical Constants Test Reactor .......................................................................... 9

2.1.5 305-B Thermal Test Reactor ...........................................................................................9

2.1.6 309 Plutonium Recycle Test Reactor............................................................................... 9

2.1.7 309 Plutonium Recycle Critical Facility ............................................................................ 9

2.1.8 318 High Temperature Lattice Test Reactor.................................................................... 9

2.1.9 405 Fast Flux Test Facility............................................................................................. 10

2.2 Fuel Separations Facilities ........................................................................................................ 10

2.2.1 Original Fuel Separations Facilities ............................................................................... 10

2.2.2 202-S REDOX Plant...................................................................................................... 11

2.2.3 202-A PUREX Plant ...................................................................................................... 11

2.2.4 221-U U Plant................................................................................................................12

2.2.5 224-U UO3 Plant............................................................................................................ 12

2.2.6 225 Waste Encapsulation and Storage Facility.............................................................. 12

2.2.7 201-C C Plant or Hot Semiworks................................................................................... 12

2.2.8 108-B Tritium Extraction Facility .................................................................................... 12

2.3 Fuel Fabrication Facilities ......................................................................................................... 13
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2.3.1 313 Uranium Metal Fuels Fabrication Facility ................................................................ 13

2.3.2 314 Uranium Metal Extrusion Facility ............................................................................ 13

2.3.3 333 Fuel Cladding Facility ............................................................................................. 14

2.3.4 306 Reactor Fuel Manufacturing Pilot Plant................................................................... 14

2.3.5 303 Facilities Fresh Metal Storage Facilities................................................................. 14

2.4 Plutonium Finishing Facilities.................................................................................................... 14

2.4.1 231-Z Plutonium Isolation Facility.................................................................................. 15

2.4.2 234-5Z Plutonium Finishing Plant Complex ................................................................... 16

2.4.2.1 Rubber Glove Line .......................................................................................... 16

2.4.2.2 Remote Mechanical A Line ............................................................................. 16

2.4.2.3 Remote Mechanical C Line ............................................................................. 16

2.4.2.4 Recovery of Uranium and Plutonium by Extraction Facility.............................. 17

2.4.2.5 232-Z Incinerator Facility................................................................................. 17

2.4.2.6 236-Z Plutonium Reclamation Facility ............................................................. 17

2.4.2.7 242-Z Waste Treatment Facility ...................................................................... 18

2.4.3 Plutonium Storage Facilities .......................................................................................... 18

2.5 Research, Development, and Testing Facilities ........................................................................ 18

2.5.1 108-F Biology Facility .................................................................................................... 18

2.5.2 120 Critical Mass Laboratory Facility ............................................................................. 18

2.5.3 209-E Critical Mass Laboratory ..................................................................................... 19

2.5.4 222-B Laboratory........................................................................................................... 19

2.5.5 222-S Laboratory........................................................................................................... 19

2.5.6 222-T Laboratory........................................................................................................... 19

2.5.7 308 Plutonium Fuels Pilot Plant..................................................................................... 19

2.5.8 318 Radiological Calibration and Development Laboratory............................................ 20

2.5.9 320 Low-Level Radiochemistry Facility.......................................................................... 20

2.5.10 321 Separation Facility .................................................................................................. 20

2.5.11 324 Chemical and Materials Engineering Laboratory..................................................... 20

2.5.12 325 Radiochemistry Laboratory..................................................................................... 21

2.5.13 326 Pile Physics Technology and Metallurgy Facility..................................................... 21

2.5.14 327 Radiometallurgy Laboratory Facility........................................................................ 21

2.5.15 329 Biophysics Laboratory ............................................................................................ 22

2.5.16 331 Life Sciences Laboratory Facility ............................................................................ 22

2.5.17 3706 Radiochemistry Laboratory................................................................................... 22

2.5.18 3730 Gamma Irradiation Facility.................................................................................... 22

2.5.19 3732 Process Equipment Development Laboratory....................................................... 23

2.5.20 3741 Graphite Hot Shop Facility.................................................................................... 23

2.5.21 3745 Radiological Calibrations and Standards Laboratory ............................................ 23

2.6 Waste Handling Facilities.......................................................................................................... 23

2.6.1 High-Level Liquid Waste Tanks ..................................................................................... 23

2.6.2 216-Z-9 Trench Facility.................................................................................................. 24

2.6.3 241-Z Settling Tank ....................................................................................................... 24

2.6.4 242 Evaporator Facilities ............................................................................................... 24

2.6.5 Chemical Separations Exhaust Filtration Facilities ........................................................ 25

2.6.6 340, 340-A and 340-B Liquid Waste Handling Buildings................................................ 25

References ........................................................................................................................................26
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Glossary ............................................................................................................................................28

Attachment A – Description of Facilities and Processes .................................................................... 29
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LIST OF TABLES

Table

2.4.1-1 Plutonium nitrate processing tasks ................................................................................

Page

16

2.6.1-5 Exhaust filtration facilities .............................................................................................. 25

1 
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RECORD OF ISSUE/REVISIONS

ISSUE 

AUTHORIZATION 

DATE

EFFECTIVE 

DATE

REV. 

NO. DESCRIPTION

Draft 10/02/2003 00-A New document to establish the Hanford Facilities 

and Processes, Section 2, TBD. Initiated by 

Edward D. Scalsky.

10/02/2003 10/02/2003 00 First approved Issue of Revision 00. Initiated by 

Edward D. Scalsky.

10/02/2003 12/29/2004 00 PC-1 Added two paragraphs required by OGC on page 

7. Made additional changes resulting from the 

comments received at the NIOSH/PACE 

discussion in Richland, WA on April 22, 2004. 

These include the sentence on page 11 regarding 

the 137Cs and 90Sr recovery operations, the date 

change from 1979 to 1978 (page 12), the addition 

of one paragraph on page 14, section 2.3.5, 

discussing the ventilation problems in Building 

303-L, and the two deletions on page 32. Initiated 

by Edward D. Scalsky. 

Approval:

Edward D. Scalsky, TBD Team Leader

Signature on File_____________ _12/09/2004

Judson L. Kenoyer, Task 3 Manager

Signature on File_____________ _ 12/09/2004

Richard E. Toohey, Project Director

Signature on File_____________ _ 12/09/2004

James W. Neton, Associate Director for Science

Signature on File_____________ _12/29/2004
Effective Date: 10/02/2003 Revision No. 00 Document No. ORAUT-TKBS-0006-2 Page 6 of 39

ACRONYMS AND ABBREVIATIONS

Burnup Depletion of fissionable material i.e., 235Pu

CEDE Committed Effective Dose Equivalent

D&D Decontamination and Decommission

EBR II Experimental Breeder Reactor II

FP Fission Products

FFTF Fast Flux Test Facility

GETR General Electric Test Reactor

HTLTR High Temperature Lattice Test Reactor

HTR High Temperature Reactor

kVp kiloVolt potential

MeV Million electron Volts

MW Megawatts

Mint Tritium

MTR Materials Test Reactor

P-10 Tritium

PCTR Physical Constants Test Reactor

PFP Plutonium Finishing Plant

PFPP Plutonium Fuels Pilot Plant

Pile Reactor

Pit A machined part of a nuclear weapon

PNNL Pacific Northwest National Laboratory

PRCF Plutonium Recycle Critical Facility

PRF Plutonium Reclamation Facility

PRTR Plutonium Recycle Test Reactor 

PUREX Plutonium-Uranium Extraction Plant

QA Quality Assurance

QC Quality Control

RECUPLEX Recovery of Uranium and Plutonium by Extraction

REDOX Reduction Oxidation Plant 

RG Rubber Glove

RMA Remote Mechanical A Line

RMC Remote Mechanical C Line 

Slugs Another name for fuel elements

TRIGA Training Research Isotopes, General Atomics Reactor

TTR Thermal Test Reactor 
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“Technical Basis Documents and Site Profile Documents are general working documents that provide 

guidance concerning the preparation of dose reconstructions at particular sites or categories of sites. 

They will be revised in the event additional relevant information is obtained about the affected site(s).

These documents may be used to assist NIOSH in the completion of the individual work required for 

each dose reconstruction.

HANFORD SITE DESCRIPTION AND PROCESSES

In this document the word “facility” is used as a general term for an area, building or group of buildings 

that served a specific purpose at a site. It does not necessarily connote an “atomic weapons 

employer facility” or a “ Department of Energy facility” as defined in the Energy Employee 

Occupational Illness Compensation Program Act of 2000 (42 U.S.C. § 7384l (5) and (12)).” 

Construction of facilities at the Hanford Site, an area of approximately 600 square miles, commenced 

in Mar. 1943 when several major nuclear facilities were started. These included 105-B (Production 

Reactor); 221-T (Separation Facility); 305 (Test Pile); and 313 (Fuel Element Fabrication). The 

production reactors designed to produce plutonium by irradiating metallic uranium, were constructed 

in the 100 Areas located along the Columbia River on the north side of the Hanford site. The 

separation facilities were built in the 200 Areas located on a high plateau in the center of the Hanford 

Site. The fuel fabrication facilities, test reactors and research and development laboratories were built 

in the 300 Area located on the south side of the Hanford Site. The facilities discussed in subsequent 

sections represent those facilities out of more than 500 major facilities where nuclear activities were 

conducted. Note: Throughout this document, where a “*” is included with a date – this indicates either 

there were two dates found (the most claimant-favorable was listed) or the actual year in the decade 

was not found in the documents. Where “UNK” is used, a date has not been found.

2.1 REACTORS

Nine-graphite-moderated, light water cooled reactors were constructed near the Columbia River in the 

Hanford 100 Areas over a period of 20 years commencing in 1943 (Carlisle, 1996). The production 

reactors were used to produce plutonium by irradiating metallic uranium fuel elements with neutrons 

during the fission reaction in the reactor core. Other defense-related radionuclides that were 

experimented with included: irradiation of thorium to produce 233U, irradiation of depleted uranium to 

produce 240Pu, irradiation of neptunium targets to produce 238Pu, and irradiation of americium to 

produce medical grade 238Pu. These nine production reactors designated 100-B, C, D, DR, F, H, KW, 

KE, N were constructed in the B, D, F, H, K, and N Areas, respectively from 1944 to 1963. The first 

eight reactors at Hanford designated 105-B, C, D, DR, F, H, KW, and KE were similar in design 

utilizing a once-through light-water cooling system. The ninth reactor, 105-N, utilized a closed-loop 

light water cooling system. The years of operation and radionuclides of concern are shown in Tables 

A.1-1 and A.1-2 respectively in appendix A. External exposures are primarily due to the presence of 

activation and fission products (FP). During operation, entry was controlled into areas where high 

direct dose rates from photons and neutrons could occur. Internal exposures involving uranium, 

activation products, and fission products, were primarily limited to maintenance and refueling 

activities.

Additionally, there were seven physical testing, research and demonstration reactors operated at 

Hanford over a period of 40 years (Carlisle, 1996). Six Research and Test Reactors, located in the 

300 Area were constructed and operated from 1943 to1978. These include the 305 Hanford Test 

Reactor (HTR), Physical Constants Test Reactor (PCTR), Thermal Test Reactor (TTR), Plutonium 

Recycle Test Reactor (PRTR), Plutonium Recycle Critical Facility (PRCF), and High Temperature 
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Lattice Test Reactor (HTLTR) (Newman, 1989). The Fast Flux Test Facility (FFTF Reactor) was 

constructed and operated from 1980 to 1993 in the 400 Area. The years of operation and 

radionuclides of concern are shown in Tables A.1-3 and A.1-4 in Appendix A. 

2.1.1

The first three reactors (100-B, D, and F) were built in B, D, and F Areas starting in Aug, Nov. and 

Dec. 1943. The B reactor commenced operation in Sept. 1944. The D and F Reactors commenced 

operation in Dec. 1944 and Feb. 1945 respectively. In addition to producing plutonium for nuclear 

weapons, the reactors also produced polonium for use as a neutron source trigger or initiator in the 

weapons. By May 1945 four of the tubes in D Reactor were charged with bismuth slugs for polonium 

production. Construction of DR Reactor, located in D Area, was started in Dec. 1947 with startup 

commencing in Oct. 1950. The H Reactor was constructed in H Area starting in Mar. 1948 with 

startup in Oct. 1949. Construction of C Reactor in B Area commenced in Jun 1951 with startup in Nov 

1952. The KW and KE Reactors were constructed in KW and KE Areas starting in Nov. 1952 and 

Jan. 1953. They commenced operation in Dec. 1954 and Feb. 1955 respectively. These eight 

reactors were graphite moderated and single pass cooled using treated river water. The first three 

reactors (B, D and F) were the same design. The remaining five reactors (DR, H, C, KW and KE) 

were similar in design with the KE and KW reactors differing primarily in the number, size and type of 

process tubes, the size of the graphite stack, and the type of shielding. 

105-B, C, D, DR, F, H, KW, and KE Production Reactors 

The fuel elements were metallic uranium clad with aluminum. In 1960, confinement systems were 

incorporated in the first eight reactors and these reactors were shut down over a period of years 

starting in 1964 and ending in 1971. See Table A.1-1 for shutdown dates.

