ORAU Team

NIOSH Dose Reconstruction Project

Technical Basis Document for the Oak Ridge National Laboratory 

– Site Description

Document Number:

ORAUT-TKBS-0012-2 

Effective Date: 11/14/2003

Revision No.: 00

Controlled Copy No.: ______

Page 1 of 66

Subject Expert: Fran Dickens/Kenny Fleming

Document Owner

Approval: Signature on File_________________Date: 11/19/2003

Robert Burns, TBD Team Leader

Approval: _Signature on File________________Date: 11/19/2003

Judson L. Kenoyer, Task 3 Manager

Concurrence: _Signature on File_____________Date: 11/20/2003

Richard E. Toohey, Project Director

Approval: __Signature on File_______________Date: 11/21/2003

James W. Neton, OCAS Health Science Administrator

Supersedes:

None

TABLE OF CONTENTS

Section

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

Page

4

Acronyms and Abbreviations ...............................................................................................................5

2.1 Introduction................................................................................................................................. 7

2.2 Major Facility Descriptions ..........................................................................................................8

2.2.1 Building 2000 (formerly 101-D) Metallurgy Laboratory ...................................................... 9

2.2.2 Building 2005 (formerly 706-B) Metallurgy Annex ........................................................... 10

2.2.3 Building 2026 Radioactive Materials Analytical Laboratory ............................................. 10

2.2.4 Building 3001 (formerly 105) Graphite Reactor Building (Clinton Pile) ............................ 10

2.2.5 Building 3002 (formerly 114) Graphite Reactor Filter House ........................................... 10

2.2.6 Building 3003 (formerly 115) Graphite Reactor Fan House and Surface 

Modification and Characterization Laboratory ................................................................. 10

2.2.7 Building 3004 (formerly 807) Water Demineralization ..................................................... 10

2.2.8 Building 3005 (formerly 106) Low Intensity Training Reactor (LITR) ............................... 11

2.2.9 Building 3010 Bulk Shielding Reactor Facility ................................................................. 11

2.2.10 Building 3018 Exhaust Stack (for Building 3003)............................................................. 11

2.2.11 Building 3019 (formerly 205) Radiochemical Processing Pilot Plant................................ 11

2.2.12 Building 3020 Exhaust Stack (for Building 3019)............................................................. 11

2.2.13 Building 3021 Fan House (Northeast of Building 3020)................................................... 11

2.2.14 Building 3023 (formerly 206) North Tank Farm ............................................................... 11

2.2.15 Building 3025E Physical Examination Hot Cells.............................................................. 12

2.2.16 Buildings 3026-C and 3026-D (formerly 706-C and 706-D) By-Product 

Processing and Chemical Separation Laboratory ........................................................... 12

2.2.17 Building 3027 Special Nuclear Materials Storage Vault................................................... 12

2.2.18 Building 3028 (formerly 910) Alpha Powder Facility ........................................................ 12

2.2.19 Building 3029 (formerly 909) Source Development Lab .................................................. 13
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2.2.20 Building 3030 (formerly 908) Radioisotope Processing Building “C”................................ 13

2.2.21 Building 3031 (formerly 907) Radioisotope Processing Building “D”................................ 13

2.2.22 Building 3032 (formerly 906) Radioisotope Processing Building “E”................................ 13

2.2.23 Building 3033 (formerly 905) Radioactive Gas Process Facility ...................................... 13

2.2.24 Building 3033A Actinide Fabrication Facility Annex......................................................... 13

2.2.25 Building 3034 Radioisotopes Services Building............................................................... 13

2.2.26 Building 3038 (formerly 902) Isotope Research Materials Laboratory, 

Radioisotope Analytical and Packing Building................................................................. 14

2.2.27 Building 3039 (formerly 911) Central Exhaust Stack (Radioisotope Area)....................... 14

2.2.28 Building 3042 ORNL Research Reactor.......................................................................... 14

2.2.29 Building 3047 Radioisotopes Development Laboratory ................................................... 14

2.2.30 Building 3118 Radioisotope Processing Building “H”....................................................... 14

2.2.31 Building 3505 Metal Recovery Facility ............................................................................ 14

2.2.32 Building 3507 (formerly 206) South Tank Farm............................................................... 15

2.2.33 Building 3515 Fission Product Pilot Plant........................................................................ 15

2.2.34 Building 3518 Acid Neutralization Plant........................................................................... 15

2.2.35 Building 3525 High Radiological Level Examination Laboratory...................................... 15

2.2.36 Building 3544 Process Waste Treatment Facility ............................................................ 16

2.2.37 Building 4500 Central Research and Administration Facility ........................................... 16

2.2.38 Building 4501 High Level Radiochemistry Laboratory ..................................................... 17

2.2.39 Building 4508 Metals and Ceramics Laboratory .............................................................. 17

2.2.40 Building 5505 Transuranium Research Laboratory ......................................................... 17

2.2.41 Building 6000 Holifield Radioactive Ion Beam Facility ..................................................... 18

2.2.42 Building 6010 Oak Ridge Electron Linear Accelerator..................................................... 18

2.2.43 Building 7500 Homogeneous Reactor Experiment Reactor Building ............................... 18

2.2.44 Building 7503 Molten Salt Reactor Experiment ............................................................... 18

2.2.45 Building 7700 Tower Shielding Facility............................................................................ 18

2.2.46 Building 7735 Dosimetry Applications Research Calibration Laboratory ......................... 18

2.2.47 Building 7852 Old Hydrofracture Facility ......................................................................... 19

2.2.48 Solid Waste Storage Areas............................................................................................. 19

2.3 Oak Ridge National Laboratory Site Operations and Processes ............................................... 20

2.3.1 Early Operation of Graphite Reactor and Associated Facilities ....................................... 20

2.3.2 Radioactive Lanthanum Activities ................................................................................... 23

2.3.3 Isotope Production Areas................................................................................................ 25

2.3.4 Waste Areas and Processes........................................................................................... 27

2.3.5 ORNL Facilities at the Y-12 National Nuclear Security Complex..................................... 29

2.3.6 Other Reactor Development and Operations .................................................................. 31

2.3.6.1 Low-Intensity Test Reactor..................................................................................... 31

2.3.6.2 Critical Experiments Facility ................................................................................... 32

2.3.6.3 Bulk Shielding Reactor/Pool Critical Assembly....................................................... 32

2.3.6.4 ORNL Research Reactor ....................................................................................... 33

2.3.6.5 Tower Shielding Facility ......................................................................................... 33

2.3.6.6 Health Physics Research Reactor.......................................................................... 34

2.3.6.7 Homogeneous Reactor Experiment........................................................................ 34

2.3.6.8 Aircraft Nuclear Propulsion Experiment.................................................................. 34

2.3.6.9 High Flux Isotope Reactor...................................................................................... 35

2.3.6.10 Molten Salt Reactor Experiment............................................................................. 35

References ........................................................................................................................................36
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Glossary ............................................................................................................................................38

Attachment 2A Oak Ridge National Laboratory Facility Index

Attachment 2B Major Facilities and Radionuclides of Concern

Attachment 2C ORNL Facility Maps

LIST OF TABLES

Table Page

2-1 Contractors of the Oak Ridge National Laboratory........................................................................ 8

2-2 North Tank Farm (Facility 3023) contents................................................................................... 12

2-3 South Tank Farm (Facility 3507) contents .................................................................................. 15

2-4 Sealed sources available at DOSAR Calibration Laboratory (Building 7735).............................. 19

2-5 Radioisotopes of concern in isotope production facilities ............................................................ 25

2-6 Radiation sources in Biology Division at Y-12............................................................................. 30
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RECORD OF ISSUE/REVISIONS

ISSUE 

AUTHORIZATION 

DATE

EFFECTIVE 

DATE

REV. 

NO. DESCRIPTION

Draft 10/29/2003 00-A Draft TBD for Oak Ridge National Laboratory -

Site Description. Initiated by Robert E. Burns, Jr.

11/14/2003 11/14/2003 00 First approved issue. Initiated by Robert E. 

Burns, Jr.
Effective Date: 11/14/2003 Revision No. 00 Document No. ORAUT-TKBS-0012-2 Page 5 of 66

ACRONYMS AND ABBREVIATIONS

AEC U.S. Atomic Energy Commission

amu atomic mass unit

ANP aircraft nuclear propulsion

BSR Bulk Shielding Reactor

Bq Becquerel

CEF Critical Experiments Facility

cfm cubic feet per minute

Ci curie

cm centimeter

d day

DOE U.S. Department of Energy

DOSAR Dosimetry Applications Research Calibration Laboratory

FCAF Fuel Cycle Alpha Facility

ft foot

ft2 square foot

g gram

g an acceleration equal to the force of gravity at the Earth’s surface

gal gallon

GCR Gas-Cooled Reactor

HEPA high-efficiency particulate air

HFIR High Flux Isotope Reactor

HPRR Health Physics Research Reactor

hr hour

HRE Homogeneous Reactor Experiment

in. inch

IPL Interim Plutonium Laboratory

kg kilogram

kW kilowatt

kW(t) kilowatt (thermal)

L liter

LITR Low Intensity Test Reactor

MeV megavolt-electron

mi mile

ml milliliter

mph miles per hour

mR milliroentgen

mrad millirad

mrem millirem

MRF Metals Recovery Facility

MSRE Molten Salt Reactor Experiment
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MTR Materials Test Reactor

MV megavolt

MW megawatt

ORNL Oak Ridge National Laboratory

ORR ORNL Research Reactor

PCA Pool Critical Assembly

PUREX plutonium uranium extraction

RaLa radioactive lanthanum

REDOX reduction oxidation

s second

SNAP Systems for Nuclear Auxiliary Power

SWSA Solid Waste Storage Area

TBP tributylphosphate

THOREX thorium extraction

TSF Tower Shielding Facility

TSR Tower Shielding Reactor

WAG Waste Area Grouping

X-10 Oak Ridge National Laboratory

Y-12 Y-12 National Nuclear Security Complex

μCi microcurie
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2.1 INTRODUCTION

Since its operations began in 1943, the mission of Oak Ridge National Laboratory (ORNL) has been 

to conduct research and development and production missions in support of the U.S. Department of 

Energy (DOE) and its predecessor agencies. (ORNL has also been known as X-10 or Clinton 

Laboratories and, briefly, Holifield National Laboratory.) Much of the earliest site work was devoted to 

the development and operation of the original reactor to test the larger production reactors for the 

Hanford site. The Graphite Reactor was used to produce gram quantities of plutonium and later 

fission products [e.g., radioactive lanthanum (RaLa)] and other types of radioactive materials were 

separated in other site facilities. Waste control technologies during early operations were in their 

infancy and much of the current knowledge of transport of radionuclides in the environment was 

obtained during this time. The ability to detect, identify, and quantify radiation types and radiation 

exposures was similarly progressing along with the new technologies being discovered in radioisotope 

production. Much of the early information gained during the early years at ORNL was used for the 

design of future U.S. Atomic Energy Commission (AEC)/DOE facilities and detection systems. Waste 

radioactive material was released from early site operations as gaseous, liquid, and solid effluents 

with little or no pretreatment. Later, methods were developed to capture many of the contaminants at 

their source and to reduce overall plant emissions. In some cases this increased direct exposures to 

individuals in the area and also created locations in which incidents and spills occurred.

During the more than 60 years of operations at the site, facilities have been constructed, operated, 

decontaminated, and decommissioned based on need. Many of the buildings that have remained 

standing in the main plant area were renumbered in the early 1950s to the current building numbering 

system. Attachment 2-A lists the buildings under the current numbering system along with the 

previous numbers if the building existed before the current system. 

Major historical operations and processes that have occurred at ORNL include: 

• The operation of the Graphite Reactor for producing plutonium and other radioisotopes

• The development of chemical processes to separate plutonium, uranium, and thorium from 

irradiated fuel

• Chemical separations of RaLa from irradiated fuel slugs for use in implosion dynamics studies 

at Los Alamos

• Operation of various facilities for the separation, packaging, and distribution of radioisotopes 

for government and commercial use

The ORNL site was also used to develop new reactor technologies. Various different reactor designs 

(pool, pressurized-water, boiling-water, liquid-metal, gas-cooled) were designed and in most cases 

tested at ORNL and then either scrapped or further developed elsewhere. Reactors operated by 

ORNL include the Low Intensity Test Reactor (LITR), Critical Experiments Facility [CEF, at the Y-12 

National Nuclear Security Complex (Y-12)], Bulk Shielding Reactor (BSR)/Pool Critical Assembly 

(PCA), ORNL Research Reactor (ORR), Tower Shielding Reactor (TSR), Health Physics Research 

Reactor (HPRR), Homogeneous Reactor Experiment (HRE), Aircraft Nuclear Propulsion (ANP) 

Program, the High Flux Isotope Reactor (HFIR), and the Molten Salt Reactor Experiment (MSRE). 

In 1947, several ORNL divisions moved to Y-12. These divisions were responsible for conducting 

research in biological sciences, production of stable isotopes, and engineering technology.
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2.2 MAJOR FACILITY DESCRIPTIONS

The ORNL site has been used to test new ideas for DOE and other agencies. Thus, many of the 

earliest buildings at the site have transitioned through various mission objectives. For example, 

Building 3019 was the original pilot plant facility used to separate plutonium from irradiated uranium 

slugs received from the Graphite Reactor. The original bismuth–phosphate separation process was 

inefficient and created a lot of waste. Subsequent chemical separations processes conducted in 

Building 3019 better refined the dissolved material, leaving less final product in the waste stream. 

The majority of the land and facilities at the ORNL site are owned by DOE. The management and 

operation of the site has been contracted to various organizations over the years (see Table 2-1). 

Table 2-1. Contractors of the Oak Ridge National Laboratory. 

