ORAU TEAM

Dose Reconstruction

Project for NIOSH

Oak Ridge Associated Universities I Dade Moeller & Associates I MJW Corporation

Page 1 of 46

Document Title:

Hanford Site – Site Description

Document Number: ORAUT-TKBS-0006-2 

Revision: 01

Effective Date: 05/17/2007

Type of Document TBD

Supersedes: Revision 00

Subject Expert(s): 

Site Expert(s): Jack M. Selby

Approval: Signature on File Approval Date: 05/03/2007

Edward D. Scalsky, Document Owner

Concurrence: Signature on File Concurrence Date: 05/04/2007

John M. Byrne, Task 3 Manager

Concurrence: Signature on File Concurrence Date: 05/03/2007

Edward F. Maher, Task 5 Manager

Concurrence: James P. Griffin Signature on File for Concurrence Date: 05/03/2007

Kate Kimpan, Project Director

Approval: Brant A. Ulsh Signature on File for Approval Date: 05/17/2007

James W. Neton, Associate Director for Science

 New Total Rewrite Revision Page Change

FOR DOCUMENTS MARKED AS A TOTAL REWRITE, REVISION, OR PAGE CHANGE, REPLACE THE PRIOR 

REVISION AND DISCARD / DESTROY ALL COPIES OF THE PRIOR REVISION.
Document No. ORAUT-TKBS-0006-2 Revision No. 01 Effective Date: 05/17/2007 Page 2 of 46

PUBLICATION RECORD

EFFECTIVE 

DATE

REVISION 

NUMBER DESCRIPTION

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 00 First approved Issue of Revision 00. Initiated by Edward D. Scalsky.

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, Document Owner

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

05/17/2007 01 Approved revision initiated to include Attributions and Annotations. 

Constitutes a total rewrite of the document. Incorporates formal 

internal review comments. This revision results in no change to the 

assigned dose and no PER is required. Training required: As 

determined by the Task Manager. Initiated by Edward D. Scalsky.
Document No. ORAUT-TKBS-0006-2 Revision No. 01 Effective Date: 05/17/2007 Page 3 of 46

TABLE OF CONTENTS

SECTION TITLE

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

PAGE

6

2.1 Introduction ..............................................................................................................................8

2.1.1 Purpose........................................................................................................................9

2.1.2 Scope...........................................................................................................................9

2.2 Site Activities and Processes ...................................................................................................9

2.3 Reactors ..................................................................................................................................9

2.3.1 105-B, C, D, DR, F, H, KW, and KE Production Reactors........................................... 10

2.3.2 105-N Production Reactor ..........................................................................................10

2.3.3 305 Hanford Test Reactor ..........................................................................................10

2.3.4 305-B Physical Constants Test Reactor .....................................................................11

2.3.5 305-B Thermal Test Reactor ......................................................................................11

2.3.6 309 Plutonium Recycle Test Reactor..........................................................................11

2.3.7 309 Plutonium Recycle Critical Facility .......................................................................11

2.3.8 318 High Temperature Lattice Test Reactor ...............................................................11

2.3.9 405 Fast Flux Test Facility..........................................................................................12

2.4 Fuel Separations Facilities ..................................................................................................... 12

2.4.1 Original Fuel Separations Facilities ............................................................................12

2.4.2 202-S REDOX Plant...................................................................................................13

2.4.3 202-A PUREX Plant ...................................................................................................13

2.4.4 221-U U Plant.............................................................................................................14

2.4.5 224-U UO3 Plant.........................................................................................................14

2.4.6 225 Waste Encapsulation and Storage Facility...........................................................14

2.4.7 201-C C Plant or Hot Semiworks ................................................................................14

2.4.8 108-B Tritium Extraction Facility .................................................................................14

2.5 Fuel Fabrication Facilities....................................................................................................... 15

2.5.1 313 Uranium Metal Fuels Fabrication Facility .............................................................15

2.5.2 314 Uranium Metal Extrusion Facility..........................................................................15

2.5.3 333 Fuel Cladding Facility ..........................................................................................16

2.5.4 306 Reactor Fuel Manufacturing Pilot Plant................................................................16

2.5.5 303 Facilities Fresh Metal Storage Facilities...............................................................16

2.6 Plutonium Finishing Facilities ................................................................................................. 16

2.6.1 231-Z Plutonium Isolation Facility ...............................................................................17

2.6.2 234-5Z Plutonium Finishing Plant Complex ................................................................17

2.6.2.1 Rubber Glove Line ....................................................................................... 17

2.6.2.2 Remote Mechanical A Line .......................................................................... 18

2.6.2.3 Remote Mechanical C Line .......................................................................... 18

2.6.2.4 Recovery of Uranium and Plutonium by Extraction Facility........................... 18

2.6.2.5 232-Z Incinerator Facility.............................................................................. 18

2.6.2.6 236-Z Plutonium Reclamation Facility .......................................................... 19

2.6.2.7 242-Z Waste Treatment Facility ................................................................... 19

2.6.3 Plutonium Storage Facilities .......................................................................................19
Document No. ORAUT-TKBS-0006-2 Revision No. 01 Effective Date: 05/17/2007 Page 4 of 46

2.7 Research, Development, and Testing Facilities...................................................................... 19

2.7.1 108-F Biology Facility ................................................................................................. 19

2.7.2 120 Critical Mass Laboratory Facility ..........................................................................20

2.7.3 209-E Critical Mass Laboratory...................................................................................20

2.7.4 222-B Laboratory........................................................................................................20

2.7.5 222-S Laboratory........................................................................................................20

2.7.6 222-T Laboratory........................................................................................................20

2.7.7 308 Plutonium Fuels Pilot Plant..................................................................................21

2.7.8 318 Radiological Calibration and Development Laboratory......................................... 21

2.7.9 320 Low-Level Radiochemistry Facility.......................................................................21

2.7.10 321 Separation Facility ...............................................................................................21

2.7.11 324 Chemical and Materials Engineering Laboratory..................................................22

2.7.12 325 Radiochemistry Laboratory..................................................................................22

2.7.13 326 Pile Physics Technology and Metallurgy Facility..................................................22

2.7.14 327 Radiometallurgy Laboratory Facility.....................................................................23

2.7.15 329 Biophysics Laboratory .........................................................................................23

2.7.16 331 Life Sciences Laboratory Facility .........................................................................23

2.7.17 3706 Radiochemistry Laboratory ................................................................................23

2.7.18 3730 Gamma Irradiation Facility .................................................................................24

2.7.19 3732 Process Equipment Development Laboratory ....................................................24

2.7.20 3741 Graphite Hot Shop Facility .................................................................................24

2.7.21 3745 Radiological Calibrations and Standards Laboratory.......................................... 24

2.8 Waste Handling Facilities ....................................................................................................... 25

2.8.1 High-Level Liquid Waste Tanks ..................................................................................25

2.8.2 216-Z-9 Trench Facility...............................................................................................25

2.8.3 241-Z Settling Tank ....................................................................................................25

2.8.4 242 Evaporator Facilities ............................................................................................26

2.8.5 Chemical Separations Exhaust Filtration Facilities......................................................26

2.8.6 340, 340-A and 340-B Liquid Waste Handling Buildings............................................. 26

2.9 Attributions and Annotations .................................................................................................. 27

References ........................................................................................................................................32

Glossary ............................................................................................................................................35
Document No. ORAUT-TKBS-0006-2 Revision No. 01 Effective Date: 05/17/2007 Page 5 of 46

Attachment A, Description of Facilities and Processes ......................................................................36

A.1 Reactors ...............................................................................................................................37

A.2 Fuel Reprocessing Facilities .................................................................................................. 37

A.3 Fuel Fabrication Facilities....................................................................................................... 41

A.4 Plutonium Finishing Facilities ................................................................................................. 42

A.5 Research and Development Facilities .................................................................................... 44

A.6 Waste Facilities......................................................................................................................45

LIST OF TABLES

TABLE TITLE

2-1 Plutonium nitrate processing tasks.........................................................................................

PAGE

17

2-2 Exhaust filtration facilities ....................................................................................................... 26

A-1 Production reactors years of operation................................................................................... 37

A-2 Radionuclides of concern for all production reactors .............................................................. 38

A-3 Research and test reactors years of operation....................................................................... 38

A-4 Radionuclides of concern for all research and test reactors ................................................... 38

A-5 Fuel reprocessing facilities years of operation........................................................................ 39

A-6 Radionuclides of concern for all reprocessing facilities........................................................... 40

A-7 Activity composition of Hanford reference weapons-grade plutonium 

mixture...................................................................................................................................40

A-8 Activity composition of Hanford reference fuel-grade plutonium mixture................................. 40

A-9 Activity composition of Hanford reference commercial power fuel-grade 

plutonium mixture................................................................................................................... 41

A-10 Fuel fabrication facilities years of operation............................................................................ 42

A-11 Radionuclides of concern for all fuel fabrication and storage facilities .................................... 42

A-12 Radiological characteristics of Hanford uranium mixtures ...................................................... 42

A-13 Impurities in recycled uranium at Hanford .............................................................................. 43

A-14 Inhalation class for Hanford uranium compounds................................................................... 43

A-15 Plutonium finishing facilities years of operation ...................................................................... 44

A-16 Radionuclides of concern for plutonium finishing facilities ...................................................... 44

A-17 100 and 200 Area research and development facilities years of operation ............................. 45

A-18 300 Area research and development facilities years of operation........................................... 45

A-19 Radionuclides of concern for all 100, 200, and 300 Area research and 

development facilities............................................................................................................. 45

A-20 Waste facilities years of operation.......................................................................................... 46

A-21 Radionuclides of concern for all waste facilities...................................................................... 46