2.1.2

Construction of 105-N (ninth production reactor) was started in N Area in 1959. The N Reactor design 

was based on the original graphite production reactors. However, it differed substantially from the first 

eight since it incorporated closed-loop cooling and it was the first Hanford reactor to incorporate a 

confinement system in the original design. It was designed to be a dual-purpose reactor (i.e. 

producing both plutonium and steam to be used to generate power). The dual-purpose reactor 

started producing plutonium in Mar. 1964 and electrical power some time later. The N reactor fuel 

was a tube-in-tube design consisting of a metallic uranium core surrounded by a thin zircaloy-2 

cladding. The core consisted of an inner tube enriched to 0.95% U-235 and an outer tube enriched to 

either 0.95% or 1.25% U-235. From 1965 to 1967, tritium was produced at N-Reactor using fuel 

elements manufactured in the 333 facility. The N reactor was shut down in 1987.

105-N Production Reactor

2.1.3

The 305 Hanford Test Reactor (HTR) (also called the Test Pile) located in the 305 Building was the 

first reactor to operate at Hanford starting in 1943. It was operated until 1972 at a very low critical 

level (usually less than 50 W) to test fuel elements, fuel configuration, graphite samples and other 

materials for the production reactors. It was used as a quality assurance tool to house testing of 

samples of each lot of graphite, uranium, aluminum jacketing material, and other materials used in the 

large production reactors. The reactor consisted of a graphite pile and was air-cooled. It was 

removed from the 305 building in 1976-1977. 

305 Hanford Test Reactor
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2.1.4

The Physical Constants Test Reactor (PCTR) started operation in 1954. The 800 W test reactor was 

located in a shielded room in the 305-B building. The mission of the PCTR was to measure reactor 

changes as a result of use of different reactor fuels. Some plutonium contamination that occurred in 

the reactor room as a result of an accident could have been the source of minor internal exposure 

during cleanup. External exposure was negligible since the reactor was located in a shielded 

underground room and operated remotely. Operation was terminated in 1970.

305-B Physical Constants Test Reactor

2.1.5

The Thermal Test Reactor (TTR) started operation in 1954. The 1 KW reactor was located in a 

shielded underground room in the 305-B building and operated remotely. The mission of the TTR 

was to measure thermal impact on fission cross sections. It functioned as an early and small version 

of the HTLTR. External exposure was minimized since the reactor was operated remotely. Operation 

was terminated in the 1978.

305-B Thermal Test Reactor

2.1.6

The Plutonium Recycle Test Reactor (PRTR), located in the 309 building, started operating in 1960. 

The PRTR was a 40 MW heavy-water-cooled and heavy-water-moderated reactor. The reactor was 

chosen for a large fuels diversification program known as the Plutonium Fuels Utilization Program. 

Tests were to be performed with various mixed oxide fuels using various methods of manufacture. As 

an example, tests were performed on a variety of powdered and pelletized fuels using plutonium oxide 

blended with uranium oxide and other metallic oxides. The fuel was a nominal 96% depleted uranium 

oxide and 4% plutonium oxide powder that was vibration compacted within the fuel pin. External 

exposure was minimized as a result of the remote operation and the shielding. Maintenance 

operations resulted in external exposure from activation and fission products. A high extremity 

exposure occurred when a worker picked up an irradiated steel pin. Tritium (3

H) oxide was the 

principal internal exposure contaminant during normal operation. This whole body exposure was 

added into the external whole body dose summary (See sections 5 and 6 - Internal and External 

Dosimetry). The reactor was shutdown in 1969 after an accident resulted in contamination in the 

reactor. A sample of the contamination showed the major contaminant was 95Zr/Nb. Other 

contaminants included 60Co, 103Ru, 106Ru, 106Rh, 140Ba/La, 141Ce, 144Ce, and 144Pr. 

309 Plutonium Recycle Test Reactor

2.1.7

The Plutonium Recycle Critical Facility (PRCF), which was located in the 309 building, began 

operating in 1962. Tests were conducted in the PRCF to determine which geometrical arrangement 

of fissionable materials would work in a reactor. It was shut down in 1976.

309 Plutonium Recycle Critical Facility

2.1.8

The High Temperature Lattice Test Reactor (HTLTR) was a 2 MW test reactor built in the 318 building 

in 1967 with operation commencing in 1968. The reactor consisted of a graphite cube located in a 

large shielded room and was operated at elevated temperatures up to 10000 C. The mission was to 

advance reactor physics technology. It was shut down in 1971 after 3-years of operation spanning 4 

years during which time they operated with six different cores (i.e. three - 233U, one - 235U, one - 238U, 

and one - 239Pu). Since the reactor was heavily shielded and operated remotely, external exposure 

was at background levels. There were no contamination incidents so internal exposure was 

318 High Temperature Lattice Test Reactor
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negligible. The building and the shielded room were modified in the early 1980’s and used as the new 

Hanford Radiation Calibration Facility (see section 2.5.8).

2.1.9

The Fast Flux Test Facility (FFTF) was a 400 MW sodium-cooled test reactor located in the 405 

building. It began start-up operations in Feb. 1980 in support of the fast breeder reactor program. 

The FFTF was used to test the irradiation of fuels and materials that would be used in a breeder 

reactor and to perform long-term testing of reactor components and systems. It was also used for the 

production of Medical Isotopes and research on space power systems. The external and internal 

exposures were at background levels. The facility was shutdown in 1994 and currently is waiting 

D&D. 

405 Fast Flux Test Facility

2.2 FUEL SEPARATIONS FACILITIES

Seven separation facilities, B Plant, T Plant, U Plant, Reduction/Oxidation (REDOX), PlutoniumUranium Extraction Facility (PUREX), UO3, and C Plant, were constructed and operated in the 200-W 

and 200-E Areas from 1943 to 1993. The tritium processing facility was operated from 1949 to 1955 

in the 108-B building located in the 100-B Area. Natural uranium and thorium fuel elements and 

lithium-aluminum (Li-Al) target elements were irradiated to produce Pu-239, U-233, and tritium, 

respectively. The spent reactor fuel was transported to the 200 Areas (i.e. Separations Areas) for 

processing. Initially spent fuel was stored in the reactor storage basins and the 212-N, 212-P, and 

212-R buildings in the 200-N Area prior to processing in the fuel separations facilities (e.g.221-B 221-

T, REDOX and PUREX). The irradiated lithium-aluminum target elements were transferred to the 

108-B building, 100-B Area for processing. Irradiated thorium fuel elements were processed in the 

PUREX Plant to recover U-233 in two separate campaigns that occurred in 1966 and 1971. External 

exposures were primarily high-energy betas and photons in the separations facilities associated with 

fission products (FP). Internal exposures, primarily associated with contamination incidents, could be 

due either to FP and/or plutonium. The years of operation and radionuclides of concern are shown in 

Tables A.2-1 and A.2-2 respectively in Appendix A.

2.2.1

Three large canyon buildings 221-T, 221-B and 221-U were originally constructed in the 200 Area in 

1943 (?) to chemically separate plutonium from uranium and fission products. These buildings were 

massive rectangular canyons that housed the chemical separations equipment. This equipment was 

operated remotely to provide protection to the workers from the high radiation fields. The T Plant was 

started up Dec.1944 and shutdown Aug. 1956 while B Plant started up in Apr. 1945 and shutdown in 

Oct. 1952. Since the capacity was not needed, the start up of U Plant was delayed until 1952 when 

the mission was changed (see section 2.2.4). The 221-T and 221-B buildings known as the T and B 

Plants utilized a bismuth phosphate precipitation batch process to separate plutonium from the 

uranium and fission products after the aluminum jackets were dissolved in sodium hydroxide solution 

and the uranium metal slugs were dissolved in nitric acid. The dilute plutonium solution from T and B 

plants was transferred to the 224 Concentration Buildings (e.g.224-B and 224-T) located behind each 

canyon building where the product was purified, the product volume was reduced and the carrier was 

changed from bismuth phosphate to lanthanum fluoride. The final plutonium product was 

concentrated in the 231-Z Building. The B Plant was closed in 1952. Starting in 1954 and 1955, the 

processing capacity was increased in both facilities. The 221-B and 221-T plants were not restarted 

because of the success of PUREX.

Original Fuel Separations Facilities 
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In March 1956 221-T was converted to perform equipment decontamination (WHC-MR-0452). In 

1959 the 2706 T Decon Annex was added to the 221-T building to enhance the equipment 

decontamination capabilities, particularly pieces of equipment too large to take into T-Plant. The TPlant is still in operation.

The B Plant facilities were modified in 1968 to remove 90Sr and 137Cs from high-level wastes from the 

single and double-shell waste tanks. This was in support of a new mission “to isolate the longer-lived 

fission products by fractionalization for storage in a safer form and to return the short-lived fractions to 

underground storage and ultimate solidification”. The purified 90Sr and 137Cs solutions were 

transferred to the 225-B Waste Encapsulation Storage Facility (see section 2.2.6). The 137Cs and the 

90Sr recovery operations were at the B Plant were completed in September, 1983 and February, 1985 

respectively.

2.2.2

Construction of the REDOX Facility (S Plant) was started in 1949. In Jan. 1952, REDOX started up in 

the 200-W Area utilizing the REDOX (i.e. reduction/oxidation process) as a replacement for the 

bismuth phosphate process. This new REDOX process differed from the process used in B and T 

Plants in that with the exception of the metal dissolving and feed preparation steps, all steps were 

continuous rather than batch. The new process, which involves solvent extraction utilizing hexone, 

resulted in improved throughput, recovery of uranium, improved recovery of plutonium and a decrease 

in the amount of high-level liquid waste generated. The aqueous plutonium product was concentrated 

for shipment to the plutonium finishing facilities. In 1950* processing of irradiated 94 metals (0.947 

enrichment) was assigned to REDOX. Shutdown of this facility occurred in Dec. 1967. 

202-S REDOX Plant

In an effort to enhance production capacity, the 233-S building was constructed in 1957 to contain the 

third and final concentration cycle at 202-S. This building was shut down in July 1967 after a major 

fire resulted in extensive plutonium contamination. The facility is currently undergoing 

decontamination and decommissioning.

2.2.3

Construction of the PUREX Facility (A Plant) commenced in 1953. It was started up in Jan. 1956 

utilizing the plutonium-uranium extraction process (WHC-MR-0437: Marceau, 2002). The PUREX 

process was an organic solvent extraction process that utilizes tributyl phosphate in kerosene instead 

of hexone, nitric acid as a salting agent, pulse column contractors, and nitric acid recovery by 

distillation. The nominal design capacity was 8.33 short tons uranium per day as opposed to 2.5 for 

the REDOX Plant. In 1955 due to the development of more restrictive 131I release limits the 293-A 

facility was constructed between PUREX and the 291 A stack. In 1958 PUREX initiated 237Np 

recovery activities. Equipment was added in 1962 to permit continuous recovery of 237Np. In 1963 the 

processing of e-metal fuel containing 235U enriched to 1.75 %. The processing of irradiated powdered 

thorium oxide targets to recover 233U commenced in 1965 and 1966. In 1970 the targets were 

changed to pelletized thorium oxide. The PUREX Plant was shutdown in June 1972 and restarted in 

Nov. 1983. During the shutdown a new process was added to convert plutonium nitrate to plutonium 

oxide. It was started-up and shutdown several times between 1983 and 1992 with final closure 

announced in Dec. 1992.

202-A PUREX Plant 
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A 500-foot railroad tunnel that extended south from PUREX was designed and constructed to permit 

the remote storage of highly contaminated processing equipment. In 1964 a new 1500-foot tunnel 

was added to PUREX to accommodate the storage of additional equipment. 

2.2.4

As noted in section 2.2.1 above, the U Plant was constructed in 1943. The U Plant startup was 

delayed until Mar. 1952 when it was reconfigured for use in recovering uranium from process waste. 

The high-level liquid wastes from the B and T Plants, which were stored in single-shell tanks, 

contained large quantities of uranium. The uranium bearing sludge from the underground storage 

tanks was pumped to process vessels in the U Plant. The sludge was dissolved in nitric acid and the 

uranium extracted by solvent extraction using tributyl phosphate in kerosene. The recovered Uranium 

was shipped off-site for reuse. The U Plant was shutdown in Jan. 1958.

221-U U Plant

2.2.5

The 224-U Bulk Reduction Building (known as UO3 Plant) was constructed in the 1940’s. In 1951 it 

was converted to process the liquid uranium nitrate solution from U Plant to produce a powdered 

uranium oxide (UO3) using a calcination process. It was started up in Jan. 1952. The product was 

shipped off-site for reuse. A major addition (224 UA) was added to the UO3 Plant in the fourth quarter 

1956 to house 3 new calciners. It was shutdown in 1972 and opened again in 1983 (there were 17 

start ups and shutdowns between 1984 and 1992 corresponding to activities at PUREX) and was 

deactivated in the summer of 1993. 

224-U UO3 Plant 

2.2.6

The 225-B Waste Encapsulation and Storage Facility is located in the 200-E Area near the 221-B 

Building. In 1978 as a part of the effort to “isolate the longer-lived fission products from high-level 

waste tanks the 137Cs and 90Sr solutions were transferred to the 225-B from 221-B for conversion to a 

solid, encapsulation, and storage (see section 2.2.1 for more details). A large amount of 

encapsulated 137Cs and 90Sr was stored in the 225 Building as a result of this operation. External 

exposures that were associated with the high- energy photons and beta particles from the large 

quantities of strontium and cesium processed were minimized as a result of remote operation. 

