ORAU TEAM

Dose Reconstruction

Project for NIOSH

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

Page 1 of 30

DOE Review Release 04/30/2009

Document Title:

Mound Site – Site Description

Document Number: ORAUT-TKBS-0016-2

Revision: 00 PC-2

Effective Date: 03/13/2009

Type of Document TBD

Supersedes: Revision 00 PC-1

Subject Expert(s): Jeff Vollmer

Site Expert(s): N/A

Approval: Signature on File Approval Date: 03/02/2009

Donald N. Stewart, Document Owner

Concurrence: Signature on File Concurrence Date: 03/03/2009

John M. Byrne, Task 3 Manager

Concurrence: Signature on File Concurrence Date: 03/02/2009

Edward F. Maher, Task 5 Manager

Concurrence: Signature on File Concurrence Date: 03/11/2009

Kate Kimpan, Project Director

Approval: Signature on File Approval Date: 03/13/2009

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-0016-2 Revision No. 00 PC-2 Effective Date: 03/13/2009 Page 2 of 30

PUBLICATION RECORD

EFFECTIVE 

DATE

REVISION

NUMBER DESCRIPTION

03/30/2004 00 New Technical Basis Document for the Mound Site – Site 

Description. First approved issue. Initiated by Jeff Vollmer.

07/07/2006 00 PC-1 Page change revision initiated for biennial review. Incorporates 

NIOSH formal review comments. Changes were made to the 

required language on pages 5 and 6 in Section 2.0. No sections 

were deleted. Approved issue of Rev 00 PC-1. 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 Paul J. 

Demopoulos.

Approval:

Signature on File ____________________________________

Stanley J. Waligora, TBD Team Leader

06/06/2006

Signature on File_____________________________________

John M. Byrne, Task 3 Manager

06/06/2006

Signature on File_____________________________________

Edward F. Maher, Task 5 Manager

06/07/2006

Signature on File_____________________________________

Kate Kimpan, Project Director

06/06/2006

Signature on File_____________________________________

James W. Neton, Associate Director for Science

07/07/2006

03/13/2009 00 PC-2 Approved page change initiated to remove information pertaining to 

Monsanto Chemical Company, the subject of a class of employees 

added to the Special Exposure Cohort. These changes occurred on 

pages 6 - 13, 15, 16, 18, and 20 in Sections 2.0, 2.2, and 2.3, 

respectively. NIOSH required language was revised on page 5 in 

Section 2.0. Updated references on pages 29 - 30 in Reference 

Section. In this revision, Figure 2-1 was formerly Figure 2-3. Figures 

2-1 and 2-2 from the previous revision were deleted. Incorporates 

formal internal and NIOSH review comments. No Sections were 

deleted. Training required: As determined by the Task Manager. 

Initiated by Donald N. Stewart.
Document No. ORAUT-TKBS-0016-2 Revision No. 00 PC-1 Effective Date: 07/07/2006 Page 3 of 30

TABLE OF CONTENTS

SECTION TITLE PAGE

Acronyms and Abbreviations ...............................................................................................................4

2.0 Introduction ..............................................................................................................................5

2.1 Purpose........................................................................................................................6

2.2 Scope...........................................................................................................................6

2.3 Site Activities and Processes........................................................................................6

2.3.1 Dayton Laboratory History ................................................................................6

2.3.2 Mound Laboratory.............................................................................................7

2.3.3 Buildings with Radionuclide Activity ................................................................ 10

2.3.4 Buildings without Radionuclide Activity ........................................................... 28

References ........................................................................................................................................29

LIST OF TABLES

TABLE TITLE

2-1 Locations and descriptions.......................................................................................................

PAGE

7

2-2 Chronology of significant Mound Laboratory programs and events .......................................... 9

2-3 Radionuclides and related compounds for HH Building.......................................................... 11

2-4 Radionuclides and related compounds for Building PP (38)................................................... 13

2-5 Radionuclides and related compounds for R Building ............................................................ 13

2-6 Radionuclides and related compounds for SM Building.......................................................... 15

2-7 Radionuclides and related compounds for SW Building ......................................................... 16

2-8 Radionuclides and related compounds for T Building............................................................. 18

2-9 Radionuclides and related compounds for WD and WDA Buildings ....................................... 20

LIST OF FIGURES

FIGURE TITLE

2-1 Mound (Unit V) site map.........................................................................................................

PAGE

11
Document No. ORAUT-TKBS-0016-2 Revision No. 00 Effective Date: 03/30/2004 Page 4 of 30

ACRONYMS AND ABBREVIATIONS

CERCLA Comprehensive Environmental Response, Compensation, and Liability Act

D&D decontamination and demolition

DOE U.S. Department of Energy

EEOICPA Energy Employees Occupational Illness Compensation Program Act

ft foot

LLW low-level [radioactive] waste

LSA low specific activity

MEMP Miamisburg Environmental Management Project

NIOSH National Institute for Occupational Safety and Health

ORAU Oak Ridge Associated Universities

R&D research and development

RTG radioisotopic thermoelectric generator

SRP Savannah River Plant

TBD technical basis document

TRU transuranic
Document No. ORAUT-TKBS-0016-2 Revision No. 00 PC-2 Effective Date: 03/13/2009 Page 5 of 30

2.0

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 at particular sites or categories of sites. They will be revised in the event 

additional relevant information is obtained about the affected site(s). These documents may be used 

to assist NIOSH staff in the completion of the individual work required for each dose reconstruction.

INTRODUCTION

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

The statute also 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 excludes Naval Nuclear Propulsion Facilities from being covered under the Act, 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 occupational radiation exposures are considered valid for inclusion in a 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 (NIOSH 2007a):

] 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, 42 C.F.R. Pt. 82) define “performance of duty” for 

DOE employees with a covered cancer or restrict the “duty” to nuclear weapons work (NIOSH 2007a).

• Background radiation, including radiation from naturally occurring radon present in 

conventional structures

• Radiation from X-rays received in the diagnosis of injuries or illnesses or for therapeutic 

reasons

 1 The U.S. Department of Labor (DOL) is ultimately responsible under the EEOICPA for determining the POC.
Document No. ORAUT-TKBS-0016-2 Revision No. 00 PC-2 Effective Date: 03/13/2009 Page 6 of 30

2.1 PURPOSE

The purpose of this document is to provide a Mound Laboratory Site Profile that contains technical 

basis information for use by the ORAU Team to evaluate the total occupational dose for EEOICPA 

claimants. 

2.2 SCOPE

The Mound Laboratory played an important role in the U.S. nuclear weapons program. Mound 

Laboratory activities were originally established in Dayton, Ohio, in the summer of 1943. The 

Monsanto Chemical Company operated the Dayton Laboratory at Units I, II, III, and IV. Of these, 

Units III and IV were created to produce large quantities of polonium. Operational experience at Units 

III and IV demonstrated the need for a specialized facility for polonium production and associated 

activities. This need led to the design and construction of the Mound Laboratory, initially known as 

Unit V of the Dayton Laboratory. The Mound Laboratory was initially occupied in 1948, and various 

research programs were begun; polonium production work was transferred to the new facility in 1949. 

The site’s role grew to include nuclear weapons component development and production, and such 

secondary missions as radioactive waste management and recovery, the use of radioactive materials 

for nonweapons purposes and the purification of nonradioactive isotopes for scientific and commercial 

research. This TBD contains supporting documentation to assist in the evaluation of worker dose 

from these processes at the Mound Laboratory, using the methodology in NIOSH implementation 

guides (NIOSH 2002, 2007b). 

Consideration of potential exposures and dose reconstruction methods for Monsanto Chemical 

Company operations are outside the scope of the Mound Laboratory TBDs.

Methods and concepts of measuring radiation exposure to workers have evolved since the beginning 

of Mound operations. An objective of this TBD is to provide supporting technical data to evaluate, 

with claimant-favorable assumptions, the total Mound occupational dose that can be associated 

reasonably with worker radiation exposure covered under EEOICPA legislation. This dose includes 

occupational internal and external exposures, occupationally required diagnostic X-ray examinations, 

and onsite exposure to site environmental releases. This TBD addresses evaluation of unmonitored 

and monitored worker exposure and missed dose. Consistent with NIOSH (2002, 2007b), this 

document identifies how to adjust the historic occupational dose to account for current scientific 

methods and protection factors.

In addition, this TBD presents technical basis methods used to prepare the Mound worker dose 

records for input to the NIOSH Interactive RadioEpidemiological Program and the Integrated Modules 

for Bioassay Analysis computer programs used to evaluate worker dose. Because information on 

measurement uncertainties is an integral component of the NIOSH approach, this document 

describes the uncertainty evaluation for the Mound exposure and dose records. 

This TBD describes Mound facilities and processes and historic information related to worker internal 

and external exposures. 

2.3 SITE ACTIVITIES AND PROCESSES

2.3.1

Dr. Charles Allen Thomas was director of Monsanto’s central research department in Dayton when, in 

1943, he was called into conference with General Leslie Groves. Following several days of 

discussions with General Groves, Monsanto accepted responsibility for the chemistry and metallurgy 

of polonium. This activity became known as the Dayton Project, or the Dayton Laboratory. Monsanto 

Dayton Laboratory History
Document No. ORAUT-TKBS-0016-2 Revision No. 00 PC-2 Effective Date: 03/13/2009 Page 7 of 30

started preliminary organization of the project at the company’s central research department on 

Nicholas Road in Dayton in September 1943. When the project expanded to other locations during 

World War II, the original Nicholas Road location became known as Unit I. Table 2-1 lists this and 

other Monsanto Chemical Company facilities.

Table 2-1. Locations and descriptions.

Location Description

Unit I Monsanto Central Research Department – 1515 Nicholas Road, Dayton, Ohio

Unit II Monsanto rocket propellant laboratory off Betty Lane, adjacent to present St. 

Henry’s Church next to Dayton Mall

Unit III Bonebrake Theological Seminary, 1601 W. First St., Dayton, Ohio

Unit IV Runnymede Playhouse, Dixon Ave. and Runnymede Road in Oakwood, Ohio

Unit V Mound Laboratory, Miamisburg, Ohio

Warehouse Warehouse at 3rd and Sears St., Dayton, Ohio

Marion Duplicate production facility in Marion, Ohio

The Dayton Laboratory’s primary activity was to extract Po-210 from radioactive feedstock provided 

by the Hanford Works located in the state of Washington, and using the material to fabricate parts for 

nuclear weapons. Polonium was never produced at Unit I. 

Early in July 1943 it became apparent that the Nicholas Road location would not be sufficient to house 

polonium production operations, so Monsanto leased a building at 1601 West First Street in Dayton. 