Period Operated by Name

1/1943–6/30/1945 E. I. DuPont de Nemours for The University of 

Chicago

Clinton Laboratories

7/1945–12/1946 Monsanto Chemical Company Clinton Laboratories

1/1/1947–2/28/1948 Atomic Energy Commission Clinton Laboratories

3/4/1948 Carbide & Carbon Chemicals Company, Union 

Carbide Corporation

ORNL

1950 Carbide & Carbon Chemical Division, UCC ORNL

1956 Union Carbide Nuclear Corporation, Division of UCC ORNL

1964–1974 Union Carbide Nuclear Corporation, Nuclear Division ORNL

1975 Union Carbide Corporation, Nuclear Division Holifield National Laboratory

1976–3/31/1984 Union Carbide Corporation, Nuclear Division ORNL

4/1/1984–3/31/1995 Martin Marietta Energy Systems, Inc. ORNL

4/1/1995–12/31/1995 Lockheed Martin Energy Systems, Inc. ORNL

1/1/1996–3/31/2000 Lockheed Martin Energy Research, Inc. ORNL

4/1/2000–Present UT-Battelle ORNL

Since the late 1990s, two parcels of land immediately east of the main ORNL plant site within Bethel 

Valley have been deeded to organizations outside of DOE (Battelle and the State of Tennessee). 

Many of the new buildings currently being constructed at ORNL are using joint, private funding 

sources and are being occupied by non-DOE contractors. Though ownership and maintenance is the 

responsibility of the owner, the individuals within those facilities that are included under the ORNL Site 

Radiation Protection Program plan are issued thermoluminescent dosimetry and/or included in the 

internal dosimetry program as necessary.

The original building identification numbers from the 1940s were different than they are today. At the 

beginning, buildings were given three digit numbers, (e.g., 105, 225, 706). In the early 1950s, the 

building numbering nomenclature was changed to one with predominantly four digits. The current 

general ORNL site building numbering system is as follows: 

• Numbers 0000 to 0999 are north of Bethel Valley Road.

• Numbers 1000 to 1499 are north of Central Avenue and west of First Street.

• Numbers 1500 to 1999 are south of Central Avenue and west of First Street.

• Numbers 2000 to 2499 are north of Central Avenue, east of First Street, and west of Third 

Street.
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• Numbers2500 to 2999 are south of Central Avenue, east of First Street, and west of 

Third Street.

• Numbers 3000 to 3499 are north of Central Avenue, east of Third Street, and west of 

Fifth Street.

• Numbers 3500 to 3999 are south of Central Avenue, east of Third Street, and west of 

Fifth Street.

• Numbers 4000 to 4499 are north of Central Avenue, east of Fifth Street, and west of the East 

Vehicle Gate.

• Numbers 4500 to 4999 are south of Central Avenue, east of Fifth Street, and west of the East 

Vehicle Gate.

• Numbers 5000 to 5499 are north of Central Avenue, east of East Vehicle Gate, and west of 

Main Entrance Drive.

• Numbers 5500 to 5999 are south of Central Avenue, east of East Vehicle Gate, and west of 

Swan Pond.

• Numbers 6000 to 7499 facilities are further east of the main plant site in Bethel Valley.

• Numbers 7500 to 7999 are south of Haw Ridge in Melton Valley. 

• The ORNL facilities in the Y-12 National Nuclear Safety Complex begin with the 9000 

numbers.

Maps of the main ORNL campus and sub-areas are provided in Attachment 2C.

A March 1, 1953, document from the ORNL site Facilities and Operations Directorate, Oak Ridge 

National Laboratory Building List (ORNL 1953), indicated a cross-linking from the old and new 

building numbering nomenclature at that time. In addition, the Directorate provided a current ORNL 

building list for all facilities at the site (ORNL 2002). Attachment 2A shows the combined list. 

The remainder of this section provides information for those buildings where information was available 

for specific facilities. For convenience, the principal facilities and radionuclides of concern identified in 

the following sections are summarized in Attachment 2B, “Major Facilities and Radionuclides of 

Concern.” Section 2.3 provides additional information on ORNL processes and programs. 

2.2.1

Building 2000 is a Quonset-style hut. It was built in 1948 to house Metallurgy Operations. The 

23,000-ft2 building had equipment and facilities to produce fuel elements containing highly enriched

uranium. Processes in the building included metal casting and fabrication equipment; laboratories for 

testing the mechanical, chemical, and physical properties of uranium and fuel elements; and office 

space. The building was equipped with a once-through ventilation system to remove radioactive 

materials from the air using a cyclone separator system and absolute filters before release to the 

environment. This facility was used in the development of the aluminum-clad, aluminum-uranium fuel 

element used in the Materials Test Reactor (MTR) and Low Intensity Testing Reactor (LITR) 

(ORNL 1997a).

Building 2000 (formerly 101-D) Metallurgy Laboratory
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2.2.2

Building 2005 was a frame structure built to serve Manhattan Project operations. It had approximately 

4,000 ft2 of floor space. The building was modified in 1950 to contain multiple test loops as well as 

early equipment for studying welding, braising, and nondestructive inspection. Liquid metals and 

molten salts were tested for compatibility with reactor materials in thermally driven test loops in the 

building.

Building 2005 (formerly 706-B) Metallurgy Annex

2.2.3

Building 2026 was constructed in 1964 (with additions in 1966 and 1985) and provides 22,600 ft2 of 

laboratory and office space dedicated to the application of general analytical chemistry of radioactive 

materials. The facility is equipped with special containment and ventilation systems to handle 

radioactive materials with high gamma dose rates (hot cells) and high levels of alpha radiation bearing 

material (glovebox system). The building houses facilities designed to segregate both low and high 

levels of radioactivity. In addition, the facility includes a radioactive liquid waste system that meets 

current regulatory requirements. The facility is fully equipped to handle the packaging and disposal of 

radioactive solid waste (ORNL 2001).

Building 2026 Radioactive Materials Analytical Laboratory

2.2.4

The Graphite Reactor is described in Section 2.3.1. Radionuclides produced in the reactor included 

35S, 32P, 31Si, 42K, 41-45Ca,46Sc, 51Ti, 59Fe, 55Fe, 60Co,65Ni, 64Cu, 75Se, 110Ag, 114In, 115Cd, 124Sb, 152Eu, 

154Eu, 155Eu, 182Ta, 185W, 185Os, 191Os, 193Os, 204Tl, 206Tl, 210Bi, 24Na, 76As, 82Br, 86Rb, 99Mo, 198Au, 131I, 

141-143Ce, 14C, and 192Ir. Activation of the cooling air resulted in the chronic release of 41Ar from the 

Building 3018 stack whenever the reactor was operating. In 1948, 41Ar releases totaled 540 Ci d-1at a 

reactor power of 4,000 kW(t) and an exit airflow rate of 51,000 cfm. Fuel slug ruptures in 1947 

resulted in emissions of 131I, 133I, 129I, 137Cs, 90Sr, 85Kr, 133Xe, 239Pu, 103Ru, 106Ru, 144Ce, 140La, 140Ba, 

95Zr, 89Sr, 235U, 238U, and 95Nb. 

Building 3001 (formerly 105) Graphite Reactor Building (Clinton Pile)

2.2.5

The Graphite Reactor Filter House is north of the Graphite Reactor outlet air duct, and west of the Fan 

House (Building 3003) and Exhaust Stack (Building 3018). The purpose of the building was to 

provide high-efficiency particulate air (HEPA) filtration to prevent the release of radioactive 

particulates from the 3018 stack due to ruptured fuel slugs. The building was constructed in 1948 and 

operated until 1963. 

Building 3002 (formerly 114) Graphite Reactor Filter House

2.2.6

The Graphite Reactor fan house provided negative pressure and served as a passageway for the 

filtered exhaust from the graphite reactor air filter building to the stack (Building 3018). The building 

was in operation from 1948 to 1963. Information concerning operations at the Characterization 

Laboratory was not available.

Building 3003 (formerly 115) Graphite Reactor Fan House and Surface Modification 

and Characterization Laboratory

2.2.7

The water demineralizer building no longer exists, but was identified in an early building listing. 

Building 3004 supported reactor operations for the Low Intensity Training Reactor (LITR), but it 

Building 3004 (formerly 807) Water Demineralization
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appears that the water from this facility was also used in the Bulk Shielding Reactor pool (Rupp and 

Cox 1955).

2.2.8

The Low-Intensity Test Reactor (LITR) facility consists of three buildings: the Low Intensity Test 

Reactor Building (3005), the Demineralization Water Building (3004), and the Low-Intensity Test 

Reactor Water-to-Air Heat Exchanger (3077). The LITR is made up of five cylindrical steel and 

aluminum sections with all but the lowest tank section above ground. It measures 70 by 62 by 57 ft. 

The LITR facility is immediately east of the Graphite Reactor. Section 2.3.6.1 describes the LITR 

facility further.

Building 3005 (formerly 106) Low Intensity Training Reactor (LITR)

2.2.9

The Bulk Shielding Reactor (BSR) is a two-story steel-frame building with corrugated metal siding with 

a footprint of approximately 4000 ft2

. The pool has internal dimensions of 40 by 20 ft. In addition to 

the pool, the building contains offices, instrument rooms, experiment rooms, and a small shop. 

Section 2.3.6.3 describes the BSR further.

Building 3010 Bulk Shielding Reactor Facility

2.2.10

Building 3018 is a 200-ft stack of steel-reinforced concrete used for venting exhaust from the Graphite 

Reactor from 1943 until 1963. Section 2.3.1 describes the Graphite Reactor further. 

Building 3018 Exhaust Stack (for Building 3003)

2.2.11

This building contained the reprocessing cells and equipment to chemically dissolve irradiated fuel 

slugs and separate plutonium from solution. The facility contains six thick concrete hot cells used in 

the separation processes. Section 2.3.1 describes several of the more important operations that 

occurred in Building 3019.

Building 3019 (formerly 205) Radiochemical Processing Pilot Plant

2.2.12

Building 3020 was initially used to exhaust from Building 3019. Later the exhausts were directed to 

the Building 3039 stack.

Building 3020 Exhaust Stack (for Building 3019)

2.2.13

This facility provided negative pressure to Building 3019 process activities and exhausted through the 

Building 3020 Exhaust Stack.

Building 3021 Fan House (Northeast of Building 3020)

2.2.14

The North Tank Farm occupies an area of approximately 100 by 200 ft in the northeast corner of the 

intersection of Central and Third Streets and contains eight buried tanks (four gunite and four 

stainless steel). Wastes generated from chemical separations were collected in these tanks. Section 

2.3 describes the North Tank Farm further. Table 2-2 lists tank contents in the North Tank Farm.

Building 3023 (formerly 206) North Tank Farm
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Table 2-2. North Tank Farm (Facility 3023) contents. 

Tank Years of operation Radioisotopes of concern

W-1 1943-1960 238,239Pu, 90Sr, 137Cs, 60Co, and 3H

W-1A 1951 to 1986 233U, 241Am, 244Cm, 238,239Pu, 90Sr, 137Cs, 60Co, and 3H

W-2 1943 until the 1960s 233U, 235U, 237Np, 238,239Pu, 90Sr, 137Cs, 60Co, and 3H

W-3 1943 until the 1960s 233U, 235U, 237Np, 241Am, 244Cm, 238,239Pu, 90Sr, 137Cs, 60Co, and 3H

W-4 1943 until the 1960s 233U, 235U, 237Np, 241Am, 244Cm, 238,239Pu, 90Sr, 137Cs, 60Co, and 3H

W-13 1943 to 1958 238Pu, 90Sr, 137Cs, 60Co, and 3H

W-14 1943 to 1958 238,239Pu, 90Sr, 137Cs, 60Co, and 3H

W-15 1943 to 1958 238,239Pu, 90Sr, 137Cs, 60Co, and 3H

2.2.15

The facility was constructed in 1950 and is about 70% to 80% utilized. The literature indicates that 

the facility handled more radioactive material in the early years, but as the years progressed lesser 

quantities of radioactive materials were examined there. The hot cells were used to assess activated 

radioisotopes. A remote storage facility was added in 1958 and decommissioned in 1985. Cell 6 was 

enlarged and upgraded to a sealed cell in 1958. Sealed storage wells were installed in 1985. A major 

upgrade of the LLLW system was completed in 1998 (ORNL 2001).

Building 3025E Physical Examination Hot Cells

2.2.16

The chemical separations facilities in Buildings 3026-C and –D were specifically designed and 

constructed to process 1- to 100-Ci amounts of RaLa. Quantities of radioactivity much larger than 

those designed for the facilities were processed. After RaLa operations ended in 1956, the 

operational areas within each facility were later used for other operations. Section 2.3.2 further 

describes the major operations in Buildings 3026-C and –D. The following isotopes would have been 

in the Building 3026-C and –D complex: 129I, 131I, 79Se, 107Pd, 147Pm, 137Cs, 140Ba/La, 90Sr, 85Kr, 188W, 

191Os, 133Xe, actinides, U, 99Tc, 60Co, Pu, and 3

H. 

Buildings 3026-C and 3026-D (formerly 706-C and 706-D) By-Product Processing and 

Chemical Separation Laboratory

2.2.17

The Special Nuclear Materials Storage Vault was constructed in 1980. The building is used for the 

storage of Security Category III radioactive materials. No material processing is performed in the 

building and special nuclear materials are contained by two sealed barriers at all times. The materials 

stored in the vault are inspected weekly. The building contains eight rooms and is constructed with an 

18-in. concrete slab, reinforced 18-in. thick walls, and a 10-in. reinforced concrete roof. The building 

was designed and constructed to withstand both a 0.15g earthquake and a 350-mph wind. The rooms 

are equipped with drains piped to a steel storage tank in a below-grade pit. The building is ventilated 

to the central off-gas system (ORNL 2001). 