Internal exposures from the operation were minimal due to the remote operation.

225 Waste Encapsulation and Storage Facility

2.2.7

The Hot Semiworks (also known as hot sloppy) started up in 1949 as a pilot plant (Marceau, 2002) to 

develop REDOX reprocessing technologies. The REDOX process was tested in the 201-C 

reprocessing pilot plant starting in 1952, with work continuing until 1954. In 1954, the C Plant was 

switched to being the PUREX process pilot plant and was shutdown in 1956. In 1962, C Plant was 

restarted as a pilot plant for the recovery of Cs and Sr from fission product waste. The C Plant was 

retired in 1967.

201-C C Plant or Hot Semiworks

2.2.8

The 108-B building (known as P-10 Plant and also the Mint Works) located in the 100-B Area started 

in Aug. 1944 to extract tritium. The Li-Al (for a short period lithium fluoride) target elements were 

transferred to the 108-B facility after irradiation in one of the production reactors. Tritium extraction 

operations were performed intermittently between Aug. 1949 and 1955. The 108-B tritium operation 

was terminated in 1955. The Li-Al target irradiation was continued with transportation to an offsite 

108-B Tritium Extraction Facility
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facility for processing until Sep, 1964. A total of 10.6 kg of tritium was produced at Hanford. Internal 

exposure was related to tritium (3

H). This whole body exposure was added to whole body dose 

summary (See sections 5 and 6 - External and Internal Dosimetry).

2.3 FUEL FABRICATION FACILITIES

The Hanford Fuel Fabrication facilities described in subsequent sections were built and operated in 

the 300 Area from 1944 to 1988. These include three fuel fabrication facilities, 313 (Uranium Metal 

Fuels Fabrication), 314 (Uranium Metal Extrusion), and 333 (Fuel Cladding) buildings, and two 

support facilities, 303 (Uranium Storage and Oxide Burner), and 306 (Reactor Fuel Manufacturing 

Pilot Plant). External exposures were related to betas and photons associated with uranium. Due to 

the pyrophoric nature of uranium turnings and chips, internal exposure was related primarily to 

inhalation of uranium. The years of operation and radionuclides are shown in Tables A.3-1 and A.3-2 

respectively in Appendix A.

2.3.1

The aluminum-clad fuel for the first eight production reactors was produced in the 313 Building 

starting in Mar. 1944 (Key dates doc says Dec. 1943). Natural uranium billets or bars were heated to 

a red heat and shaped into long rods using an extrusion press (see 314 building below). These were 

cut into shorter lengths called slugs using a turret lathe. After receiving a finish cut in another turret 

lathe, the slugs were degreased using nitric acid. The cleaned slugs were dipped in a succession of 

molten baths (i.e. triple-dip method) and pushed into an aluminum can. An aluminum cap was 

pushed into the can and the top edge of the cap was welded to the can. Bismuth fuel targets were 

fabricated in the 313 Building beginning in 1944. These were irradiated in the production reactors to 

produce 210Po (used as an initiator in the earliest atomic weapons). Lead-cadmium fuel rods, welded 

into non-bonded aluminum cans, were produced for use as “poison” elements for the production 

reactors. Lithium targets were manufactured for tritium production from 1949 to 1952 and again from 

1965 to1967. In the 1950’s, production reactor fuel changed from natural uranium to low enriched 

uranium (LEU). In Mar. 1954 a new, simpler, canning method involving a lead-dip process was 

initiated to replace the old method. All uranium scrap and waste from these processes was salvaged 

as uranium oxide and shipped off the Hanford site. In 1955 the fuel production facilities were 

expanded to produce the fuel for the K Reactors. In Jan. 1971 the manufacture of aluminum-clad fuel 

used in the first six reactors was terminated. After that time, only N-Reactor fuel was manufactured

(see section 2.3.3 below). 

313 Uranium Metal Fuels Fabrication Facility

2.3.2

The 314 building was known as the Press Building, Metallurgical Engineering Laboratory and later as 

the Uranium Metal Extrusion Facility. Operation of the 314 Press Building was commenced in July 

1944 with a mission to process raw uranium billets into extruded rods that were suitable for fabrication 

into fuel elements. In early 1945, a 1000-ton large extrusion press was installed in the 314 building. 

After installation, the 313 and 314 buildings assumed all of the fuel manufacturing responsibilities for 

Hanford. An additional mission, uranium scrap recovery, was started in 1945. An oxide burner was 

operated outside the building in 1946. A milt plant started operation in December 1947. Uranium 

scraps were mixed with UF4 (green salt) and calcium chips. Conversion to metal took place in a 

reduction furnace (HS300AHD). The high air contamination that occurred frequently, involved a 

highly soluble, class F material. The milt plant was shut down in 1954. The uranium billets were 

extruded into rods, outgassed and straightened in the 314 building. The extrusion process was 

terminated in 1948 the fuel element process was changed to use rolled uranium rods. An oxide314 Uranium Metal Extrusion Facility
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burner was installed in the 314 building in 1946. In1950, a rolling mill was installed in the 314 building 

in order to fabricate Hanford fuel elements on site. The building was deactivated in 1971. 

2.3.3

The N Reactor fuel was produced in the 333 building starting in 1961. The N Reactor fuel elements 

used a tube-in-tube design consisting of slightly enriched uranium inner and outer cores and thin 

zircaloy-2 cladding. The production process included: cleaning of the uranium billets and Zirconium-2 

cladding shells; billet assembly and preheating; extrusion; fuel element shaping and cleaning; and 

welding of the end cap. In 1965 -1967 outer driver fuel elements were produced in support of tritium 

production at N Reactor. The Li/Al inner target element was manufactured in the 3722 Area Shop. 

The 333 building was placed on standby in 1988 when the manufacture of N Reactor fuels ceased. 

333 Fuel Cladding Facility

2.3.4

Construction on the 306 building was completed in 1956 and it began operation in May 1957 as a pilot 

plant for reactor fuel production. The 306 building had a complete fuel element canning line with the 

exception of autoclaving. The co-extrusion process was developed in the 306-E building in the early 

1960’s in support of the N Reactor fuel needs. This facility was shut down in 1984*.

306 Reactor Fuel Manufacturing Pilot Plant

2.3.5

Ten buildings (303-A, B, C, D, E, F, G, J, K, and M) were built over a period of years from 1944 

to1983 to store fresh uranium, chemicals, uranium scraps and plutonium. Uranium was shipped to 

Hanford in the form of metal billets. The metal billets were moved to the 303 Fresh Metal Storage 

buildings where they were inspected, entered into accountability records and held for processing. 

Building 303-L is another building not mentioned above, however, Building 303L was a small building 

that was constructed in 1961 to burn uranium metal scraps to an oxide form that would be suitable for 

shipment to the Feed Materials Production center (FMPC) for recovery. Burning was stopped in 1971 

due to the use of unconventional burning vessels (two cement mixers lined with concrete) and poor 

ventilation. These two factors combined to produce airborne contamination readings that frequently 

exceeded the then-current HW maximum permissible concentration (MPC) of 2 x 10-12 μCi/mL for 

unrestricted areas and 6 x 10-11 μCi/mL for restricted areas (see WHC-MR-0388, Past Practices 

Technical Characterization Study-300 Area-Hanford Site, M. S. Gerber, December 1992). Building 

303L was shut down in 1971 and the building removed in 1976. In 1983, the new Oxide Burning 

Facility (303-M) was placed into operation at the same site. It operated from 1984 to 1987. In 1970*, 

the 303-C building was utilized by PNNL for the storage of plutonium and americium. A pressurization 

of one of the sealed metal storage cans resulted in the spread of plutonium contamination and the 

subsequent shut down of the building until cleanup. It currently is being used for other purposes.

303 Facilities Fresh Metal Storage Facilities

2.4 PLUTONIUM FINISHING FACILITIES

Two plutonium finishing facilities, 231-Z (Plutonium Isolation Building) and 234-5Z (Plutonium 

Finishing Plant Complex) operated at Hanford from 1945 to present. The latter is still involved in 

plutonium stabilization efforts as a part of the Hanford cleanup program. Both of these complexes are 

located in the 200-W Area. As noted in section 2.4.3 below, the Plutonium Finishing Plant Complex 

consists of several buildings including: the 234-5Z that involves several processes (i.e. Rubber Glove 

line, Remote Mechanical A line, Remote Mechanical C line, and RECUPLEX); the 232-Z Incinerator; 

the 236-Z Plutonium Reclamation Facility; and the 242-Z Waste storage Facility. External exposures 
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were related to radiation fields primarily from plutonium low-energy x-rays and spontaneous fission 

neutrons. During the early years of plutonium finishing operations, essentially all photon radiation 

resulted from plutonium x-rays. Later, 60 keV gamma radiation from 241Am contributed significantly 

to worker exposure. Neutron radiation was substantially elevated in part of the finishing operation 

where alpha radiation from plutonium produced neutrons as a result of the α/η reaction with fluorine. 

Although relatively few Hanford personnel were involved in plutonium finishing, these facilities 

provided the majority of personnel exposures to neutron radiation. Internal exposures were related to 

contamination incidents involving americium and plutonium. These exposures occurred by inhalation, 

absorption and injection (i.e. wound sites). The years of operation and the radionuclides of concern 

are listed in Tables A.4-1 and A.4-2 respectively in Appendix A.

2.4.1

The 231-Z, Plutonium Isolation Facility began the plutonium finishing process in Jan. 1945 when the 

first plutonium nitrate solution was received. Adding hydrogen peroxide to separate the plutonium 

from the nitrate solution purified plutonium. Until July 1949 the plutonium was dried and shipped 

offsite for further refining. When the 234-5Z (see Table A.4-1) went into operation, in July 1949, the 

refined product was shipped offsite for plutonium finishing. Chemical processing was continued in the 

231-Z building until 1956 when all steps were transferred to the 234-5Z building. In 1956 the 

plutonium metallurgy developmental laboratory was moved from 234-5Z to 231-Z. The 231-Z building 

continued to be used for metallurgical research on plutonium and alloys until 19UNK. Studies on the 

use of U-233 were also performed in this building.

231-Z Plutonium Isolation Facility
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Table 2.4.1-1. Plutonium nitrate processing tasks.

Task Name Function

I Purification, Oxalate Precipitation, Wet 

Chemistry, or Feed Production

Precipitate the plutonium-nitrate feed solution with Oxalic 

acid and other agents;

II Hydrofluorination or Dry Chemistry Diffuse hydrogen fluoride gas through the precipitate;

III Reduction Combine the plutonium tetrafluoride with calcium; Fire at 

high temperature until fused into a metallic plutonium 

chunk called a button;

IV Casting Render plutonium buttons into pits;

V Machining Machine the pit to specified dimensions;

VI Cleaning Chemically clean the pit;

VII Coating Coat the pit for radiation safety; and

VIII Final Inspection Inspect the pit for correct specifications.

2.4.2

The 234-5Z building was used starting in July 1949 for plutonium finishing operations. The Plutonium 

Finishing Plant (PFP) Complex consists of the 234-5Z building including several production areas and 

several other buildings discussed in subsequent sections. The building is currently under going D & 

D.

234-5Z Plutonium Finishing Plant Complex

2.4.2.1 Rubber Glove Line

The Rubber Glove (RG) Line in the 234-5Z building was used starting in July 1949 for processing 

plutonium nitrate. All of the tasks listed in the following table with the exception of task 1 were 

performed in the RG line. 

In Dec. 1949, production was temporarily halted to make repairs to solve operational and mechanical 

problems. It was restarted early in 1950. The RG line was placed on standby at the end of Mar. 1953 

with the exception of the coatings units that were shutdown in May 1953. In 1955, equipment from 

Tasks I and II was removed and buried. A majority of the remaining process equipment was removed 

from the RG line in early 1957 in preparation for installation of the new RMC line. 

2.4.2.2 Remote Mechanical A Line

The Remote Mechanical A Line (RMA) was designed to reduce worker radiation exposure by 

automating the process described in the above table. In Mar. 1952, the RMA line began to process 

the plutonium (IV) oxalate that was prepared in 231-Z. By Mar. 1953 the RMA line began handling all 

of the plutonium work. In July 1954 a fire in the RMA line stopped fabrication of pits for three weeks. 

The RMA line was taken completely out of service in 1964. The weapon fabrication portion of the 

RMA line was removed (see RMC line below) in Mar. 1966. In Sept. 1967, a glove box in the RMA 

line was reactivated in order to grind plutonium-aluminum scraps into turnings suitable for plutonium 

recovery. In 1968, Tasks I-III of the RMA line were cleaned out and reactivated to participate in 

expanded programs for commercial (i.e. non-defense) nuclear development and experiments such as 

oxides for the Hanford Fast Flux Test Facility. In 1984, it was decided to keep the RMA line in 

standby status. It was never operated again. 