This building, which was built in 1879 to house the Bonebrake Theological Seminary, became known 

as Unit III. Polonium production activities were begun at Unit III in October 1944. In response to the 

need for additional space, in February 1944, the Army Corps of Engineers leased the Runnymede 

Playhouse and turned it over to Monsanto. This location was designated as Unit IV. In 1946, several 

floors were leased in a large warehouse in Dayton at Third and Sears Streets. Operations at this 

facility, known as the Warehouse, used only trace amounts of polonium, which were present from the 

analysis of environmental monitoring samples, bioassay samples from project personnel, and 

preliminary biological studies on the effect of polonium on laboratory animals.

2.3.2

As early as 1946, it became evident that a permanent polonium production facility was needed. The 

site selected for the permanent Mound Laboratory facility was on a hill 878 feet above sea level and 

about 200 ft above the Miami River in Miamisburg, Ohio. Mound Laboratory became the first 

permanent U.S. Atomic Energy Commission facility in May 1948. It is the Mound Laboratory that is 

the subject of this site profile; Units I-IV, referred to as ‘the Monsanto Chemical Company’ or ‘Dayton 

Laboratory’ are not within the scope of this document. At the Mound Laboratory there were originally 

14 buildings with 360,000 ft2 of space. Polonium processing began in February 1949. 

Mound Laboratory

At the same time, a standby facility, which was a duplicate of the Mound T Building, was built in 

Marion, Ohio. Radioactive material was never brought to that facility, which was referred to as the 

Marion, Ohio, facility or just Marion. Process equipment there was later dismantled and the facility 

was turned over to the General Services Administration. 

During World War II the Dayton Project was tasked with developing neutron sources for use as 

initiators in atomic bombs. Research included the chemistry of polonium and other elements as 

neutron sources, and the majority of manufacturing was of polonium-beryllium sources. In addition, 

the Project experimented with making liquid polonium sources and solid polonium sources of every 

sort. The basic process for manufacturing polonium-beryllium sources was to electroplate polonium 

onto an inert substrate, then chemically or electrochemically react some form of beryllium with the 

plated polonium to form a stable solid source. 
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During the early years of operating at the Mound facility in Miamisburg, OH, a number of small 

research activities were carried out involving radioisotopes of Ra-226, Ac-227, Th-228, and Th-232, 

Th-230, Pa-231 and U-233. From the early 1950s to the early 1980s Mound conducted various 

programs involving extraction and purification of Ra-226, Ac-227, Th-230 and Pa-231. Ores were 

typically depleted of Uranium before processing.

The narrowly focused polonium production work expanded to the development and production of 

weapons components. Production of 238Pu and 239Pu grew from the early work with polonium. 

Mound’s main focus was to support U.S. Department of Energy (DOE) weapons and nonweapons 

programs, especially in the areas of chemical explosives and nuclear technology. Its principal mission 

was to research, develop, and manufacture non-nuclear explosive components for nuclear weapons 

that were assembled at other sites.

Early programs investigated chemical and metallurgical properties of 210Po and its applications. 

Research and development (R&D) included the fabrication of neutron and alpha sources for weapons 

and nonweapons use. Starting in the early 1950s, Mound developed radioisotopic thermoelectric 

generators (RTGs), which have been used on a variety of missions to provide heat and power for 

spacecraft. Po-210 production declined in the 1960s until it phased out in 1971.

Developing, producing, and providing surveillance of detonators for military applications began in 

1957. Explosive timers were developed in 1959, and manufacture of the timers began in 1963. 

Ferroelectric transducers and firing set component development and manufacture began in 1962.

Tritium handling technologies began in the mid-1950s. Mound tritium programs supported weapons 

and nonweapons programs. Metal tritides were used at Mound primarily to trap 3

H using uranium 

tritides. In addition, research was conducted on metal tritides and tritium targets might also have 

been processed.

Other major operations included:

• Manufacture of enriched stable isotopes for medical, industrial, and general research

• Development and manufacture of chemical heat sources

• Recovery and purification of tritium from waste generated by Mound and other DOE sites

• Development of radioisotopic heat sources used by the National Aeronautics and Space 

Administration and other programs

• Research and development of chemical explosives and pyrotechnics, adhesives, plastics, and 

elastomers for the nuclear weapons program

• Research and development of thermonuclear energy fuel systems

• Research and development of the joining of exotic metals

• Development of instrumentation for the nuclear safeguard program

• Research and development of separation of gases and energy conversion systems

• Research and development of technologies for radioactive waste management

Table 2-2 summarizes Mound operations.
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Table 2-2. Chronology of significant Mound Laboratory programs and events.

Year Activity

1946 Mound Laboratory planning started.

1948 Mound Laboratory occupied (May).

1949 Polonium operations moved from Dayton Units to Mound Laboratory, beginning in February.

First program separated Ra-226 from barium rich uranium ore, pitchblende residue called K-65

K-65 wt%

Water 30%

Lead Oxide 19%

Barium Sulfate 7% (375 mg or Radium in the Barium)

Silicon dioxide 35%

Metals 9% Trace metals similar to Cotter Concentrate

Experimental extraction of Ra-226 from the K-65 was conducted in the R Bldg. In October Mound 

received 200 lbs of K-65 in a single drum.

Study of processes for decon of rad waste generated by Pu production reactors at Hanford.

From 1948-1952 three different types of processing wastes were studied to concentrate 

constituents such as Cs-137, Ru-106, SR-90, Zr-93, Co-60, Nb-94, Sb-125, Te-123, ni-63 and rare 

earth elements and Pu-239. Bench scale testing began in R building 

1950 Separation of 208Po and 209Po from proton (accelerator) irradiation of bismuth.

Separation of 227Ac from irradiated 226Ra.

Uranyl sulfate – heavy water fuel system research.

Civilian power reactor research involving uranium, 231Pa, and 239Pu; mission ended in 1963.

1951 Small amount of research with Ra-226 in preparation of cave operation in SW building. Involved 

irradiated Ra-226 and recovery of Ac-227 and Th-228 from Ra-226.

1952 Pilot plant installed in SW building for processing reactor waste. Reactor waste processing areas 

also included Warehouses 9 and 13, WD, SD, SW, R and M.

1953 SW Building (tritium handling) constructed with a dirt floor.

1954 Invention of the 210Po-fueld thermoelectric generator.

Initiation of several programs requiring tritium-handling technologies.

Construction of thorium refinery for breeder reactor program (never operated).

1955 Repackaging of 6,000 55-gallon drums containing thorium ore and sludge occurred through 1965 at 

three different times to help prevent the possibility of further contamination.

August 1955 small research program in R Bldg. Involving recovery and subsequent purification of 

Protactinium-231 from natural sources.

June 1955- Radium Cave operation shut down in June (Ra-226, Ac-227, Th-228, Ra-223, Ra-224 

daughters)

1956 Completed separation of 1.3 grams of 231Pa in Building HH.

Weighable quantities of 230Th (ionium) separated. 239PuBe neutron sources manufactured.

Nuclear weapon detonator development, production, and surveillance; mission ended in 1989.

1959 239Pu reactor fuels laboratory operational.

Tritium waste recovery and purification facility operational.

U-233 research involving about 10 research personnel

1960 Pu-238 used in large quantities in production operations. Process areas included the R, SM and 

PP Buildings.

1961 Development of 238Pu heat sources for thermoelectric generators.

1963 Several Po and Gadolinium Polinide heat sources containing 100-1000 Ci of Po-210 were 

encapsulated in refractory metal.

1964 190 mg of Ac-227 was processed in the New cave area.

1965 Gaseous effluent control system operational in SW Building.

1966 Thorium ore and sludge moved to bulk storage in Building 21.

1967 1. 54,000 Ci of high purity Po-210 were processed for Mound experimental work and commercial 

use.

2. 14.5 kg of Pu-238 were recovered from waste material.
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Year Activity

1968 PP Building 38 operational for processing 238Pu.

1969 1. Waste line break and subsequent contamination of the abandoned Miami-Erie Canal bed with 

238Pu.

Began tritium recycling from retired weapon parts.

2. Three thousand seven hundred and one Curies of Po-210 were produced for both internal and 

external customers.

3. Six Snap 27 sources were produced. Each source contained 3735 Ci of Pu-238

10/70 –

6/71

Plutonium inventory was reduced to a minimum level. 22.5 kg of Pu-238 scrap was shipped to SRS 

burial.

1972 Tritium effluent control project began.

Non-weapons polonium work terminated.

1973 Pu-238 oxide was processed for 4 multihundred watt (4.2 Kq each) and 2 viking sources (1.2 Kg 

each)

1974 Thorium ore and sludge completely removed from site.

210Po decontamination of Technical (T) Building completed.

1975 238Pu recovery operations terminated.

1977 Californium Multiplier Neutron Radiography Facility installed.

1989 Removal of soil contaminated with uranium near Building 34.

1990 238Pu decontamination of inactive laboratories in the Research (R) Building.

1991 Removal of 238Pu-contaminated waste line connecting the HH Building with the WD facility.

1993 DOE decision to transfer defense mission from Mound.

238Pu decontamination of PP Building 38 and Acid Leach Field (Area D).

1994 Demolition of SM Building structure contaminated with 238Pu.

1995 All weapon components production terminated.

1996 Demolition of SD Building (sanitary waste treatment facility) and Building 21 (thorium ore and 

sludge bulk storage facility) including excavation of contaminated soil.

Miami-Erie Canal removal action (238Pu contaminated sediments) fieldwork begins in October.

1997 Removal of soil contaminated with 227Ac at Area 7.

1998 Miami-Erie Canal removal action fieldwork completed; approximately 30,000 yd3 removed for off 

site disposal.

2.3.3

Figure 2-1 shows the Mound Laboratory site. The buildings of concern at the Mound Laboratory 

include HH, PP (also called Building 38), R, SM, SW, T, and WD/WDA. Supporting buildings that 

were not directly involved in research or productions considered in this TBD evaluation include: 

Buildings with Radionuclide Activity

• Warehouses 9, 13, and 15

• Buildings 15, 21, 34, 50, 59, 68, B, E, H, I, M, P, RR, and SD

HH Building

HH Building or Hydrolysis House derived its name from its primary function, the hydrolysis of highly 

radioactive bismuth chloride and aluminum chloride solutions. In 1963, the HH Building was 

converted to stable gaseous isotope separation using thermal diffusion, liquid diffusion, and cryogenic 

processes. Table 2-3 is a summary of the rooms, dates, and radionuclides for the HH Building. (All 

dates represent the duration of actual use of radioisotopes in the projects.) 

PP Building (38)

The Plutonium Processing (PP) Building (38) was completed in December 1967. SM Building 

processes, fabrication operations, and recovery processes were transferred to PP Building along with 

waste treatment facilities, R&D, which included material research, and analytical laboratory support 
Document No. ORAUT-TKBS-0016-2 Revision No. 00 PC-2 Effective Date: 03/13/2009 Page 11 of 30

Figure 2-1. Mound (Unit V) site map.

Table 2-3. Radionuclides and related compounds for HH Building.