Building 3027 Special Nuclear Materials Storage Vault

2.2.18

Building 3028 was constructed in 1950 and originally housed the 131I processing facility and the 

separation facility for 147Pm. The building has a four-story central section with one-story cell operation 

areas on the east and west sides. The first floor covers 4000 ft2 and has seven cells where various 

processes took place. Section 2.3.3 further describes Building 3028.

Building 3028 (formerly 910) Alpha Powder Facility
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2.2.19

Building 3029 was constructed in 1952 to support the Isotopes Program. The building is a singlestory steel-frame structure covered by corrugated metal siding. The floor area is 3,000 ft2 and has 

four cells where various processes took place. Section 2.3.3 further describes Building 3029. 

Building 3029 (formerly 909) Source Development Lab

2.2.20

Building 3030 was constructed for production and development of radioisotopes to be used in 

industry, medicine, and research. The building is a steel-frame structure covered by corrugated 

aluminum siding. The single story facility has a floor area of 825 ft2

, a hot cell, two lab hoods, and a 

glovebox. The hot cell has 2-ft concrete walls with 4 in. of lead brick on the west and south sides. 

Section 2.3.3 describes Building 3030 further. 

Building 3030 (formerly 908) Radioisotope Processing Building “C”

2.2.21

Building 3031 was constructed for production and development of radioisotopes to be used in 

industry, medicine, and research. The building is a single-story frame structure, has a floor area of 

825 ft2

, a hot cell, and two lab hoods. The hot cell has 1-ft thick barites concrete and 5 in. of steel 

armor plate. Section 2.3.3 describes Building 3031 further. 

Building 3031 (formerly 907) Radioisotope Processing Building “D”

2.2.22

Building 3032 was constructed to house the analytical facility for radiochemical support of the 

Isotopes Production activities. The facility has a laboratory with five hoods on the north side of the 

building and an office on the south side connected by an open passageway. Section 2.3.3 further 

describes Building 3032.

Building 3032 (formerly 906) Radioisotope Processing Building “E”

2.2.23

Building 3033 was used for processing 14C, 85Kr, and 3

H. The building is a steel-frame structure 

covered with aluminum siding with about 1200 ft2 of floor space. Three internal structures were 

present to process the three different gases. Section 2.3.3 describes Building 3033 further. 

Building 3033 (formerly 905) Radioactive Gas Process Facility

2.2.24

Building 3034 was constructed about 1960 and used to house and contain the facilities for the 

production, loading, welding, and decontamination of neutron dosimeter materials as well as weighing 

milligram to gram quantities of actinide materials for research. It is a metal structure with 242 ft2 of 

floor space. Section 2.3.3 describes Building 3033A further.

Building 3033A Actinide Fabrication Facility Annex

2.2.25

Constructed in the late 1950’s, this facility currently houses the central electrical distribution station for 

the Isotopes Circle Area. The facility was used as a field shop for the Plant and Equipment Division 

and supported isotope production; however, no handling of radioactive materials occurred in this 

building.

Building 3034 Radioisotopes Services Building
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2.2.26

Building 3038 has been in operation since 1949. It was constructed to house all the radioisotope 

shipping activities for ORNL. It is a masonry structure divided by concrete brick interior walls into 

three sections. There is 7250 ft2 of floor space. Section 2.3.3 further describes Building 3038.

Building 3038 (formerly 902) Isotope Research Materials Laboratory, Radioisotope 

Analytical and Packing Building

2.2.27

The 3039 stack ventilation system, which was originally built in 1950, was extensively modified and 

upgraded in 1984 to increase its efficiency and reliability. The 3039 stack is a 76.2-m (250-ft) high, 

unreinforced radial, brick masonry chimney. The 3039 Stack Ventilation System consists of seven 

collection systems, each with its own underground or aboveground ducting, fans, and controls. Five 

of these are designed to handle the cell ventilation waste streams from limited-access areas and hot 

cells. The other two systems are designed to handle the off-gas from process equipment and 

laboratory experiments (ORNL 2002). Section 2.3.4 further describes the Central Exhaust Stack.

Building 3039 (formerly 911) Central Exhaust Stack (Radioisotope Area)

2.2.28

Building 3042 was built to house the ORR. The facility covers approximately 11,000 ft2

. The building 

is a semi-airtight, steel-frame structure covered with insulated metal panels. The pool in which the 

reactor was placed had a minimum shield of 4 ft of barites concrete with a 10-ft thickness at the east 

end where the experimental beam ports were. Section 2.3.6.4 further describes the ORR. 

Building 3042 ORNL Research Reactor

2.2.29

Constructed in 1962 and still in operation, Building 3047 is a three-story steel-frame building with 

concrete block exterior and interior walls. The building houses the Radioisotopes Development 

Laboratory. The facility has four high-level beta-gamma cells, one alpha hot cell, seven laboratories 

for handling low-level radioactive materials, a decontamination room, offices, and service areas. The 

facility is used to conduct research and development and to produce of radioisotopes. Radioactive 

materials normally handled at the facility include 90Sr (up to 100,000 Ci), with single sealed sources of 

90Sr up to 350,000 Ci. Other radionuclides handled at the facility include 137Cs, 152,154Eu, 238Pu, 111mSn, 

166Dy/166Ho, 186Re, and 188W/188Re. 

Building 3047 Radioisotopes Development Laboratory

2.2.30

Building 3118 was constructed to enclose the space between Buildings 3030 and 3031 to provide 

direct access between the hot cells in each facility. The steel frame structure is covered with 

corrugated aluminum siding. 

Building 3118 Radioisotope Processing Building “H”

2.2.31

The Metal Recovery Facility was constructed in late 1951 and operated from 1952 until 1960 as a pilot 

and small-scale production facility for nuclear fuel reprocessing. It was a two-story, steel-frame metal 

siding structure with numerous windows. The building contained seven concrete or concrete block 

cells, which were secured and maintained under negative pressure, with ventilation using HEPA 

filters. The building was used to recover uranium, plutonium, neptunium, and americium from various 

waste solutions, scrap, and miscellaneous fuel elements. Twenty-five different processing campaigns 

were run through the facility. The facility was shut down due to lack of secondary containment.

Building 3505 Metal Recovery Facility
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2.2.32

The South Tank Farm occupies an area of about 130 by 200 ft in the southeast corner of the 

intersection of Central and Third Streets and contains six buried, gunite tanks. It also includes an 

area to the east of approximately 80 by 230 ft containing another smaller buried gunite tank and six 

buried stainless-steel tanks. Wastes generated from chemical separations were collected in these 

tanks. Section 2.3.4 describes the South Tank Farm further. Table 2-3 lists the tank contents in the 

South Tank Farm. 

Building 3507 (formerly 206) South Tank Farm

Table 2-3. South Tank Farm (Facility 3507) contents. 

Tank

Years of 

operation Radioisotopes of concern

W-5 1943-1978 233U, 235U, 3H, 60Co, 90Sr, and 238,239Pu 

W-6 1943-1978 233U, 235U, 3H, 60Co, 90Sr, 238,239Pu, 244Cm, 152,154Eu, and 252Cf 

W-7 1943-1978 233U, 235U, 3H, 60Co, 90Sr, 232Th, 238,239Pu, 244Cm, 152,154Eu, and 252Cf 

W-8 1943-1978 233U, 235U, 3H, 60Co, 90Sr, 241Am, 238,239Pu, 244Cm, 152,154Eu, and 252Cf 

W-9 1943-1978 233U, 235U, 3H, 60Co, 90Sr, 241Am, 238,239Pu, 244Cm, 152,154Eu, and 252Cf 

W-10 1943-1978 233U, 235U, 3H, 60Co, 90Sr, 241Am, 238,239Pu, 244Cm, 152,154Eu, and 252Cf 

2.2.33

The Fission Product Pilot Plant (formerly known as the 106Ru tank arrangement) began operation in 

1948 as a two-room hot cell and was taken out of service in 1958. The facility consists of a concrete 

pad surrounded by stacks of concrete blocks; it is on the east end of the South Tank Farm. Section 

2.3.1 further describes Building 3515.

Building 3515 Fission Product Pilot Plant

2.2.34

In 1957, a new process waste treatment plant was built. The plant had the capacity of 

500,000 gal d-1. The plant included an 800,000-gal equalization and hold-up basin. The hold-up 

basin was able to store wastewater before treatment. A lime–soda softening process was used to 

remove strontium through co-precipitation. The neutralization plant was capable of removing 90% of 

the strontium and rare earths. After treatment the wastewater was monitored, sampled, and 

discharged to White Oak Creek.

Building 3518 Acid Neutralization Plant

2.2.35

Building 3525, constructed in 1963, is a two-story brick building with a partial basement. The first floor 

houses the primary containment-shielded cell complex, consisting of three hot cells arranged in a 

U-shape. The hot cells are constructed of 3-ft-thick barites concrete walls and compatible oil-filled, 

lead glass viewing windows, creating an essentially leak-tight barrier. The remainder of the laboratory 

outside the hot cell complex consists of the charging area, the equipment maintenance air lock areas, 

the operating area, the truck unloading area, the photographic rooms, the main change room, and the 

rooms housing supporting mechanical equipment. A small laboratory that houses the core conduction 

cool down test facility is on the east side of the truck unloading area. The core conduction cool down 

test facility is used to test radioactive samples under controlled thermal conditions while monitoring 

the samples to determine the release of radioactive materials. 

Building 3525 High Radiological Level Examination Laboratory 

The processes performed in the facility consist of:

• Receipt and handling of irradiated materials (fuel or non-fuel, typically as experimental 

capsules) in shielded casks
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• Transfer of material into and out of the hot cells

• Capsule disassembly

• Nondestructive and destructive testing of irradiated materials

• Packaging and shipment of irradiated materials (on-site or off-site)

• Waste packaging for disposal

• Maintenance of remote equipment

• Decontamination of the facility and equipment 

Examination and testing activities include metrology; metallographic sample preparation by 

sectioning, grinding, and polishing; optical and electron microscopy; mass spectrometry of fission 

gases; gamma spectrometry; and other physical properties evaluations as appropriate to the 

experimental objectives of a particular program.

2.2.36

The process waste collection system consists of a series of underground pipes where process waste 

water flows from the source facility to a pumping station for transfer to the Process Waste Treatment 

Complex—either Building 3544 (for radiological treatment) or Building 3608 (for nonradiological 

treatment). The waste acceptance criteria administratively limits the wastes that can be added to the 

Process Waste system to a total radionuclide concentration of the ingestion dose equivalent of 

1 x 104 Bq L-1 90Sr. Chemicals are limited based on treatment system capabilities and effluent 

discharge permit limits. At strategic points throughout the collection system, manholes are equipped 

with beta-gamma radiation monitors, pH monitors, and flow monitors that are continuously monitored 

at the Waste Operations Control Center (WOCC) to allow personnel to detect any unusual activity in 

the system (ORNL 2001).

Building 3544 Process Waste Treatment Facility

2.2.37

The Building 4500 complex consists of two, two-story, brick buildings with basement and attic levels. 

Built in the early 1950s, the buildings consist of a main area with four wings. The buildings consist 

primarily of offices, laboratories, storage areas, maintenance shop areas, a mailroom, a canteen area, 

and utility equipment areas. Primary utilities include sanitary water and sewer; process water and 

sewer; steam and condensate return systems; compressed air; electrical utilities; and heating, 

ventilation and air conditioning systems. The facility contains numerous hoods and other sources that 

are vented locally. A radioactive hot drain from 4500 South no longer in use is in place and connects 

the service chases serving the first- and second-floor laboratories. 

Building 4500 Central Research and Administration Facility

No information is available that specifically describes work conducted with radioactive materials in the 

Building 4500 complex, but it is believed that only small-scale operations with radioactive materials 

occurred in the two buildings. The ORNL annual stack report indicates many emission sources exist 

from the two buildings, but that they emit very low levels of total radioactivity.
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2.2.38

Building 4501 is a steel, concrete, concrete block, and brick building. Interior partitions are made 

primarily of poured concrete and concrete block faced with transite, gypsum block, or steel paneling. 

The building was constructed in 1952 and has four floors. Except for the first floor, there are interior 

access connections from Building 4501 to Building 4505 through hallways and stairwells. The 

basement contains laboratories, shop areas, cell ventilation ducts, and storage areas. Four hot cells 

surrounded by support laboratories and operating areas are centrally located on the first floor. The 

outside part of this floor contains chemical and radiochemical laboratories and office space. On the 

second floor, immediately above the hot cells and surrounding laboratories, is the high bay area, 

which contains chemical and radiochemical laboratories and office space. The third floor is the attic 

area and provides space for building utilities, ventilation fans, and controlled storage. The roof of the 

building contains several exhaust stacks for building ventilation systems. A process to convert 233U 

adsorbed on sodium-fluoride traps as part of the Molten Salt Reactor Experiment (MSRE) design and 

development was conducted in the building.

Building 4501 High Level Radiochemistry Laboratory

2.2.39

Building 4508 is immediately west of Building 4500 South. The Interim Plutonium Laboratory (IPL) 

was assembled on the first floor of Building 4508 within the confines of the Ceramics Laboratory in the 

1960s. Placement of the IPL in building 4508 was made possible by the secondary containment 

design. The IPL was equipped with very high-quality gloveboxes and a purge system that provided 

the gloveboxes with working atmospheres having very low oxygen and water contents. The inert 

atmosphere was required for work with plutonium and uranium nitrides. The gloveboxes were 

equipped to synthesize, press, and sinter pellets of these nitrides.