A-22 Tank waste radionuclide inventory ......................................................................................... 46
Document No. ORAUT-TKBS-0006-2 Revision No. 01 Effective Date: 05/17/2007 Page 6 of 46

ACRONYMS AND ABBREVIATIONS

Ci curie

D&D Decontamination and Decommissioning

DOE U.S. Department of Energy

EEOICPA Energy Employees Occupational Illness Compensation Program Act of 2000

EBR II Experimental Breeder Reactor II

FFTF Fast Flux Test Facility

FP Fission Products

g gram

GETR General Electric Test Reactor 

HEPA high-efficiency particulate air

hr hour

HTLTR High Temperature Lattice Test Reactor

HTR High Temperature Reactor

in inch

kVp applied kilovoltage; peak kilovoltage

kCi kilocurie

kg kilogram

kW kilowatt

L liter

lb pound

m meter

MeV mega-electron volt, Million electron Volts

Mint tritium

mL milliliter

MTR Materials Test Reactor

MW megawatt

n neutron

nCi nanocurie

NIOSH National Institute for Occupational Safety and Health

P-10 tritium

pCi picocurie

PCTR Physical Constants Test Reactor

PFP Plutonium Finishing Plant

PFPP Plutonium Fuels Pilot Plant

POC probability of causation

ppb parts per million
Document No. ORAUT-TKBS-0006-2 Revision No. 01 Effective Date: 05/17/2007 Page 7 of 46

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

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 

s second

TRIGA Training Research Isotopes, General Atomics Reactor

TTR Thermal Test Reactor 

U.S.C. United States Code

W watt

μCi microcurie

§ section or sections
Document No. ORAUT-TKBS-0006-2 Revision No. 01 Effective Date: 05/17/2007 Page 8 of 46

2.1 INTRODUCTION

Technical basis documents and site profile documents are not official determinations made by the 

National Institute for Occupational Safety and Health (NIOSH) but are rather general working 

documents that provide historic background information and guidance to assist in the preparation of 

dose reconstructions for 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 staff in the completion of the individual work required for each dose reconstruction.

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 [DOE] facility” as defined in the Energy Employees 

Occupational Illness Compensation Program Act [EEOICPA; 42 U.S.C. § 7384l(5) and (12)]. 

EEOICPA defines a DOE facility as “any building, structure, or premise, including the grounds upon 

which such building, structure, or premise is located ... in which operations are, or have been, 

conducted by, or on behalf of, the Department of Energy (except for buildings, structures, premises, 

grounds, or operations ... pertaining to the Naval Nuclear Propulsion Program)” [42 U.S.C. § 

7384l(12)]. Accordingly, except for the exclusion for the Naval Nuclear Propulsion Program noted 

above, any facility that performs or performed DOE operations of any nature whatsoever is a DOE 

facility encompassed by EEOICPA.

For employees of DOE or its contractors with cancer, the DOE facility definition only determines 

eligibility for a dose reconstruction, which is a prerequisite to a compensation decision (except for 

members of the Special Exposure Cohort). The compensation decision for cancer claimants is based 

on a section of the statute entitled “Exposure in the Performance of Duty.” That provision [42 U.S.C. § 

7384n(b)] says that an individual with cancer “shall be determined to have sustained that cancer in the 

performance of duty for purposes of the compensation program if, and only if, the cancer ... was at 

least as likely as not related to employment at the facility [where the employee worked], as 

determined in accordance with the POC [probability of causation1

As noted above, the statute includes a definition of a DOE facility that excludes “buildings, structures, 

premises, grounds, or operations covered by Executive Order No. 12344, dated February 1, 1982 

(42 U.S.C. 7158 note), pertaining to the Naval Nuclear Propulsion Program” [42 U.S.C. § 7384l(12)]. 

While this definition contains an exclusion with respect to the Naval Nuclear Propulsion Program, the 

section of EEOICPA that deals with the compensation decision for covered employees with cancer 

[i.e., 42 U.S.C. § 7384n(b), entitled “Exposure in the Performance of Duty”] does not contain such an 

exclusion. Therefore, the statute requires NIOSH to include all occupationally derived radiation 

exposures at covered facilities in its dose reconstructions for employees at DOE facilities, including 

radiation exposures related to the Naval Nuclear Propulsion Program. As a result, all internal and 

external dosimetry monitoring results are considered valid for use in dose reconstruction. No efforts 

are made to determine the eligibility of any fraction of total measured exposure for inclusion in dose 

reconstruction. NIOSH, however, does not consider the following exposures to be occupationally 

derived:

] guidelines established under 

subsection (c) ...” [42 U.S.C. § 7384n(b)]. Neither the statute nor the probability of causation 

guidelines (nor the dose reconstruction regulation) define “performance of duty” for DOE employees 

with a covered cancer or restrict the “duty” to nuclear weapons work.

• Radiation from naturally occurring radon present in conventional structures

• Radiation from diagnostic X-rays received in the treatment of work-related injuries

 

1 The U.S. Department of Labor is ultimately responsible under the EEOICPA for determining the POC. 
Document No. ORAUT-TKBS-0006-2 Revision No. 01 Effective Date: 05/17/2007 Page 9 of 46

2.1.1

The purpose of this TBD is to provide a Hanford site profile that contains technical basis information 

used by the Oak Ridge Associated Universities (ORAU) Team to evaluate the total occupational dose 

for EEOICPA claimants. This section provides information on Hanford facilities and operations.

Purpose

2.1.2

The Hanford Site played an important role in the development of the U.S. nuclear weapons program. 

Operations at the Site included the construction of nine production reactors to produce plutonium for 

weapons and seven physical testing, research and demonstration reactors. Facilities for the 

separation of uranium and plutonium, uranium and tritium extraction facilities and many support 

facilities evolved over the years. This TBD is part of the Hanford Site Profile, which provides a 

description of all the facilities and processes, radionuclides significant for dose reconstruction, and

historical information related to the programs and operations on the Hanford Site. It contains 

technical information to assist the dose reconstructors in the historical development of radiological 

doses received by the workers dating back to the 1940s.

Scope

Attributions and annotations, indicated by bracketed callouts and used to identify the source, 

justification, or clarification of the associated information, are presented in Section 2.9. 

2.2 Site Activities and Processes

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

in March 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 Site. The separation 

facilities were built in the 200 Areas located on a high plateau in the center of the 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 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 indicates either there were two dates 

found (the most provided is the most favorable to claimants) or the actual year in the decade was not 

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

2.3 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 [1]. 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 medicalgrade 238Pu. These nine production reactors, designated 100-B, C, D, DR, F, H, KW, KE, and 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 listed in Tables A-1 and A-2 

respectively, in Attachment A. External exposures are primarily due to the presence of activation and 

fission products (FPs). During operation, entry was controlled into areas where high direct dose rates 
Document No. ORAUT-TKBS-0006-2 Revision No. 01 Effective Date: 05/17/2007 Page 10 of 46

from photons and neutrons could occur. Internal exposures involving uranium, activation products, 

and fission products, were primarily limited to maintenance and refueling activities.

In addition, seven physical testing, research, and demonstration reactors were operated at Hanford 

over a period of 40 years [2]. Six Research and Test Reactors, located in the 300 Area, were 

constructed and operated from 1943 to 1978. 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 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 

listed in Tables A-3 and A-4 in Attachment A. 

2.3.1

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

November, and December 1943. The B reactor commenced operation in September 1944. The D 

and F Reactors commenced operation in December 1944 and February 1945, respectively. In 

addition to producing plutonium for nuclear weapons, the reactors 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 December 1947 with startup commencing in October 1950. The H Reactor was 

constructed in H Area starting in March 1948 with startup in October 1949. Construction of C Reactor 

in B Area commenced in June 1951 with startup in November 1952. The KW and KE Reactors were 

constructed in KW and KE Areas starting in November 1952 and January 1953. They commenced 

operation in December 1954 and February 1955 respectively. These eight reactors were graphitemoderated and single-pass-cooled using treated river water. The first three reactors (B, D, and F) 

had 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 [3]. 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 for shutdown dates.

2.3.2

Construction of 105-N (the 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 because 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., to produce both plutonium and steam to be used to generate power). The dual-purpose reactor 

started producing plutonium in March 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% 235U and an outer tube enriched to 

either 0.95% or 1.25% 235U. 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

2.3.3

The 305 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 

305 Hanford Test Reactor
Document No. ORAUT-TKBS-0006-2 Revision No. 01 Effective Date: 05/17/2007 Page 11 of 46

W) to test fuel elements, fuel configuration, graphite samples, and other materials for the production 

reactors. It was used as a quality assurance (QA) 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 and 1977. 

2.3.4

The 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 because the reactor was located in a shielded underground room and 

operated remotely. Operation was terminated in 1970.

305-B Physical Constants Test Reactor

2.3.5

The 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 because the reactor was operated remotely. Operation was terminated in 

1978.

305-B Thermal Test Reactor

2.3.6

The PRTR, located in the 309 Building, started operating in 1960. The PRTR was a 40-MW, heavywater-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 ORAUT 2004 and ORAUT 2006b). 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. 

309 Plutonium Recycle Test Reactor

2.3.7

The PRCF, which was located in the 309 Building, began operating in 1962. Tests were conducted in 

the PRCF to determine which geometric arrangement of fissionable materials would work in a reactor. 

It was shut down in 1976.