Rooms Radionuclides and related compounds Dates used

HH-3,4 H-3 1960-1990

Xe (all isotopes) 1964-1983

Stable isotopes, Kr-85 1964-present

HH-5 Pa-231, Fe-59, Al-26, Ca-45, Co-60, Cu-65 1955-1956

U-233, -234, -235, -238, Th-230, -232, Pa-231, Th-230, -232 daughters 1956

H-3 1960-1990

Xe (all isotopes) 1964-1983

Stable isotopes, Kr-85 1964-present

HH-6 Pa-231, Fe-59, Al-26, Ca-45, Co-60, Cu-65 1955-1956

U-233, -234, -235, -238, Th-230, -232, Th-230, -232 daughters 1956

HH-8 Ag-Po, Te-Po, PoCl2, Po-208, -209, -210, Bi-209, -210, Po(NO3)2, Fe-55, -59, 

Si-31, Co-60, Pb-209, Sb-124, Sn-121, Zn-65, Cr-55, V-52, Te-121-134, 

Hg-203

1949-1958

Kr-85, Xe (all radioisotopes) 1961-1963

HH-9 H-3 1965-1985

HH-10, 11, 12 Ag-Po, Te-Po, PoCl2, Po-208, -209, -210, Bi-209, -210, Po(NO3)2, Fe-55, -59, 

Si-31, Co-60, Pb-209, Sb-124, Sn-121, Zn-65, Cr-55, V-52, Te-121-134, 

Hg-203

1949-1958

HH-119, 120, 121, 122 H-3 1964-1980

activities. PP Building was used primarily for processing 238Pu dioxide received from the Savannah 

River Plant (SRP).
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Plutonium dioxide was received in a powder form with the following isotopic mixture and a purity of 

99.9% according to (King 1995). 

(1 part per million) – 1E-4% Pu-236 3.0% Pu-240

80.2% Pu-238 0.6% Pu-241

15.9% Pu-239 0.1% Pu-242

Reference to 238Pu in PP Building was a composite of the mixture identified above. This mixture 

included trace amounts of 241Am, 237Np, and 234U. Dates represent the duration of radioisotope use in 

the projects. 

Thorium-232 was often substituted for 238Pu compounds for modeling purposes in research and 

development, because this isotope was less expensive and less hazardous, and had physical 

characteristics similar to 238Pu. It is possible, therefore, to find 232Th compounds identical to the 238Pu 

compounds.

The term high-fired, which is sometimes used, implies that the plutonium compound has been heated 

in a plasma torch process such that the lung solubility type is definitely S. The term non-high-fired

implies an absence of such heating and in extreme cases, where indicated, a lung solubility type of M 

or even F might exist where there is high solubility.

Table 2-4 summarizes PP Building rooms, dates, and radioisotopes.

R Building

R (for Research) Building, which was built in 1948, has handled a number of programs involving a 

number of radionuclides over the years. Some of the major programs are discussed below, as are 

elemental radionuclides and radioisotopic compounds from those processes.

Beginning in the fall of 1948, R&D for the 210Po program began. This was pilot-scale work for 

processing in T Building. R&D work with polonium extended into the 1970s.

Plutonium-238 research began in R Building in1959 and continued through the 1960s. The plutonium 

isotope concentration was the same as referenced in King 1995 for the material received at Mound 

from the Savannah River Site.

R&D was conducted with tritium in the “R” building. Experimentation with metal tritides and 

deuterides such as uranium tritide and lithium tritide occurred, as did developmental studies with

tritiated water.

Some tritides and tritiated compounds were so poorly metabolized that their biological half-lives were 

in the order of hours. This was not true for uranium tritides.

Table 2-5 summarizes rooms, dates, and radioisotopes in R Building.

SM Building

Special Metallurgical (SM) Building was built in 1960 and became operational in 1961. It was 

designed for the reception of a liquid plutonium nitrate mixture from the SRP that was used in a 

variety of programs, mainly heat source projects. In addition, SM Building housed recovery 

processing, waste treatment facilities, R&D, and analytical support activities.

Table 2-6 summarizes SM Building rooms, dates, and radioisotopes.
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Table 2-4. Radionuclides and related compounds for Building PP (38).

Room Radionuclides and related compoundsa Dates used

PP-CORR-5A PuO2 1967-1974

PP-6 PuO2, Pu(NO3)4, Pu(C2O4)4, Pu(OH)4 1967-1980

PP-6W PuO2, Pu(NO3)4, Pu(C2O4)4, Pu(OH)4 1967-pres

PP-CORR-10 PuO2 1967-pres

PP-13, PP-14 PuO2, Pu(NO3)4, Pu(C2O4)4, Pu(OH)4 1967-1980

PP-CORR-15, CORR-16, CORR-17 PuO2, Pu(NO3)4, Pu(C2O4)4, Pu(OH)4 1967 -1974

PP-18 PuO2, Pu(NO3)4 1967-pres

PP-24 PuO2, Pu(NO3)4, Pu(C2O4)4, Pu(OH)4 1967-pres

PP-100 PuO2 1967-pres

PP-113 Pu-(238,239)O2

Varied orphaned sources

1957-1989

1988-pres

PP-CORR-115 Pu-(238,239)O2 1967-pres

PP-127 PuO2, Pu(NO3)4, Pu(C2O4)4, Pu(OH)4 1967-pres

PP-CORR-134, PP-CORR-135, 

PP-CORR-136

PuO2 1967-pres

PP-CORR-140, PP-CORR-141, 

PP-CORR-142

PuO2, Pu(NO3)4, Pu(C2O4)4, Pu(OH)4, Th-232, ThO2, 

Th(NO3)4, Th(C2O4)4, Th(OH)4

1967-pres

PP-143(A1) PuO2, Pu(NO3)4, Pu(C2O4)4, Pu(OH)4, Th-232, ThO2, 

Th(NO3)4, Th(C2O4)4, Th(OH)4

1967-1980

PP-142(A2) PuO2, Pu(NO3)4, Pu(C2O4)4, Pu(OH)4, PuF4, PuC, 

Th-232, ThO2, Th(NO3)4, Th(C2O4)4, Th(OH)4, ThF4

1967-1980

PP-145(A3) PuO2 1967-1982

PP-146(B1) PuO2, Pu(NO3)4, Pu(C2O4)4, Pu(OH)4, PuF4, PuC 1967-1980

PP-147(B2), PP-148(B3) PuO2, Pu(NO3)4, Pu(C2O4)4, Pu(OH)4, PuF4, PuC, 

Th-232, ThO2, Th(NO3)4, Th(C2O4)4, Th(OH)4, ThF4

1967-1980

PP-149(B4) PuO2 1967-1982

PP-150->156 (C1->C3, D1->D3) PuO2, Pu(NO3)4, Pu(C2O4)4, Pu(OH)4, PuF4, PuC 1967-1980

PP-157(E1),158(E2),162,163 PuO2 1967-1980

PP-159(E3) PuO2, Pu(NO3)4, Pu(OH)4, PuF4 1967-1980

a. Plutonium-238 was the designated radioisotope in every room unless otherwise specified. Other isotopes of the mixture 

identified in the introduction along with small amounts of 241Am, 237Np, and 234U. Thorium-232 was sometimes used as 

a stand-in for plutonium.

Table 2-5. Radionuclides and related compounds for R Building. Rooms Radionuclides and related compounds Dates used

R-117, 120, 

127, 128, 129, 

130, 131, 133, 

143, 144, 151, 

152, 155, 159, 

160, 161, 162 

and 167

AlCl3, BiCl4, Ag-Po, Te-Po, PoCl2, Po-210, Bi-210, Po(NO3)2, Fe-55, -59, Si-31, Co-60, Pb-209, Sb-124, 

Sn-121, Zn-65, Cr-55, V-52, Ga-70, -72, Cs-137, Sr-90, Se-75, Ag-112, Te-121-134, Hg-203

1948-1951

R-105, 106 H-3, HTO, 1958-1965

H-3, Li(D,T), U-238(D,T) 1965-1978

R-108 Po-208, -210, H-3, 1948-1965

H-3, Li(D,T), U-238(D,T), Ti(D,T), Other tritides (Type F, S) 1975-PRES

R-110 Po-208, -210 1955-1972

H-3 1972-present

R-111 Ac-227, AcO2, Ac(NO3)4, Ac(C2O4)4, Ra-223, -224, -226, Th-228, -229, -239, Ac and Ra daughters 

Po-208, -210, H-3

1951-1965

R-112 H-3, Li(D,T), U-238(D,T), Other Tritides (Type F, S) 1973-1993

R-113,114,115 Ac-227, AcO2, Ac(NO3)4, Ac(C2O4)4, Ra-223, -224, -226, Th-228, -229, -239, Ac and Ra daughters 1951-1955

Po-210, Pu-238, -239, Po/Be, PoF2, Po/B, Pu/Be, PuF2, Pu/B 1956-1961

H-3 1978-present

R-116 Po-210, Pu-238, -239, Po/Be, PoF2, Po/B, Pu/Be, PuF2, Pu/B 1956-1961

Pu-238, -239, PuBe, Am-241 1956-1962

H-3, Li(D,T), U-238(D,T) 1960-1965
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R-117 Pu-238, -239, Pu/Be, PuO2, Pu-238/Zr, Pa-231, Po-210/Be, Th-230 1948-1990

R-118 Ac-227, AcO2, Ac(NO3)4, Ac(C2O4)4, Ra-223, -224, -226, Th-228, -229, -230, (Ac and Ra daughters) 1955

U-234, -235, -238, Pa-231, Th-230, -232, and Th-232 daughters 1956-1958

R-119, 120, 

121,123

Po-210, Bi-210, AlCl3, BiCl3, Po(NO3)2, PoCl2, Po/Ag, Po/Te 1948-1951

Ac-227, AcO2, Ac(NO3)4, Ac(C2O4)4, Ra-226, Th-228, -229, -230, AcF4, AcI4, Ac-227 daughters, 1951-1953

Pa-231, Th-230, -232, and Th-232 daughters, U-234, -235, -238 1956-1958

Pu-239, Am-241 1956-1962

Pu-238, Oxide, Neutrons 1959-1962

Pu-238, Pu(NO3)4, Pu(NO3)6, PuO2, Pu-Cu, Pu(C2O4)4, Pu(O2).5H2O, Pu(OH), PuF4, PuCl4, Pu-Se, 

Pu-Zr, H-3, Pu rare earths, Po alloys and compounds

1959-1979

R-127 Po-210, Bi-210, AlCl3, BiCl3, Po(NO3)2, PoCl2, Po/Ag, Po/Te 1948-1951

Fe-55, -59 1952-1954

H-3 1956-1961

PuO2, PuF4, Pu-MoCl4, Pu-MoF4 1965-1978

H-3, Pu-239 1987-present

R-128 Po-210, Bi-210, Po(NO3)4, PoCl2, Po/Ag, Po/Te 1948-1954

PuO2, PuF4, Pu-MoCl4, Pu-MoF4. 1965-1978

H-3, U(D,T) 1987-present

R-129,130 Po-210, Bi-210, P(NO3)2, PoCl2, Po/Ag, Po/Te 1948-1951

Ac-227, AcO2, Ac(NO3)4, Ac(C2O4)4, Ra-223, -224, -226, Th-228, -229, -230 1951-1953