Building 4508 Metals and Ceramics Laboratory

In addition, Building 4508 housed the Fuel Cycle Alpha Facility (FCAF). The FCAF fabricated 

plutonium oxide, and plutonium-uranium oxide fuel pellets, and was used for coating sol gel derived 

microspheres with pyrolytic carbon. Special target materials for the HFIR were also developed and 

fabricated in this facility. This laboratory was initially in the basement of Building 3019 before being 

relocated to Building 4508. Two additional and unique fuel-rod-loading techniques, vibratory 

compaction and slug injection, were also studied in the FCAF.

2.2.40

Construction of Building 5505, the Transuranium Research Laboratory, was completed in 1967. The 

building is a one-story structure with an equipment room on the roof. The building is constructed of 

reinforced concrete with exterior walls of concrete block faced with brick. The equipment room is of 

steel-frame construction with exterior walls of uninsulated aluminum panels. The laboratories are 

back-to-back in the central portion of the building and are separated by a central corridor providing 

controlled access to each laboratory for transfer of radioactive materials. The offices occupy the 

north, west, and south perimeters of the building and are across a corridor from the laboratories. At 

present, no radioactive liquid waste is generated in the facility, but provisions are in place for a 

radioactive bottling station if needed. The facility maintains negative pressure through the interaction 

of the laboratory and office air supply system, the laboratory exhaust system, and the glovebox 

exhaust system. Research in the facility involves the chemistry, physics, and material science of 

actinides and their compounds to provide fundamental and technological information as well as a 

platform for the development of analytical instrumentation.

Building 5505 Transuranium Research Laboratory
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2.2.41

Building 6000, immediately east of the main plant site, contains the Holifield Radioactive Ion Beam 

Facility. The high-voltage generator is inside a 100-ft-high, 33-ft-diameter pressure vessel, with both 

low- and high-energy acceleration tubes contained in the same column structure. Production of 

radioactive ions occurs using the Isotope-Separator-On-Line technique with subsequent injection into 

a 25-MV tandem electrostatic accelerator where the ions are accelerated to energies of 0.1 to 10 MeV 

per nucleon for light nuclei and up to 5 MeV per nucleon for nuclei heavier than 100 amu. Site 

preparation for the tandem accelerator was begun in August 1975. The first successful transmission 

of beam through the entire system occurred in May 1980.

Building 6000 Holifield Radioactive Ion Beam Facility

2.2.42

The ORELA facility consists of a 180-MeV electron accelerator, neutron producing targets, buried and 

evacuated flight tubes up to 200 m long leading to underground detector locations, a wide variety of 

sophisticated detectors, and data acquisition and analysis systems. Neutrons are produced by 

bremsstrahlung from a tantalum radiator. Moderated or unmoderated neutrons are available, and 

further tailoring of the spectral shape is accomplished with movable filters. 

Building 6010 Oak Ridge Electron Linear Accelerator

An intense, pulsed source of neutrons is produced at the accelerator when bursts of electrons from 

the linac stop inside a tantalum target. As the electrons slow down in the tantalum, they generate an 

intense flux of gamma ra ys . The s e ga mma rays in turn produce ne utrons via (ga mma , xn) 

reactions on the tantalum. The neutrons are moderated in the cooling water surrounding the target 

and then travel to the various experimental stations through evacuated flight tubes. The resulting 

neutron spectrum is white in the sense that the covered energy range is relatively broad (from 

subthermal to approximately 50 MeV) and the flux is roughly proportional to E-0.7 where E is the 

neutron energy. The integrated flux is about 0.8 x 1014 neutron s-1 at a power of 50 kW.

2.2.43

Section 2.3.6.7 describes the HRE Building.

Building 7500 Homogeneous Reactor Experiment Reactor Building

2.2.44

Section 2.3.6.10 describes the MSRE facility.

Building 7503 Molten Salt Reactor Experiment

2.2.45

Section 2.3.6.5 describes the Tower Shielding Facility. 

Building 7700 Tower Shielding Facility

2.2.46

The DOSAR CalLab is a 2800-ft2 concrete block building consisting primarily of a control room, a 

6.1- by 7.0- by 4.3-m gamma irradiation room, a beta/X-ray room that is the same size as the gamma 

room, and a low-scatter 9.1- by 9.1- by 5.8-m neutron room. Sources currently at the DOSAR CalLab 

include a 90Sr/90Y irradiator; a Büchler irradiator and PTB source set that includes 147Pm, 204Tl, and 

two 90Sr/90Y sources; a 10-Ci 137Cs beam irradiator and 1.2-Ci 137Cs panoramic irradiator; a bare 

238PuBe source; and two 252Cf sources that can be used bare and with various moderators, including 

polyethylene and heavy water (3

H2O). Also available is a Pantak model HF320 X-ray generator for 

reproducing NIST beam codes. Table 2-4 lists the sealed sources present in the facility. The assay 

date for the radionuclide sources is September 2, 2003. 

Building 7735 Dosimetry Applications Research Calibration Laboratory
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Table 2-4. Sealed sources available at DOSAR Calibration Laboratory (Building 

7735). 

Radiation Source Dose rate

Source distance

(cm)

Beta 90Sr/Y 5,861 mrad hr-1 35

Beta 147Pm 14.3 mrad hr-1 (surface) 20

Beta 204Tl 8.8 mrad hr-1 35

Beta 90Sr/Y 1,012 mrad hr-1 35

Beta 90Sr/Y 25,375 mrad hr-1 35

Gamma 137Cs 1,042 mR hr-1 51

Gamma 137Cs 2,442 mR hr-1 100

Neutron 252Cf (bare) 140 mrem hr-1 50

Neutron 252Cf (bare) 35.0 mrem hr-1 100

Neutron 252Cf (poly-moderated) 16.4 mrem hr-1 50

Neutron 252Cf (poly-moderated) 4.1 mrem hr-1 100

Neutron 252Cf (D2O-moderated) 93.9 mrem hr-1 50

Neutron 252Cf (D2O-moderated) 23.5 mrem hr-1 100

Neutron 238Pu:Be 21.5 mrem hr

-1 100

X-ray Various beam qualities 2 to 300 R hr-1 318

2.2.47

The Old Hydrofracture site was built in 1963 and used from 1964 to 1979 for permanent disposal of 

low-level liquid radioactive waste in shale formations at depths of more than 780 ft. Various facilities 

were required to support the waste disposal operations, including: a building containing a mixing cell, 

pump cell, and injection well cell; five underground tanks used for storage of the liquid waste prior to 

mixing it with grout; and an impoundment (Old Hydrofracture Pond) and waste pit (T-4 Waste Pit) for 

emergency storage of liquid waste due to system failures. Each of the cells had 1-ft thick concrete 

walls and roofs of diamond-plated steel. The liquid waste tanks, both interior to the building and the 

Pond, contained elevated levels of radioactive materials producing high exposure rates. Shielding 

was added to the roof in 1974 to reduce the dose rate over the mixer cell from 1 to 2 R hr-1 to about 

100 to 200 mR hr-1 (ORNL 1996). 

Building 7852 Old Hydrofracture Facility

Operations ended in 1980 leaving approximately 50,000 gal of transuranic waste in the five 

underground storage tanks. This waste was removed and transferred to the Melton Valley Storage 

Tanks for processing and disposal. 

2.2.48

Section 2.3.4 discusses Solid Waste Storage Areas (SWSAs) 1 to 6 in further detail. The following 

paragraphs detail the known information about the presence of radioactive material.

Solid Waste Storage Areas

1. Analyses from several SWSA 1 groundwater wells showed low concentrations of 90Sr, but no 

indication of 137Cs or transuranic elements.

2. Analyses of soil core samples taken from the SWSA 2 area indicated no contamination. 

Analyses included uranium, plutonium, and 137Cs. Groundwater samples also showed no 

contamination. Water sample analyses included tritium, gross alpha, and gross beta.

3. Groundwater samples indicated small amounts of trivalent rare earths, 90Sr, 89Sr, and 3

H 

contamination.
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4. Groundwater and surface-water samples from the area indicated radioactive contamination in 

both. One well sample indicated alpha contamination while another 8 of the 16 well samples 

indicated beta/gamma contamination. Identified radioactive contaminants include 90Sr, 106Ru, 

137Cs, 60Co, 210Po, 239Pu, 3

H, 125Sb, and trivalent rare earths.

5. Water sample analyses indicated radioactive contamination of 244Cm, 238Pu, 90Sr, 3

H, 125Sb, 

106Ru, 137Cs, 60Co, and trivalent rare earths.

6. Estimates of total radioactivity in SWSA 6 included 252,000 Ci through 1984, of which 

211,000 Ci has been buried since 1977. Waste consists of 155,000 Ci europium; 2,970 Ci 

90Sr; 5,110 Ci 137Cs; 32,200 60Co; and 7,110 Ci 3

H. Water seepage has occurred in a majority 

of the 49 trenches. In an attempt to decrease the water seepage, a near-surface seal of a 

mixture of bentonite-shale was applied to three sections of SWSA 6, and the area was 

covered with grass. Water seepage has been observed under the seal since it was applied; 

the migration of water has been both lateral and vertical.

2.3 OAK RIDGE NATIONAL LABORATORY SITE OPERATIONS AND PROCESSES

Section 2.2 provides information concerning specific operating facilities and the radioactive materials 

that were or are present at those facilities. This section describes specific processes associated with 

many of those facilities (e.g., the Graphite Reactor had a fan house, filter house, stack and other 

ancillary facilities associated with its operation). Section 2.3.1 discusses early operation of the 

Graphite Reactor, the Hot Pilot Plant (Building 3019), and some associated facilities. Section 2.3.2 

describes RaLa activities. Section 2.3.3 describes isotope production areas. Section 2.3.4 discusses 

waste areas and processes. Section 2.3.5 describes biological and life sciences research in ORNL 

facilities at Y-12. Section 2.3.6 describes the remaining reactor development and operation activities 

at ORNL. 

2.3.1

After Glenn Seaborg had proven that plutonium could be produced from the bombardment of 238U with 

a cyclotron and Enrico Fermi had designed a graphite-moderated reactor that had achieved a 

self-sustaining, critical reaction; it was recognized that to produce plutonium in quantities great 

enough for weapons production could only be attained by the construction of large reactors. The 

Federal government decided to build an air-cooled, graphite-moderated reactor using natural uranium 

(enrichments), with sufficient concrete shielding to minimize radiation exposures to site personnel. 

The U.S. Army Corps of Engineers constructed the reactor at the Clinton Laboratories, which became 

the Oak Ridge National Laboratory in 1948. In 1942, the Manhattan Engineering District of the Corps 

became responsible for the management of uranium and plutonium plant construction and nuclear 

weapons production. 

Early Operation of Graphite Reactor and Associated Facilities

The Graphite Reactor, Building 3001 (originally 105), operated from November 1943 to November 

1963. The reactor was designed and built as a pilot plant to test the control and operating procedures 

of the proposed larger production reactors and to provide needed quantities of plutonium for 

Manhattan Engineering. The reactor was designed to operate at a thermal power rating of 1,000 kW, 

but with subsequent modifications reached at least 4,400 kW (Rupp and Cox 1955). There were 7 ft 

of concrete shielding between the reactor and the front wall of the shield that operators would work 

from [5 ft of barites concrete with 1 ft of structural concrete on each side as retaining walls (Rupp 

1955)]. Natural uranium fuel slugs (4 in. long by approximately 1.1 in. diameter) were loaded in the 

reactor by inserting them through holes in the front face into horizontal channels in the graphite 

matrix. (The Aluminum Company of America provided the aluminum-clad fuel slugs for use in the 
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reactor.) Following irradiation, slugs were pushed out the back side of the reactor into a water-filled 

transfer canal. 

In 1958, the maximum radiation levels in the transfer canal area ranged from 30 to 40 mR hr-1 due to 

highly contaminated concrete on its sides. Cox (1958) stated that the majority of the exposure to 

reactor operations personnel occurred during work adjacent to the transfer canal. The water level 

was increased and steel plate was placed over the contaminated concrete the next year. Exposure 

rates to the workers who worked “several hours at a time” were “reduced to about one-tenth of its 

former value” (Cox 1959). Ruptured fuel slugs, allowed to oxidize in the transfer canal, were the 

major source of contamination and dose in the reactor building. Irradiated fuel slugs were moved 

underwater to the separations building (Building 3019, originally 205) after a cooling period to allow for 

decay of the short-lived radioisotopes. Rupp and Cox (1955) reported that elevated levels of 60Co and 

137Cs were present in the canal waters in 1954. 

Airborne wastes were removed from Building 3001 and exhausted to the atmosphere from a 200-ft 

stack (Building 3018) immediately north of the Graphite Reactor Building. Initial design of the exhaust 

system did not include a filtering mechanism. By 1948, it was recognized that radioactive particulates 

were being emitted from the stack. Particulate filtration was added to reduce the emissions. 

Researchers later discovered that particulate contamination became elevated in the airborne effluent 

stream when fuel slugs, pushed out the back of the reactor, would fall and strike the mattress plates. 

The impact would sometimes breach or further breach the aluminum cladding, resulting in a release of 

particulate matter into the air. The large building ventilation fans would entrain these particles and 

exhaust the particles out the stack. Therefore, concentrations of gaseous wastes such as noble 

gases (41Ar and several xenon/krypton isotopes) and radioiodines were not filtered and were not 

quantified. 

Construction activities for Building 3019 (originally 205) began in March 1943. Primary construction 

included six hot cells: one for dissolution of uranium from the irradiated fuel slugs, four that housed 

equipment for successive chemical treatment of the uranium (precipitation, oxidation, and reduction); 

and one that stored contaminated equipment removed from the other cells. The cell area was within a 

frame structure that also contained the operating gallery and office areas. This facility, known as the 

Pilot Plant, was where various new chemical separations processes were tested [e.g., bismuth 

phosphate, reduction-oxidation (REDOX), Hexone-25, TBP (tributyl phosphate)-25, 

plutonium-uranium extraction (PUREX), fluoride volatility chemical process, and thorium extraction 

(THOREX)]. 