2.4.2.3 Remote Mechanical C Line

The Remote Mechanical C Line (RMC) began processing plutonium nitrate feed in Oct. 1960. In1962 

a project was undertaken to install ten-inch thick water-filled shielding tanks to substantially reduce 
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the neutron exposure to operators. Because of fire(s) in other facilities and the RECUPLEX criticality, 

other safety improvements including a new criticality alarm system, a new air sample counter and a 

new paging system were installed in 1963 and 1964. By 1964 the RMC line was being used for a bulk 

of the metal processing and the throughput was increased substantially. As a result of a decision to 

concentrate weapon fabrication work at Rocky Flats, the fabrication portion of the RMC line was 

removed in Mar. 1966. The line continued to operate on a mixed schedule for the next several years 

producing weapons-grade plutonium and fuel-grade plutonium and oxides. As a result of the 

explosion in the americium recovery process in the 242-Z facility, the RMC line was shutdown in 

1976. After preparing to restart production of weapons-grade components, the RMC Line restarted in 

July 1985. The RMC line was permanently shut down in May 1989.

2.4.2.4 Recovery of Uranium and Plutonium by Extraction Facility 

The Recovery of Uranium and Plutonium by Extraction (RECUPLEX) process facility began in July 

1955, over the next few years; the facility was heavily used with increasing equipment failures and 

increasing radiation levels. In Feb. 1960, RECUPLEX was temporarily shut down to permit an 

extensive cleanup of hoods and operating equipment. In Apr. 1962, a criticality accident resulted in 

widespread contamination throughout the RECUPLEX room and in high external exposures to several 

workers. In May 1962 the Atomic Energy Commission decided to deactivate that section of the 234-

5Z facility. 

2.4.2.5 232-Z Incinerator Facility

In Jan. 1962, the 232-Z Incinerator began processing miscellaneous solid wastes to recover small 

quantities of plutonium. The process involved incineration of combustible materials, leaching noncombustible materials in nitric acid and wet leaching of ash. The recovered plutonium was transferred 

to RECUPLEX and later the Plutonium Reclamation Facility. In 1973 the 232-Z incinerator was shut 

down.2.4.3.6 236-Z Plutonium Reclamation Facility

The 236-Z Plutonium Reclamation Facility (PRF) was placed into operation in May 1964 to recover 

plutonium from liquid waste generated in the plutonium finishing plant operations. Using a solution of 

tributyl phosphate diluted with carbon tetrachloride, metal nitrates and other wastes were stripped 

from a plutonium bearing feed. Nitric acid-hydroxylamine solution was then used to separate the 

plutonium as a nitrate. The plutonium nitrate was then ready as a feed for the RMA and RMC lines. 

In Dec. 1975, 236-Z was shut down for maintenance upgrades and reviews of criticality safety 

specifications and procedures. In 1976 the 236-Z operated for only a short time after restart until the 

explosion in 242-Z resulted in widespread, high levels of 241Am contamination in the work area. This 

accident resulted in the shutdown of the entire Plutonium Finishing Complex in April1976. Any 

internal exposures would be the result of an accident.

2.4.2.6 236-Z Plutonium Reclamation Facility

The 236-Z Plutonium Reclamation Facility (PRF) was placed into operation in May 1964 to recover 

plutonium from liquid waste generated in the plutonium finishing plant operations. Using a solution of 

tributyl phosphate diluted with carbon tetrachloride, metal nitrates and other wastes were stripped 

from a plutonium bearing feed. Nitric acid-hydroxylamine solution was then used to separate the 

plutonium as a nitrate. The plutonium nitrate was then ready as a feed for the RMA and RMC lines. 

In Dec. 1975, 236-Z was shut down for maintenance upgrades and reviews of criticality safety 

specifications and procedures. In 1976 the 236-Z operated for only a short time after restart until the 

explosion in 242-Z resulted in widespread, high levels of 241Am contamination in the work area. This 

accident resulted in the shutdown of the entire Plutonium Finishing Complex in April1976. 
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2.4.2.7 242-Z Waste Treatment Facility

The 242-Z Waste Treatment Facility began operation in 1963 to recover plutonium from aqueous 

waste streams from the PFP. An americium-241 recovery process was installed in a glove box in 

242-Z and began operation in May 1965. The recovery process was converted from a batch to a 

continuous process in 1969. In April 1976, the 242-Z facility was shut down as a result of a strike. In 

August 1976 during restart of the americium recovery process, an explosion occurred in a cation ion 

exchange column containing approximately 100 grams of americium-241. This resulted in substantial 

Americium internal exposure. As a result, the 242-Z facility was permanently closed. Doors into the 

operating area were welded shut and the facility currently is waiting D&D efforts.

2.4.3

Several plutonium storage facilities were constructed at the PFP (234-5Z) starting in 1949. These 

include: 2736-Z, 2736-ZA, and 2736-ZB built in 1971, 1977, and1982 respectively. There were 12 

vault or vault-type rooms in the PFP. These vaults contained 93 percent of the Hanford Site’s

unirradiated plutonium items and 92 percent of the total Hanford unirradiated plutonium inventory in 

July 1994 at the time the Plutonium Vulnerability Study (DOE, 1994) was performed. External 

exposure in the vault rooms from low-energy photons and neutrons occurred during periodic inventory 

and inspection activities. Internal exposure was minimal since there were no routine activities that 

involved opening the storage containers. Internal exposure would have been a concern in the event 

of an incident that voided the containment afforded by the storage containers. Stabilization efforts 

were completed in Aug. 2003.

Plutonium Storage Facilities

2.5 RESEARCH, DEVELOPMENT, AND TESTING FACILITIES

The 21-major Research, Development, and Testing Facilities at Hanford were located in the 100, 200 

and 300 Areas. Construction of these started in 1944 with the last one completed in 1977. These 

facilities were built to support the development and testing of new processes, materials, and 

equipment. In some instances the facilities were used for several different purposes throughout their 

operating life. Therefore, the potential exposures are dependent on the processes involved and the 

mission/process at any given time. The years of operation and the radionuclides of concern are listed 

in Tables A.5-1, A.5-2 and A.5-3 in Appendix A. 

2.5.1

The 108-F building was remodeled in 1949 to provide laboratory and office space for the Hanford Site 

Biology Program. The facility was used to perform radiation effects studies on plants, animals and 

fish in support of Hanford plant operations. Studies involved many radionuclides including 90Sr, 131I, 

238U, and 239Pu. The building was expanded in 1953 and again in 1962 to provide additional space for 

biological experiments. The facility was closed in 1977 when the Biology Program moved to the 331 

building (see section 2.5.16 below). 

108-F Biology Facility

2.5.2

The Critical Mass Laboratory was originally operated in the 120 building located near the100-F Area 

starting in Apr. 1950. This laboratory was used for nuclear physics R&D studies of plutonium 

solutions and solids to avoid the accidental occurrence of a criticality event in an operating facility. In 

Nov. 1951, a substantial spread of contamination occurred as a result of an experiment performed 

with a plutonium solution. In Dec. 1950, spontaneous ignition of rags soaked with nitric acid occurred 

during cleanup. While the metal building was not destroyed, the facility was permanently closed due 

120 Critical Mass Laboratory Facility
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to the extensive plutonium contamination. The site was subsequently decontaminated and 

decommissioned. 

2.5.3

The 209-E Critical Mass Laboratory was placed into operation in July 1961. The laboratory, located in 

a room shielded by at least 3 ft of concrete, included a mixing room with a glove box and mixing hood 

and a control room from which critical mass physics experiments were remotely conducted. Both 

239Pu and 240Pu was used in the criticality studies. As a result external exposures were minimized. 

Internal exposures were related to contamination incidents involving plutonium. This facility was shut 

down in 1986* after a series of occurrences involving criticality safety specifications. 

209-E Critical Mass Laboratory

2.5.4

The 222-B laboratory was opened in the 222-B building in 1945 to perform process or research and 

development radiochemical operations in support of irradiated fuel-reprocessing facilities. One of the 

main functions was to test the solution samples from the 221-B and 224-B buildings at various steps 

in the separations process. External and internal exposures were associated with the FP and 

plutonium in the process samples. It was shutdown in ~1975. This facility was converted to office 

space.

222-B Laboratory

2.5.5

Construction of the 222-S laboratory was started in 1949. The laboratory contains laboratories and 

shielded cells that were used to provide analytical services in support of process control of REDOX, 

B-Plant and 242-S and 242-A Evaporators. It currently is used for analytical operations in support of 

waste management and environmental control processes. External exposures were related primarily 

to FP in process samples. Internal exposures would primarily be associated with samples associated 

with the separations plants process samples (e.g. FP and plutonium). In the early 1960’s, some work 

was performed with 147Pm. Internal exposures were primarily related to contamination incidents. 

222-S Laboratory

2.5.6

The 222-T Laboratory was the first to operate commencing in 1944 in support of the separation 

process in 221-T and supporting work in 224-T. External and internal exposure potential was similar 

to that in 222-B above. It was shutdown in 1980*. Fire protection was shutoff in 1986. 

222-T Laboratory 

2.5.7

The Plutonium Fuels Pilot Plant (PFPP) was constructed in the 308 building in1960 to perform 

research and development on fuel elements used in the PRTR. In the mid 1960’s the PRTR fuel work 

was terminated. In the late 60’s, neptunium-aluminum alloy fuel target elements were produced for 

use in N Reactor for a Pu-238 production run. A high bay area was added to the building in 1971. A 

147Pm contamination incident occurred in the 308 building in 1971. From 1977 to 1991 the facility was 

used for the production of FFTF fuel elements. The 308-A annex was added to the Plutonium 

Fabrication Pilot Plant in 1979 to accommodate additional plutonium fuels work. A 250 kW Training 

Research Isotopes, General Atomics (TRIGA) reactor was installed in the annex in the late 1970’s to 

perform neutron radiography, a feature of the QA testing program. During its operation, the building 

experienced many incidents involving the loss of control of radioactive materials, primarily plutonium. 

Most of these were contained within usually one laboratory and in adjacent corridors. Glove box fires, 

explosions, and/or ruptures were the most frequent cause of contamination. Improperly sealed 

308 Plutonium Fuels Pilot Plant
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irradiated sample containers were another common cause. These incidents occasionally resulted in 

internal exposures. The 308 facilities were deactivated in 1990*.

2.5.8

The 318 building was originally built in 1967 to house the HTLTR reactor (see section 2.1.8). In the 

early 1980’s, the reactor was removed and the heavily shielded10-meter cube reactor cell was 

converted to a free-in-air calibration facility that contains a large 252Cf neutron source (109 n/s) and a 

large 137Cs photon source (~100 Ci) that were used for dosimeter calibration. A shielded facility was 

built in the basement to house a high-level 60Co source (~1kCi) to create accident dose rate levels 

and three 300 kVp X-ray machines. The calibration laboratory commenced operation in 1983. Three 

major additions were constructed in 1985, 1987 and 1989. The first contained four source wells that 

held two 137Cs, one 60Co, and one 252Cf sources used for instrument calibration. The second addition 

houses instrument testing and repair laboratories and the last addition provided office facilities for the 

staff. As a result of the shielding, isolation, remote operations, and operating procedures, external 

exposures were minimized. Internal exposures were negligible. The facility is still in operation.

318 Radiological Calibration and Development Laboratory

2.5.9

The Low-Level Radiochemistry Laboratory was built in the 320 building in 1966. The original mission 

was to house analytical chemistry services and provide plant support involving low-level and nonradioactive samples. The 320 Building currently provides a low-level radiochemistry facility in which 

very sensitive radiochemical analysis, sample preparation, and methods development can be 

performed. External and Internal exposures were minimal. The facility is still in operation.

320 Low-Level Radiochemistry Facility

2.5.10

The 321 Separation Facility (Cold Semi-Works) was built in 1944 with a mission to be used as a cold 

(i.e. non-irradiated material) pilot plant to test the bismuth phosphate chemical reprocessing methods 

and equipment and to study problems as the 221, 224, and 231 buildings were being constructed. In 

late 1944, it was decided to add a laboratory for work with small amounts of solutions containing 

several tenths of a curie to a curie of radioactive materials (Gerber, 1993; HS300AHD). Soon after 

start-up, the 321 building assumed a mission to demonstrate the effects of proposed process changes 

on decontamination factors in the 221, 224, and 231 buildings, conducting isotope separations, and 

experiments on small-irradiated samples. In 1949 321 was used to develop the REDOX process. 

Tests using radioactive materials were discontinued after 1949. The 321 building was used in 1953 to 

perform a cold test of the PUREX process. Pilot scale tests of the U-Plant recovery process were 

conducted in 1955. Isotope Campaigns were conducted in the 1960’s using tracer-levels of 

90Sr,137Cs, 144Ce,147Pm, and 237Np. Primary contamination in the facility was due to thorium and 

uranium. External and Internal exposures were minimal. The building was deactivated in 1988.

321 Separation Facility

2.5.11

The Chemical and Materials Engineering Laboratory began operation in 1966 to provide research and 

development studies in support of the PRTR operations. It was used first as a fuel recycle pilot plant 

by housing chemical reprocessing and metallurgical examination capabilities used for PRTR fuel 

elements. It consisted of two groups of large shielded cells used for both radiochemical and 

metallurgical studies. The chemistry cells consisted of four cells connected to an air lock where 

studies of various processes for solidifying high-level liquid waste were performed. It was used in 

conjunction with the 325-A hot cells to perform studies on solidification of high-level liquid waste (i.e. 