Pu-238, PuO2, PuF4, Pu-MoCl4, Pu-MoF4, PuCl4 (Th-232 compounds replacing Pu-238 compounds for 

analytical studies)

1965-1978

H-3, Pu rare earths, Polonium alloys and compounds 1990-present

R-131 Po-210, Bi-210, Po(NO3)2, PoCl2, Po/Ag, Po/Te 1948-1951

Pu-238, PuO2, PuF4, Pu-MoCl4, Pu-MoF4, PuCl4, Cm-244 1965-1978

R-133 Po-210, Bi-210, Po(NO3)2, PoCl2, Po/Ag, Po/Te 1948-1954

Ac-227, AcO2, Ac(NO3)4, Ac(C2O4)4, Ra-226, Th-228, -229, -230, AcF4, AcI4, Ac-227 daughters 1951-1953

Pa-231, U-234, -235, -238, Th-230, -232; also Th-230, -232 daughters 1956-1958

Pu-238, PuO2, PuF4, Pu-MoCl4, Pu-MoF4, PuCl4, Cm-244. 1965-1978

R-134 H-2, U-238, U-238(D,T) 1986-present

R-137 Ac-227, AcO2, Ac(NO3)4, Ac(C2O4)4, Ra-226, Th-228, -229, -230, AcF4, AcI4, Ac-227 daughters 1951-1953

R-140 Th-228, -230, -232, U-234, -235, -238, Pu-238, -239, Po-208, -209, -210, Cs-137, Pa-231, Ac-227, 

Ra-223, -224, -226, Sr-90

1950-1969

Pu-238, -239, -240, -241 (alloys, compounds and mixtures), Pu(NO3)2, Ac-227, Am-241 1969-present

R-142 Ra-226, Ra(CO3), Ra(NO3)2, RaBr2, Ac-227, Ac(C2O4)4, AcF2, K-40, Ba(NO3)2, Th-228, -229, -230, 

radon and daughters, Po-208, -209, -210 

1949-1953

Pu-238,239, U-234,235,238, Th-230, Pa-231, Th-230 daughters 1956-1969

PuO2, (for Pu-238,239) 1966-1979

R-143,144 Po-210, Bi-210, AlCl3, BiCl3, Po(NO3)2, PoCl2, Po/Ag, Po/Te 1948-1951

PuO2, (for Pu-238, -239) 1972-1976

R-145,147 Ra-226, Ra(CO3), Ba(CO3), Ac(NO3)2, Ra/Ba, Ac-227, Ac(C2O4)4, AcO2, Th-228, -229, -230 1949-1954

Fe-59, Al-26, Ca-45, Co-60, Pa-231, Cu-65 1955-1956

Pu-239, Am-241 1956-1959

Pu-238 oxide, neutrons 1960-1962

Pu-238, -239, PuO2, U-234, -235, -238 1968-1975

R-148,149 Ra-226, Ra(CO3), Ba(CO3), Ac(NO3)2, Ra/Ba, Ac-227, Ac(C2O4)4, AcO2, Th-228, -229, -230, Po-208, 

Pa-231

1949-1954

Fe-59, Al-26, Ca-45, Co-60, Pa-231, Cu-65, Pu-238 1954-1958

Pu-238, Pu(C2O4)4, Pu(NO3)4, Th-230, 1960-1968

PuO2, Pm-146->149, U(234)(NO3)4, U(234)O2, Pu/Zr 1970-1980

R-151 Po-210, Bi-210, Po(NO3)2, PoCl2, Po/Ag, Po/Te 1948-1951

Pu-238, -239, Pu(NO3)4, Pu(NO3)6, PuO2, Pu(OH), Pu(C2O4)4, Pu(O2).5H2O, PuCl4, PuF4, Pu(SO4)2, 

Np-237, and EDTA, citrates, and other substances acting like chelating agents were present

1958-1983

R-152 Po-210, Bi-210, AlCl3, BiCl3, Po(NO3)2, PoCl2, Po/Ag, Po/Te 1948-1954

Ac-227, AcO2, Ac(NO3)4, Ac(C2O4)4, Ra-226, Th-228,229,230, AcF4, AcI4 1951-1953

R-155 Po-210, Bi-210, AlCl3, BiCl3, Po(NO3)2, PoCl2, Po/Ag, Po/Te 1948-1951

U-235, -238, Pu-239, Np-237, Cm-244, Am-241, (the following were tried in combination with those 

listed: Ni-63, Co-60, Si-31, Z-65, Bi-210, Pb-210, Zr-95, Al-26 are rare earth elements)

1956-1969

R-159 Po-210, Bi-210, AlCl3, BiCl+, Po(NO3)2, PoCl2, Po/Ag, Po/Te 1948-1951

U-235, -238, Pu-239, Np-237, Cm-244, Am-241, (the following were tried in combination with those 

listed: Ni-63, Co-60, Si-31, Z-65, Bi-210, Pb-210, Zr-95, Al-26 are rare earth elements)

1956-1969

R-160,161 Po-210, Bi-210, AlCl3, BiCl3, Po(NO3)2, PoCl2, Po/Ag, Po/Te 1948-1951

Ac-227, AcO2, Ac(NO3)4, Ac(C2O4)4, Ra-226, Th-228, -229, -230 1951-1953

R-162 Ru-106, Cs-137, Sb-125, Te-121,127, Zr-93,95, Nb-94, Sr-90, Pu-238, -239, Y-88, -90, -91, Ce-144 and 

other rare earths

1948-1951

Pu-238, -239 1950

U-233, -235, -238 1958-1959
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R-166 Po-210 1961-1968

R-167 Ru-106, Cs-137, Sb-125, Te-121->134, Zr-93, -95, Nb-94, Sr-90, Pu-238, -239, Y-88, -90, -91, Ce-144 

and other rare earths

1948-1951

Pu-239, U-234, -235, -238, I-131, Cs-137, Ce-144, Sr-90, Tc-99, Xe-133, Y-88, -90, -91 1949-1952

Fe-55, -59, Al-26, Ca-45, Co-60, Pa-231, Cu-65. 1954-1955

Pu-239, Ac-227, neutrons 1955-1957

U-233, Th-229, -230, -232 1958

Sr-90, Y-88, -90, -91, Pa-231. 1960-1962

Pa-231, -233, Ce-141, -144, Am-241, Cm-244, U-233, Th-230, -232, Ra-226, Ti-208 1956-1987

R-168 U-238, UF4, UO2 1958

R-169 Th-230, -232, U-234, -235, -238, Pu-238, -239, Po-208, -209, -210, Cs-137, Pa-231, Ac-227, Ra-223, 

-224, -226

1960-1980

U-235, -238, Pm-147, Ca-45 1980-present

R-170 U-238, Ca-45 1960-1964

R-171,172 Ra-223, -224, -226, Ac(NO3)2, Ac-227, Ac(C2O4)4, AcO2, Th-228, -229, -230, Ac and Ra daughters 1949-1954

U-235, -238 1961-1963

Pu-238, -239, -240, -241 (compounds, alloys and mixtures), Am-241, Ac-227, Ra-226 1965-1991

R-175,176 H-3 1970-present

R-197A Pu-238, -239, PuO2, Cm-244 1970-present

R-198 Pu-238, -239, Pu(NO3)4, PuO2, PuF4, Np-237, Ac-227, Cm-244, H-3, Po-210, PoF4, Li(D,T), U-234, 

-235, -238, U(D,T), Am-241, Pr-146->149

1956-1982

R Building 

crawl space 

Pu-238, -239, Ra-226, Ac-227, Po-210, Th-228, -229, -230 1948-present

R-CORR-5 Ac-222 1948-1984

Table 2-6. Radionuclides and related compounds for SM Building.

Room Radionuclides and related compounds Dates used

SM-1 Pu(NO3)4, PuO2, Pu(C2O4)4, Pu(OH)4, PuF4 1961-1962

Pu(NO3)4.5H2O, Pu(NO3)6, PuO2.XH2O, PuO2, Pu(C2O4)4, PuO2.5H2O, Pu(OH), Th(NO3)4, 

ThO2, Th(OH)4, ThO2.XH2O

1962-1967

SM-2 PuO2 1961-1967

SM-3,10 Pu(NO3)4, PuO2, Pu(C2O4)4, Pu-238, neutrons 1961-1967

SM-20 Sealed sources 1961-1967

SM-21 PuO2, Th-232 oxide (EDTA and citrates acted like chelating agents) 1961-1967

SM-26 Pu(NO3)4, PuO2, Pu(C2O4)4, Pu(OH)4, PuF4 1961-1967

SM-27,28 Pu(NO3)4.5H2O, Pu(NO3)6, PuO2, Pu(C2O4)4, PuO2.5H2O, Pu(OH), PuF4, PuCl4 1961-1965

Pu(NO3)4, Pu(NO3)4.5H2O, PuO2, PuO2.X H2O, Pu(C2O4)4, Pu(OH) 1965-1967

SM-34 Pu(NO3)4.5H2O, PuO2, Pu(SO4)2, PuF4, Am(NO3)4, AmO2, Am(SO4)2, AmF4, Np(NO3)4, UO2, 

U(SO4)2, UF4

1963-1967

SM-35,35

A

Pu(NO3)4.5H2O, Pu(NO3)6, PuO2, Pu(C2O4)4, Pu(O2).5H2O, Pu(OH)4, PuF4, PuCl4 1961-1965

Pu(NO3)4, Pu(NO3)4.5H2O, PuO2, PuO2.X H2O, Pu(C2O4)4, Pu(OH)4 1965-1967

SM-38 

(SM-I)

Pu(NO3)4, PuO2, Pu(SO4)2, PuF4, Am(NO3)4, AmO2, Am(SO4)2, AmF4, Np(NO3)4, NpO2, 

Np(SO4)2, NpF4

1963-1967

Np(NO3)4, UO2, U(SO4)2, UF4, Pu(NO3)4.5H2O, Pu(NO3)6, PuO2, Pu(C2O4)4, PuO2 1965-1970

SM-39 Pu(NO3)4.5H2O, Pu(NO3)6, PuO2, Pu(C2O4)4, PuO2.5 H2O, Pu(OH)4, PuF4, PuCl4 1961-1965

Pu(NO3)4, Pu(NO3)4.5H2O, PuO2, PuO2.X H2O, Pu(C2O4)4, Pu(OH)4 1965-1967

SM-58, 59 

(A&B)

Pu(NO3)4, PuO2, Pu(SO4)2, PuF4, Am(NO3)4, AmF4, AmO2, Am(SO4)2, Np(NO3)4, NpO2, 

Np(SO4)2, NpF4, U(NO3)4, UO2, U(SO4)2, UF4

1963-1967

SM-60 PuO2 1965-1967

SM-61,62 PuO2, Th-232 (EDTA and Citrates acted like chelating agents) 1961-1967

SW Building

SW Building is similar to R Building in that it consists of many laboratories engaged in a variety of 

research, development, analytical, recovery, and surveillance activities. The “old cave” and “new 

cave” areas consisted of several rooms which were set up for “hot” work with several types of alpha 

and gamma radiation and project capabilities. Other major programs were the thorium refinery 

project, rare isotope program, neutron source, 234U separation program, and the tritium programs. 