Because of the variety of processes that took place in the building, many different radioisotopes were 

and are still present in the facility. At first, airborne emissions were exhausted through the 200-ft 

stack from Building 3020 (the fanhouse was adjacent in Building 3021). In about May 1962, a deep 

bed glass fiber filter was added, and effluents were then sent to the large Central Exhaust Facility 

stack at Building 3039 (Klima 1962). Arnold, Gesky, and Nichols (1961) provide a description of the 

types of materials expected to be exhausted through the filter. A description of all processes that 

have taken place in Building 3019 is given in Historical and Programmatic Overview of Building 3019

(Brooksbank, Patton, and Krichinsky 1994). This facility conducted much of the research and 

development operations for separations at the site. Several of the processes are described below.

From 1943 until 1945, the Bismuth Phosphate Process took place in Building 3019. The process 

recovered plutonium from the fuel slugs from the Graphite Reactor. The process took place in six hot 

cells. The fuel slugs were transported from the Graphite Reactor through an underground water-filled 

canal. The process included the slugs being dissolved in acid in the initial cell. The remaining cells 

housed the equipment used in precipitating the plutonium from the dissolved fuel slugs and oxidation 
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and reduction of the uranium. This batch process is based on the fact that plutonium will 

co-precipitate with bismuth phosphate in the +4 valence state, but not in the +6 valence state. 

Aluminum cladding was dissolved away from the fuel elements using boiling sodium hydroxide 

solution. The bare uranium was then dissolved in concentrated aqueous nitric acid and plutonium 

was separated and concentrated by many cycles of precipitation and dissolution using bismuth 

phosphate. The bismuth-phosphate process could only extract plutonium; the uranium remained as a 

waste product. Radionuclides of concern include 234U, 235U, 238Pu, 239Pu, and mixed fission products.

The REDOX Process took place in Building 3019 from 1945 until 1951. The REDOX facility was a 

pilot plant for the Argonne National Laboratory REDOX Processing Plant. REDOX was a method of 

extracting uranium and plutonium from reactor fuel using solvents. Radionuclides of concern include 

234U, 235U, 238Pu, 239Pu, and mixed fission products.

PUREX processing took place in building 3019 from 1949 to 1960. The PUREX process involved the 

use of TBP for solvent extraction. The TBP was used in organic and hydrocarbon diluents to isolate 

plutonium, uranium, zirconium, niobium, and ruthenium from fission product wastes. Radionuclides of 

concern include 234U, 235

U, 238Pu, and mixed fission products.

Building 3019 housed the fluoride volatility chemical process. This process used the volatility of 

uranium hexafluoride to separate 235U from molten salt fuels and other fuels that were soluble in 

molten salt. Radionuclides of concern include 234U, 235U, 85Kr, 133Xe, 127Te, 129Te, 131I, 103Ru, 106Ru, 

and 238Pu.

The THOREX process was used in Building 3019 to separate 233U, 232Th, 233Th, and 233Pa from 

irradiated thorium metal and other fission products. During 1956 and 1957 the thorium metal was 

decayed at shorter periods than normal to test the equipment and processes under high radiation 

conditions. In 1959, an explosion in the THOREX pilot plant released 0.6 g of plutonium from a hot 

cell, spreading it onto the street and the graphite reactor. Radionuclides of concern include 238Pu, 

239Pu, 233U, 232Th, 233Th, 85Kr, 95Zr, 95Nb, 103Ru, 106Ru, 131I, 132I (132Te), 133Xe, 140Ba/140La, 141Ce, 144Ce, 

and 233Pa.

Building 3019 also originally housed the Fuel Cycle Alpha Facility (FCAF) in a basement area before it 

was relocated to Building 4508. The FCAF fabricated PuO and (Pu,U)O fuel pellets and was used for 

coating sol gel-derived microspheres with pyrolytic carbon. Special target materials for the High Flux 

Isotope Reactor were also developed and fabricated in this facility. Two additional and unique fuelrod-loading techniques, vibratory compaction and slug injection, were also studied in the FCAF.

Wastes generated from Building 3019 operations flowed to the underground storage tanks in the 

North and South Tank Farm area, facilities 3023 and 3507. At times volatile gases were released 

from the head space of the tanks when liquids were being filled in the tanks. Section 2.3.4 contains 

additional information concerning waste operations. 

A chemical explosion occurred in Building 3019 on November 20, 1959 at approximately 11:00 p.m. in 

the intercycle evaporator in Cell 6. The explosion contaminated the interior of the cell area and blew 

the door to the outside open and contaminated the area immediately outside with significant levels of 

plutonium. The explosion also contaminated the Graphite Reactor and several other buildings, but “it 

was slight and readily cleaned up” (King 1960). The same report indicates that environmental 

contamination was immediately fixed at buildings and grass with paint, with asphalt on the roads, and 

with either paint or tar on the roofs. With the exception of Building 3019, the Graphite Reactor 

Building, and Hillside Road between Third Street and Building 3042, all areas were back in service by 

Monday morning, November 23 (King 1960). A report issued August 25, 1961 (Parrott 1961) 
Effective Date: 11/14/2003 Revision No. 00 Document No. ORAUT-TKBS-0012-2 Page 23 of 66

indicates that decontamination efforts took place over an extended period and that approximately 

141 g of plutonium were flushed from the cell area. The report indicates that though many entries 

were made into the cell area for decontamination efforts, that none of the workers involved were 

overexposed to beta/gamma radiation and that there was “no detectable increase in the body burden 

of plutonium of any individual involved” in the decontamination efforts (Parrot 1961)

Other buildings in the Main Plant Area where radioisotopic separations were conducted using slugs 

irradiated in the Graphite Reactor included 3026C, 3026D, 3505, 3515, and 3517. (Section 2.3.2 

discusses the activities in Buildings 3026C and -D.) The Building 3505 Metal Recovery Facility 

received irradiated fuel slugs from 1952 to 1960 and reprocessed the slugs to produce 320,662 kg of 

uranium, 184 kg of plutonium, 1,344 kg of neptunium, and 55 kg of americium (Alexander et. al. 

1982). Radiological fission products would have been present during the reprocessing of the 

irradiated fuel. A radiological survey conducted in 1981, indicated that the facility had widespread 

residual fission products, 137Cs and 90Sr, and uranic and transuranic radioisotopes present. The 

building was demolished and removed from the site in the 2000 timeframe.

Buildings 3515 (Fission Product Pilot Plant) and 3517 (Fission Product Development Laboratory) were 

used in the further separation of fission products from the waste solutions that came from Building 

3505. Building 3515 operated from 1948 to 1958 and was originally known as the 106Ru tank 

arrangement. It was used to extract radioisotopes of ruthenium, strontium, cesium, cerium, and other 

fission products (ORNL 1994). In 1948, the facility consisted of a concrete pad with tanks surrounded 

by stacks of concrete blocks three rows deep. The pad was once covered by a tent. In 1950 or 1951, 

an 18-in.-thick, walled concrete hot cell with a 2-ft-thick concrete roof was constructed. Numerous 

spills occurred over the years in the building, and the internal structure, particularly the concrete floor, 

was frequently soaked with contaminated waste. The building was posted as a high radiation area. 

Operations in Building 3515 were moved to Building 3517 in 1958. 

The hot cells in Building 3517 processed kilocurie amounts of fission products from REDOX and 

PUREX waste streams. A total of 1 × 106 Ci of fission products were processed until building 

operations ended in 1975. The radioisotopes separated during the late 1950s and early 1960s 

included 144Ce, 137Cs, 90Sr, 147Pm, 106Ru, and 99Tc, but some uranic and transuranic isotopes would 

have been present in the waste as would be other fission products.

2.3.2

During mid-1942, much research was being directed at small-scale studies of various different 

radioisotopes in the Metallurgical Laboratory at the University of Chicago. While most of the 

radiological research was focused on the production of fissionable material for use in weapons 

manufacturing, some was conducted on other radioisotopes (i.e., activation and fission products) to 

determine their potential value to the war effort. While the Graphite Reactor was still being 

conceptualized by its designers, special attention was being given to barium, strontium, and 

lanthanum separation chemistry. It was found that though initially purified 140Ba had little gamma 

activity present, the activity of 140La growing into the purified 140Ba created much interest due to the 

presence of a 1.6-MeV gamma emitted from 140La. Production activities were called the RaLa Project. 

In the fall of 1943, much of the Metallurgical Laboratory moved to ORNL to continue the research on 

fission products. This research was initiated at ORNL in Building 3550 (706-A) and soon (October 21, 

1943) a request to construct a larger production facility was made. Building 3026-C (originally 706-C) 

was designed and constructed with larger containers and equipment during the following year, and 

the new facility was placed in operation with its initial production run beginning on September 10, 

1944. 

Radioactive Lanthanum Activities
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The 3026-C facility was designed to handle 1- to 10-Ci amounts of radioactivity, but due to time 

constraints and unusual circumstances the facility was producing greater-than-100-Ci amounts of 

product upon startup. The 3026-C facility processed irradiated slugs from the Graphite Reactor. In 

addition, nine production runs of RaLa were completed for shipment to Los Alamos, for a total of 

3,852 Ci in the building. (Multiple batches of irradiated slugs were dissolved to make up a completed 

run.) The last run in Building 3026-C was conducted May 28, 1945. During these initial, lower-activity 

production runs, there were many incidents of spills, plugged lines, low chemical yields (requiring 

additional batches of slugs to be dissolved), and failed equipment that affected the completion of runs 

(Thompson 1949).

After the second successful RaLa run in Building 3026-C, discussions were held that indicated the 

need to further increase production rates. Though the use of existing facilities in the Pilot Plant 

(Building 3019) was discussed and evaluated, it was determined that a new facility annexed to the 

current facility would be needed. Building 3026-D (originally 706-D) was designed to process much 

larger (up to 1,000 Ci) amounts of radioactivity and was attached to the east end of the existing 

3026-C facility. As in the construction of Building 3026-C, time constraints caused the design and 

development work for the new facility to coincide with facility construction. The first production run of 

materials occurred on May 26, 1945 as the ninth and final run of RaLa was being completed within 

Building 3026-C. This facility also processed much higher activities than were designed for the 

facility. 

Around 1948 the AEC decided to use irradiated slugs from the Hanford production reactors as feed 

for RaLa. The higher power of the Hanford reactors (relative to the Graphite Reactor) meant much 

larger quantities of RaLa could be produced in a shorter time even after the slugs were shipped 

across the country. A total of 68 RaLa runs had been completed at ORNL when operations ended in 

October of 1956. The RaLa program was subsequently transferred to the Idaho Chemical Processing 

Plant.

Due to the relatively short half-life of the parent 140Ba, the freshly irradiated fuel slugs used in the 

RaLa process still contained relatively large quantities of short-lived fission products, most notably 

noble gases and radioiodines. 

Much of the iodine volatilized during the slug dissolving process was effectively removed from the 

dissolver offgas stream by the reflux condenser and chemical scrubber that were in line before the 

gaseous waste went to the stack. Dissolver offgas from RaLa production was vented to the 3020 

stack from 1944 to 1950 and to the 3039 stack from 1950 to 1956. From 1944 to 1950, other airborne

wastes were withdrawn from the building’s two process cells to a 30-ft stack adjacent to the building, 

until this stream to was routed to the 3039 stack. In the latter part of 1948, it was determined that the 

operations within Building 3026-D were a major contributor of airborne particles on the site. Air filter 

houses were installed to reduce particulate material in the effluent stream before release from the 

building. Liquid wastes from RaLa operations went to the local tank farms. 

Other than operational problems (failed equipment, breached control systems, plugged feed lines) 

that occurred at times during RaLa operations, the worst incident occurred at about 5:00 p.m. on April 

29, 1954. The incident was described as “the most serious accidental release of activity ever 

experienced in the history of the process” (Rupp and Witkowski 1955). The Building 706-D logbooks 

indicate that during Run 56, 161 Hanford slugs had been loaded into the dissolver and 3 successful 

batches had been processed. After the third batch dissolution, the slugs that remained in the 

dissolver tank were not covered with liquid for approximately 28 hr and became thermally hot due to 

radioactive decay. When the fourth batch addition of acid was poured into the dissolver to initiate 

additional dissolution, a violent reaction occurred forcing dissolver solution up the slug-loading chute 
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and solution addition lines. Air monitors in the building immediately sounded an alarm, indicating 

elevated airborne radioactive material. The investigation that followed indicated that individuals in the 

building donned gas masks and evacuated the building soon. The release lasted from between 

10 min to 2 hr before the scrubbers could recover and begin filtering radioiodine from the building. A 

letter written by the Laboratory Shift Superintendent to the ORNL Director indicated that “all people 

involved in the incident and later in the high level decontamination work are being given the standard 

HP check including urine checks, etc.” (Stanley 1954). Radiation levels reached 100 R hr-1 on the 

third floor, but were reduced to 100 mR hr-1 by 7:00 a.m. the next day; air sample results did not 

exceed the tolerance level of 3.0E-08 μCi ml-1. A preliminary check of film badge results was 

indicated as having been conducted, but the reference did not provide confirmation.

Detailed information concerning RaLa operations, source terms, emissions, and offsite radiation 

doses is available in ChemRisk (1999). This document provides much of the historical process 

information, as well as modeled concentrations of iodine to conduct offsite dose assessments. 

2.3.3

Following the small-scale production of plutonium from the Graphite Reactor and large quantity 

production of RaLa in Buildings 3026-C and –D, other site facilities were constructed to produce 

various other radioisotopes. Table 2-5 provides a list of the facilities involved in the ORNL isotope 

production program, including radioisotopes that would have been present. Note that Building 3026-C 

was the initial facility for commercial isotope production at ORNL (ORNL 1997b). The majority of all 

the other isotope production facilities were built in the early 1950s. While some of the facilities have 

not produced any product material since the 1960s, some are still used for storage. The following 

paragraphs provide additional information for several of the isotope production buildings. 