309 Plutonium Recycle Critical Facility

2.3.8

The HTLTR was a 2-MW test reactor built in the 318 Building in 1967 with operation commencing in 

1968 (Newman 1989). The reactor consisted of a graphite cube located in a large shielded room; it

318 High Temperature Lattice Test Reactor
Document No. ORAUT-TKBS-0006-2 Revision No. 01 Effective Date: 05/17/2007 Page 12 of 46

was operated at elevated temperatures up to 1,000°C. The mission was to advance reactor physics 

technology. It was shut down in 1971 after 3 years of operation over 4 years, during which time it

operated with six different cores (i.e., three - 233U, one - 235U, one - 238U, and one - 239Pu). Because

the reactor was heavily shielded and operated remotely, external exposure was at background levels. 

There were no contamination incidents so internal exposure was negligible. The building and the 

shielded room were modified in the early 1980s and used as the new Hanford Radiation Calibration 

Facility (see Section 2.7.8).

2.3.9

The FFTF was a 400-MW sodium-cooled test reactor located in the 405 Building. It began startup

operations in February 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 longterm 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 shut down in 1994 and currently is awaiting decontamination and 

decommissioning (D&D). 

405 Fast Flux Test Facility

2.4 FUEL SEPARATIONS FACILITIES

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

and 200-E Areas from 1943 to 1993 [4]. 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 239Pu, 233U, 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 before 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 in the 100-B Area for processing. Irradiated thorium fuel elements were processed 

in the PUREX Plant to recover 233U 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 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 listed in 

Tables A-5 and A-6, respectively, in Attachment A.

2.4.1

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 in December 1944 and shut down in August 1956, while B Plant started up in April

1945 and shut down in October 1952. Because the capacity was not needed, the startup of U Plant 

was delayed until 1952 when the mission was changed (see Section 2.4.4). 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. 

Original Fuel Separations Facilities 
Document No. ORAUT-TKBS-0006-2 Revision No. 01 Effective Date: 05/17/2007 Page 13 of 46

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.

In March 1956, 221-T was converted to perform equipment decontamination (Gerber 1994). In 1959, 

the 2706 T Decon Annex was added to the 221-T Building to enhance the equipment decontamination 

capabilities, particularly for pieces of equipment too large to take into T Plant. The T Plant 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 2.4.6). The 137Cs and the 

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

respectively [5].

2.4.2

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

up in the 200-W Area utilizing the 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 involved 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 December 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 [6].

2.4.3

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

utilizing the PUREX process (Gerber 1993a; Marceau et al. 2002). The PUREX process was an 

organic solvent extraction process that utilized 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 was 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 shut down in June 1972 and restarted in November 1983. 

During the shutdown, a new process was added to convert plutonium nitrate to plutonium oxide. The 

Plant was started up and shut down several times between 1983 and 1992, with final closure 

announced in December 1992.

202-A PUREX Plant 
Document No. ORAUT-TKBS-0006-2 Revision No. 01 Effective Date: 05/17/2007 Page 14 of 46

A 500-ft 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 1,500-ft tunnel was 

added to PUREX to accommodate the storage of additional equipment. 

2.4.4

As noted in Section 2.the U Plant was constructed in 1943. The U Plant startup was delayed until 

March 1952 when it was reconfigured for use in the recovery of 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 the site for reuse. The U Plant was shut down in January 1958.

221-U U Plant

2.4.5

The 224-U Bulk Reduction Building (known as UO3 Plant) was constructed in the 1940s. 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 January 1952. The product was 

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

quarter of 1956 to house three new calciners. It was shut down in 1972 and opened again in 1983 

(there were 17 startups and shutdowns between 1984 and 1992 corresponding to activities at 

PUREX) and was deactivated in the summer of 1993. 

224-U UO3 Plant 

2.4.6

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 225-B from 221-B for conversion to a 

solid, encapsulation, and storage (see Section 2.4.1 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

2.4.7

The Hot Semiworks (also known as hot sloppy) started up in 1949 as a pilot plant (Marceau et al.

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 shut down in 1956. In 1962, C Plant was 

restarted as a pilot plant for the recovery of cesium and strontium from fission product waste. The 

C Plant was retired in 1967.

201-C C Plant or Hot Semiworks

2.4.8

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

in August 1944 to extract tritium [7]. 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 August 1949 and 1955. The 108-B tritium 

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

108-B Tritium Extraction Facility
Document No. ORAUT-TKBS-0006-2 Revision No. 01 Effective Date: 05/17/2007 Page 15 of 46

offsite 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 ORAUT 2004 and ORAUT 2006b).

2.5 FUEL FABRICATION FACILITIES

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

the 300 Area from 1944 to 1988 [8]. 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 listed in Tables A-10 and A-11 

respectively, in Attachment A.

2.5.1

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

starting in March 1944. (Note: The Key dates document says December 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). Leadcadmium 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 to 1967. In the 1950s, production reactor fuel changed from 

natural uranium to low enriched uranium. In March 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 were 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 January 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 2.5.3 below). 

313 Uranium Metal Fuels Fabrication Facility

2.5.2

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 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 1,000-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 melt 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 (Hanford Site Historical District no date). The high air contamination that occurred 

frequently involved a highly soluble class F material. The melt 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 when the fuel element process was changed to use rolled 

uranium rods. An oxide-burner was installed in the 314 Building in 1946. In 1950, a rolling mill was 

314 Uranium Metal Extrusion Facility
Document No. ORAUT-TKBS-0006-2 Revision No. 01 Effective Date: 05/17/2007 Page 16 of 46

installed in the 314 Building to fabricate Hanford fuel elements on the site. The building was 

deactivated in 1971. 

2.5.3

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. From 1965 to 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

2.5.4

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

306 Reactor Fuel Manufacturing Pilot Plant

2.5.5

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

1983 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; it 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 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 thencurrent Hanford Works (HW) maximum permissible concentration of 2 × 10-12 μCi/mL for unrestricted 

areas and 6 × 10-11 μCi/mL for restricted areas (see Gerber 1992). Building 303L was shut down in 

1971 and the building was 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 Pacific Northwest National Laboratory 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 shutdown of the building until cleanup. It currently is being used 

for other purposes.

303 Facilities Fresh Metal Storage Facilities

2.6 PLUTONIUM FINISHING FACILITIES

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

Finishing Plant Complex) have operated at Hanford from 1945 to the present [9]. 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 2.6.3, the Plutonium Finishing Plant 

Complex consists of several buildings including 234-5Z that involves several processes [i.e., Rubber 

Glove Line, Remote Mechanical A Line, Remote Mechanical C Line, and Recovery of Uranium and 

Plutonium by Extraction (RECUPLEX)]; the 232-Z Incinerator; the 236-Z Plutonium Reclamation 

Facility; and the 242-Z Waste Storage Facility. External exposures were related to radiation fields, 
Document No. ORAUT-TKBS-0006-2 Revision No. 01 Effective Date: 05/17/2007 Page 17 of 46

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-15 

and A-16 respectively in Attachment A.

2.6.1

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

the first plutonium nitrate solution was received. Adding hydrogen peroxide separated the plutonium 

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

the Site for further refining. When the 234-5Z (see Table A-15) went into operation, in July 1949, the 

refined product was shipped off the Site 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 233U were also performed in this building. 

231-Z Plutonium Isolation Facility

2.6.2

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 undergoing D & D.

234-5Z Plutonium Finishing Plant Complex

2.6.2.1 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 Table 2-1 with the exception of Task I were performed 

in the RG Line. 

Table 2-1. Plutonium nitrate processing tasks [10].

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.

In December 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 March 1953 with the exception of the coatings units that were shut down in May 1953. In 1955, 
Document No. ORAUT-TKBS-0006-2 Revision No. 01 Effective Date: 05/17/2007 Page 18 of 46

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 

Remote Mechanical C (RMC) Line. 

2.6.2.2 Remote Mechanical A Line

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

automating the process described in the Table 2-1. In March 1952, the RMA Line began to process 

the plutonium (IV) oxalate that was prepared in 231-Z. By March 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 March 1966. In Sept. 1967, a glovebox 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., nondefense) 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. 

2.6.2.3 Remote Mechanical C Line

The RMC Line began processing plutonium nitrate feed in October 1960. In 1962, a project was 

undertaken to install ten-inch thick water-filled shielding tanks to substantially reduce 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 the 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 Plant, the fabrication portion of the RMC Line

was removed in March 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 shut down 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.

2.6.2.4 Recovery of Uranium and Plutonium by Extraction Facility 

The 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 February 1960, 

RECUPLEX was temporarily shut down to permit an extensive cleanup of hoods and operating 

equipment. In April 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. 

2.6.2.5 232-Z Incinerator Facility

In January 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.
Document No. ORAUT-TKBS-0006-2 Revision No. 01 Effective Date: 05/17/2007 Page 19 of 46

2.6.2.6 236-Z Plutonium Reclamation Facility

The 236-Z Plutonium Reclamation Facility 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 December 1975, 236-Z was shut down for maintenance upgrades and reviews of criticality safety 

specifications and procedures. In 1976, 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 April 1976. 

2.6.2.7 242-Z Was te Treatment Facility

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

waste streams from the PFP. An 241Am recovery process was installed in a glovebox 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 g of 241Am. 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.

2.6.3

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, and 1982, respectively. There were 12 

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

plutonium items and 92% 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 because 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 

August 2003.

Plutonium Storage Facilities

2.7 RESEARCH, DEVELOPMENT, AND TESTING FACILITIES

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

and 300 Areas [11]. 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 lives. Therefore, the potential exposures were 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-17 and A-18 in Attachment A. 

2.7.1

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

Biology Program [12]. The facility was used to perform radiation effects studies on plants, animals, 

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

108-F Biology Facility
Document No. ORAUT-TKBS-0006-2 Revision No. 01 Effective Date: 05/17/2007 Page 20 of 46

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 2.7.16 below). 