The tritium programs include the tritium enrichment, effluent capture, process development, 

component evaluation, and scrap recovery and tritium waste solidification. 

SW building was used in the Cotter Concentrate (St. Louis Airport Cake) starting in the early 1970s 

and terminated late in that decade. Pilot plant operations in SW were to recover Th-230 and Pa-231. 
Document No. ORAUT-TKBS-0016-2 Revision No. 00 PC-2 Effective Date: 03/13/2009 Page 16 of 30

Cotter Concentrate Weight %

Uranium oxide – 21,740 g/drum

Th-232 – 99.9 g/drum

Pa-231 – 0.060 g/drum

Th-230 – 11.1 g/drum

Ave. moisture content 47%

The Old Cave was built in the early 1950s and occupied approximately 1,000-ft2 area located in the 

Semi-Works (SW) Building. Radium-226 and 227Ac were processed from 1951 to 1955 in this area. 

This process could result in possible contamination requiring decontamination efforts at various times 

during operations. From 1955 until 1959, D&D activities occurred in the old cave as manpower and 

budgets permitted. The cave structure was removed, including the exhaust systems. In March 1959, 

the old cave was cleaned and decontaminated.

SW-19 was the Old Cave, where radium–actinium separation and processing was conducted. The

area was originally drained by a concrete channel and sumps and later filled with several feet of 

gravel and concrete due to high concentrations of radium and radon. By 1957, the area was filled 

over with additional concrete for radiation protection purposes. SW-19 had a history of elevated 

radon concentrations that were reduced by ventilation of the underground tunnel in 1980. A 1990 

DOE study showed an average radon concentration in SW-19 was found to be 5.8 picocuries per liter. 

Elevated radon, thoron, and actinon concentrations in the tunnel were also observed due to 

underlying contamination.

SW-22 was the New Cave and had few radon problems. 

The radionuclides and their respective compounds that were present in SW-1A cave (King 1995) 

include:

Radium-226 Radium carbonate

Actinium-227 Radium nitrate

Radium bromide Actinium oxalate

Actinium bromide Potassium-40

Radon and daughters Thorium-228, -229, -230

Table 2-7 summarizes rooms, dates, and radioisotopes for SW Building.

Table 2-7. Radionuclides and related compounds for SW Building.

Room Radionuclides and related compoundsa Dates used

SW-2 H-3 1973-present

SW-8 H-3, tritides(Li, Ba, Ti, Ca, U-238, Others), U-235 1957-present

Xe(All Isotopes) 1957-1960

U(238)(D,T), Li(D,T), Ba(D,T), Ti(D,T) 1960-1985

SW-9 H-3, tritides (Type F, S), 1965-present

U(D,T), Li(D,T), U/Al(D,T), Other tritides (Type F, S) 1989-present

SW-10 H-3 1967-1972
Document No. ORAUT-TKBS-0016-2 Revision No. 00 Effective Date: 03/30/2004 Page 17 of 30

SW-11->16 Ru-106, Cs-137, Sb-125, Te-121,127, Zr-93, -95, Nb-94, Sr-90, Pu-238, -239, Y-88, 

-90, -91, rare earths (especially Ce).

1951-1953

Th-228, -232, U-238, Ra-224, -228, Th-232 daughters 1955

Fe-55, -59, Al-26, Ca-45, Co-60, Pa-231, Cu-65 1956

H-3, Li tritide 1959-1965

H-3, U(D,T), Li(D,T), LiO(D,T), U-238, U-235, sOBT, other tritides (Type F) 1959-1978

H-3, U-238, U tritide 1964-1974

H-3, U(D,T), U-238, Pu-239, other tritides (Type F, S) 1968-pres

H-3, Tritides (type S) 1964-1975

H-3 Oxide 1975-1985

H-3, U-238, sOBT, tritides (Type F) 1975-1978

SW-19 Ra-226, Ra(CO3), Ra(NO3)2, RaBr2, Ac-227, Ac(C2O4)4, AcF4, K-40, Th-228, -229, 

-230, radon and daughters

1951-1953

H-3, Pu-239, U-238, U-235, tritides (Type F, S), Rn-222 and daughters 1962-1988

H-3, Pu-239, U-238, tritides (Type F) Ra daughters 1973-pres

SW-20,21 H-3 1961-1973

SW-22 U-232, -233, Th-228, -229, Ra-224, -225, Ac-225, Fr-221, At-217, Th-228 daughters 1966-1975

Th-230, -232, U-234, -235, -238, Pa-231, Ac-227, Ra-223, -224, -226, Ac(NO3), AcO2. 1970-1979

Po-208, -209, -210, Po-210 daughters 1976-1979

Pu-238, Pu-239, U-233 (Type F, M) 1984-1986

SW -128, 

129,130,134

Th-230, -232, U- -234, -235, -238, Pa-231, Ac-227, Ra-223, -224, -226 1970-1979

SW-132 Th-230, -232, U-234, -235, -238, Pa-231, Ac-227, Ra-223, -224, -226, Ac(NO3), AcO2 1970-1979

Po-208, -209, -210, Po-210 daughters 1976-1979

SW-136,137 Th-230, -232, U-234, -235, -238, Pa-231, Ac-227, Ra-223, -224, -226, Ac(NO3), AcO2 1964-1979

SW-140 Ac-227, Ac(NO3)2, AcO2 1964-1968

Th-230, -232, U-234, -235, -238, Pa-231, Ac-227, Ac(NO3), AcO2, Ra-223, -224, -226 1974-1979

Po-208, -209, -210, Po-210 daughters 1976-1979

SW-142 Ra-226, Ra(CO3), Ra(NO3)2, RaBr2, Ac-227, Ac(C2O4)4, AcF2, K-40, Th-228, -229, 

-230, Po-208, -209, -210, radon and daughters

1950-1961

H-3, Li tritide 1959-1969

H-3, U-238, U(D,T), Pu-239, other tritides (Type F, S), U-233 1969-1985

SW-146,147 H-3, U-238, U(D,T). 1967-1985

Tritiated stainless steel 1985-pres

SW-149,149A All radionuclides in SW Building 1965-1968

H-3, HTO, tritiated organics 1969-present

SW-150,152 H-3, U-238(D,T), Other tritides (Type F, S) 1968-present

H-3, U-238 tritides (Type F, S) 1973-present

SW-200 H-3 1958-present

SW-202 Po-210 1958-1962

H-3. 1963-present

SW-205 H-3 1958-present

SW-208 H-3, U-238(D,T), Pu-239, other tritides (Type F) 1965-present

SW-210 H-3, U-238(D,T), Pu-239, other tritides (Type F) 1968-1989

SW-219 Pu-238/Be, Pu-239/Be, Am-241, Pu-239 1962-1965

Po-210, Pu-238, -239 1966-1971

H-3 1968-1978

H-3, U-238(D,T), tritides (Type F, S) 1968-1980

H-3, U-238(D,T), tritides (Type F) 1985-present

SW-231 H-3, HTO 1970-present

SW-238,240 H-3, U-238(D,T), U-238, U-235, natural U, other tritides (Type F, S) 1968-present

a. sOBT = (physiologically) soluble, organically bound tritium.

T Building

T Building was host to a number of research, development, and production programs with various 

radioisotopes. The two major programs were the polonium and tritium programs. From 1949 to 1973, 

210Po programs included processing and separation, fuels research and development, neutron source, 

and other research, development, and production programs. This work was performed on the first 

and second floors of T Building. 
Document No. ORAUT-TKBS-0016-2 Revision No. 00 PC-2 Effective Date: 03/13/2009 Page 18 of 30

An extensive renovation program from 1966 to 1968 prepared the way for additional R&D work, but 

the renovations were never used due to unanticipated funding reductions. T Building was essentially 

dormant from 1969 to 1972 due to this loss of funding. Tritium programs resumed in the 1970s. 

Other activities in T Building included nondestructive testing, environmental testing, gamma and mass 

spectroscopy, calorimetry, neutron activation analysis, and safeguards R&D. 

Table 2-8 summarizes T Building rooms, dates, and radioisotopes.

Table 2-8. Radionuclides and related compounds for T Building.

Room Radionuclides and related compounds Dates used

T-1W, 2W, 

4E

Pu-238,-239, U-233,-235,-238, H-3 1965-1987

T-5W H-3, HTO 1956-1962

1975-1982

T-5E Pu-238, -239, H-3, Co-60, Ir-192, Fe-55, -59, Ra-226, Am-241, Cd-109 1955-present

T-8 Po-210 1949-1965

T-9, 9A H-3, Pu-238 (encapsulated) 1987-present

T-13 Po-210 1949-1953

T-15B, 18 Neutron generator, neutron activation on surfaces 1963-present

T-16A H-3, tritiated organics 1984-present

T-19, 19A Pu-238, -239, H-3, Co-60, Ir-192, Fe-55, Ra-226, Am-241, Cd-109; all were encapsulated 1985-present

H-3, tritiated organics 1985-present

T-20 No radioactive work performed 1985-present

T-22 Ag-Po, Te-Po, PoCl2, Po-208, -209, -210, Bi-210, Po(NO3)2, Fe-55, -59, Si-31, Co-60, 

Pb-209, Sb-124, Sn-121, Z-65, Cr-55, V-52, Ga-70,72, Cs-137, Sr-90, Se-75, Ag-112, 

Te-121-134, Hg-203

1949-1969

Pu-238, -239 1979-present

T-25, 26, 27 Ag-Po, Te-Po, PoCl2, Po-208, -209, -210, Bi-210, Po(NO3)2, Fe-55, -59, Si-31, Co-60, 

Pb-209, Sb-124, Sn-121, Zn-65, Cr-55, V-52, Ga-70,72, Cs-137, Sr-90, Se-75, Ag-112, 

Te-121-134, Hg-203.

1949-1969

Pu-238,239 (encapsulated) 1979-present

T-28->35 Ag-Po, Te-Po, PoCl2, Po-208, -209, -210, Bi-210, Po(NO3)2, Fe-55, -59, Si-31, Co-60, 

Pb-209, Sb-124, Sn-121, Zn-65, Cr-55, V-52, Ga-70,72, Cs-137, Sr-90, Se-75, Ag-112, 

Te-121-134, Hg-203.