Isotope Production Areas

Table 2-5. Radioisotopes of concern in isotope production facilities. 

Building name

Building 

number Isotopes formerly stored, used, or produced

Krypton-85 Enrichment Facility 3026-C 129I, 131I, 79Se, 107Pd, 147Pm, 137Cs, 90Sr, actinides, 

85Kr, U, 99Tc, 60Co, Pu, 3

H

Alpha Powder Facility 3028 131I, 133Xe, 242/244Cm, 147Pm, 99Mo, 238Pu

Source Development Laboratory 3029 192Ir, 60Co, 137Cs, 90Sr, 131I, CH3

131I, 14C, 99Tc

Radioisotope Production Laboratory–C 3030 56/57Co, 198Au, 55Fe, 234Np, 75Se, 90Sr nitrate, 

110Sn, 237U, 33P, 192Ir, 63Ni

Radioisotope Production Laboratory–D 3031 90Y, 153Gd

Radioisotope Production Laboratory–E 3032 241Am, 235U, 233Pu, 152,154Eu, 153Gd, 56Co, 57Co, 

198Au, 55Fe, 234Np, 75Se, 90Sr, 137Cs, 111Sn, 237U, 

33P, 192Ir, 244Cm, 131Xe, 131I, 99Mo, and 147Pm

Radioactive Gas Processing Facility 3033 3H, 85Kr, 14C

Radioactive Production Laboratory Annex 3033-A 14C, 241Am, 237Np, 238Pu, highly enriched actinide 

isotopes

Radioisotopes Area Services 3034 Not established - former field shop for Plant and 

Equipment Division support

Alpha Handling Facility 3038-AHF 252Cf, 244Cm, 241Am, 238Pu, 234U, 237Np, 231Pa, and 

others

Isotope Materials Laboratory 3038-E Transuranics, 90Y, 235U, 147Pm, 90Sr, 244Cm, 241Am

Radioisotope Packaging and Shipping 

Facility

3038-M 129I, 137Cs, 60Co, 90Sr, 99Tc, 89Mn, 106Ru, 36Cl

Isotope Technology Building 3047 14C, 152,154Eu, 60Co, 153Gd, 241Am, 242/243Cm

Storage Cubicle 3093 85Kr

Storage Pad 3099 N/A

Radioisotope Production Laboratory–H 3118 not established
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Table 2-5. (Continued). 

Building name

Building 

number Isotopes formerly stored, used, or produced

Fission Products Development Laboratory 3517 90Sr, 137Cs, 144Ce, 147Pm, 106Ru, 99Tc, 60Co, 192Ir, 

235U, 152,154Eu, 241Am

Tritium Target Preparation Facility 7025 3H, ThO2, UO2, 90Sr, 137Cs, 244Cm

Building 3028, also referred to as the Alpha Powder Facility, was constructed in 1950 and originally 

housed the 131I processing facility and the separation facility for 147Pm. The 131I facility was converted 

to manipulator cells and expanded to the Short-Lived Fission Product Facility in the early 1960s, 

which operated until 1985. The 133Xe facility was added at that time and operated until 1980. 

Isotopes made for sale included 133Xe, 131I, and 99Mo. Curium source fabrication began in 1964 to 

support Space Nuclear Systems. The process took place on the first floor of the building in 

water-shielded cells. The cells were partially decontaminated in the mid 1980s and the facility was 

redesignated as the Alpha Powder Facility to support full-cost-recovery isotopes program. In the late 

1970s the target facility was moved to Building 3038 and the upper floors were occupied by Nuclear 

Medicine Research until 1988. 

Building 3029 was constructed in 1952 to support the Isotopes Program. A small manipulator cell 

(now called Cell 4) and a system of remotely operated barricades were used to support source 

fabrication of 192Ir. There were also some small 60Co sources fabricated in the facility. In 1955 and 

1956 an additional cell (Cell 1) was built to handle large amounts of 60Co for source fabrication. The 

amount of 60Co sources fabricated in the facility diminished in the late 1950s. Between 1960 and 

1962, Cell 3 was built for 137Cs source fabrication. Cell 2 is located between Cells 1 and 3 and was 

used to handle waste and served as a pass-through between the two cells. The exact dates of 

operation of this facility are not known, but the program ended in the late 1980s. 

Building 3030 was constructed for production and development of radioisotopes for industry, 

medicine, and research. The building contained a hot cell for processing irradiated cyclotron and 

reactor targets to produce, purify, and separate numerous radioisotopes such as 56Co, 57Co, 198Au, 

55Fe, 234Np, 75Se, 90Sr, 111Sn, 237U, 33P, and 192Ir. There is also 63Ni and 103Pd contamination in the 

facility. The exact dates of operation of this facility are not known. The program it supported began in 

the late 1940s and ended in the late 1980s.

Building 3032 was constructed to house the analytical facility for radiochemical support of the 

Isotopes Production activities. The facility has a laboratory with five hoods on the north side of the 

building and an office on the south side connected by an open passageway. The exact dates of 

operation of this facility are not known. The program it supported began in the late 1940s and ended 

in the late 1980s.

Building 3033 was used for processing 14C, 85Kr, and 3

H. Processing of 14C ended in 1975. 

Radioactive gas processing of tritium and krypton took place in Building 3033. Bulk tritium shipments 

from the Savannah River Site were received, purified, loaded into canisters, and shipped. Krypton 

from Idaho was received and purified for sale to private industries or used as feed to the thermal 

diffusion columns in Building 3026-C. The exact dates of operation of this facility are not known. The 

program it supported began in the late 1940s. The processing of 3

H ended in 1990. The last 85Kr was 

produced in September 1989.

Building 3038 was used for packaging, inspection, and shipping activities for radioisotopes from 1949 

until 1990. The building contained five hot cells shielded by water-filled steel tanks. The operating 

face of each cell consisted of 3 ft of shielding, a viewing window, and manipulator ports. Each cell 
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was 10 ft deep. From 1968 until 1990 part of the facility was used for the fabrication of targets and 

was referred to as the Alpha Handling Facility.

Section 2.3.6.9 discusses the High Flux Isotope Reactor, which is currently in operation for isotope 

production.

2.3.4

Due to the varied history and growth of operations at ORNL, several waste disposition areas have

been used. Early sites were on or near the ORNL Main Plant Area to accept both solid and liquid 

production wastes. In later years the disposal areas were moved south of the Main Plant Area 

(across Haw Ridge) into Melton Valley. The following paragraphs provide a short description of the 

areas and amounts of radioactive materials that are present, if available.

Waste Areas and Processes

The original design of the ORNL site was to operate for a short time to develop processes for use at 

other DOE facilities. Because of this short-term design, much of the wastes were expected to be 

maintained in consolidation areas on the site. The North and South Tank Farms were put in place to 

temporarily store liquid wastes. Processing included treatment and precipitation of solids and draining 

off of the supernatant. The waste was then sent to the waste holding basin and then to White Oak 

Creek. These holding areas were able to treat the liquids and precipitate much of the radioactivity out 

of solution offsite release. However, the sediments in White Oak Creek and Lake do contain 

radioactive materials that settled from the process liquids. 

The North Tank Farm (Facility 3023) was constructed in 1943. It included four large concrete (gunite) 

underground tanks to store liquid chemical and radioactive wastes, identified as W-1, W-2, W-3, and 

W-4. In 1950 an additional four underground stainless-steel tanks were constructed in the same 

general area (W-1A, W13, W-14, and W-15). An extensive underground piping system transported 

the liquid waste from Buildings 3019 and 3026 to the tanks. 

The South Tank Farm (Facility 3023) is a series of six 170,000-gal underground gunite storage tanks 

placed into service in 1943. The South Tank Farm was part of the liquid low-level waste collection 

system used for the collection, neutralization, storage, and transfer of the aqueous radiological and 

chemical wastes generated at the ORNL.

The Waste Holding Basin (Facility 3513) was constructed in 1944 by scooping out a depression in the 

native clay and constructing earthen berms to contain the liquids. The unlined disposal area had 

dimensions of 220 by 220 ft and was 6.5 ft deep. Supernatant wastes from the South Tank Farm 

were piped to the northern end of the basin. Later, water from the process waste treatment plant that 

had been treated with fly ash and lime was discharged to the Building 3513 holding basin before 

discharge to White Oak Creek. The Waste Holding Basin was removed from service in 1976, but still 

contains water and contaminated sediments.

The contaminants maintained in the three areas discussed above consisted of soluble and insoluble 

radioisotopes that flowed from the chemical separations areas. Often, the liquid wastes were treated 

with caustic material to increase the pH of the liquid and prompt much of the radioactive material to 

settle out. Once treated, the liquid waste could be transferred elsewhere to make room for additional 

waste transfers into the holding basin. Initially, the treated waste liquid was pumped into White Oak 

Creek. Later, liquid wastes were transported by truck to Melton Valley where they were poured 

directly into pits and trenches, where the liquid evaporated and chemically combined with the soil. 

The Old Hydrofracture Facility (Building 7852, described in Section 2.2.47) was constructed to 
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dispose of low-level liquid radioactive wastes deep in the geological faults separate from sources of 

drinking water. 

Several additional underground storage tanks exist in the main ORNL plant area (thorium tanks, area 

4500 tanks, and several additional tanks near the South Tank Farm).

Solid wastes were originally placed in disposal areas on or very near the main plant site (SWSAs 1, 2, 

and 3). Later, solid wastes were transported to Melton Valley where other landfills were operated. 

The following paragraphs describe SWSAs 1 to 6.

Solid Waste Storage Area (SWSA) 1 is a 1.5-acre site on the north side and at the foot of Haw Ridge 

and immediately southeast of White Oak Creek in Bethel Valley at the ORNL site. Solid waste was 

buried in this area in trenches south of Incinerator Road beginning in April 1944. Additional solid 

waste was added in 1944, but the site was abandoned later in the year due to water accumulating in 

the trenches. The area contains only a small amount of solid radioactive waste because fissionable 

material was being maintained at the site. At the time of waste generation, site operations did not 

include isotope separation and concentration of the waste. Analyses from groundwater wells show 

low concentrations of 90Sr, but no indication of 137Cs or transuranic elements.

SWSA 2 is approximately 3.6 acres in size and is north of the East Vehicle Gate, on the lower half of 

the hill adjacent to the main parking lot. The site is neither fenced nor marked to readily identify its 

location. The site was used from 1944 until 1946 for the disposal of waste. Beta/gamma 

contaminated solid waste was placed in black drums and buried in trenches. Liquid waste 

contaminated with plutonium was placed in stainless-steel drums and either buried in trenches or 

stored above ground in a ravine. Following the closure of SWSA 2, both the stainless-steel and black 

drums were removed, transferred, and reburied in SWSA 3. Following the drum removal, the hillside 

of SWSA 2 was bulldozed, backfilled and contoured, and seeded sometime between 1946 and 1949. 

Analyses of core samples taken from there indicated no contamination. Analyses included uranium, 

plutonium, and 137Cs. Groundwater samples taken at SWSA 2 also showed no detectable

contamination. Groundwater analyses included tritium, gross alpha, and gross beta.

SWSA 3 is about 7 acres in size and about 0.5 mi west of SWSA 1 and about 0.6 mi west of the west 

entrance of ORNL. The disposal facility was opened in 1946 and received contaminated trash, 

laboratory equipment, and other materials. The drums that were removed from SWSA 2 were placed 

in this burial area. Alpha-contaminated waste was placed in drums and disposed in concrete-lined 

trenches on the northeast end of the burial ground. Later, as the burial ground was extended to the 

west, the drums were placed directly in unlined trenches and covered with concrete. 

Beta/gamma-contaminated wastes were buried in separate unlined trenches and backfilled with soil. 

Some large equipment contaminated with low levels of radioactivity was stored above ground until 

1979 when they were removed. Some of those items were relocated to an area between SWSA 4 

and the Chemical Waste Pits, while other items were transferred to SWSA 5 or 6 and buried. SWSA 

3 was closed in 1951. Groundwater samples indicate small amounts of trivalent rare earth, 90Sr, 89Sr, 

and 3

H contamination.

SWSA 4, which is approximately 23 acres, received waste from 1951 until 1959. The disposal area is 

in Melton Valley on the south side of and at the foot of Haw Ridge, immediately west of White Oak 

Creek. Records about the waste disposed in SWSA 4 before 1957 are incomplete due to a fire. 

ORNL generated about 50% of the waste buried in SWSA 4 during 1957 and 1958; the remainder 

came from over 50 other agencies. Argonne National Laboratory, Knolls Atomic Laboratory, Mound 

Laboratory, and the General Electric Company (Evendale, Ohio) were some of the principal 

generators of waste disposed in SWSA 4. Surface- and groundwater samples taken from the area 
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indicate the presence of radioactive contamination. One well sample indicated alpha contamination 

while another 8 of the 16 well samples indicated beta/gamma contamination. Radioactive 

contaminants in SWSA 4 include 90Sr, 106Ru, 137Cs, 60Co, 210Po, 239Pu, 3

H, 125Sb, and trivalent rare 

earths.

SWSA 5 is in Melton Valley, north of Melton Branch and east of the area where White Oak Creek and 

Melton Branch merge. The waste area is 33 acres and was opened in 1958 after burial space in 

SWSA 4 became limited. Low-level radioactive waste is stored in trenches in the larger southern 

section of the disposal area and transuranic waste is stored in trenches in the SWSA 5 North area in 

the northwest corner. Disposal of waste in SWSA 5 ended in 1975. Water seepage problems have 

caused the trenches to fill with water because the trenches were excavated with the long portions 

extending in a downslope manner parallel to the hydraulic gradient of the water table. In 1975, two 

underground dams were installed across two parallel trenches to reduce the water seepage in the 

south end of the area. A plastic membrane was installed to cap the southern area where the dams 

were installed and grass was planted to inhibit erosion. A bentonite-shale mixture was added to seal 

the northern part of the disposal area in over 14 trenches in the transuranic waste area. Water 

sample analyses indicate the presence of 244Cm, 238Pu, 90Sr, 3

H, 125Sb, 106Ru, 137Cs, 60Co, and trivalent 

rare earths.