2.7.2

The Critical Mass Laboratory was originally operated in the 120 Building located near the 100-F Area 

starting in April 1950 [13]. This laboratory was used for nuclear physics research and development

studies of plutonium solutions and solids to avoid the accidental occurrence of a criticality event in an 

operating facility. In November 1951, a substantial spread of contamination occurred as a result of an 

experiment performed with a plutonium solution. In December 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 to the extensive plutonium contamination. The site was 

subsequently decontaminated and decommissioned. 

120 Critical Mass Laboratory Facility

2.7.3

The 209-E Critical Mass Laboratory was placed into operation in July 1961 [14]. The laboratory, 

located in a room shielded by at least 3 ft of concrete, included a mixing room with a glovebox 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 that involved criticality safety 

specifications. 

209-E Critical Mass Laboratory

2.7.4

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 [15]. 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 shut down in about 1975. This facility was converted to 

office space.

222-B Laboratory

2.7.5

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 [16]. 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 1960s, some work was performed with 147Pm. Internal exposures were primarily related to 

contamination incidents. 

222-S Laboratory

2.7.6

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 [17]. External and internal exposure potential was 

similar to that in 222-B. It was shut down in 1980*. Fire protection was shut off in 1986. 

222-T Laboratory 
Document No. ORAUT-TKBS-0006-2 Revision No. 01 Effective Date: 05/17/2007 Page 21 of 46

2.7.7

The Plutonium Fuels Pilot Plant (PFPP) was constructed in the 308 Building in 1960 to perform 

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

was terminated. In the late 1960s, neptunium-aluminum alloy fuel target elements were produced for 

use in N Reactor for a 238Pu 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 1970s to 

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

experienced many incidents that involved the loss of control of radioactive materials, primarily 

plutonium. Most of these were contained within usually one laboratory and in adjacent corridors. 

Glovebox fires, explosions, and/or ruptures were the most frequent cause of contamination. 

Improperly sealed irradiated sample containers were another common cause. These incidents 

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

308 Plutonium Fuels Pilot Plant

2.7.8

The 318 Building was originally built in 1967 to house the HTLTR (see Section 2.3.8). In the early 

1980s, the reactor was removed and the heavily shielded 10-m3 reactor cell was converted to a freein-air calibration facility that contains a large 252Cf neutron source (109 n/s) and a large 137Cs photon 

source (approximately 100 Ci) that were used for dosimeter calibration [18]. A shielded facility was 

built in the basement to house a high-level 60Co source (approximately 1 kCi) 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 housed 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

2.7.9

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

missions were 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

2.7.10

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

(i.e., nonirradiated 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 that contained

several tenths of a curie to a curie of radioactive materials (Gerber 1993a; Hanford Site Historical 

District no date). Soon after startup, the 321 Building assumed a mission to demonstrate the effects 

of proposed process changes on decontamination factors in the 221, 224, and 231 Buildings, conduct 

isotope separations, and perform 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 Separation Facility
Document No. ORAUT-TKBS-0006-2 Revision No. 01 Effective Date: 05/17/2007 Page 22 of 46

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 1960s

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.

2.7.11

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 the solidification of 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 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. Because most of 

the work was performed in hot cells, external and internal exposures were minimized. The 324 

Building is currently undergoing D&D activities.

324 Chemical and Materials Engineering Laboratory

2.7.12

The 325 Building was completed in 1953 to permit multicurie level chemical development work in 

support of production and process improvement (Marceau 2002; Hanford Site Historical District no 

date). A high-level radiochemistry wing, 325-A, was placed into operation on the east side of the 

building in 1959 and 1960. It included three large hot cells for isotope research activities. This 

included separation and concentration of 90Sr, 90Y, 131I, 137Cs, 144Ce, 147Pm, 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 1975*. In 1990*, 90Y was separated from 

90Sr in multicurie 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 1970s involved high “burnup” commercial fuel elements that were 

characterized by nominally 26% 240Pu (Carbaugh 2003). High-level radioanalytical 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 1960s. 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

2.7.13

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; Hanford Site Historical 

District no date). Po-Be and Ra-Be neutron sources with neutron emissions up to 1 × 108 n/s were 

used to irradiate cobalt and copper test foils. The test foils exhibited radiation levels up to 10 rad/hr at 

3 in. The facility was also used for metallurgical studies of reactor components and fuel elements to 

326 Pile Physics Technology and Metallurgy Facility
Document No. ORAUT-TKBS-0006-2 Revision No. 01 Effective Date: 05/17/2007 Page 23 of 46

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.

2.7.14

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

1993b; Marceau et al. 2002; Hanford Site Historical District no date). It was designed to provide 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 freestanding 

shielded cells and two water-filled storage pools. Several modifications were undertaken to provide a 

shielded loadout 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 238Pu. It was used to study irradiated PRTR, FFTF, General Electric Test Reactor

(GETR), Experimental Breeder Reactor (EBR) II, and Material Test Reactor (MTR) fuel elements. In 

1967, it was involved in a serious contamination event. The 327 Building was renamed the Post 

Irradiation Testing Laboratory in the 1980s. 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.

327 Radiometallurgy Laboratory Facility

2.7.15

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, and 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

2.7.16

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 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 at a minimum. The facility is still in operation.

331 Life Sciences Laboratory Facility

2.7.17

The 3706 Building, the original radiochemistry laboratory, was placed in operation in early 1945 

(Gerber, 1993c; Marceau et al. 2002; Hanford Site Historical District no date). 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/Quality Control activities associated with 

fuel element fabrication also were performed in the 3706 Building. Other missions were 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 

3706 Radiochemistry Laboratory 
Document No. ORAUT-TKBS-0006-2 Revision No. 01 Effective Date: 05/17/2007 Page 24 of 46

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 1970s and 1980s, most of the remaining building was converted 

to offices that still were in use in the early 1990s. 

2.7.18

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 

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

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

improvements were made during 1974 to 1981. 

3730 Gamma Irradiation Facility

2.7.19

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 (Gerber 1992). It is a one-story, metal 

frame structure 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

2.7.20

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 cobalt and copper 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 (Hanford Site Historical District no date).

3741 Graphite Hot Shop Facility

2.7.21

The Radiological Calibrations and Standards Laboratory opened in the 3745 Building in October 1944 

[19]. 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-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 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
Document No. ORAUT-TKBS-0006-2 Revision No. 01 Effective Date: 05/17/2007 Page 25 of 46

2.8 WASTE HANDLING FACILITIES

2.8.1

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

single- and double-shell tanks starting in 1944 [20]. The high-level radioactive waste is transported 

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

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

cylinder-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 more than 10,000 gal of high-level radioactive waste for each ton of uranium processed. 

These wastes were transferred to the first 64 tanks constructed in 1944 and 1945. Thirty new singleshall tanks were constructed in 1947 and 1948. Additional single-shell tanks were constructed in 

1950 and 1952 (30), in 1953 to 1955 (21), and in 1963 and 1964 (4). From 1968 to 1988, 28 doubleshell tanks were 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 FPs stored in the tanks. Under 

normal conditions shielding, distance, and time minimize personnel exposures. Most external 

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

through the use of respiratory protection. 

High-Level Liquid Waste Tanks

2.8.2

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

approximately 500 ft 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 to 

1962. The trench was an underground excavation within an active floor area of 30 by 60 ft, 21 ft

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

reinforced concrete slab, 90 ft wide and 120 ft 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 kg of waste plutonium. An approximately 

1,000-ft2 containment structure was built underground to conduct the operation. It housed a soil 

packaging glovebox, 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 in the west side of the trench cover through a reinforced opening in the trench cover. 

The mining operation commenced in August 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 glovebox. Because 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

2.8.3

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

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

supernate were removed from the tank leaving an estimated 94-in.-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. 

241-Z Settling Tank
Document No. ORAUT-TKBS-0006-2 Revision No. 01 Effective Date: 05/17/2007 Page 26 of 46

2.8.4

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 FPs 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 

2.8.5

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

exhaust ventilation air. Dissolver off-gases were 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 2-2 lists 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 2-2. Exhaust filtration facilities [21]. 

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 included 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. 

2.8.6

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 [22]. 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, 238

Pu, 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
Document No. ORAUT-TKBS-0006-2 Revision No. 01 Effective Date: 05/17/2007 Page 27 of 46

2.9 ATTRIBUTIONS AND ANNOTATIONS

Where appropriate in the preceding text, bracketed callouts have been inserted to indicate 

information, conclusions, and recommendations to assist in the process of worker dose 

reconstruction. These callouts are listed in this section with information that identifies the source and 

justification for each item. Conventional references are provided in the next section that link data, 

quotations, and other information to documents available for review on the ORAU Team servers.

John (Jack) Selby served as the initial Subject Expert for this document. Mr. Selby was previously 

employed at Hanford and his work involved management, direction, or implementation of radiation 

protection and/or health physics program policies, procedures, or practices related to atomic weapons 

activities at the site. This revision has been overseen by a Document Owner, who is fully responsible 

for the content of this document, including all findings and conclusions. Mr. Selby continues to serve 

as a Site Expert for this document because he possesses or is aware of information relevant for 

reconstructing radiation doses experienced by claimants who worked at the site. In all cases where 

such information or prior studies or writings are included or relied on by the Document Owner, those 

materials are fully attributed to the source. 

[1] Selby, Jack M. M. H. Chew & Associates. Senior Health Physicist. September 2006.

The information and data are a summation by the author based on material in Ballinger and 

Hall (1991), Carlisle (1996), Marceau et al. (2002, Chapter 2, Section 3), Gerber (1992), 

Gerber (1996), and Author unknown (no date a).

[2] Selby, Jack M. M. H. Chew & Associates. Senior Health Physicist. September 2006.

The information and data are a summation by the author based on material in Ballinger and 

Hall (1991), Marceau et al. (2002, Chapter 2, Sections 2 and 3), and Gerber (1996).