1949-1969

T-36, 36A Ag-Po, Te-Po, PoCl2, Po-208, -209, -210, Bi-210, Po(NO3)2, Fe-55, -59, Si-31, Co-60, 

Pb-209, Sb-124, Sn-121, Zn-65, Cr-55, V-52, Ga-70,72, Cs-137, Sr-90, Se-75, Ag-112, 

Te-121-134, Hg-203.

1949-1969

Classified 1985-present

T-37 H-3, U-238(D,T), Pu-238(encapsulated), tritiated organics 1985-present

T-40 H-3, Pu-238 (encapsulated) 1985-present

T-41 H-3 1985-present

T-46 Po-210 1949-1969

T-48, 49, 50 H-3, U-238, tritides (Type F, S) 1983-present

T-53, 54, 55, 

55A

Ag-Po, Te-Po, PoCl2, Po-208, -209, -210, Bi-210, Po(NO3)2, Fe-55, -59, Si-31, Co-60, 

Pb-209, Sb-124, Sn-121, Zn-65, Cr-55, V-52, Ga-70,72, Cs-137, Sr-90, Se-75, Ag-112, 

Te-121-134, Hg-203.

1949-1969

T-57 Ag-Po, Te-Po, PoCl2, Po-208, -209, -210, Bi-210, Po(NO3)2, Fe-55, -59, Si-31, Co-60, 

Pb-209, Sb-124, Sn-121, Zn-65, Cr-55, V-52, Ga-70,72, Cs-137, Sr-90, Se-75, Ag-112, 

Te-121-134, Hg-203.

1949-1971

H-3 1985-present

T-58 H-3 1985-present

T-59 Ag-Po, Te-Po, PoCl2, Po-208, -209, -210, Bi-210, Po(NO3)2, Fe-55, -59, Si-31, Co-60, 

Pb-209, Sb-124, Sn-121, Zn-65, Cr-55, V-52, Ga-70,72, Cs-137, Sr-90, Se-75, Ag-112, 

Te-121-134, Hg-203.

1949-1969

H-3, U(D,T) 1985-present
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T-61, 61A Po-210, Pu-238, -239 1960-1963

Po-210 1964-1966

H-3, U(D,T) 1973-present

T-63 H-3, HTO 1973-present

T-72, 73, 74, 

75, 92, 93, 

96, 97, 98

Ag-Po, Te-Po, PoCl2, Po-208, -209, -210, Bi-210, Po(NO3)2, Fe-55, -59, Si-31, Co-60, 

Pb-209, Sb-124, Sn-121, Zn-65, Cr-55, V-52, Ga-70,72, Cs-137, Sr-90, Se-75, Ag-112, 

Te-121-134, Hg-203.

1949-1969

T-99 AlCl3, BiCl4, Ag-Po, Te-Po, PoCl2, Po-210, Bi-210, Po(NO3)2, Fe-55, -59, Si-31, Co-60, 

Pb-209, Sb-124, Sn-121, Zn-65, Cr-55, V-52, Ga-70,72, Cs-137, Sr-90, Se-75, Ag-112, 

Te-121-134, Hg-203

1947-1969

H-3 1984-present

T-100, 102, 

103, 104

Ag-Po, Te-Po, PoCl2, Po-208, -209, -210, Bi-210, Po(NO3)2, Fe-55, -59, Si-31, Co-60, 

Pb-209, Sb-124, Sn-121, Zn-65, Cr-55, V-52, Ga-70,72, Cs-137, Sr-90, Se-75, Ag-112, 

Te-121-134, Hg-203

1949-1969

H-3 1972-present

T-208A Pu-238, -239, H-3, Co-60, Ir-192, Fe-55, Ra-226, Am-241, Cd-109, Po-210; all were 

encapsulated...

1947-present

T-229 Po-210, Pu-238, -239 1963-1964

Rn-222, Po-210,214,218, Bi-210, Pb-210,214 1978-1988

Pu-238, -239 (encapsulated) 1989-present

T-234 H-3, U-238 tritides, other tritides (Type F) 1988-present

T-236 Ag-Po, Te-Po, PoCl2, Po-208, -209, -210, Bi-210, Po(NO3)2, Fe-55, -59, Si-31, Co-60, 

Pb-209, Sb-124, Sn-121, Zn-65, Cr-55, V-52, Ga-70,72, Cs-137, Sr-90, Se-75, Ag-112, 

Te-121-134, Hg-203

1949-1973

H-3, U-235, -238, -239, Pu-238, -239 (Pu was encapsulated) 1985-present

T-237 Ag-Po, Te-Po, PoCl2, Po-208, -209, -210, Bi-210, Po(NO3)2, Fe-55, -59, Si-31, Co-60, 

Pb-209, Sb-124, Sn-121, Zn-65, Cr-55, V-52, Ga-70,72, Cs-137, Sr-90, Se-75, Ag-112, 

Te-121-134, Hg-203

1949-1971

H-3, Pu-238, -239 (Pu was encapsulated) 1985-present

T-238 H-3, Pu-238, -239 (Pu was encapsulated) 1985-present

T-242 Po-210 1949-1964

T-243 H-3, HTO 1956-1982

T-245 Po-210 1949-1969

Pu-238 (encapsulated). 1968-1974

T-246 H-3 1972-1980

T-247 Po-210, classified 1949-1958

Po-208, -209, -210, rare earth polonides, Pm-147 1966-1969

T-248-259 Po-210, neutrons 1949-1965

Room T-257 only, orphan sources 1993-present

T-260 Po-210 1949-1969

Po-208, -209, -210, rare earth polonides, Pm-147 1966-1969

T-266, 267 Po-210, Bi-209, -210 1949-1969

Po-208, -209, -210, rare earth polonides, Pm-147 1963-1966

H-3, U-238(D,T), other tritides (Type F). 1988-present

T-270 Po-210, Bi-209, -210 1949-1963

T-274 External dose only 1948-1971

Po-210, Bi-210, Fe-55, -59, Si-31, Co-60, Pb-209, Sb-124, Sn-121, Zn-65, Cr-55, V-52, 

Ga-70,-72, Cs-137, Sr-90, Se-75, Ag-112, Te-121-134, Hg-203.

1966-1969

H-3, U-238(D,T) 1986-pres

T-275, 276 AlCl3, BiCl4, Ag-Po, Te-Po, PoCl2, Po-210, Bi-210, Po(NO3)2, Fe-55, -59, Si-31, Co-60, 

Pb-209, Sb-124, Sn-121, Zn-65, Cr-55, V-52, Ga-70,72, Cs-137, Sr-90, Se-75, Ag-112, 

Te-121-134, Hg-203

1949-1969

T-277, 279 Am-241, Pu-239, neutrons 1949-1964

Po-210 1949-1969

Bi-209, -210 1964-1969

T-300A Orphan sources, sources left in containers

T-307 Po-210 1949-1964

H-3 1972-present
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T-310 AlCl3, BiCl4, Ag-Po, Te-Po, PoCl2, Po-210, Bi-210, Po(NO3)2, Fe-55, -59, Si-31, Co-60, 

Pb-209, Sb-124, Sn-121, Zn-65, Cr-55, V-52, Ga-70, -72, Cs-137, Sr-90, Se-75, Ag-112, 

Te-121-134, Hg-203

1949-1969

Pu-238, -239, -240, -241, Pm-147, U-233, -235, Am-241, H-3 1969-1983

Pu-238, -239 (encapsulated) 1986-present

T-311 Po-210. 1949-1969

Pu-238, -239 (encapsulated) 1986-present

T-319 Pu-238, -239, -240, -241, Pm-147, U-233, -235, Am-241, H-3, HTO 1949-present

WD and WDA Buildings

WD Building, which became operational in February 1949, is the central facility at Mound for the 

treatment of radioactive liquid wastes. From its inception, this facility included a low-level alpha 

wastewater system, with SW, R, PP, SM, HH, T, B, and H Buildings as sources. On arriving at WD 

Building, wastewater is precipitated, coagulated, and filtered, and the sludge is solidified so it can be 

shipped off the site. The supernatant from the clarifloculator is filtered, neutralized to the proper pH, 

monitored to see if below standard, and released to the Great Miami River. 

The WDA alpha wastewater treatment facility was built in 1966 as an annex to WB Building for the 

treatment of plutonium wastewater from the PP and SM Buildings. It was designed as both a high-risk 

drumming station and a low-risk wastewater treatment facility. 

Table 2-9 summarizes rooms, dates, and radioisotopes for WD and WDA Buildings.

Table 2-9. Radionuclides and related compounds for WD and WDA Buildings.

Room Radionuclides and related compounds Dates used

WD-1, 8, 

101, 104

Ag-Po, Te-Po, PoCl2, Bi-210, Po(NO3)2, Si-31, Sb-124, Sn-121, Zn-65, Cr-55, V-52, Ga-70,72, 

Se-75, Ag-112, Hg-203

1949-1958

Am-241, Ac-227, Ra-223, -226, Ac(C2O4)4, Th-228, -229, -230, U-234, -235, -238, Pu-238, 

-239, Po-208, -209, -210, Cs-137, Pa-231, AcO2, Ac(NO3)2, AcBr4, AcF4, K-40, Ba(NO3)2, 

Np-237, H-3, rare earth isotopes, tritiated octane, Co-60, Sr-90, Fe-55, -59, Te-121-134, UO2

1949-1990

Th-228, -232, Ra-224, -228, U-238 1955

Pu-236, -238, -239, -240, -241, -242, Pu(NO3)4, PuO2, Pu(SO4)2, Pu(OH)4, PuF4 (also nitrate, 

sulfate, oxide, and fluoride compounds of Am-241, Np-237, and U-234)

1961-1974

Th-230, -232, U-234, -235, -238, Pu-238, -239, Pa-231, Ac-227, Ra-223, -224, -226 1974-1979

WD-9 H-3, U-239(D,T), U-235, -238, -239, Pu-238, -239, Am-241, Rn-222, Po-208, -209, -210 and 

Po-210 daughters, Bi-210, -214, Pb-210, -214, Ra-223, -224, -226 and Ra daughters, U(D,T), 

Li(D,T), U/Al(D,T)

1973-present

WD-10 Pu-236, -238, -239, -240, -241, -242, Pu(NO3)4, PuO2, Pu(SO4)2, Pu(OH)4, PuF4 (also nitrate, 

sulfate, oxide, and fluoride compounds of Am-241, Np-237, and U-234)

1961-1974

WD-107 Cs-137, Am-241, Np-237, U-235,238 1976-1981

WD-108 Pu-236, -238, -239, -240, -241, -242, Pu(NO3)4, PuO2, Pu(SO4)2, Pu(OH)4, PuF4 (also nitrate, 

sulfate, oxide, and fluoride compounds of Am-241, Np-237, and U-234)