SWSA 6 opened in 1969 and is still operational, receiving low-activity solid radioactive waste and 235U 

for storage. The 68-acre disposal area is in Melton Valley, north of White Oak Lake, southeast of 

Lagoon road and Haw Ridge, and immediately east of Highway 95. Beta/gamma and transuranic 

radioactive waste is buried in trenches and auger holes at the site. 

The Central Exhaust Facility (Building 3039) is the major exhaust stack in the main plant area. The 

3039 Stack Ventilation System off-gas and cell-ventilation facilities include various cell-ventilation, offgas scrubber, and waste systems. Because of the diversity of the activities carried out in the buildings 

that the system serves, any gaseous waste stream can contain transuranic or fission product 

radioisotopes. Building operators, as the waste generators, are responsible for keeping the amounts 

of radionuclides in the gaseous waste streams that discharge into the 3039 Stack Ventilation System 

to levels that limit risk to the health and safety of the public and employees. This is accomplished 

through a combination of administrative controls, input controls, application of health physics 

procedures, and treatment (usually by HEPA filters) of the gaseous waste stream before discharge 

into the 3039 Stack Ventilation System. 

2.3.5

Due to a moratorium on construction activities immediately after the war, insufficient space at the 

ORNL site caused the Biological Sciences division to move to building space at the Y-12 National 

Nuclear Security Complex. The building complex included Buildings 9207, 9208, 9210, 9211, 9220, 

9224, 9743, 9767-3, 9767-5, and 9982. This list of facilities does not include several cooling towers. 

The Biological Sciences division was tasked with conducting animal research, typically using 

low-strength radiological sources for carcinogenic research, determination of the relative biological 

effectiveness of differing radiation types and source strengths, and dosimetry in space flight. Many of 

the studies were conducted in Building 9210, known as The Mouse House. 

ORNL Facilities at the Y-12 National Nuclear Security Complex

Discussions with the current Radiological Control Officer for the Life Sciences Division (Biological 

Sciences later became the Life Sciences division) indicated that the type of radiological studies 

conducted in the building complex used sealed radioactive sources for direct radiological exposures. 

The sources were sealed sources that consisted of welded metal capsules. The greatest potential 

hazard was a direct exposure to an unshielded capsule. This is unlikely to have presented a 
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contamination hazard except in the event of a broken capsule weld. No information was available that 

indicated that this type accident ever occurred in these facilities. The source rooms had lead-lined 

walls and doors at all locations where there was any potential for personnel or public exposure. 

Procedures and safety interlocking devices were in place to minimize the potential for personnel to be 

exposed. 

The sources are no longer present in any of the Y-12 Biological Sciences facilities. Table 2-6 depicts 

the radiation sources used by the Biological Sciences Division at Y-12 over the last few decades. 

Table 2-6. Radiation sources in Biology Division at Y-12. 

Building Room

Radioactive 

source

Quantity 

(curies)

Dose rate (at 1 m, 

unshielded) 

(rad hr-1)

Type of 

radiation Main irradiation use

9207 403A 137Cs 137Cs1300

65

430

21.5

Gamma Mice, rats

Mice, rats

9207 4040 137Cs 0.83 0.3 Gamma Mice, rats

9210 341 137Cs 2.5 0.8 Gamma Mice

9779-2 137Cs 80 26.5 Gamma Mice

9207 127 60Co 3.75 5 Gamma Insects, mammalian tissue

9983-17 Trailer 252Cf 3.91 0.8 Neutrons and 

gamma

Mice, rats, mammalian tissue

In addition, two other programs from ORNL were moved to the Y-12 site. The Stable Isotopes 

Program emerged at the end of the war when site staff stopped using calutrons to separate uranium 

isotopes for atomic weapons. Researchers at first used four calutrons salvaged from electromagnetic 

equipment. Copper isotopes were the first to be collected, followed by isotopes of iron, platinum, 

lithium, and mercury. These were separated and shipped to universities, governments, and national 

laboratories. In 1958, the building containing two beta calutron tracks (Building 9204-3, Tracks 5 and 

6) became available and was assigned to the Stable Isotopes Program. One track of calutrons was 

modified with heavy iron yokes so that individual sections could be operated to separate isotopes of 

different elements. As of 1963, the ORNL electromagnetic isotope separations program was 

providing more than 250 high-purity, highly enriched isotopes for use in a wide variety of research and 

technical applications. During 1963, more than 17,000 g of separated material were collected from 28 

of the calutrons allocated for the Stable Isotope Program. As of late 1985, the Stable Isotope 

Program of ORNL, at Y-12, made over 229 isotopes available by direct sale or on a loan basis. At 

one time, the Stable Isotopes Program was the largest DOE involvement with commercial markets. 

Stable isotopes were used in preparing the specialty isotopes used in medical research, as tracers, 

and in a number of physics applications. Every year, the ORNL program produced and sold millions 

of dollars worth of these materials. Calutrons were last used for stable isotope production at Y-12 in 

1990.

In the 1951, the ORNL Engineering Technology Division was split into two divisions, the Aircraft 

Nuclear Propulsion (ANP) and Reactor Experimental Engineering Divisions. Later that same year the 

two divisions were moved to Y-12 (ANP to Building 9201-3 and the Reactor Experimental Engineering 

Division to 9204-1). There is little indication from the material that this division used substantial 

amounts of radioactive materials. 

The ORNL Critical Experiments Facility (CEF), also at Y-12, is discussed in Section 2.3.6.2.
Effective Date: 11/14/2003 Revision No. 00 Document No. ORAUT-TKBS-0012-2 Page 31 of 66

2.3.6

In addition to the Graphite Reactor operations described in Section 2.3.1, there have been numerous 

facilities at ORNL that were built to test reactor designs, train individuals, or to test criticality 

configurations. The facilities discussed in this section include:

Other Reactor Development and Operations

• Low-Intensity Test Reactor (LITR)

• Critical Experiments Facility (CEF)

• Bulk Shield Reactor (BSR)/ Pool Critical Assembly (PCA)

• ORNL Research Reactor (ORR)

• Tower Shielding Facility (TSF)

• Health Physics Research Reactor (HPRR)

• Homogeneous Reactor Experiment (HRE)

• Aircraft Nuclear Propulsion Experiment (ANP)

• High Flux Isotope Reactor (HFIR)

• Molten Salt Reactor Experiment (MSRE)

In addition to routine, elevated external exposures present adjacent to these facilities, each facility 

was known to have had incidents that provided for increased external and internal exposures. The 

following sections provide information related to the operation of these facilities.

2.3.6.1 Low-Intensity Test Reactor 

The LITR (Building 3005) was originally built as a mock up of the Materials Test Reactor (MTR) in 

Idaho. It was a pool-type reactor with beryllium reflectors positioned on each side and water used as 

reflector on the top and bottom of the reactor. Reactor specifications indicate that there could be up 

to 25 fuel elements in a slab arrangement, but at times 25 fuel elements were not in place (Cox 

1960b). (This reactor was sometimes described as a box-type reactor.) Minimum shielding around 

the reactor was 10 ft, 7 in. of unmortared concrete block with maximum measured exposure rates 

outside the shields of 6 mR hr-1. Maximum radiation leakage around the beam plugs reached 1 R hr-1

(Rupp and Cox 1955). During original operational testing of the reactor, it was noted that the core 

region of the original reactor was close enough to the final design of the reactor being built in Idaho 

that it could be brought up to criticality and operated. The LITR was used for testing and the checkout 

of instruments and controls of the MTR. It was also used as a training facility for the operators of the 

MTR. The LITR controls were co-located within the Graphite Reactor Building. Later, it was decided 

by ORNL and AEC to modify and operate the reactor for experimental and training purposes. It 

operated at a power level of 3 MW. 

The reactor operated from 1951 until October 1968. Experiments that took place at LITR were 

allowed to be approved by one individual and no written procedures were followed during the 

experiments (Stapleton 1993). A series of documents (Cox 1960b) described several minor incidents 

that caused elevated external exposure rates as well as contamination in the pool waters and airborne 

contamination within the facility. The cotton cord filters used in the bypass filters had approximately a 

6-week operational life and were required to be changed before disintegration. After eight years of 

satisfactory use, sintered stainless-steel filters replaced the cotton filters. These filters failed after 

about one year, possibly from the dissolution of nickel in the filters. In addition, high-exposure 

conditions were encountered when experimental beam ports were vacuumed to minimize the spread 

of contamination when taking experiments from the beam ports. Radioactive particles were removed 

when vacuuming that caused exposure rates to exceed 10 R hr-1 at 4 in. Some contamination was 

dropped on blotter paper and on the floor, with exposure rates of 10 and 4 R hr-1, respectively. The 
Effective Date: 11/14/2003 Revision No. 00 Document No. ORAUT-TKBS-0012-2 Page 32 of 66

demineralizers used to filter radioisotopes out of solution would become sources of direct radiation 

exposure. Concentrations of 239Np were detected in the pool waters in 1954 (Rupp and Cox 1955).

2.3.6.2 Critical Experiments Facility

The CEF is at a remote site in the southwest portion of the Y-12 Main Plant Site in a pocket formed by 

the surrounding hills (Stapleton 1993). It began critical and near-critical experiments in August 1950 

in support of upcoming reactor designs (e.g., ANP, liquid fuels, TSR (Tower Shielding Reactor)-II, and 

HFIR). The facility has three assembly areas and a control room and was designed with several 

safety features (water-filled windows and an intercom system) to minimize occupational exposures to 

personnel. The facility operated until March 1987, and shutdown permanently in 1992. Four incidents 

occurred: 

• A polonium-beryllium neutron source, containing nearly 7 Ci of polonium and 0.4 g of 

beryllium, was accidentally opened in a CEF assembly area. This caused widespread 

dispersal of the polonium throughout one of the assembly areas and resulted in internal and 

external contamination of an employee.

• On May 26, 1954, in an experiment with a uranium solution in a vertical cylinder, a poison 

cylinder, placed in the center of the larger cylinder to absorb neutrons, accidentally became 

tilted from its proper vertical position, resulting in 2.1% excess reactivity. Approximately 

1 × 1017 fissions occurred. Automatic safety systems functioned and the reaction was 

terminated. The incident occurred inside an area shielded by 5 ft or more of concrete. 

Personnel exposures indicated on film badges ranged from 0.08 to 0.9 rem, with an average of 

about 0.3 rem.

• On February 2, 1956, in an experiment with a uranium solution in a vertical cylinder, there was 

an unintentional over-addition of solution. The safety system actuated, and waves caused in 

the solution by a falling cadmium sheet formed a prompt-critical configuration. About 

1.6 x 1017 fissions occurred. The incident occurred in the shielded CEF facility designed for 

such tests under remote operation. A considerable volume of solution was ejected from the 

cylinder. Personnel exposure indicated on film badges ranged from 0.14 to 0.575 rem.

• On November 10,1961, a criticality incident occurred when enriched uranium metal that was 

paraffin-reflected was being assembled. Two pieces of metal were brought together too 

quickly, which caused an excursion that yielded 1 x 1015 to 1 x 1016 fissions. There was 

reportedly no exposure to personnel in the building, and no dispersal of radioactive material 

beyond the assembly area where the incident occurred.

2.3.6.3 Bulk Shielding Reactor/Pool Critical Assembly

The BSR (Building 3010) was a pool type reactor, originally designed to operate at a power level of 

10 kW for the purposes of conducting radiation shielding experiments (Stapleton 1993). It served as a 

model for many university, industry, and government pool reactors. It began operating in 1951 for 

conducting shielding experiments, but in 1963 it was made available to the site as a general research 

reactor due to the shutdown of the Graphite Reactor. The BSR shutdown in March 1987. (The 

reactor was permanently shutdown September 10, 1991.) Modifications to the reactor allowed it to 

run at a thermal power level of 2 MW when it was designated as a general research reactor. Reactor 

fuel was aluminum-clad uranium-aluminum alloy fuel and appears to have been highly enriched 

similar to that used in the MTR.
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The PCA is in the northwest corner of the same pool as the BSR (Stapleton 1993). It was designed 

as a low-power reactor (up to 10 kW) to supplement experiments that took place at several other site 

reactors. The reactor controls were similar to those for the BSR. PCA was used to train nuclear 

engineering students from around the country. It was shut down in 1987 and has not operated since.

2.3.6.4 ORNL Research Reactor

Construction of the ORR (Building 3042) was completed near the end of 1957 and criticality was 

attained in March 1958 (Stapleton 1993). The reactor was a light-water moderated and cooled, 

beryllium- and water-reflected research reactor using highly enriched uranium-aluminum alloy plate 

fuel. It was located at one end of the pool. Though it initially operated at 20 MW, during mid-1960 

power levels up to 30 MW were reached. The reactor was designed to produce high neutron fluxes 

for basic research in the fields of physics and chemistry and to test materials and potential fuels for 

power-producing reactors. When operational, the ORR produced greater quantities of radioisotopes 

for research, medical, and industrial use than any reactor in the world. It also contained the most 

advanced safety devices, including filters and scrubbers to minimize airborne releases. A document 

written by Cox (Cox 1961) indicates several releases from 1959 to 1961.