Nuclear Waste Vitrification Project) from processing irradiated fuel elements from commercial 

324 Chemical and Materials Engineering Laboratory
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reactors). A special underground liquid waste pipe line connected the hot cells in 324 and 325-A. 

Most recently, it was used as a Waste Technology-Engineering Laboratory. Since most of the work 

was performed in hot cells, external and internal exposures were minimized. The 324 building is 

currently undergoing decontamination and decommissioning activities.

2.5.12

The 325 building was completed in 1953 to permit multi-curie level chemical development work in 

support of production and process improvement (Marceau, 2002; HS300AHD). A high-level 

radiochemistry wing, 325-A, was placed into operation on the east side of the building in 1959/1960. 

It included three large hot cells for isotope research activities. This included separation and 

concentration of 90Sr, 90Y, 131I, 137Cs, 144Ce147Pm, 210Po, 238Pu, 239Pu, and 244Cm for special programs. 

The 147Pm was used in the manufacture of heat sources starting in 1966. The 210Po work started in 

June 1972 and was terminated in 1970*. In 1990*, 90Y was separated from 90Sr in multi-Curie 

quantities for medical use. These cells were also used in support of the studies on solidification of 

high-level radioactive waste (i.e. Nuclear Waste Vitrification Project) from processing irradiated fuel 

elements from commercial reactors. A special underground liquid waste pipe line connected the hot 

cells in 324 and 325-A. The Nuclear Waste Vitrification Project that was conducted in the 324 and 

325 buildings in the 1970’s, involved high “burnup” commercial fuel elements were characterized by 

nominally 26% 240Pu (Carbaugh 2003). High-level radio-analytical hot cells were added on the west 

side in 19UNK. The building became known as the Radiochemistry/Cerium recovery Building. 

Limiting access to high-level dose-rate or contamination areas controlled external and internal 

exposures. Most exposures were related to maintenance performed in hot cells or accidents in 

laboratory areas where work was being performed with FP, plutonium, and other radionuclides. A 

major 147Pm contamination incident occurred in the late 1960’s. The radiochemical laboratory work 

resulted in external exposure and any internal exposure resulted from contamination incidents. The 

325 building still is in use in support of cleanup efforts at Hanford. 

325 Radiochemistry Laboratory

2.5.13

Operation of the 326 building started in 1953 to continue exponential pile physics development work 

originally performed in the P-11 Facility and later in 189-D (Marceau, 2002; HS300AHD). Po-Be and 

Ra-Be neutron sources with neutron emissions up to 1X10E+8 n/s were used to irradiate Co and Cu 

test foils. The test foils exhibited radiation levels up to 10 rad/h at 3 inches. The facility was also 

used for metallurgical studies of reactor components and fuel elements to evaluate characteristics and 

performance. Some of this work was transferred to 209 E in 1961. A High Energy Electron 

Microscope was installed in the basement in 1971 to perform materials studies. During microscope 

operations, there was a major spread of plutonium and irradiated steel (i.e. Fe) contamination. This 

and other contamination incidents resulted in some internal exposure. In 1983 the 326 building 

became the “Chemical Science Building”. This facility is still in operation.

326 Pile Physics Technology and Metallurgy Facility

2.5.14

The 327 Radiometallurgy Laboratory was built in 1953(?) to replace the 111-B Test Building (Gerber, 

1993; Marceau, 2002; HS300AHD). It was designed to provide for post testing and other studies on 

irradiated materials, particularly fuel elements and fuel cladding materials from and for the production 

reactors. These facilities originally consisted of eight free standing shielded cells and two water-filled 

storage pools. Several modifications were undertaken to provide a shielded load out facility to handle 

high-level radioactive waste, a large shielded cell to perform special environmental Radiometallurgy 

studies and office space. In 1967 it was used for the experimental production of Pu-238. It was used 

to study irradiated PRTR, FFTF, GETR, EBR II and MTR fuel elements. In 1967 it was involved in a 

327 Radiometallurgy Laboratory Facility
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serious contamination event. The 327 building was renamed the Post Irradiation Testing Laboratory 

in the 1980’s. External and internal exposures were related to irradiated materials, and FP that were 

undergoing metallurgical studies. Work was also performed with 233U and 238Pu. The facility was 

deactivated in 1987.

2.5.15

The biophysics laboratory was opened in 1952 to pioneer development of water chemistry, 

environmental monitoring, and bioassay analysis programs. Missions for the Laboratory include the 

analyses of low-level (i.e. near background) quantities of radioactive materials in air, vegetation, soil, 

wildlife, river and well water samples. A neutron multiplier facility was built in 1974 as section D of the 

biophysics laboratory. It commenced operation in 1977 with a large 252Cf source. External and 

internal exposures were minimized. The building is still in operation. 

329 Biophysics Laboratory

2.5.16

The Life Sciences Laboratory opened in the 331 building in 1972 as a replacement to the 108-F 

complex. The facility was used to perform radiation effects studies on plants, animals and fish in 

support of Hanford plant operations. Studies involved many radionuclides including 90Sr, 131I, 238U, 

and 239Pu. A hot cell that originally contained a 15 kCi 60Co source was used for special irradiation 

studies. External and internal exposures were a minimum. The facility is still in operation.

331 Life Sciences Laboratory Facility

2.5.17

The 3706 building, the original radiochemistry laboratory was placed in operation in early1945 

(Gerber, 1993; Marceau, 2002; HS300AHD). This building was also known as the Technical Building. 

The original mission was to perform small-scale experiments with both low- and high-activity 

radioactive materials in support of production activities with the primary focus on improving the 

bismuth phosphate process. The QA/QC activities associated with fuel element fabrication also were 

performed in 3706 building. Another mission was the metallurgical examination of irradiated fuel 

elements, fuel development for the 313 Building, examination of graphite from the experimental levels 

of the 100 Area piles and special sample analyses from 231Z and 200 Area separation facilities. In 

1947, it was used in the development of the REDOX process. Pioneering radiochemistry work in the 

development of the REDOX, PUREX, and RECUPLEX processes was performed until 1953. Work 

involved many radionuclides including FP, 14C,131I, 235U, 238U, and 239Pu. External and internal 

exposures were related to these radionuclides. Thyroid checks were initiated in May 1947. In 1954, 

many of the laboratories were decontaminated and converted to offices. During the 1970’s and 

1980’s most of the remaining building was converted to offices and still were in use in the early 

1990’s. 

3706 Radiochemistry Laboratory 

2.5.18

The 3730 building was originally constructed in 1949 as a shop. In 1956 the work performed in the 

3741 building was transferred to this building. A 350 kCi Co-60 source was added to a pool in the 

1960’s for special irradiation studies. Irradiated samples measured from 25 to 50 rad/h. Respiratory 

protection was required in the 1950’s because of 14C and 35S airborne contamination. Several facility 

improvements were made during 1974 to 1981. 

3730 Gamma Irradiation Facility
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2.5.19

The 3732 Process Equipment Development Laboratory was constructed in 1949 as an engineering 

pilot plant for the triple-dip and lead-dip fuel canning processes (WHC-MR-0388). It is a one-story, 

metal frame structure seated on a concrete foundation, with a concrete floor and a corrugated metal 

roof. Overall dimensions are 28.5 ft by 48.16 ft. Powdered thorium oxide fuel targets for 233U 

production were fabricated in the 3732 Building from 1965 to 1967. The process of handling these 

powder targets spread powdered and particulate thorium contamination throughout the building. After 

the thorium oxide program switched to pelletized targets in the 3722 Building in 1968, these new fuel 

targets were canned in the 3732 Building through 1970. As a result, the 3732 building contains 

standard fuel fabrication chemical wastes, as well as residual thorium oxide contamination in crevices 

and areas throughout and near the building. The facility is now empty.

3732 Process Equipment Development Laboratory

2.5.20

The Graphite Hot Shop was constructed in 1944 to perform metallurgical studies on irradiated 

graphite samples. Po-Be and Ra-Be neutron sources were used in irradiation facilities in the 

basement to irradiate Co and Cu foils Internal exposures would have been primarily due to the large 

quantities of irradiated graphite (i.e. 14C) that were studied. The facility was torn down in 1956 and 

work was transferred to 3730 (HS300AHD).

3741 Graphite Hot Shop Facility

2.5.21

The Radiological Calibrations and Standards Laboratory was opened in the 3745 building in Oct. 

1944. The two-story wooden frame building contained a low scatter room in which dosimeters were 

calibrated using a 226Ra source and a 220 kVp X-ray machine. Other sources used included large 

60Co and 137Cs photon sources and 252Cf, 226Ra-Be, 84Po-B, 84Po-Be, 238Pu-Be, 239Pu-F, and 124Sb-Be 

neutron sources. Instrument calibrations were performed in a different room that contained two 

vertical concrete-shielded wells in which the photon sources were housed and used. Instrument 

calibration sources included 60Co, 137Cs, and 226Ra sources. A supporting facility, 3745B, was 

constructed out of concrete blocks to house a 4 MeV Van de Graff positive ion accelerator. This was 

used starting in 1955 to perform fast neutron calibrations. A companion facility, 3745A, was built in 

1950* to house a 2 MeV negative ion Van de Graff accelerator. As a result of the shielding, isolation, 

remote operations, and operating procedures, external exposures were minimized. Internal 

exposures were negligible. The calibration operations were moved to the 318 building in 1983. The 

building is still used for office space.

3745 Radiological Calibrations and Standards Laboratory

2.6 WASTE HANDLING FACILITIES

2.6.1

High-level radioactive liquid wastes from reprocessing facilities at Hanford were stored in underground 

single-shell and double-shell tanks starting in 1944. The high-level radioactive waste is transported 

through underground process lines to the storage tanks that are located in tank farms in both 200-E 

and 200-W Areas. The storage tanks are of two types, single-shell and double-shell tanks. Both 

types are cylindrical shaped concrete structures with carbon steel liners. The single-shell tank has a 

single liner and the double-shell tank has two liners with a space in between. Initially, the T and B 

Plants produced over 10,000 gallons of high-level radioactive waste for each ton of uranium 

processed. These wastes were transferred to the first 64 tanks constructed in 1944-1945. Thirty new 

single-shall tanks were constructed in 1947-1948. Additional single-shell tanks were constructed in 

1950-1952 (30), in 1953-1955 (21), and 1963-1964 (4). From 1968-1988 a total of 28 double-shell 

High-Level Liquid Waste Tanks
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tanks was constructed. Most of the single and double shell tanks are still in use. A new waste 

glassification facility is under construction to process the stored high-level liquid wastes. External 

exposure is due to high-energy beta and photon radiations from the fission products stored in the 

tanks. Under normal conditions shielding, distance and time, minimizes personnel exposures. Most 

external exposures would be related to leaks of high-level wastes. Internal exposures to FP were 

controlled through the use of respiratory protection. 

2.6.2

The 216-Z-9 Facility known as the (Z-9) crib (i.e. enclosed trench) is located in the 200-W Area 

approximately 500 feet east of the Z Plant (i.e. PFP) exclusion area. The Z-9 trench was placed into 

operation in 1955 to serve the RECUPLEX Facility by receiving the acid waste stream of both 

aqueous and organic wastes as well as unwashed fabrication oil from the RMA line from 1955-1962. 

The trench was an underground excavation within an active floor area of 30 by 60 feet, 21 feet 

beneath the top of the concrete slab cover. The excavation was covered by a 9 to 12-inch thick 

reinforced concrete slab, 90 feet wide and 120 feet long at ground level. In 1965 because of concern 

that the waste plutonium posed a “potential criticality hazard” a decision was made to develop a soil 

mining and leaching operation to recover an estimated 45 kilograms of waste plutonium. A~1000 

square foot containment structure was built underground to conduct the operation. It housed a soil 

packaging glove box, personnel entry to the trench, and a personnel change room. The structure was 

located on the east side of the trench with part of the structure located over the top of the trench 

cover. The mining operator’s cubicle, which contained the controls for operating the mining 

equipment, was located within the west side of the trench cover through a reinforced opening in the 

trench cover. The mining operation commenced in Aug. 1976 and was completed in July 1978. The 

principal internal exposure potential was related to 239Pu contamination, most of which occurred in the 

soil packaging glove box. Since the waste site was used only for plutonium, the external exposure 

potential during the mining operation was minimal. The facility currently is in a laid away status.

216-Z-9 Trench Facility

2.6.3

The 241-Z Settling Tank, located within the fence of the PFP complex in the 200 West Area, was used 

from 1949-1973 to store large quantities of plutonium-bearing wastes. In 1974, 80,000 liters of 

supernate were removed from the tank leaving an estimated 94-inch deep layer of wet sludge 

containing a few tens of kilograms of plutonium. Internal and external exposures from this operation 

are minimal. The facility is currently awaiting D & D efforts. 

241-Z Settling Tank

2.6.4

The evaporator facilities (242-A, 242-B, 242-S and 242-T) were constructed near each of the 

separation facilities to reduce and concentrate the volume of high level wastes. The 242-T and 242-B 

Evaporators started processing high-level radioactive waste starting in 1951. Two new evaporator 

plants, 242-S and 242-A, commenced operation in 1973 and 1976, respectively. External exposure 

would be due to high-energy beta and photon radiations from the fission products stored in the tanks. 