[3] Selby, Jack M. M. H. Chew & Associates. Senior Health Physicist. September 2006.

The information and data are a summation by the author based on material in Ballinger and 

Hall (1991), Carlisle (1996), Hanford Site (no date), Marceau et al. (2002, Chapter 2, Sections 

3 and 7), Gerber (1993b) and Author unknown (no date a).

[4] Selby, Jack M. M. H. Chew & Associates. Senior Health Physicist. September 2006.

The information and data are a summation by the author based on material in Ballinger and 

Hall (1991), Marceau et al. (2002, Chapter 2, Section 4), Gerber (1993a,b,c, 1994, 1996), and 

Author unknown (no date a). 

[5] Selby, Jack M. M. H. Chew & Associates. Senior Health Physicist. September 2006.

This information is a summation by the author based on material in Ballinger and Hall (1991), 

Marceau et al. (2002, Chapter 2, Sections 4 and 6), and Gerber (1994). 

[6] Selby, Jack M. M. H. Chew & Associates. Senior Health Physicist. September 2006.

The information and data are a summation by the author based on material in Marceau et al. 

(2002, Chapter 1 and Chapter 2, Sections 4 and 6), Ballinger and Hall (1991), and Gerber 

(1994). 

[7] Selby, Jack M. M. H. Chew & Associates. Senior Health Physicist. September 2006.

The information and data are a summation by the author based on material in Ballinger and 

Hall (1991) and Marceau et al. (2002, Chapter 2, Sections 2 and 3). 
Document No. ORAUT-TKBS-0006-2 Revision No. 01 Effective Date: 05/17/2007 Page 28 of 46

[8] Selby, Jack M. M. H. Chew & Associates. Senior Health Physicist. September 2006.

The information and data are a summation by the author based on material in Ballinger and 

Hall (1991), Fisher (1986), Hanford Site (no date), Marceau et al. (2002, Chapter 1 and 

Chapter 2, Section 2), Gerber (1992, 1993b,c), Author unknown (no date a and b).

[9] Selby, Jack M. M. H. Chew & Associates. Senior Health Physicist. September 2006.

The information and data are a summation by the author based on material in Ballinger and 

Hall (1991), DOE (1994), Marceau et al. (2002, Chapter 1 and Chapter 2, Sections 2 and 5), 

Selby and Soldat (1958), and Gerber (1993b).

[10] Selby, Jack M. M. H. Chew & Associates. Senior Health Physicist. September 2006.

Table 2-1 is adapted by the author based on Table 2-5.2 in Marceau et al. (2002, Chapter 2, 

Section 5). 

[11] Selby, Jack M. M. H. Chew & Associates. Senior Health Physicist. September 2006.

The information and data are a summation by the author based on material in Ballinger and 

Hall (1991), DOE (1994), Hanford Site (no date), Marceau et al. (2002, Chapter 1 and Chapter 

2, Section 7), Gerber (1992, 1993b,c, 1996), Author unknown (no date a and b).

[12] Selby, Jack M. M. H. Chew & Associates. Senior Health Physicist. September 2006.

The information and data are a summation by the author based on material in Ballinger and 

Hall (1991), Marceau et al. (2002, Chapter 2, Sections 7 and 10), Gerber (1993b,c).

[13] Selby, Jack M. M. H. Chew & Associates. Senior Health Physicist. September 2006.

The information and data are a summation by the author based on material in Ballinger and 

Hall (1991), Marceau et al. (2002, Chapter 2, Section 7), Selby and Soldat (1958), and Kruesi 

(1951).

[14] Selby, Jack M. M. H. Chew & Associates. Senior Health Physicist. September 2006.

The information and data are a summation by the author based on material in Ballinger and 

Hall (1991), DOE (1994), Hanford Site (no date), Marceau et al. (2002, Chapter 2, Section 7), 

and Author unknown (no date a).

[15] Selby, Jack M. M. H. Chew & Associates. Senior Health Physicist. September 2006.

The information and data are a summation by the author based on material in Ballinger and 

Hall (1991), Marceau et al. (2002, Chapter 2, Section 4), and Gerber (1993b). 

[16] Selby, Jack M. M. H. Chew & Associates. Senior Health Physicist. September 2006.

The information and data are a summation by the author based on material in Ballinger and 

Hall (1991), Marceau et al. (2002, Chapter 2, Section 4), and Gerber (1993b).

[17] Selby, Jack M. M. H. Chew & Associates. Senior Health Physicist. September 2006.

The information and data are a summation by the author based on material in Ballinger and 

Hall (1991), Marceau et al. (2002, Chapter 2, Section 4), and Gerber (1993b).

[18] Selby, Jack M. M. H. Chew & Associates. Senior Health Physicist. September 2006.

The information and data are a summation by the author based on material in Ballinger and 

Hall (1991), Hanford Site (no date), Marceau et al. (2002, Chapter 2, Sections 7 and 10), 

Newman (1989), Gerber (1992), Author unknown (no date a and b), personal experience, and 

discussions with site personnel.
Document No. ORAUT-TKBS-0006-2 Revision No. 01 Effective Date: 05/17/2007 Page 29 of 46

[19] Selby, Jack M. M. H. Chew & Associates. Senior Health Physicist. September 2006.

The information and data are a summation by the author based on material in Ballinger and 

Hall (1991), Hanford Site (no date), Marceau et al. (2002, Chapter 2, Sections 7 and 10), 

Gerber (1992, 1993b,c, 1996), Author unknown (no date a and b), personal experience, and 

discussions with site personnel.

[20] Selby, Jack M. M. H. Chew & Associates. Senior Health Physicist. September 2006.

The information and data are a summation by the author based on material in Ballinger and 

Hall (1991), Boomer et al. (1994), and Marceau et al. (2002, Chapter 2). 

[21] Selby, Jack M. M. H. Chew & Associates. Senior Health Physicist. September 2006.

The information and data are a summation by the author based on material in Ballinger and 

Hall (1991), and Marceau et al. (2002, Chapter 2, Section 4).

[22] Selby, Jack M. M. H. Chew & Associates. Senior Health Physicist. September 2006.

The information and data are a summation by the author based on material in Ballinger and 

Hall (1991), Marceau et al. (2002, Chapter 2, Sections 4 and 6), Gerber (1993b,c, 1996).

[23] Selby, Jack M. M. H. Chew & Associates. Senior Health Physicist. September 2006.

The information and data are a summation by the author based on material in Ballinger and 

Hall (1991), Marceau et al. (2002, Chapter 2, Section 3), Wilson (1987), and Wilson et al. 

(1990).

[24] Selby, Jack M. M. H. Chew & Associates. Senior Health Physicist. September 2006.

The information and data are a summation by the author based on discussions in Ballinger 

and Hall (1991), Carbaugh (2003), Marceau et al. (2002, Chapter 2, Section 3), Sula, 

Carbaugh, and Bihl (1989, 1991), Wilson (1987), and Wilson et al. (1990).

[25] Selby, Jack M. M. H. Chew & Associates. Senior Health Physicist. September 2006.

The information and data are a summation by the author based on material in Ballinger and 

Hall (1991), Bihl, Buschbom and Sula (1993), Carbaugh (2003), Lyon et al. (1989), Marceau et 

al. (2002, Chapter 2, Section 3), Wilson (1987), Wilson et al. (1990), and Gerber (1993a).

[26] Selby, Jack M. M. H. Chew & Associates. Senior Health Physicist. September 2006.

The information and data are a summation by the author based on material in Ballinger and 

Hall (1991), Marceau et al. (2002, Chapter 2, Sections 3 and 7), Gerber (1993b), and Author 

unknown (no date a).

[27] Selby, Jack M. M. H. Chew & Associates. Senior Health Physicist. September 2006.

The information and data are a summation by the author based on material in Ballinger and 

Hall (1991), Bihl, Buschbom and Sula (1993), Carbaugh (2003), Lyon et al. (1989), Marceau et 

al. (2002, Chapter 2, Section 3), Wilson (1987), Wilson et al. (1990), and Gerber (1993a).

[28] Selby, Jack M. M. H. Chew & Associates. Senior Health Physicist. September 2006.

The information and data are a summation by the author based on material in Ballinger and 

Hall (1991), Marceau et al. (2002, Chapter 2, Section 4), Gerber (1993a,b,c, 1996), and Author 

unknown (no date a). 

[29] Selby, Jack M. M. H. Chew & Associates. Senior Health Physicist. September 2006.

The information and data are a summation by the author based on material in Ballinger and 

Hall (1991), Carbaugh (2003), Cooke and Holt (1974), Fisher (1986), Marceau et al. (2002, 
Document No. ORAUT-TKBS-0006-2 Revision No. 01 Effective Date: 05/17/2007 Page 30 of 46

Chapter 2, Section 2), Rich et al. (1988), Sula, Carbaugh, and Bihl (1989, 1991), Wilson 

(1987), Wilson et al. (1990), ORAUT (2006a,b).

[30] Selby, Jack M. M. H. Chew & Associates. Senior Health Physicist. September 2006.

The information and data are a summation by the author based on material in Ballinger and 

Hall (1991), Hanford Site (no date), Marceau et al. (2002, Chapter 2, Section 2), Gerber (1992, 

1993b,c, 1996), and Author unknown (no date a). 

[31] Selby, Jack M. M. H. Chew & Associates. Senior Health Physicist. September 2006.

The information and data are a summation by the author based on material in Carbaugh 

(2003), Hanford Site (no date), Gerber (1992), ORAUT (2004, 2006a), and discussions with 

site personnel. 

[32] Selby, Jack M. M. H. Chew & Associates. Senior Health Physicist. September 2006.