1949-1981

WDA-110 Pu-236, -238, -239, -240, -241, -242, Pu(NO3)4.5H2O, Pu(NO3)6, PuO2, Pu(C2O4)4, 

Pu(O2).5H2O, Pu(OH)4, PuF4 (also nitrate, sulfate, oxide, and fluoride compounds of Am-241, 

Np-237, and U-234)

1966-1970

H-3 1967-present

WDA-112 Pu-236, -238, -239, -240, -241, -242, Pu(NO3)4.5H2O, Pu(NO3)6, PuO2, Pu(C2O4)4, 

Pu(O2).5H2O, Pu(OH)4, PuF4 (also nitrate, sulfate, oxide, and fluoride compounds of Am-241, 

Np-237, and U-234)

1966-1979

Cs-137 1980-1984

WDA-113 Cs-137, Co-60, I-131, Pu-238, -239 1979-1994

WDA-118A Co-60, Cs-137, I-131, Sr-90 1977-1981

WDA-118B Pu-238, -239, H-3 1975-1985

Co-60, Cs-137, Mn-54, Sr-90 1981-present
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WDPenthouseTh-230, -232, U-234, -235, -238, Pu-238, -239, Pa-231, Ac-227, Ra-223, -224, -226, -228, 

Co-60, Cs-137, Np-237, Sr-90, Po-208, -209, -210, Am-241, H-3, Te-121-134, Fe-55, -59

1949-present

Warehouse 9 (1953)

All of the drums stored in Warehouse 13 from the Purex/Bismuth phosphate materials 

decontamination were moved to Warehouse 9 in preparation for shipment off the site. The following 

radionuclides of concern and their compounds are of equal concern:

Antimony-125 Ruthenium-106

Cesium-137 Strontium-90

Niobium-94 Tellurium-121 and -127

Plutonium-238 and -239 Yttrium-88, -90, and -91

Rare earths (especially cerium) Zirconium-93 and -95

Warehouse 13 (1953)

This warehouse was used for the storage and shipment of several drums of sludge from the 

Purex/Bismuth phosphate decontamination program. The settling and mixing tanks were also taken 

there. The following radioisotopes and their compounds are of equal concern:

Antimony-125 Ruthenium-106

Cesium-137 Strontium-90

Niobium-94 Tellurium-121 and -127

Plutonium-238 and -239 Yttrium-88, -90, and -91

Rare earths (especially cerium) Zirconium-93, -95

This warehouse was also used for temporary storage for drums of low level contamination from the 

226Ra/227Ac decontamination operations. Radioisotopes of concern and their compounds are:

Actinium fluoride Radium nitrate

Actinium oxalate Radium-226

Actinium-227 Radon and daughters

Barium nitrate Thorium-228

Potassium-40 Thorium-229

Radium bromide Thorium-230

Radium carbonate

Actinium-227 is the major radionuclide of concern. Radium-226 and 228Th are of nearly equal 

concern, and 208Po, 209Po, and 210Po are of much less concern. The remaining isotopes are of small 

concern.

Warehouse 15 (1955–1961)

This warehouse stored 1,650 tons of the 232Th refinery program (Monex) sludge. It was highly 

corrosive and continually leaked through the barrels causing much contamination. More than 34 

isotopes were identified from the feedstock of this program with most being nonradioactive. 

Radioisotopes of concern and their compounds are:

• Radium-228 and -224

• Thorium-232 daughters (especially thallium-208)

• Thorium-232 and -228

• Uranium-238
Document No. ORAUT-TKBS-0016-2 Revision No. 00 Effective Date: 03/30/2004 Page 22 of 30

Thorium-228 and -232 and 224Ra are equal as major radionuclides of concern. Uranium-238 is a 

secondary concern. However, when considering the quantity or mass of radionuclides, and not 

activity, 99% are 232Th.

Building 21

This building was constructed in 1964 for bulk storage of thorium ores and sludge from the old Monex 

project, a 232Th refinery program. It was originally designed like a silo with no doors or windows; 

oxalate sludge was stored in one side and hydroxide sludge in the other. Until 1973 at least 117 

55-gallon leaky drums remained outside the building. Contamination of the surrounding grounds 

occurred from fugitive dust resulting from the dumping of this sludge into this silo. From October 1974 

to July 1975, the sludge was repackaged in 55-gallon drums and shipped off the site. Radionuclide 

contents of the sludge were primarily thorium isotopes, rare earth isotopes, uranium, and others.

A total of 1,252 55-gallon drums of Cotter Concentrate were stored in Building 21 from 1975 until 

1987 when they were shipped off the site. This concentrate contained significant quantities of the 

following, which are radionuclides of concern:

• Actinium nitrate

• Actinium oxide

• Actinium-227

• Protactinium-231

• Radium-223, -224, and -226

• Thorium-230 and-232

• Uranium-234, -235, and -238

Thorium-230 was the major radionuclide of concern with more than 95% of the activity.

Fourteen elements beside the isotopes listed above are in the Cotter Concentrate. There is no 

indication that these 14 elements are radioactive.

The surrounding grounds served as storage for 238Pu waste packages in 1967. There was leakage of 

the plutonium waste packages. The area around Building 21 was contaminated because of the 

leakage of the Monex sludge drums, the debris from dumping sludge through the roof, and 

repackaging into drums. 

Building 34

This building has a dual purpose: It was a drop test area for waste packages and an area for 

simulation of pyrophoric metal training for the fire fighters. The empty low specific activity (LSA) 

containers were dropped in various ways to test and ensure their structural integrity. Similar tests 

were done on drums.

Depleted uranium and metal shavings of various types were used in firefighting practice to simulate 

pyrophoric situations. Radioisotopes of concern include 238U oxide.

Building 50

Building 50 is designated as the assembly and testing building for RTGs. In Building 50, RTGs are 

assembled in an inert atmosphere. All plutonium used as the heat source is encapsulated, which 

gives little probability for a radionuclide release. External dose is still possible from gamma and 

neutron flux.

Associated with the RTG program is a testing program. Approximately 20 tests (vibration, space 

simulation, extreme heat, extreme cold, shock, vacuum performance, etc.) are done on the RTG 

module.
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Building 59

This building contains a subcritical assembly, which has the capability to produce fission products. 

However, all fission products were sealed in aluminum containers, so the probability of contamination 

is remote. The water surrounding the containers inside the assembly is constantly monitored and 

contamination has been observed.

Californium-252 and enriched uranium were used for irradiation. These radioisotopes were 

encapsulated in metal cladding, so there is no concern for internal dosimetry. Some intentional 

irradiation is done, with the major contaminants being 55Fe, 59Fe, and 60Co. Radionuclides of concern 

are:

• Californium-252

• Cobalt-60

• Iron-55 and -59

• Uranium-234, -235, and -238

The historical radionuclides of major concern were 252Cf and 235U, equally. This building has not been 

operational since 1990 and is not likely to operate again. In the future, radionuclides of concern will 

be 235U and 59Fe in the form of rust during building demolition. 

Building 68

This building functions as a decontamination and decommissioning staging area and handles the 

radionuclide waste from R Building.

A corollary activity of this area is to perform testing on empty LSA containers. These are dropped in 

various ways to test and ensure their structural integrity. Similar tests are also done on drums. 

Radioisotopes of concern are 238Pu oxide and 239Pu oxide.

B Building

From around 1950 to about 1955, this building was used for biological research of the effects of 210Po, 

227Ac, and other alpha emitters on animals. The results were used to estimate the effects of 

radionuclides used at Mound on humans. Biological testing was discontinued in about 1955 when 

detonator manufacturing began. 

A Biological Research Quarterly from June 1954 discusses mice and rat experiments, which were 

conducted over a 2-year period with 210Po. In another experiment rats were given a 227Ac solution that 

also contained 227Th, 223Ra, 239Rn, 215Po, and 211Bi.

A report by D. S. Anthony and K. A. Bush discusses experimental results of single acute and multiple 

exposures of 210Po to rats with higher dosages of polonium than previously reported. In addition, 

studies with plutonium were done with a special emphasis on 238Pu. Other reports discuss 

experimental work using 226Ra and 227Ac.

Room B-146

This was a laboratory where early research was done. Radioisotopes of concern and their 

compounds are:

Actinium-227 Polonium-215

Bismuth-211 Radium-223 and -226

Plutonium-238 Radon-219

Polonium-210 Thorium-227
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Polonium-210 was the major radionuclide of concern with 227Ac being secondary. B-Building was 

decontaminated by July of 1955.

Rooms E-141, -142, -144, -155

In use from 1981 to the present, Room E-141 uses small amounts of radionuclide standards of 

varying amounts and kinds as tracers for environmental testing. The tracers are in liquid form with 

only 210Pb being encapsulated. They are used and stored in Room E-141, and are used in rooms 

E-142, 144, 155, which are also environmental laboratories. Radionuclides of concern are:

Plutonium-238, -239 Thorium-229, -230

Tritium Uranium-232, -234, -236, -238

Lead-210

Rooms E-174, -175, -177, -185, -194

These rooms have been used for cold storage and, therefore, were thought not to contain 

radionuclides. However, recent surveys found items in these rooms contaminated with alpha, beta, 

and gamma radiation. The following specific results were found:

• Room E-174—alpha from an unknown source

• Room E-175—beta and gamma from an unknown source

• Room E-177—beta and gamma from a U-235 rod, epoxy metallurgical sample, metal chips

• Room E-185—(~1985-present) alpha and beta on metallurgical sample contaminated with 

235U, a second sample with suspected contamination from 232Th

• Room E-194—alpha from possible plutonium, beta and gamma from possible 235U or 238U

An overview of operations in E-Building includes the following radionuclides of concern:

Nitrate and chloride solutions of:

Lead-210 Thorium-229 and -230

Plutonium-238, -239, and -242 Tritium

Polonium-210 Uranium-232, -234, -235, -236, and -238

Plutonium-238 was the major radionuclide of concern with 210Po second and tritium third.

H Building

Although this building houses many innocuous functions such as the credit union and change rooms, 

there are activities that have the potential for radionuclide intakes.

The laundry had a “hot laundry” capability to handle clothes exposed to radionuclides, which is the 

primary reason the structure was built. Bioassay and other environmental laboratories in H-Building 

have the potential for low levels of exposure. Most radionuclides are tracer nitrate and chloride 

solutions of 238Pu, 239Pu, 242Pu, 232U, 236U, and 229Th. Tritium and 210Po could be included. It has been 

suggested that 226Ra, 228Th, and 227Ac be included in the list.

Radionuclides and related compounds of concern are:

Actinium-227 Thorium-228 and -229

Plutonium-238, -239, and -242 Tritium

Polonium-210 Uranium-232 and -236
Document No. ORAUT-TKBS-0016-2 Revision No. 00 Effective Date: 03/30/2004 Page 25 of 30

Radium-226

Plutonium-238 was the major radionuclide of concern with 210Po second and 227Ac third.