Personnel exposures normally are controlled using shielding, distance and time. Most external 

exposures would be related to leaks of high-level wastes. Internal exposures to FP were controlled 

through the use of respiratory protection. The first three evaporator facilities were shut down in 

19UNK. The 242-A is still in operation.

242 Evaporator Facilities 
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2.6.5

Gaseous waste is grouped into three headings: dissolver off-gases, process vessel vent systems, and 

exhaust ventilation air. Dissolver off-gases contained the major portion of the radioactive iodine 

(primarily 131I), as well as krypton and xenon isotopes. Dissolver off-gases also carried a high 

concentration of nitrogen oxides resulting from the reduction of nitric acid during the dissolution of the 

irradiated fuel elements. Table 2.6.5-1 shows the three exhaust filtration devices that were used 

starting in 1947 to reduce radioactive material releases from the B and T Separations Plants and later 

the REDOX Plant: 

Chemical Separations Exhaust Filtration Facilities

Table 2.6.5-1. Exhaust filtration facilities. 

Filtration Devices Date Installed

Caustic scrubbers 1947-1948

Sand filters and fiberglass filters 1947-1948 1954(REDOX)

Silver reactors 1950

These filtration devices accumulated substantive quantities of radioactive materials from the 

separations and plutonium concentrations. The caustic scrubbers were used to remove radiochemical vapors from the process vessels. Sand filters were installed in the 202-S, 221-B, 221-T, 

291-B, 291-S, 291-T, 291-Z facilities. The filters were used in exhaust streams associated with the 

separations process to remove particulates and to reduce ruthenium emissions from the exhaust 

stream. Silver reactors were installed primarily to remove 131I from the exhaust stream. 

Radionuclides of interest in the filtration devices include FP, 103Ru, 106Ru, 131I, and 239Pu. Internal and 

external exposures associated with these radionuclides would occur primarily during maintenance 

operations. These filtration devices became inactive as the separations facilities were shut down. 

2.6.6

The 340-facility complex was operated starting in 1954 to receive radioactive liquid wastes from 

various 300 Area laboratories via the radioactive liquid waste sewer line. The complex accumulates 

the liquid wastes in storage tanks. After sample analyses and pH adjustment, the liquid wastes are 

shipped via a shielded railcar tank to the 200-E Area Tank Farms for treatment and disposal. The 

radionuclides of concern include: 60Co.90Sr, 90Y, 137Cs, 147Pm, 238Pu, 239Pu, and 144Ce. Access to the 

tank area was administratively controlled. The external exposures to the operators were related to the 

high-energy betas and photons. Internal exposures were unplanned and would be related to leaks or 

an accident. The facility is still in use.

340, 340-A and 340-B Liquid Waste Handling Buildings
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REFERENCES

Ballinger, M.Y. and R.B. Hall. 1991, A History of Major Hanford Facilities and Processes Involving 

Radioactive Material, PNL-6964 HEDR, March 

Bihl, D. E., R.L. Buschbom, and M.J. Sula, 1993, Experience with a Routine Fecal Sampling Program 

for Plutonium Workers, Health Physics, 65(5) 

Boomer, K.D., et al. 1994, Tank Waste Remediation System Facility Configuration Study, WHC-SDWM-ES-295, June 

Carbaugh, E.H. 2003, Methods and Models of the Hanford Internal Dosimetry Program, PNL-MA86024) WHC-MR-0388 NOTE: Need title, author and date

Carlisle, R.P., 1996, Supplying The Nuclear Arsenal American Production Reactors, 1942 – 1992, 

John Hopkins University Press

Cooke, N., F.B. Holt. 1974. “The Solubility of Some Uranium Compounds in Simulated Lung Fluid.” 

Health Physics, Vol. 27 (July). 

Crowe, R.D. and R.W. Szempruch, 1994, Technical Basis for Characterization of Plutonium for PFP 

Safety Analyses, WHC-SD-CP-TI-190, February

Department of Energy (DOE), 1994, Plutonium ES&H Vulnerability Assessment, July 27

Fisher, D.R. 1986. Letter to Monte J. Sula, “Particle Size Distribution and Solubility of Uranium 

Aerosols in 333 and 303 M Buildings at UNC and PNL’s 306W Building.”

Hanford Site Historical District – Hanford Site 300 Area Historical Directory (HS300AHD)

Lyon, M.M., et al, 1989, Hanford Radiological Protection Support Services at Hanford for 1988, PNL6952

Lyon, M.M., J.J. Fix, J.L. Kenoyer, J.A. Leonowich, H.E. Palmer, and M.J. Sula, 1988, Hanford 

Radiological Protection Support Services Annual Report for 1987, PNL-6624,

Marceau, T.E., et al, 2002, History of the Plutonium Production Facilities at the Hanford Site Historic 

District, 1943-1990, DOE/RL–97—1047, June

McConnon, D. 1966, Exposure Estimates vs. Film Badge Results, Letter to K.R. Heid, April 22

Newman, D.F., 1989, Summary of HTLTR Benchmark Data from the High Temperature Lattice Test 

Reactor, PNL-7178, October 

Rich, B.L., S.L. Hinnefeld, C.R. Lagerquist, W.G. Mansfield, L.H. Munson, E.R. Wagner, 1988. Health 

Physics Manual of Good Practices for Uranium Facilities. EGG-2530 

Selby, J.M. and J.K. Soldat. 1958, Summary of Environmental Contamination Releases at Hanford 

1952 – 1957, HW 54636, January 25

Sula, M.J., E.H. Carbaugh, and D.E. Bihl. 1989, Technical Basis for Internal Dosimetry at Hanford, 

PNL-6866, April
Effective Date: 10/02/2003 Revision No. 00 Document No. ORAUT-TKBS-0006-2 Page 27 of 39

Sula, M.J., E.H. Carbaugh, D.E. Bihl. 1991. Technical Basis for Internal Dosimetry at Hanford. PNL6866, Rev. 1. Pacific Northwest Laboratory, Richland, WA. 

Thompson, R.J. 1986, Operating Specifications for the Uranium Oxide Plant, OSD-U-185-00001 

Till, J.E., P.G. Voilleque, G.G. Killough, and S.K. Rope. 2002, Methods for Estimating Radiation 

Doses from Short-Lived Gaseous Radionuclides and Radioactive Particles Released to the 

Atmosphere During Early Hanford Operations, RAC Report No. 2-CDC-Task Order 3-2000-

Final,

Wilson, R.H., 1987, Historical Review of Personnel Dosimetry Development and its Use in Radiation 

Protection Programs at Hanford 1944 to the 1980s, PNL-6125, February

Wilson, R.H., W.V. Baumgartner, J.J. Fix, and L.L. Nichols. 1990, Description and Evaluation of the 

Hanford Personnel Dosimeter Program From 1944 Through 1989, PNL-7447

Gerber, M.S., 1992, Past Practices Technical Characterization Study – 300 Area – Hanford Site, 

WHC-MR-0388, December

Gerber, M.S., 1993, Manhattan Project Buildings and Facilities at the Hanford Site: A Construction

History, WHC-MR-0425, September, UNK

19UNK, A Brief History of the T-Plant Facility, WHC-MR-0452,UNK

19UNK, The Hanford Site—An Anthology of Early Histories, WHC-MR-0435,

19UNK, Plutonium Production Story at the Hanford Site, WHC-MR-0521,

19UNK, Brief History of the Purex and UO3 Facilities, WHC-MR-0437
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GLOSSARY

Burnup 

Depletion of fissionable material i.e., 235Pu

Mint 

Tritium

Pile 

Reactor

Pit

A machined part of a nuclear weapon

Slugs 

Another name for fuel elements
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ATTACHMENT A – DESCRIPTION OF FACILITIES AND PROCESSES

TABLE OF CONTENTS

Section

A.1 Reactors ................................................................................................................................

Page

30

A.2 Fuel Reprocessing Facilities .................................................................................................. 31

A.3 Fuel Fabrication Facilities....................................................................................................... 34

A.4 Plutonium Finishing Facilities ................................................................................................. 36

A.5 Research and Development Facilities .................................................................................... 37

A.6 Waste Facilities......................................................................................................................38

LIST OF TABLES

Table

A.1-1 Production reactors years of operation................................................................................

Page

30

A.1-2 Radionuclides of concern for all production reactors ........................................................... 31

A.1-3 Research and test reactors years of operation .................................................................... 31

A.1-4 Radionuclides of concern for all research and test reactors................................................. 31

A.2-1 Fuel reprocessing facilities years of operation..................................................................... 32

A.2-2 Radionuclides of concern for all reprocessing facilities........................................................ 32

A.2-3 Activity composition of Hanford reference weapons-grade plutonium mixture ..................... 32

A.2-4 Activity composition of Hanford reference fuel-grade plutonium mixture.............................. 33

A.2-5 Activity composition of Hanford reference commercial power fuel-grade plutonium 

mixture................................................................................................................................34

A.3-1 Fuel fabrication facilities years of operation......................................................................... 34

A.3-2 Radionuclides of concern for all fuel fabrication and storage facilities ................................. 34

A.3-3 Radiological characteristics of Hanford uranium mixtures ................................................... 35

A.3-4 Impurities in recycled uranium at Hanford ........................................................................... 35

A.3-5 Inhalation class for Hanford uranium compounds................................................................ 36

A.4-1 Plutonium finishing facilities years of operation ................................................................... 37

A.4-2 Radionuclides of concern for plutonium finishing facilities ................................................... 37

A.5-1 100 and 200 Area research and development facilities years of operation .......................... 37

A.5-2 300 Area research and development facilities years of operation........................................ 37

A.5-3 300 Area research and development facilities years of operation (continued) ..................... 38

A.5-4 Radionuclides of concern for all 100, 200, and 300 Area research and development 

facilities ...............................................................................................................................38

A.6-1 Waste facilities years of operation....................................................................................... 39

A.6-2 Radionuclides of concern for all waste facilities................................................................... 39

A.6-3 Tank waste radionuclide inventory ...................................................................................... 39
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A.1 REACTORS

External exposures at the Production Reactors are primarily due to presence of activation and fission 

products. During operation, entry was restricted or prevented into areas where high direct dose rates 

from photons and neutrons could occur. 

Internal exposures at the Production Reactors are related primarily to the inhalation or absorption of 

activation products and, to a lesser degree, fission products during refueling and maintenance 

operations. Studies in later years at N-Reactor to characterize worker exposure indicated the primary 

internal exposure in the Production Reactors was due to 60Co, a corrosion product. It was stated 

(Sula, et al 1989), “In general, a major characteristic of these corrosion product radionuclides, 

regardless of origin, is the presence of several radionuclides within a matrix of oxidized metal with 

60Co the predominant radionuclide”. Several radionuclides in the metal oxide corrosion product 

mixture include: 58Co, 60Co, 54Mn, and 59Fe with 60Co being the predominant contributor to dose and 

activity. These radionuclides are all associated with elements found in steel and alloys used in 

reactor components. Other radionuclides may be present in trace amounts, but they generally are of 

minimal internal dosimetry significance. 

There were seven small Research and Test reactors operated at Hanford starting in 1944 with only 

FFTF still in existence. Both external and internal exposures at these reactors were low (i.e. minimal 

in most cases) and unique to the specific reactor. With the exception of routine tritium exposures 

when working in the containment vessel at PRTR, external and internal exposures are primarily 

associated with minor accidents. 

External exposure at the PRTR was minimized as a result of the remote operation and the shielding. 

Maintenance operations resulted in external exposure from activation and fission products. A high 

extremity exposure occurred when a worker picked up an irradiated steel pin. Tritium (3

H) oxide was 

the principal internal exposure contaminant during normal operation. This was added into the whole 

body dose (see Internal and External Dosimetry Sections). The reactor was shut down in 1969 after 

an accident resulted in contamination in the reactor. A sample of the contamination showed the major 

contaminant was 95Zr/Nb. Other contaminants included 60Co, 103Ru, 106Ru, 106Rh, 140Ba/La, 141Ce, 

144Ce, and 144Pr. 

Table A.1-1. Production reactors years of operation. 

Reactor

B C D Dr F H KE KW N

9/1944-

2/1968

11/1952-

4/1969

12/1944-

6/1967

10/1950-

12/1964

2/1945-

6/1965

10/1949-

4/1965

2/1955-

1/1971

12/1954 

-1970

12/1963-

1987
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Table A.1-2. Radionuclides of concern 

for all production reactors.

a

As-76 I-135 Sr-91

Ca-41 Mn-54 Sr-92

Co-58 Mn-56 U-238

Co-60 Na-24 Y-90

Cr-51 Nb-97 Y-92

Cu-64 Np-239 Y-93

Fe-59 P-32 Zn-65

Ga-72 Si-31 Zn-69

I-133

a. The composition and relative abundance are 

not known. These radionuclides represent 

98% of radioactive materials in effluents. It 

should be noted that several of these are 

short-lived activation products (e.g. 31Si, 76As, 

etc) that would result in only limited, if any, 

exposure to workers.

Table A.1-3. Research and test reactors years of operation. 