The information and data are a summation by the author based on material in Wilson (1987), 

Wilson et al. (1990), ORAUT (2006b), and discussions with site personnel.

[33] Selby, Jack M. M. H. Chew & Associates. Senior Health Physicist. September 2006.

The information and data are a summation by the author based on material in Sula, Carbaugh, 

and Bihl (1989, 1991), ORAUT (2004), and discussions with site personnel.

[34] Selby, Jack M. M. H. Chew & Associates. Senior Health Physicist. September 2006.

The information and data are a summation by the author based on material in Ballinger and 

Hall (1991), Marceau et al. (2002, Chapter 2, Sections 5 and 10), Wilson (1987), Wilson et al. 

(1990), and discussions with site personnel.

[35] Selby, Jack M. M. H. Chew & Associates. Senior Health Physicist. September 2006.

The information and data are a summation by the author based on material in Ballinger and 

Hall (1991), Marceau et al. (2002, Chapter 2, Section 5), Gerber (1993b,c, 1996), and Author 

unknown (no date a). 

[36] Selby, Jack M. M. H. Chew & Associates. Senior Health Physicist. September 2006.

The information and data are a summation by the author based on material in Carbaugh 

(2003), Marceau et al. (2002, Chapter 2, Section 4), and ORAUT (2006a). 

[37] Selby, Jack M. M. H. Chew & Associates. Senior Health Physicist. September 2006.

The information and data are a summation by the author based on material in Ballinger and 

Hall (1991), Marceau et al. (2002, Chapter 2, Sections 4, 7 and 10), Selby and Soldat (1958), 

Gerber (1993b,c, 1996), Author unknown (no date a), and Kruesi (1951). 

[38] Selby, Jack M. M. H. Chew & Associates. Senior Health Physicist. September 2006.

The information and data are a summation by the author based on material in Ballinger and 

Hall (1991), DOE (1994), Hanford Site (no date), Marceau et al. (2002, Chapter 2, Sections 7 

and 10), Gerber (1992, 1993b,c, 1996), and Author unknown (no date b). 

[39] Selby, Jack M. M. H. Chew & Associates. Senior Health Physicist. September 2006.

The information and data are a summation by the author based on material in Carbaugh 

(2003), Marceau et al. (2002, Chapter 2, Sections 4, 7 and 10), ORAUT (2004, 2006a), and 

discussions with site personnel. 
Document No. ORAUT-TKBS-0006-2 Revision No. 01 Effective Date: 05/17/2007 Page 31 of 46

[40] Selby, Jack M. M. H. Chew & Associates. Senior Health Physicist. September 2006.

The information and data are a summation by the author based on material in Ballinger and 

Hall (1991), Boomer et al. (1994), Marceau et al. (2002, Chapter 2, Sections 4, 5 and 6), 

Gerber (1993b,c, 1996), and Author unknown (no date b). 

[41] Selby, Jack M. M. H. Chew & Associates. Senior Health Physicist. September 2006.

The information and data are a summation by the author based on material in Carbaugh 

(2003), Marceau et al. (2002, Chapter 2, Section 6), Wilson (1987), ORAUT (2004), and 

discussions with site personnel. 

[42] Selby, Jack M. M. H. Chew & Associates. Senior Health Physicist. September 2006.

The information and data are an adaptation by the author based on material in Boomer et al. 

(1994).
Document No. ORAUT-TKBS-0006-2 Revision No. 01 Effective Date: 05/17/2007 Page 32 of 46

REFERENCES

Author unknown, no date a, History of Hanford Operations – A Beginning Chronology (Introduction, 

Part 2 and Part 3) (EE.14).

Author unknown, no date b, 300 Area History Hanford Site, 300 Area Research and Development 

Activities and Facilities

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

Radioactive Material, PNL-6964 HEDR, Pacific Northwest Laboratories, Richland, 

Washington, March. [SRDB Ref ID: 11569]

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

Program for Plutonium Workers,” Health Physics, Volume 65, Number 5. [SRDB Ref ID: 

13396]

Boomer, K. D., et al., 1994, Tank Waste Remediation System Facility Configuration Study, WHC-SDWM-ES-295, Westinghouse Hanford Company, Richland, Washington, June. [SRDB Ref ID: 

115215]

Carbaugh, E. H., 2003, Methods and Models of the Hanford Internal Dosimetry Program, PNL-MA860, Pacific Northwest Laboratories, Richland, Washington. 

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

John Hopkins University Press.

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

Fluid,” Health Physics, Volume 27 (July). [SRDB Ref ID: 13357]

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

Safety Analyses, WHC-SD-CP-TI-190, Westinghouse Hanford Company, Richland, 

Washington, February.

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

Fisher, D. R. 1986, “Particle Size Distribution and Solubility of Uranium Aerosols in 333 and 303 M 

Buildings at UNC and PNL’s 306W Building,” letter to Monte J. Sula. [SRDB Ref ID: 15196]

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

WHC-MR-0388, Westinghouse Hanford Company, Richland, Washington, December. [SRDB 

Ref ID: 13724]

Gerber, M. S., 1993a, A Brief History of the PUREX and UO3 Facilities, WHC-MR-0437, 

Westinghouse Hanford Company, Richland, Washington. [SRDB Ref ID: 14586]

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

History, WHC-MR-0425, Westinghouse Hanford Company, Richland, Washington, September. 

[SRDB Ref ID: 11572] 

Gerber, M. S., 1993c, The Hanford Site - An Anthology of Early Histories, WHC-MR-0435, 

Westinghouse Hanford Company, Richland, Washington. 
Document No. ORAUT-TKBS-0006-2 Revision No. 01 Effective Date: 05/17/2007 Page 33 of 46

Gerber, M. S., 1994, A Brief History of the T-Plant Facility, WHC-MR-0452, Westinghouse Hanford 

Company, Richland, Washington. [SRDB Ref ID: 14587]

Gerber, M. S., 1996, The Plutonium Production Story at the Hanford Site: Processes and Facility 

History, WHC-MR-0521, Westinghouse Hanford Company, Richland, Washington. [SRDB Ref 

ID: 474]

Hanford Site (Hanford Site Historical District), Hanford Site 300 Area Historical Directory (no date) 

(HS300AHD). [SRDB Ref ID: 14473]

Hayes, D. F., 1956, A Summary of Accidents and Incidents Involving Radiation in Atomic Energy 

Activities, June, 1945 through December, 1955, TID-5360.

Heeb, C. M., 1994, Radionuclide Releases to the Atmosphere from Hanford Operations, 1944-1972, 

PNWD-2222.

ICRP (International Commission for Radiological Protection), 1994, “Human Respiratory Tract Model 

for Radiological Protection,” Annals of the ICRP, Publication 66, Oxford, England.

Kruesi, F. E., 1951, P-11 Laboratory Fire Investigation, HW-22936.

Lyon, M. M., et al., 1989, Hanford Radiological Protection Support Services at Hanford for 1988, PNL6952, Pacific Northwest Laboratories, Richland, Washington. [SRDB Ref ID: 15197]

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, Pacific 

Northwest Laboratories, Richland, Washington. [SRDB Ref ID: 15198]

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

District, 1943-1990, DOE/RL-97-1047, U.S. Department of Energy, Richland Operations 

Office, Richland, Washington, June 14.

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, Pacific Northwest Laboratories, Richland, Washington, October. 

ORAUT (Oak Ridge Associated Universities Team), 2004, Technical Basis Document for the Hanford 

Site – Occupational Internal Dose, ORAUT-TKBS-0006-5, Rev. 01, Oak Ridge, Tennessee,

November 24.

ORAUT (Oak Ridge Associated Universities Team), 2006a, Hanford Site – Occupational 

Environmental Dose, ORAUT-TKBS-0006-4, Rev. 01, Oak Ridge, Tennessee, December 20.

ORAUT (Oak Ridge Associated Universities Team), 2006b, Hanford Site – Occupational External 

Dose, ORAUT-TKBS-0006-6, Rev. 02, Oak Ridge, Tennessee, November 21.

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. [SRDB Ref ID: 

1781] 
Document No. ORAUT-TKBS-0006-2 Revision No. 01 Effective Date: 05/17/2007 Page 34 of 46

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

1952 – 1957, HW 54636, January 25. [SRDB Ref ID: 13398]

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

PNL-6866, Pacific Northwest Laboratories, Richland, Washington, April. [SRDB Ref ID: 270]

Sula, M. J., E. H. Carbaugh, D. E. Bihl, 1991, Technical Basis for Internal Dosimetry at Hanford, PNL6866, Rev. 1., Pacific Northwest Laboratory, Richland, Washington. [SRDB Ref ID: 14485]

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. [SRDB Ref ID: 457]

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, Pacific Northwest Laboratories, 

Richland, Washington, February. [SRDB Ref ID: 262]

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, Pacific 

Northwest Laboratories, Richland, Washington. [SRDB Ref ID: 290]
Document No. ORAUT-TKBS-0006-2 Revision No. 01 Effective Date: 05/17/2007 Page 35 of 46

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
Document No. ORAUT-TKBS-0006-2 Revision No. 01 Effective Date: 05/17/2007 Page 36 of 46

TABLE OF CONTENTS

SECTION TITLE

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

PAGE

37

A.2 Fuel Reprocessing Facilities .................................................................................................. 37

A.3 Fuel Fabrication Facilities....................................................................................................... 41

A.4 Plutonium Finishing Facilities ................................................................................................. 42

A.5 Research and Development Facilities .................................................................................... 44

A.6 Waste Facilities......................................................................................................................45

LIST OF TABLES

TABLE TITLE

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

PAGE

37

A-2 Radionuclides of concern for all production reactors .............................................................. 38

A-3 Research and test reactors years of operation....................................................................... 38