I Building

I-Building refers to the Isolation Building, where low-level counting of bioassay (urine and fecal) 

samples and environmental counting for soil, vegetation, etc., were performed from 1955 to the 

present. There is little concern about the possibility of uptakes. This area is used for nondestructive 

testing and the assembly of explosive devices. No radionuclides are used.

M Building

Room M-20 had a Livermore drybox. In addition, 238U was machined in this building.

R&R Building

This small building between the SM and PP Buildings was used for sorting plutonium solid waste, 

some of which could be reprocessed. The compound forms of the plutonium and lung solubility types 

are as follows:

• Plutonium oxide, PuO2, Type S; this could also take the form of a plutonium oxide hydrate—

PuO2.XH2O

• Plutonium hydroxide, Pu(OH)4, Type S

• Plutonium nitrate, Pu(NO3)4, Type M; this could also take the form of plutonium nitrate 

pentadhydrate, Pu(NO3)4.5H2O

Plutonium-238 was the major radionuclide of concern; 239Pu was second.

SD Building (57, 112, and 113) (1947–1970)

The SD Building was a sanitation building that could have had some contaminated sludge from 

broken lines or pipes. Contamination would have been minor in concentration but could have 

contained radionuclides from polonium processing. Radionuclides of concern and related compounds 

are:

Antimony-124 Polonium-208, -209, and -210

Bismuth-210 Selenium-75

Cesium-137 Silicon-31

Chromium-55 Silver polonide

Cobalt-60 Tellurium polonide

Gallium-70 and -72 Silver-112

Iron-55,59 Strontium-90

Lead-209 Tellurium-121 and possibly Te--134

Mercury-203 Tin-121

Plutonium-238 and -239 Vanadium-52

Polonium chloride Zinc-65

Polonium nitrate

Polonium-210 was the major radionuclide of concern, with 238Pu second and 65Zn third.

Building 19

The building is a 4,800-ft2 Quonset hut and contains a small office and an area for storing 

Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) materials. The 

building was constructed in 1962 for Mound Salvage storage and sales. Since 1988 it has been used 
Document No. ORAUT-TKBS-0016-2 Revision No. 00 Effective Date: 03/30/2004 Page 26 of 30

to store CERCLA soil drums and empty drums. Low-level waste (LLW) and LSA drums have also 

been stored in this building. Plutonium-238 and 232Th were the primary isotopes in the LLW and LSA 

drums.

Building 22

Building 22 is a 9,090-ft2 one-story steel frame building constructed in 1966 for office space and 

storage of items to be sold. In 1995 the building was modified to handle radioactive LLW solid waste. 

Building 23

Building 23 is a 3,422-ft2 one story steel frame building constructed in 1966 as a warehouse used for 

preparation and shipping of LLW. It was later used to store mixed and transuranic (TRU) mixed 

waste. The building was modified in 1994 to contain spills. 

Building 30

Building 30 contains a counting laboratory. Liquid scintillation counting for tritium and gross alpha and 

beta counting were performed in this building. The facility performed gamma scans of drums and 

boxes. Several years ago the facility was converted from office space to a counting laboratory.

Building 31

Building 31 is a 3,000-ft2 metal fabricated building constructed in 1966. The building is used for 

storage and preparation of LLW waste.

Building 31A

Building 31A is a 2,650-ft2 metal fabricated building constructed in 1986 to store LSA and TRU waste. 

The building is currently used for storage of TRU wastes.

Building 35

Building 35 is a 2,500-ft2 metal fabricated building constructed in 1967 for X-ray and eddy-ray current 

nondestructive testing. The facility was also used as the control room for the 252Cf multiplier (CFX) 

neutron radiography facility.

Building 39

Building 39 is a 3,515-ft2 metal fabricated building constructed in 1967 to build Fiberglass wooden 

boxes for radioactive trash for the D&D activities. Indications are that gamma spectroscopy on these 

boxes was also performed in this building. From 1984 to 1988 the building was either inactive or used 

for storage. Since 1988 the building has been used as a maintenance shop.

Building 45

Building 45 is a 9,582-ft2 concrete building constructed in 1967. The building is the health physics 

calibration laboratory. The facility has equipment for calibration of health physics instrumentation and 

dosimeters. The facility houses a well calibration area, a beta calibration area, a calibration and repair 

area, a dosimeter preparation area, an X-ray calibration area, and a low-scatter neutron and 

maximum field calibration area.

Building 58

Building 58 is a 6,100-ft2 concrete building constructed in 1977. The building is the alpha and beta 

filter and plenum exhaust for SW Building.

Building 72

Building 72 is a 2,400-ft2 metal frame building constructed in 1984. The building is site hazardous 

storage waste facility. Liquid scintillation vials are stored in this facility.
Document No. ORAUT-TKBS-0016-2 Revision No. 00 Effective Date: 03/30/2004 Page 27 of 30

Building 90

Building 90, constructed in 1985, housed the unit controls and feed operations for the retort unit 

(rotary kiln thermal treatment unit) located in the burn area. Operations ended in January 1996.

Building 94

Building 90 is a 1,240-ft2 metal building constructed in 1985. The building is used for CERCLA 

contractor staging and storage of soil and water samples.

Building 123 (Rubb)

In addition to fulfilling a variety of uses, this temporary structure has also had different names, 

including WTS Rubb from 1989 into the 1990s and the Rubb Building later in the 1990s. More 

recently, it has been called Rubb Building 123. 

Rubb Building 123 was constructed in 1989 and was deconstructed in 2001. The building was used 

to store heavy equipment in 1989. Beginning in 1994, LSA boxes containing soils from the WTS line 

cleanup were emptied and sampled in the building. The boxes being opened were randomly selected 

from a population of nearly 700 boxes to achieve a 95% confidence level. The purpose of this 

process was to conduct content verifications of the boxes. The results of this verification sampling 

eventually lead to the ability to ship the boxes as LLW. 

In the 1990s the Rubb Building 123 was also used for storage of heavy-duty equipment for the D&D 

group. Heavy-duty equipment stored in this structure was likely used in the demolition of site 

buildings and in the cleanup of contaminated areas on the plant site. 

Rubb Building 123 was also used as a decontamination location for heavy equipment that had been 

used by D&D in the demolition of site buildings and in the cleanup of contaminated areas on the plant 

site.

The Brickmaker

The Brickmaker, built in 1992, was a temporary structure to house equipment to compress and to 

de-water low-level radioactively contaminated soils into extruded bricks that could be placed in LLW 

boxes for disposal off the site. The project area consisted of two temporary steel-framed 

Rubb®-brand buildings, an office trailer, and a lined in-ground pit to receive water from the process. 

Building 124 (CWPF)

Building 124, also know as the Consolidated Waste Processing Facility (CWPF), was constructed in 

1998. Building 124 performed various volume reduction or repackaging functions that are routinely 

performed at MEMP. The building processed LLW from various demolition sites and safe-shutdown 

activities as well as legacy waste streams. Building 124 is in an Underground Radiological Materials 

Area.

The ASA included a list of expected process input materials, as described in Section 2.3. The list 

included, but was not limited to: 

• Non-structural equipment and debris (soft objects such as rags and bags for compaction)

• Structural steel for decontamination, size reduction, and release

• Soils and other demolition debris for blending to reduce the radioactive material content to 

meet specific waste profiles

• Drums, boxes, and other types of containers in order to puncture the container lids to vent gas, 

sample and analyze the released gas and to install filter vents
Document No. ORAUT-TKBS-0016-2 Revision No. 00 Effective Date: 03/30/2004 Page 28 of 30

• Liquids generated by the air recirculation unit or tritium-contaminated liquids collected during 

opening or repackaging containers with tritium contamination

• Various types of waste packages for sampling, consolidation, or repackaging, or other 

activities that ensure that the waste is packaged in a form suitable for shipment off the site and 

final disposal.

At Building 124 the stack was monitored for potential air emissions of: 

• Tritium

• Pu-238

• Pu-239 and -240

• U-233 and -234

• U-238

Area 8, Thorium Contaminated soils from area 1 and 9

The area is located northwest of Building 31, on the SM/PP hill on the eastern side of Mound site. 

The area is approximately 25,000 ft2

. Soil was buried in this area from decontamination 

activities from repackaging of Th-232 sludges in 1965 and 1966. Pu-238 was detected at a 

maximum concentration of 24 pCi/g. The maximum Thorium concentration was 254.3 pCi/g.

Area 10, Debris from Dayton Units

The area is located west of Building 30, on the slope of the SM/PP hill on the East Central portion 

of Mound site. It was used for disposal of contaminated concrete from Dayton Units. One 

hundred and sixty truckloads from Unit IV and one hundred truckloads from Unit III were 

deposited here. The area is approximately 15,000 ft2

. The primary contaminant was Po-210. 

Soil was buried in this area in 1950.

Area 12, Thorium Contaminated soil

The area is located west of Building 38, on the SM/PP hill on the East Central portion of Mound 

site. Th-232 and Pu-238 contaminated soil from SM building and Thorium contaminated soil 

from area 1 were placed in this area in 1965. 

WTS Pipline

The pipeline line ran from SM building and Building 38 to the WD building. In 1969 the high-risk 

waste line ruptured below the WD building. The pipline may have leaked in other locations as 

well along its path.

2.3.4

The following buildings have not supported radionuclide activities: 1, 2, 3, 13, 14, 16, 17, 24, 25, 26, 

27, 28, 29, 33, 36, 37, 40, 41, 42, 43, 44, 46, 47, 49, 51, 55, 56, 60, 61, 63E, 63W, 65, 66, 67, 69, 70, 

71, 73, 74, 79, 85, 87, 88, 49, 91, 92, 93, 95, 96, 98, 99, 100, 101, 102, 104, 105, 106, 120, 

A (Administration), C (Old Cafeteria), COS, G, Generator-1, Generator-6, GH, GP-1, GP-5, GP-8, 

GP-44, GS, GW, Modular 4, OSE, OSW, P (Power Plant), PH, SST, W, WH-1, WH-2, WH-3, and 

Magazines 5, 6, 7, 8, 10, 11, 20, 52, 53, 54, 64, 80, 81, 82, 83, and 84.

Buildings without Radionuclide Activity
Document No. ORAUT-TKBS-0016-2 Revision No. 00 PC-2 Effective Date: 03/13/2009 Page 29 of 30

REFERENCES

Cited References

King, W., 1995, Mound Site Radionuclides by Location, MD-22153, EG&G Mound Applied 

Technologies, Miamisburg, Ohio. June 22. [SRDB Ref ID: 3240]

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NIOSH (National Institute for Occupational Safety and Health), 2002, Internal Dose Reconstruction 

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NIOSH (National Institute for Occupational Safety and Health), 2007a, Radiation Exposures Covered 

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Gilbert, K. V., 1969, History of the Dayton Project, Monsanto Research Corporation, Mound 

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