Reactor

HTR PCTR TTR PRTR PRCF HTLTR FFTF

1943- 1972 1954- 1970 1954-1978 1960- 1969 1962- 1976 1968- 1971 1980- 1994

Table A.1-4. Radionuclides 

of concern for all research 

and test reactors. 103Ru 235U 35S

106Rh 238Pu 210Po

106Ru 238U 226Ra

140Ba/La 239Pu 233U

141Ce 3

H 237Np

144Ce 60Co 240Pu

144Pr 95Zr/Nb 244Cm

233U 252Cf

A.2 FUEL REPROCESSING FACILITIES

External exposures were primarily from high-energy betas and photons in the separations facilities 

associated with fission products (FP). Internal exposures, primarily associated with contamination 

incidents, could be due to FP and/or plutonium. The following mix of radionuclides (238PU, 239PU, 

240Pu, and 241Pu) comprises most plutonium mixtures at Hanford. The Hanford plutonium mixtures as 

shown in Tables A.2-3, A.2-4 and A.2-5 below were categorized by their weight percent of 240Pu 

(Carbaugh, 2003). When the production reactors were operating, the target mixture `was ~ 6% 240Pu 

(i.e. weapons grade). A special study in the 1980’s indicated frequent-intermittent releases of 

plutonium in the workplaces at levels below detectability for normal air sampling. This resulted in < 10 

mrem CEDE (Bihl, 1993; Lyon, et al, 1988; Lyon, et al, 1989). 

The new lung model for internal Dosimetry uses absorption types. The new types are F, M, S for fast, 

moderate, and slow. Plutonium in nitrate form is M, which would apply to the separations plants up to 

the point when N cell was started at PUREX. Plutonium Oxide is classed as type S. This would apply 

to material calcined at either N cell at PUREX. Type S at PUREX would apply only to N cell, not the 
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PR Room. Contamination remaining in old glove boxes, hood exhaust ducts, HEPA and sand filters 

and housings, etc., probably would be classed between M and S, but the default would be S. This is 

because plutonium slowly oxides. Plutonium at 233-S was type M up until 1967 when the fire resulted 

in the facility shutdown. The plutonium would be Type S by the time D&D was started at 233-S in the 

1980s. It should be assumed after 1990 that all plutonium at Hanford would be class S because of 

natural oxidation. Note: The default solubility classes should be used only when bioassay data is 

inconclusive.

The B Plant facilities were modified in 1968 to remove 90Sr and 137Cs from high-level wastes from the 

single and double-shell waste tanks. The purified 90Sr and 137Cs solutions were transferred to the 

225-B Waste Encapsulation Storage Facility (see section 2.2.6). Internal exposures from the 

operation were minimal due to the remote operation. As a result of remote operation, external 

exposures to high-energy photons and beta particles resulting from the processing of large quantities 

of strontium and cesium were minimized. The 108-B Facility was used for the extraction of Tritium 

(

3

H) for several years. Internal exposure was related to tritium, which was added to whole body 

exposure (see External and Internal Dosimetry Sections).

Internal exposures at U and UO3 plants were due to the large quantities of uranium processed. The 

contaminant could be found ranging from soluble uranyl nitrate and UO3 to insoluble UO2 and U3O8

The inhalation class for Hanford uranium compounds, based on ICRP 66, is shown in Table A.3-5 

below. 

The years of operation and radionuclides of concern are shown in Tables A.2-1 and A.2-2 below.

Table A.2-1. Fuel reprocessing facilities years of operation. 

Separation Facility

B T REDOX PUREX U UO3 225-B C Tritium

4/1945-

10/1952(a) 

12/1944- 

Present (b)

1/1952- 

12/1967©

1/1956- 

121992 (d)

3/1952- 

1/1958

1/1952- 

1993(e)

19UNK -

Present

1949*-

1967(f)

8/1949 - 

1955

a. In1968 B Plant started to remove Sr-90 and Cs-137 from high-level wastes.

b. The T-Plant discontinued reprocessing operation in March 1956 (*) and was utilized as a Decontamination Facility; The 

2706-T Annex was added in 1959.

c. The 233-S facility located at REDOX started operation in 1957 and shutdown in 1967.

d. Closed in 6/72 and reopened in 11/83. 

e. Shutdown in 1972 and opened again in 1983 (there were 17 start ups and shutdowns between 1984 and 1992)

f. Started operations in 1952 (?) as REDOX Pilot Plant; 1954 started operations as PUREX Pilot Plant; 1962 started 

operation as Pilot Plant for recovery of Cs and Sr waste tanks NOTE: date for d has not been resolved.

* More than one date was found 

UNK - No date found 

Table A.2-2. Radionuclides 

of concern for all 

reprocessing facilities. 103Ru 235U

106Ru 237Np

131I 238U

137Cs 239Pu

140Ba/La 241Am

141Ce 3

H

144Ce 60Co

233U 90Sr

Table A.2-3. Activity composition of Hanford reference weapons-grade plutonium mixture. 
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Mixture 

designation: Fresh 5-Year 10-Year 15-Year 20-Year 25-Year 30-Year

Years of aginga: 0 5 10 15 20 25 30

Specific activity in 

mixture (Ci/g)

238Pu 8.56E-03 8.23E-03 7.91E-03 7.60E-03 7.31E-03 7.03E-03 6.75E-03

239Pu 5.77E-02 5.77E-02 5.77E-02 5.77E-02 5.77E-02 5.77E-02 5.77E-02

240Pu 1.36E-02 1.36E-02 1.36E-02 1.36E-02 1.36E-02 1.36E-02 1.36E-02

241Pu 8.24E-01 6.48E-01 5.09E-01 4.00E-01 3.15E-01 2.48E-01 1.95E-01

242Pu 1.97E-06 1.97E-06 1.97E-06 1.97E-06 1.97E-06 1.97E-06 1.97E-06

241Am 0 5.83E-03 1.04E-02 1.39E-02 1.66E-02 1.87E-02 2.03E-02

239+240Pu 7.13E-02 7.13E-02 7.13E-02 7.13E-02 7.12E-02 7.12E-02 7.12E-02

Pu-alpha 7.99E-02 7.95E-02 7.92E-02 7.89E-02 7.85E-02 7.83E-02 7.80E-02

Total alpha 7.99E-02 8.53E-02 8.96E-02 9.28E-02 9.52E-02 9.70E-02 9.83E-02

Activity ratios

239+240Pu:241Am NA 12.2 6.87 5.13 4.28 3.80 3.50

239+240Pu:238Pu 8.33 8.67 9.01 9.38 9.74 10.1 10.5

241Pu:239+240Pu 11.6 9.09 7.15 5.62 4.42 3.48 2.73

Pu alpha:239+240Pu 1.12 1.20 1.26 1.30 1.34 1.36 1.38

Pu alpha: 238Pu 9.33 9.66 10.0 10.4 10.7 11.1 11.6

Pu alpha:241Am NA 14.6 8.63 6.67 5.72 5.18 4.84

241Pu: Pu alpha 10.3 8.15 6.43 5.07 4.01 3.17 2.50

a. Time since separation of 241Am from the Pu mix.

Table A.2-4. Activity composition of Hanford reference fuel-grade plutonium mixture. 

Mixture 

designation: Fresh 5-Year 10-Year 15-Year 20-Year 25-Year 30-Year

Years of aginga: 0 5 10 15 20 25 30

Specific activity in 

mixture (Ci/g)

238Pu 1.71E-02 1.64E-02 1.58E-02 1.52E-02 1.46E-02 1.40E-02 1.35E-02

239Pu 5.26E-02 5.26E-02 5.26E-02 5.26E-02 5.26E-02 5.26E-02 5.25E-02

240Pu 2.72E-02 2.72E-02 2.72E-02 2.72E-02 2.72E-02 2.71E-02 2.71E-02

241Pu 3.09E+00 2.43E+00 1.91E+00 1.50E+00 1.18E+00 9.29E-01 7.30E-01

242Pu 3.93E-06 3.93E-06 3.93E-06 3.93E-06 3.93E-06 3.93E-06 3.93E-06

241Am 0 2.19E-02 3.89E-02 5.22E-02 6.24E-02 7.03E-02 7.63E-02

239+240Pu 7.98E-02 7.98E-02 7.98E-02 7.97E-02 7.97E-02 7.97E-02 7.97E-02

Pu-alpha 9.69E-02 9.62E-02 9.56E-02 9.49E-02 9.43E-02 9.37E-02 9.32E-02

Total alpha 9.69E-02 1.18E-01 1.35E-01 1.47E-01 1.57E-01 1.64E-01 1.69E-01

Activity ratios

239+240Pu:241Am NA 3.64 2.05 1.53 1.28 1.13 1.04

239+240Pu:238Pu 4.67 4.86 5.05 5.24 5.46 5.69 5.90

241Pu:239+240Pu 3.87 3.05 2.40 1.88 1.48 1.17 9.16

Pu alpha:239+240Pu 1.21 1.21 1.20 1.19 1.18 1.18 1.17

Pu alpha: 238Pu 5.67 5.87 6.05 6.24 6.46 6.69 6.90

Pu alpha:241Am NA 4.39 2.46 1.82 1.51 1.33 1.22

241Pu: Pu alpha 31.9 25.3 20.0 15.8 12.5 9.91 7.83

a. Time since separation of the 241Am from the Pu mix.
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Table A.2-5. Activity composition of Hanford reference commercial power fuel-grade plutonium 

mixture. 

Mixture 

designation: Fresh 5-Year 10-Year 15-Year 20-Year 25-Year 30-Year

Years of aginga: 0 5 10 15 20 25 30

Specific activity in 

mixture (Ci/g)

238Pu 1.71E-01 1.64E-01 1.58E-01 1.52E-01 1.46E-01 1.40E-01 1.35E-01

239Pu 3.41E-02 3.41E-02 3.41E-02 3.41E-02 3.41E-02 3.41E-02 3.41E-02

240Pu 5.90E-02 5.89E-02 5.89E-02 5.89E-02 5.89E-02 5.88E-02 5.88E-02

241Pu 1.34E+01 1.05E+01 8.28E+00 6.51E+00 5.12E+00 4.03E+00 3.17E+00

242Pu 1.97E-04 1.97E-04 1.97E-04 1.97E-04 1.97E-04 1.97E-04 1.97E-04

241Am 0 9.49E-02 1.69E-01 2.26E-01 2.79E-01 3.04E-01 3.31E-01

239+240Pu 9.31E-02 9.31E-02 9.30E-02 9.30E-02 9.29E-02 9.29E-02 9.29E-02

Pu-alpha 2.65E-01 2.58E-01 2.52E-01 2.45E-01 2.39E-01 2.34E-01 2.28E-01

Total alpha 2.65E-01 3.53E-01 4.20E-01 4.71E-01 5.10E-01 5.38E-01 5.59E-01

Activity Ratios

239+240Pu:241Am NA 0.981 0.551 0.411 0.344 0.305 0.281

239+240Pu:238Pu 0.544 0.568 0.589 0.612 0.636 0.664 0.688

241Pu:239+240Pu 144 113 89.1 70.0 55.1 43.3 34.1

Pu alpha:239+240Pu 2.85 2.77 2.71 2.63 2.57 2.52 2.45

Pu alpha: 238Pu 1.55 1.57 1.59 1.61 1.64 1.67 1.69

Pu alpha:241Am NA 2.72 1.49 1.08 0.857 0.770 0.689

241Pu: Pu alpha 50.6 40.7 32.9 26.6 21.4 17.2 13.9

a. Time since separation of the 241Am from the Pu mix.

A.3 FUEL FABRICATION FACILITIES

External exposures were related to betas and photons associated with uranium. Due to the 

pyrophoric nature of uranium turnings and chips, internal exposure was related primarily to inhalation 

of uranium. A pressurization of one of the sealed metal storage cans resulted in the spread of 

plutonium contamination and the subsequent shut down of the building until cleanup. The years of 

operation and radionuclides of concern are shown in Tables A.3-1 and A.3-2 below. The radiological 

characteristics of Hanford uranium mixtures are shown in Table A.3-3 and the impurities in recycled 

Hanford uranium are shown in Table A.3-4. The inhalation class for Hanford uranium compounds is 

shown in Table A.3-5. Note: The default solubility classes should be used only when bioassay data is 

inconclusive.

Table A.3-1. Fuel fabrication facilities years of operation. 

Fuel fabrication

313 314 333 303 Facilities 306

3/1944 –1/1971 7/1944 -1971 1961 -1988 1944 - Present 5/1957 -1984

Table A.3-2. Radionuclides of concern for all fuel fabrication and storage facilities. 241Am 237Np 238Pu 239Pu 232Th 235U 238U
Effective Date: 10/02/2003 Revision No. 00 Document No. ORAUT-TKBS-0006-2 Page 35 of 39

Table A.3-3. Radiological characteristics of Hanford uranium mixtures. 