A-4 Radionuclides of concern for all research and test reactors ................................................... 38

A-5 Fuel reprocessing facilities years of operation........................................................................ 39

A-6 Radionuclides of concern for all reprocessing facilities........................................................... 40

A-7 Activity composition of Hanford reference weapons-grade plutonium 

mixture...................................................................................................................................40

A-8 Activity composition of Hanford reference fuel-grade plutonium mixture................................. 40

A-9 Activity composition of Hanford reference commercial power fuel-grade 

plutonium mixture................................................................................................................... 41

A-10 Fuel fabrication facilities years of operation............................................................................ 42

A-11 Radionuclides of concern for all fuel fabrication and storage facilities .................................... 42

A-12 Radiological characteristics of Hanford uranium mixtures ...................................................... 42

A-13 Impurities in recycled uranium at Hanford .............................................................................. 43

A-14 Inhalation class for Hanford uranium compounds................................................................... 43

A-15 Plutonium finishing facilities years of operation ...................................................................... 44

A-16 Radionuclides of concern for plutonium finishing facilities ...................................................... 44

A-17 100 and 200 Area research and development facilities years of operation ............................. 45

A-18 300 Area research and development facilities years of operation........................................... 45

A-19 Radionuclides of concern for all 100, 200, and 300 Area research and 

development facilities............................................................................................................. 45

A-20 Waste facilities years of operation.......................................................................................... 46

A-21 Radionuclides of concern for all waste facilities...................................................................... 46

A-22 Tank waste radionuclide inventory ......................................................................................... 46

ATTACHMENT A

DESCRIPTION OF FACILITIES AND PROCESSES

Page 1 of 11
Document No. ORAUT-TKBS-0006-2 Revision No. 01 Effective Date: 05/17/2007 Page 37 of 46

A.1 REACTORS 

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

fission products [23]. 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 might 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 [24]. 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 wholebody dose (see Internal and External Dosimetry Sections of this Site Profile). 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. Production reactors years of operation [25]. 

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

A.2 FUEL REPROCESSING FACILITIES

External exposures were primarily from high-energy betas and photons in the separations facilities 

associated with FP [26]. 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 listed in 

Tables A-7, A-8, and A-9 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). 

ATTACHMENT A

DESCRIPTION OF FACILITIES AND PROCESSES

Page 2 of 11
Document No. ORAUT-TKBS-0006-2 Revision No. 01 Effective Date: 05/17/2007 Page 38 of 46

Table A-2. Radionuclides of concern for 

all production reactors.

a (Marceau et al. 

2002) 

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-3. Research and test reactors years of operation [27]. 

Reactor

HTR PCTR TTR PRTR PRCF HTLTR FFTF

1943–1972 1954–1970 1954–1978 1960–1969 1962–1976 1968–1971 1980–1994

Table A-4. Radionuclides of concern for all 

research and test reactors. (Marceau et al. 

2002) 

Ru-103 U-235 S-35

Rh-106 Pu-238 Po-210

Ru-106 U-238 Ra-226

Ba-140/La Pu-239 U-233

Ce-141 H-3 Np-237

Ce-144 Co-60 Pu-240

Pr-144 Zr-95/Nb Cm-244

U-233 Cf-252

A special study in the 1980s indicated frequent-intermittent releases of plutonium in the workplaces at 

levels below detectability for normal air sampling. This resulted in <10 mrem committed effective 

dose equivalent (Bihl, 1993; Lyon et al. 1988, 1989). 

The new lung model for internal dosimetry uses absorption types. The new types are F, M, S for fast, 

moderate, and slow, respectively. 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 PR Room. Contamination remaining in old gloveboxes, hood exhaust 

ducts, high-efficiency particulate air (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. 

ATTACHMENT A

DESCRIPTION OF FACILITIES AND PROCESSES

Page 3 of 11
Document No. ORAUT-TKBS-0006-2 Revision No. 01 Effective Date: 05/17/2007 Page 39 of 46

Plutonium at 233-S was type M 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 are 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 2.4.6). 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 that resulted 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 wholebody exposure (see External and Internal Dosimetry Sections of this Site Profile).

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 Publication 66 (ICRP 1994), is 

listed in Table A-14. 

The years of operation and radionuclides of concern are listed in Tables A-5 and A-6. 

Table A-5. Fuel reprocessing facilities years of operation [28]. 

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. In 1968, 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 shut down in 1967.

d. Closed in June 1972 and reopened in November 1983. 

e. Shut down in 1972 and opened in 1983 (there were 17 startups 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 cesium and strontium waste tanks NOTE: date for d has not been resolved.

* More than one date was found 

UNK - No date found 

ATTACHMENT A

DESCRIPTION OF FACILITIES AND PROCESSES

Page 4 of 11
Document No. ORAUT-TKBS-0006-2 Revision No. 01 Effective Date: 05/17/2007 Page 40 of 46

Table A-6. Radionuclides of concern for all 

reprocessing facilities. (Marceau et al. 

2002) 

Ru-103 U-235

Ru-106 Np-237

I-131 U-238

Cs-137 Pu-239

Ba-140/La Am-241

Ce-141 H-3

Ce-144 Co-60

U-233 Sr-90

Table A-7. Activity composition of Hanford reference weapons-grade plutonium mixture. (Carbaugh 

2003)

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)

Pu-238 8.56E-03 8.23E-03 7.91E-03 7.60E-03 7.31E-03 7.03E-03 6.75E-03

Pu-239 5.77E-02 5.77E-02 5.77E-02 5.77E-02 5.77E-02 5.77E-02 5.77E-02

Pu-240 1.36E-02 1.36E-02 1.36E-02 1.36E-02 1.36E-02 1.36E-02 1.36E-02

Pu-241 8.24E-01 6.48E-01 5.09E-01 4.00E-01 3.15E-01 2.48E-01 1.95E-01

Pu-242 1.97E-06 1.97E-06 1.97E-06 1.97E-06 1.97E-06 1.97E-06 1.97E-06

Am-241 0 5.83E-03 1.04E-02 1.39E-02 1.66E-02 1.87E-02 2.03E-02

Pu-239+240 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

Pu-239+240: Am-241 NA 12.2 6.87 5.13 4.28 3.80 3.50

Pu-239+240: Pu-238 8.33 8.67 9.01 9.38 9.74 10.1 10.5

Pu-241: Pu-239+240 11.6 9.09 7.15 5.62 4.42 3.48 2.73

Pu alpha:Pu-239+240 1.12 1.20 1.26 1.30 1.34 1.36 1.38

Pu alpha: Pu-238 9.33 9.66 10.0 10.4 10.7 11.1 11.6

Pu alpha: Am-241 NA 14.6 8.63 6.67 5.72 5.18 4.84

Pu-241: 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-8. Activity composition of Hanford reference fuel-grade plutonium mixture. (Carbaugh 2003)

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)

Pu-238 1.71E-02 1.64E-02 1.58E-02 1.52E-02 1.46E-02 1.40E-02 1.35E-02

Pu-239 5.26E-02 5.26E-02 5.26E-02 5.26E-02 5.26E-02 5.26E-02 5.25E-02

Pu-240 2.72E-02 2.72E-02 2.72E-02 2.72E-02 2.72E-02 2.71E-02 2.71E-02

Pu-241 3.09E+00 2.43E+00 1.91E+00 1.50E+00 1.18E+00 9.29E-01 7.30E-01

Pu-242 3.93E-06 3.93E-06 3.93E-06 3.93E-06 3.93E-06 3.93E-06 3.93E-06

ATTACHMENT A

DESCRIPTION OF FACILITIES AND PROCESSES

Page 5 of 11
Document No. ORAUT-TKBS-0006-2 Revision No. 01 Effective Date: 05/17/2007 Page 41 of 46

Am-241 0 2.19E-02 3.89E-02 5.22E-02 6.24E-02 7.03E-02 7.63E-02

Pu-239+240 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

Pu-239+240: Am-241 NA 3.64 2.05 1.53 1.28 1.13 1.04

Pu-239+240: Pu-238 4.67 4.86 5.05 5.24 5.46 5.69 5.90

Pu-241: Pu-239+240 3.87 3.05 2.40 1.88 1.48 1.17 9.16

Pu alpha:Pu-239+240 1.21 1.21 1.20 1.19 1.18 1.18 1.17

Pu alpha: Pu-238 5.67 5.87 6.05 6.24 6.46 6.69 6.90

Pu alpha: Am-241 NA 4.39 2.46 1.82 1.51 1.33 1.22

Pu-241: 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.

Table A-9. Activity composition of Hanford reference commercial power fuel-grade plutonium mixture. 

(Carbaugh 2003)

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)

Pu-238 1.71E-01 1.64E-01 1.58E-01 1.52E-01 1.46E-01 1.40E-01 1.35E-01

Pu-239 3.41E-02 3.41E-02 3.41E-02 3.41E-02 3.41E-02 3.41E-02 3.41E-02

Pu-240 5.90E-02 5.89E-02 5.89E-02 5.89E-02 5.89E-02 5.88E-02 5.88E-02

Pu-241 1.34E+01 1.05E+01 8.28E+00 6.51E+00 5.12E+00 4.03E+00 3.17E+00

Pu-242 1.97E-04 1.97E-04 1.97E-04 1.97E-04 1.97E-04 1.97E-04 1.97E-04

Am-241 0 9.49E-02 1.69E-01 2.26E-01 2.79E-01 3.04E-01 3.31E-01

Pu-239+240 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

Pu-239+240: Am-241 NA 0.981 0.551 0.411 0.344 0.305 0.281

Pu-239+240: Pu-238 0.544 0.568 0.589 0.612 0.636 0.664 0.688

Pu-241: Pu-239+240 144 113 89.1 70.0 55.1 43.3 34.1

Pu alpha:Pu-239+240 2.85 2.77 2.71 2.63 2.57 2.52 2.45

Pu alpha: Pu-238 1.55 1.57 1.59 1.61 1.64 1.67 1.69

Pu alpha: Am-241 NA 2.72 1.49 1.08 0.857 0.770 0.689

Pu-241: 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 shutdown of the building until cleanup. The years of 

operation and radionuclides of concern are listed in Tables A-10 and A-11 below. The radiological 

characteristics of Hanford uranium mixtures are listed in Table A-12 and the impurities in recycled 

Hanford uranium are listed in Table A-13. The inhalation class for Hanford uranium compounds is 

ATTACHMENT A

DESCRIPTION OF FACILITIES AND PROCESSES

Page 6 of 11
Document No. ORAUT-TKBS-0006-2 Revision No. 01 Effective Date: 05/17/2007 Page 42 of 46

listed in Table A-14. Note: The default solubility classes should be used only when bioassay data are

inconclusive [29].