Uranium mixture

Weight 

percentagea,b

Natural 

(NU)

Depleted 

(DU)

Recycled 

(RU)

Commercial 

fuel (CF)

234U 0.0057 0.0005 0.0082 0.0300

235U 0.7204 0.2500 0.9700 2.9600

236U Negligible Negligible 0.0680 Negligible

238U 99.2739 99.7500 98.9500 97.0100

Specific constituent activity in mixture (uCi/g, nCi/mg, or pCi/ugc

234U 0.3563 0.0313 0.5125 1.8750

235U 0.0156 0.0054 0.0210 0.0639

236U Negligible Negligible 0.0440 Negligible

238U 0.3336 0.3352 0.3325 0.3260

Total 0.7054 0.3718 0.9099 2.2649

Specific constituent activity in mixture (dpm/ug)c

234U 0.7909 0.0694 1.1378 4.1625

235U 0.0345 0.0120 0.0465 0.1419

236U Negligible Negligible 0.0977 Negligible

238U 0.7405 0.7441 0.7381 0.7236

Total 1.5659 0.8254 2.0200 5.0281

Constituent fraction of total uranium activity in mixture

234U 0.5051 0.0840 0.5632 0.8279

235U 0.0221 0.0145 0.0230 0.0282

236U Negligible Negligible 0.0484 Negligible

238U 0.4729 0.9014 0.3654 0.1439

Total 1.0000 1.0000 1.0000 1.0000

a. NU, DU, and CF data from Rich et al, 1988.

b. RU data based on average of data presented by Sula, et al, 1991.

c. Can be used to represent specific alpha activity in the mixture as well.

Table A.3-4. Impurities in recycled uranium at Hanford. 

Constituent Maximum alloweda Observed rangeb Reference levelc

Plutonium 10 ppb U <1 - 2 ppb U 0.4 nCi Pu-alpha/gU

Neptunium Not established 0.04-0.16 ppm U 0.4 nCi 237Np/g U

Thorium 750 ppm U 8 - 10 ppm U 5 pCi 232Th/g U

99Tc Not established 3 - 4 ppm U 0.2 uCi 99Tc/g U

103,106Ru <20 uCi/lb U <6 uCi/lb U 40 nCi 106Ru/g U

95ZrNb <10 uCi/lb U <4 uCi/lb U 20 nCi 95ZrNb/g U

Other gamma emitters excluding 99Tc <2 uCi/lb U 0.09 0.75 uCi/lbU Negligible 

a. From UO3 Plant operating specifications, OSD-U-185-0001 (Thompson 1986).

b. From analysis of uranium lots 88-1, 88-2, 88-3 that was processed in 1988, and lots 93-01, 93-02, 93-03, 93-04, and 93-

05, processed in 1993.

c. A reference level is chosen for determining bioassay-monitoring needs and for use as an initial assumption in evaluating 

intakes. The use of the reference levels is expected to result in a slight overestimate of dose compared to levels 

actually observed in 1988.
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Table A.3-5. Inhalation class for Hanford uranium compounds. 

ICRP 30 inhalation 

class from lung fluid 

studies Compound and location

Recommended 

ICRP 66 lung 

absorption type d

80% D

20% W

Hanford UO3 Plant smear sample dissolution study in 1984a, 

(UO3 powder)

F

10% D

90% Y

Hanford 303-M Building air sample dissolution studyb (300 Area 

Uranium Fuel Production Facilities)

S

29% D

71% Y

Hanford 333 Building air sample dissolution studyb (300 Area 

Uranium Fuel Production Facilities)

S

20% D

80% Y

Hanford 306-W Building Machine Shop air sample dissolution 

studyb

S

Uranyl nitrate at Purex or UO3 Plant F

UCl4 or U carbonate (assumed form after discharge to the soil) Mc

a. Sula, Bihl, and Carbaugh (1989). 

b. Fisher, (1986).

c. Cooke and Holt 1974.

d. Note: The default solubility classes should be used only when bioassay data is inconclusive. 

A.4 PLUTONIUM FINISHING FACILITIES

Although relatively few Hanford personnel were involved in plutonium finishing, these facilities 

provided the majority of personnel external exposures to neutron radiation. As production increased, 

ten-inch thick water-filled walls were installed to reduce worker exposure to neutrons. Special leadfilled gloves were installed to reduce extremity exposure. Worker external exposure in the vault 

rooms was due to low-energy photons and neutrons that occurred during periodic inventory and 

inspection activities. 

Internal exposures in the operating areas were related primarily to contamination incidents involving 

americium and plutonium since airflow patterns were designed to control the flow from areas of lower 

air contamination potential to higher. Maintenance and clean-up operations were conducted in 

protective clothing including respiratory protection. Exposures occurred by inhalation, absorption and 

injection (i.e. wound sites). Internal exposure in the vault areas was minimal since there were no 

routine activities that involved opening the storage containers. Internal exposure would have been a 

concern in the event of an incident that breached the containment. 

In Feb. 1960, RECUPLEX was temporarily shut down to permit an extensive cleanup of hoods and 

operating equipment. A criticality accident that occurred in the RECUPLEX facility in April 1962 

resulted in high external radiation exposures and in widespread contamination throughout the 

RECUPLEX room.

The new lung model for internal Dosimetry uses absorption types. The new types are F, M, S for fast, 

moderate, and slow. Plutonium in nitrate form is M, which would apply to the plutonium finishing 

plants where plutonium nitrate has been involved (e.g. RECUPLEX, 231-Z, etc.). Plutonium Oxide 

that is classed as type S, would apply to material calcined at the RMC line at PFP. Contamination 

remaining in old glove boxes, hood exhaust ducts, HEPA and sand filters and housings, etc., probably 

would be classed between M and S, but the default would be S. This is because plutonium slowly 

oxides. It should be assumed after 1990 that all plutonium at Hanford would be class S because of 

natural oxidation. In a study performed in the early 1990’s of the isotopic distribution of plutonium at 

PFP, it was stated there were ~3.7 million grams of plutonium with the 240Pu content ranging from 4% 

to >19% (Crowe, Szempruch 1994). Note: The default solubility classes should be used only when 

bioassay data is inclusive.
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The years of operation and the radionuclides of concern are listed in Tables A.4-1 and A.4-2 below. 

The activity composition for Hanford reference plutonium mixtures is shown in Tables A.2-3, A.2-4, 

and A.2-5 above.

Table A.4-1. Plutonium finishing facilities years of operation. 

Facility/process

231-Z 232-Z

2345Z 

RG

2345Z 

RMA

2345Z 

RMC

2345Z 

RECUPLEX

2345Z 

Storage vault 236-Z 242-Z

1/1945 -

19UNK(

a)

1/1962 

- 

1973

7/1949 

- 

1957

3/1952 -

1984(b)

10/1960 

- 

1989(c)

7/1955 –

1/1962

1949 -Present 5/1964 -

4/1976(

d)

1963 -

1976(e)

a. In 1956 the mission changed to plutonium metallurgy development: In 19UNK 233U metallurgy studies were undertaken.

b. In 1964 line shutdown: In 1967 a glove box was reactivated; In 1968, Tasks I-lll were cleaned out and reactivated; In 

1984 it was decided to keep the RMA on standby.

c. In 1962 ten-inch thick water-filled shielding tanks were added to substantially reduce operator exposure to neutrons; 

Several safety improvements made in 1963 and 1964; Fabrication of pits removed from line in 1966. Shutdown in 1976 

as a result of explosion in 242-Z; The RMC line restarted in 1985; Shut down in 1989.

d. In 12/1975 it was shutdown for upgrades; Restarted in 1976; Shut down in 4/1976 as a result of explosion in 242-Z.

e. In 1969 changed from batch to continuous process; In 4/1976 shut down because of strike; In 8/1976 restarted; Shut 

down in 8/1976 as a result of explosion in americium recovery area.

Table A.4-2. Radionuclides of concern for plutonium finishing facilities. 233U 237Np 238Pu 239Pu 240Pu 241Pu 242Pu 241Am

A.5 RESEARCH AND DEVELOPMENT FACILITIES

The 21-major Research, Development, and Testing Facilities at Hanford were located in the 100, 200 

and 300 Areas. Construction of these started in 1944 with the last one completed in 1977. These 

facilities were built to support the development and testing of new processes, materials, and 

equipment. In some instances the facilities were used for several different purposes throughout their 

operating life. Therefore, the potential exposures are dependent on the processes involved and the 

mission/process at any given time. See sections 2.5.1 through 2.5.21 for discussion on internal and 

external exposure potential at specific facilities. .The years of operation and the radionuclides of 

concern are listed in Tables A.5-1, A.5-2, and A.5-3 below.

Table A.5-1. 100 and 200 Area research and development facilities years of operation. 

Facility/process

108-F 120 209-E 222-B 222-S 222-T

1949 -1977 4/1950 –

11/1951

7/1961 -19860* 1945 -1975 1949 -present 1944 -1986**

*Only decade date found

**More than on date found 

Table A.5-2. 300 Area research and development facilities years of operation. 

Facility/process

308 318 320 321 324 325 326

1960 -1990*a 1983 –

Presentb

1966 -

Present

1944 -1988c 1966 -

Present

1953 –

Presentd

1953 -

Present
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Table A.5-3. 300 Area research and development facilities years of operation (continued). 

Facility/process

327 329 331 3706 3730 3732 3741 3745

1953 -

1987

1952 -

Present

1972 -

Present

1945 -

late1960’se 1949 -1981

1949 -

1970

1944 -

1956

10/1944 -

1983f

a. In mid 1960’s PRTR fuel work was terminated; Np-Al allow fuel elements produced in late 1960’s; High bay area added 

in 1971; From 1977-1991 FFTF fuel elements were produced; The 308A annex was added in 1979; Triga reactor was 

installed in the late 1970’s.

b. The HTLTR reactor commenced operation in the 318 building in 1967; The reactor was shut down in 19UNK; The 

reactor was removed in the early 1980’s; The calibration facility commenced operation in 1983; Major additions were 

added in 1986, 1987, and 1989.

c. The 321 separation building started in 1944; In late 1944 work with small amounts of irradiated materials to conduct 

separations experiments and to study decontamination factors; in1949 a cold test of REDOX process was performed; A 

cold test of the PUREX process was tested in 1953.

d. The 325-A hot cell wing was added in 1959*; Pm-147 heat sources manufactured in 1966; Po-210 work started in 

6/1972 and ended in 1970*. For use with the demonstration of the Waste Vitrification Process for commercial wastes.

e. Most of the radiation laboratories were removed in 1954;Work with radioactive materials discontinued in late 1960’s; 

building converted to offices in the 1970’s and still in use in the early 1990’s.

f. The 3745-B annex that housed a 4 MV Positive Ion Accelerator started operation in 1955; The 3745-A annex that 

housed a 2 MV Negative Ion Accelerator started operation in 1950*; The calibrations operations were transferred to the 

318 building in 1983; The building is being used as offices.

Table A.5-4. Radionuclides 

of concern for all 100, 200, 

and 300 Area research and 

development facilities. 14C 147Pm

144Ce 238Pu

60Co 239Pu

137Cs 103Ru

64Cu 106Ru

FP 90Sr

131I 238U

235U 90Y

A.6 WASTE FACILITIES

External exposure is related to high-energy beta and photon radiations from the fission products 

stored in the tanks. Under normal conditions shielding, distance and time helped keep personnel 

external exposures at a low level. Leaks of high-level wastes that could result in unusual or 

unplanned external exposures were documented in incident or accident reports. In1994, data was 

included in (Boomer, et al 1994) on tank waste radionuclide inventory. The data from that report are 

included in Table A.6-3. Internal exposures to FP were controlled through the use of respiratory 

protection.

A mining operation to remove an estimated 45 kg of plutonium from the Z-9 trench was initiated in 

Aug. 1976 and was completed in July 1978. The principal internal exposure potential was related to 

239Pu contamination, most of which occurred in the soil packaging glove box. Since the waste site 

was used only for plutonium, the external exposure potential during the mining operation was minimal. 

The years of operation and radionuclides of concern are shown in Tables A.6-1 and A.6-2 below.
Effective Date: 10/02/2003 Revision No. 00 Document No. ORAUT-TKBS-0006-2 Page 39 of 39

Table A.6-1. Waste facilities years of operation. 

Facility/Process

Waste Tanks

Z-9 Trench 

Facility 241-Z

242 Evaporator 

Facilities

Exhaust Filtration 

Facilities

340 Waste 

Complex

1944 -Present 1955 -1978 1949 -1973 1951 -Present 1947 -19UNK 1954 -Present

Table A.6-2. Radionuclides 

of concern for all waste 

facilities. 141Ce 238Pu

144Ce 239Pu

60Co 103Ru

137Cs 106Ru

FP 90Sr

131I 90 Y

147Pm

Table A.6-3. Tank waste radionuclide inventory. 

Mega curies of 

radioactive specie

Liquid components Solid components

Double-shell tanks Single-shell tanks Double-shell tanks Single-shell tanks 137Cs and 137Ba 6.40 E+01 2.53 E+01 2.33 E+00 8.45 E+00 90Sr and 90Y 3.93 E+00 1.14 E+01 2.17 E+01 1.13 E+02 99TC 2.28 E-02 7.82 E-03 1.35 E-03 7.82 E-03 241Am 1.45 E-02 4.70 E-03 7.97 E-02 4.23 E-02 237Np 1.64 E-05 3.30 E-06 1.92 E-05 2.97 E-05

Pu 3.84 E-03 5.50 E-04 6.80 E-03 2.69 E-02

TRU 1.93 E-02 5.25 E-03 9.10 E-02 6.92 E-02