Table A-10. Fuel fabrication facilities years of operation [30]. 

Fuel fabrication

313 314 333 303 Facilities 306

3/1944–1/1971 7/1944–1971 1961–1988 1944–present 5/1957–1984

Table A-11. Radionuclides of concern for all fuel fabrication and storage facilities [31]. 

Am-241 Np-237 Pu-238 Pu-239 Th-232 U-235 U-238

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, 

10-in.- 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 [32]. 

Table A-12. Radiological characteristics of Hanford uranium mixtures. 

(Carbaugh 2003)

Uranium mixture

Weight 

percentagea,b

Natural 

(NU)

Depleted 

(DU)

Recycled 

(RU)

Commercial 

fuel (CF)

U-234 0.0057 0.0005 0.0082 0.0300

U-235 0.7204 0.2500 0.9700 2.9600

U-236 Negligible Negligible 0.0680 Negligible

U-238 99.2739 99.7500 98.9500 97.0100

Specific constituent activity in mixture (μCi/g, nCi/mg, or pCi/μgc

U-234 0.3563 0.0313 0.5125 1.8750

U-235 0.0156 0.0054 0.0210 0.0639

U-236 Negligible Negligible 0.0440 Negligible

U-238 0.3336 0.3352 0.3325 0.3260

Total 0.7054 0.3718 0.9099 2.2649

Specific constituent activity in mixture (dpm/μg)c

U-234 0.7909 0.0694 1.1378 4.1625

U-235 0.0345 0.0120 0.0465 0.1419

U-236 Negligible Negligible 0.0977 Negligible

U-238 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

U-234 0.5051 0.0840 0.5632 0.8279

U-235 0.0221 0.0145 0.0230 0.0282

U-236 Negligible Negligible 0.0484 Negligible

U-238 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.

ATTACHMENT A

DESCRIPTION OF FACILITIES AND PROCESSES

Page 7 of 11
Document No. ORAUT-TKBS-0006-2 Revision No. 01 Effective Date: 05/17/2007 Page 43 of 46

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.

Internal exposures in the operating areas were related primarily to contamination incidents involving 

americium and plutonium because airflow patterns were designed to control the flow from areas of 

lower air contamination potential to higher. Maintenance and cleanup operations were conducted in 

protective clothing that included respiratory protection. Exposures occurred by inhalation, absorption, 

and injection (i.e., wound sites). Internal exposure in the vault areas was minimal because 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 [33]. 

Table A-13. Impurities in recycled uranium at Hanford. (Carbaugh 2003)

Constituent Maximum alloweda Observed rangeb Reference levelc

Plutonium 10 ppb U <1–2 ppb U 0.4 nCi Pu-alpha/g U

Neptunium Not established 0.04-0.16 ppm U 0.4 nCi Np-237/g U

Thorium 750 ppm U 8–10 ppm U 5 pCi Th-232/g U

Tc-99 Not established 3–4 ppm U 0.2 μCi Tc-99/g U

Ru-103,106 <20 μCi/lb U <6 μCi/lb U 40 nCi Ru-106/g U

ZrNb-95 <10 μCi/lb U <4 μCi/lb U 20 nCi ZrNb-95/g U

Other gamma emitters

excluding Tc-99

<2 μCi/lb U 0.09 0.75 μCi/lb U 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 were 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 evaluation 

of intakes. The use of the reference levels is expected to result in a slight overestimate of dose compared to levels 

actually observed in 1988.

Table A-14. Inhalation class for Hanford uranium compounds. (Carbaugh 2003)

ICRP 30 inhalation 

class from lung 

fluid studies Compound and location

Recommended 

ICRP 66 lung 

absorption typed

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. 

In February 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 

ATTACHMENT A

DESCRIPTION OF FACILITIES AND PROCESSES

Page 8 of 11
Document No. ORAUT-TKBS-0006-2 Revision No. 01 Effective Date: 05/17/2007 Page 44 of 46

resulted in high external radiation exposures and in widespread contamination throughout the 

RECUPLEX room [34].

The new lung model for internal dosimetry uses absorption types. The new types are F, M, S for fast, 

moderate, and slow, respectively. 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 gloveboxes, 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 1990s of the isotopic 

distribution of plutonium at PFP, it was stated there were approximately 3.7 million g of plutonium with 

the 240Pu content ranging from 4% to >19% (Crowe and Szempruch 1994). Note: The default 

solubility classes should be used only when bioassay data is inclusive.

The years of operation and the radionuclides of concern are listed in Tables A-15 and A-16. The 

activity composition for Hanford reference plutonium mixtures is listed in Tables A-7, A-8, and A-9.

Table A-15. Plutonium finishing facilities years of operation [35]. 

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 glovebox 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, 10-in.-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. Shut down in 1976 

as a result of explosion in 242-Z; the RMC Line restarted in 1985; shut down in 1989.

d. In December 1975, it was shut down for upgrades; restarted in 1976; shut down in April 1976 as a result of explosion in 

242-Z.

e. In 1969, changed from batch to continuous process; in April 1976 shut down because of strike; in August 1976 

restarted; shut down in August 1976 as a result of explosion in americium recovery area.

Table A-16. Radionuclides of concern for plutonium finishing facilities [36]. 

U-233 Np-237 Pu-238 Pu-239 Pu-240 Pu-241 Pu-242 Am-241

A.5 RESEARCH AND DEVELOPMENT FACILITIES

The 21 major Research, Development, and Testing Facilities at Hanford were 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 2.7.1 through 2.7.21 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-17 and A-18 below.

ATTACHMENT A

DESCRIPTION OF FACILITIES AND PROCESSES

Page 9 of 11
Document No. ORAUT-TKBS-0006-2 Revision No. 01 Effective Date: 05/17/2007 Page 45 of 46

Table A-17. 100 and 200 Area research and development facilities years of operation [37]. 

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-18. 300 Area research and development facilities years of operation [38]. 

Facility/process

308 318 320 321 324 325 326

1960–1990*a 1983–presentb 1966–present 1944–1988c 1966–present 1953–presentd 1953–present

Facility/process

327 329 331 3706 3730 3732 3741 3745

1953–1987 1952–present 1972–present 1945–

late1960se

1949–1981 1949–1970 1944–1956 10/1944–

1983f

a. In mid-1960s, PRTR fuel work was terminated; neptunium-aluminum fuel elements produced in late 1960s; high bay 

area added in 1971; from 1977 to 1991, FFTF fuel elements were produced; the 308A annex was added in 1979; 

TRIGA reactor was installed in the late 1970s. 

b. The HTLTR commenced operation in the 318 Building in 1967; the reactor was shut down in 1971; the reactor was 

removed in the early 1980s; 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; in 1949, a cold test of REDOX process was performed; a 

cold test of the PUREX process occurred 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 June 

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 1960s; 

building converted to offices in the 1970s and still in use in the early 1990s. 

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-19. Radionuclides of concern for 

all 100, 200, and 300 Area research and 

development facilities [39]. 

C-14 Pm-147

Ce-144 Pu-238

Co-60 Pu-239

Cs-137 Ru-103

Cu-64 Ru-106

FP Sr-90

I-131 U-238

U-235 Y-90

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 

ATTACHMENT A

DESCRIPTION OF FACILITIES AND PROCESSES

Page 10 of 11
Document No. ORAUT-TKBS-0006-2 Revision No. 01 Effective Date: 05/17/2007 Page 46 of 46

unplanned external exposures were documented in incident or accident reports. In 1994, data were

included in Boomer et al. (1994) on tank waste radionuclide inventory. The data from that report are 

included in Table A-22. 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 

August 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 glovebox. Because 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 listed in Tables A-20 and A-21 below.

Table A-20. Waste facilities years of operation [40]. 

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-21. Radionuclides of concern for 

all waste facilities [41]. 

Ce-141 Pu-238

Ce-144 Pu-239

Co-60 Ru-103

Cs-137 Ru-106

FP Sr-90

I-131 Y-90

Pm-147

Table A-22. Tank waste radionuclide inventory [42]. 

Mega curies of 

radioactive specie

Liquid components Solid components

Double-shell tanks Single-shell tanks Double-shell tanks Single-shell tanks

Cs-137 and Ba-137 6.40 E+01 2.53 E+01 2.33 E+00 8.45 E+00

Sr-90 and Y-90 3.93 E+00 1.14 E+01 2.17 E+01 1.13 E+02

Tc-99 2.28 E-02 7.82 E-03 1.35 E-03 7.82 E-03

Am-241 1.45 E-02 4.70 E-03 7.97 E-02 4.23 E-02

Np-237 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

ATTACHMENT A

DESCRIPTION OF FACILITIES AND PROCESSES

Page 11 of 11