Building 3042 housed several facilities used for experiments over the years. These experiments 

included the following: 

• The Gas Cooled Reactor (GCR) A9-B9 experiment from 1960 to 1969 to measure 

fission-product gases from ceramic fuels

• A molten salt test loop from 1959 to 1967 for the analysis of homogenous fuels

• The maritime ship reactor test loop from 1959 to 1962 for testing structural materials and fuel 

pins for nuclear merchant ship applications

• A pneumatic tube irradiation facility from 1968 until 1973 used to transfer irradiated samples 

from the ORR to a laboratory in Building 3001

• The GCR test loop from 1960 until 1967 to test new fuels for gas-cooled reactors

• The GCR Loop I from 1962 to 1963 for irradiation of unclad graphite fuel to study fission 

product releases.

2.3.6.5 Tower Shielding Facility

The TSF (7700 area) was built in 1954 to support the ANP Project. Four 315-ft towers erected on a 

200- by 100-ft rectangle were used to raise an operating reactor out of a shielded position and 

suspend it from the towers (Holland 1970). The design of the towers was such that various different 

shielding configurations could be tested. The TSF is on a knoll approximately 2.4 mi south-southeast 

of the ORNL main plant area. The facility allowed radiological measurements to be made free of 

radiation scattering from the ground or enclosed structures. Four different reactor designs have been 

employed at the TSF. The original, Tower Shielding Reactor I (TSR-I), was a box-shaped, 500-kW 

MTR-type reactor. It was replaced in 1960 with a spherically symmetric reactor (TSR-II) that operated 

at power levels up to 100 kW. For a period during 1958, the Aircraft Shield Test Reactor was used for 

shielding research for an operating aircraft. It operated at a power level of 1 MW. The fourth reactor, 

the TSF-SNAP (Systems for Nuclear Auxiliary Power) reactor, was used at the facility at a power level 
Effective Date: 11/14/2003 Revision No. 00 Document No. ORAUT-TKBS-0012-2 Page 34 of 66

of 10 kW. The TSF-SNAP reactor was removed from the site in 1973. Since 1975, the TSR-II has 

been inside a ground-based concrete shield (Big Beam Shield) (Stapleton 1993).

Safety control procedures are in place to ensure that personnel do not receive elevated exposures. A 

fence surrounds the reactor at a distance of 600 feet. Warning horns sound three minutes before the 

reactor is brought out of the shielded location. In addition, safety interlocks are in place that 

automatically shut the reactor down if a door or gate is opened while the reactor is out in the open 

(Stapleton 1993). There have been no known incidents at TSF. It is expected that external 

exposures to both neutron and gamma radiations would have been present.

2.3.6.6 Health Physics Research Reactor

The HPRR (also known as the Fast Burst Reactor) was a small, unshielded, unmoderated, fast 

reactor designed at ORNL and constructed under the Laboratory’s supervision. Following initial tests 

at the CEF in 1961, the HPRR was loaned to Operation Bare Reactor Experiment Nevada at the 

Nevada Test Site where it was used to simulate nuclear weapon effects. The reactor was returned to 

ORNL in 1963 and was operated at the Dosimetry Applications Research (DOSAR) facility (Building 

7709). When not in use, the reactor was stored in a steel and concrete vault below floor level. All the 

ancillary buildings were behind a hill and approximately 900 feetfrom the reactor building. There were 

no occurrences in which the safety of personnel was compromised or in which any failure seriously 

affected the equipment (Stapleton 1993).

2.3.6.7 Homogeneous Reactor Experiment

Building 7500 was constructed to conduct testing of homogeneous (fluidized fuel) reactors. The 

building initially contained the first experiment (HRE-1). A second reactor (HRE-2) took its place in 

1953. The HRE-1 was an aqueous, homogeneous fuel reactor. Its purpose was to prove the theory 

that a homogeneous reactor could generate electricity. The initial test run was completed in October 

1952 and the designed power level of 1 MW was achieved on February 24, 1953. Many experiments 

were performed with the HRE-1 before its shutdown and dismantling in 1954. 

The HRE-2 replaced the HRE-1 in Building 7500. It was constructed between 1953 and 1956. 

HRE-2, or sometimes referred to as the Homogeneous Reactor Test, consisted of a homogeneous 

reactor that could produce electricity as well as act as a breeder reactor, irradiating 232Th source 

material to create 233U for use as reactor fuel. The HRE-2 reactor consisted of the core and the 

thorium blanket. The reactor reached criticality in 1957 and operated at normal full power of 5 MW. 

After 16,295 MW-hr of operation, the reactor was shut down in 1961 due to a hole that developed in 

the core tank, which allowed mixing of the fuel and blanket regions.

2.3.6.8 Aircraft Nuclear Propulsion Experiment

The ANP Experiment took place in an area of Melton Valley approximately 0.75 mi from the main 

ORNL site from October 30 until November 12, 1949. The reactor operated a total of 221 hr at a 

maximum power output of 2.5 MW. The reactor fuel was a mixture of fluorides of sodium and 

zirconium that flowed in a closed loop from a pump to the reactor to a heat exchanger and back to the 

pump. The active core area was a cylinder approximately 3 ft in diameter and 3 ft high. Beryllium 

oxide blocks were used to both moderate and reflect the neutron flux. Liquid sodium was pumped 

through the bottom of the reactor shell for cooling. Radioactive releases were indicated as being 

minimal with practically all gaseous fission products and probably some of the other volatile fission 

products removed from the circulating fuel (ORNL 1955). Off-gas treatment was provided by 

nitrogen-cooled, charcoal tanks used to holdup the gaseous wastes. Waste gas was subsequently 
Effective Date: 11/14/2003 Revision No. 00 Document No. ORAUT-TKBS-0012-2 Page 35 of 66

released via the effluent stack when the wind speed was greater than 5 mph and when the 

concentration was less than 0.8 μCi ml-1. 

2.3.6.9 High Flux Isotope Reactor

The HFIR is a beryllium-reflected, light-water-cooled and moderated, flux trap reactor that uses highly 

enriched 235U as fuel (Stapleton 1993). It began low power testing in August 1965 and was completed 

in January 1966. The design power output of 100 MW was attained in September 1966. 

Radioisotopes produced in the HFIR include transuranics (most notably 252Cf), 192Ir, and 60Co. 

The Radiochemical Engineering Development Center operates in conjunction with the HFIR, and 

includes the Transuranic Facility (Building 7920) and the Thorium-Uranium Recycle Facility (Building 

7930). 

2.3.6.10 Molten Salt Reactor Experiment

The MSRE (the Building 7503 complex) was an 8-MW reactor operated from 1965 through 1969 to 

investigate the possibility of using molten salt reactor technology for commercial power applications. 

The reactor used a fluoride salt mixture of lithium, beryllium, and zirconium fluorides with uranium 

tetrafluoride as the fuel components. The reactor was initially fueled with 235U and later replaced with 

233U in 1968. In 1969, the reactor also contained less than 1 kg of plutonium trifluoride. A plan written 

in 1998 indicated the presence of 28,200 Ci of fission and activation products, 21.7 g of 233U, 915 g of 

235U, and 709 g of 239Pu in drain tanks and the fuel flush tank (ORNL 1998). Greater than 99% of the 

activity in salt is from 90Sr/Y and 137Cs. Radionuclides of concern for the MSRE include 232Th, 233U, 

90Sr, 90Y, 137Cs, 137mBa, 151Sm, 147Pm, 155Eu, 154Eu, 99Tc, 125Sb, and 93Zr. 
Effective Date: 11/14/2003 Revision No. 00 Document No. ORAUT-TKBS-0012-2 Page 36 of 66

REFERENCES

Alexander, W. A., S. Huang, T. W. Oakes, H. M. Hubbard, and J. S. Eldridge, 1962, Radionuclide 

Characterization of Subsurface Soil on the Site of Building 3505 at Oak Ridge National 

Laboratory, ORNL/TM-8479, Oak Ridge National Laboratory, Oak Ridge, Tennessee.

Arnold, E. D., A. T. Gresky, and J. P. Nichols, 1961, The Evaluation of Radioactive Releases from 

Chemical Plants, ORNL-TM-19, Oak Ridge National Laboratory, Oak Ridge, Tennessee.

Brooksbank Sr., R. E., B. D. Patton, and A. M. Krichinsky, 1994, Historical and Programmatic 

Overview of Building 3019, ORNL/TM-12720, Oak Ridge National Laboratory, Oak Ridge, 

Tennessee.

ChemRisk, 1999, Iodine-131 Releases From Radioactive Lanthanum Processing at the X-10 Site in 

Oak Ridge, Tennessee (1945-1956), An Assessment of Quantities Released, Off-Site 

Radiation Doses, and Potential Excess Risks of Thyroid Cancer, Reports of the Oak Ridge 

Dose Reconstruction, Volume 1, Alameda, California. 

Cox, J. A., 1958, “Information for Review of Graphite Reactor Operation,” intra-laboratory 

correspondence, December 3, Oak Ridge National Laboratory, Oak Ridge, Tennessee.

Cox, J. A., 1959, “Information for Review of Graphite Reactor Operation,” intra-laboratory 

correspondence, November 6, Oak Ridge National Laboratory, Oak Ridge, Tennessee.

Cox, J. A., 1960a, “Information for Review of Graphite Reactor Operation,” intra-laboratory 

correspondence, November 3, Oak Ridge National Laboratory, Oak Ridge, Tennessee.

Cox, J. A., 1960b, “Information for Review of LITR Operation,” intra-laboratory correspondence written 

for years 1958 through 1960, Oak Ridge National Laboratory, Oak Ridge, Tennessee.

Cox, J. A., 1961, “Information for Review of ORR Operation,” intra-laboratory correspondence written 

for years 1959 through 1961, Oak Ridge National Laboratory, Oak Ridge, Tennessee.

Holland, L. B., 1970, Tower Shielding Reactor II, Design and Operation Report: Vol. 1 – Description, 

ORNL-TM-2893, Oak Ridge National Laboratory, Oak Ridge, Tennessee.

King, L. J., 1960, “Intercycle Evaporator Explosion, Building 3019,” paper presented at a Chemical 

Technology Division Seminar, July 16.

Klima, B. B., 1960, Building 3019 Vessel Off-Gas Filter, ORNL Central Files 62-10-108, Oak Ridge 

National Laboratory, Oak Ridge, Tennessee.

Parrott, J. R., 1961, Decontamination of Cells 6 and 7, Building 3019, Following Plutonium Release 

Incident, ORNL-3100, Oak Ridge National Laboratory, Oak Ridge, Tennessee.

ORNL (Oak Ridge National Laboratory), 1953, Oak Ridge National Laboratory Building List, Oak 

Ridge National Laboratory, Oak Ridge, Tennessee.

ORNL (Oak Ridge National Laboratory), 1955, Operation of the Aircraft Reactor Experiment, ORNL1845, Oak Ridge National Laboratory, Oak Ridge, Tennessee.
Effective Date: 11/14/2003 Revision No. 00 Document No. ORAUT-TKBS-0012-2 Page 37 of 66

ORNL (Oak Ridge National Laboratory), 1994, Site Characterization Report for Building 3515 at Oak 

Ridge National Laboratory, ORNL/ER/Sub/87-99053/73, Oak Ridge National Laboratory, Oak 

Ridge, Tennessee.

ORNL (Oak Ridge National Laboratory), 1996, Site Characterization Summary Report for the Old 

Hydrofracture Facility, Waste Area Grouping 5, at Oak Ridge National Laboratory, Oak Ridge, 

Tennessee, ORNL/ER-360, Oak Ridge National Laboratory, Oak Ridge, Tennessee.

ORNL (Oak Ridge National Laboratory), 1997a, Metals and Ceramics Division History 1946 – 1996, 

ORNL/M-6589, Oak Ridge National Laboratory, Oak Ridge, Tennessee. 

ORNL (Oak Ridge National Laboratory), 1997b, Site Descriptions of Environmental Restoration Units 

at Oak Ridge National Laboratory, Oak Ridge, TN, ORNL/ER-391, Oak Ridge National 

Laboratory, Oak Ridge, Tennessee.

ORNL (Oak Ridge National Laboratory), 1998, Environmental Health and Safety Plan for the Molten 

Salt Reactor Experiment Remediation Project at Oak Ridge National Laboratory, ORNL/ER326/R1, Oak Ridge National Laboratory, Oak Ridge, Tennessee.

ORNL (Oak Ridge National Laboratory), 2001, Facility Environmental Vulnerability Assessment, 

ORNL/TM-2001/123, Oak Ridge National Laboratory, Oak Ridge, Tennessee. 

ORNL (Oak Ridge National Laboratory), 2002, Oak Ridge National Laboratory Land and Facilities 

Plan, ORNL/TM-2002/1, Oak Ridge National Laboratory, Oak Ridge, Tennessee. 

Rupp, A. F., and J. A. Cox, 1955, Operation of the ORNL Graphite Reactor and the Low-Intensity Test 

Reactor, ORNL-1866, Oak Ridge National Laboratory, Oak Ridge, Tennessee.

Rupp, A. F., and E. J. Witkowski, 1955, RaLa Production - 1954, Central Files 55-1-211, Oak Ridge 

National Laboratory, Oak Ridge, Tennessee.

Stapleton, D. R., 1993, A Brief History of the Research Reactors Division of Oak Ridge National 

Laboratory, ORNUM-2342, Oak Ridge National Laboratory, Oak Ridge, Tennessee.

Stanley, W. M., 1954, “Area Contamination on April 29, 1954,” interoffice correspondence to C. E. 

Larson, April 30, Oak Ridge National Laboratory, Oak Ridge, Tennessee. 

Thompson, W. E., 1949, A History of the Radioactive Barium-Lanthanum Process and Production, 

ORNL-246 Special, Oak Ridge National Laboratory, Oak Ridge, Tennessee.
Effective Date: 11/14/2003 Revision No. 00 Document No. ORAUT-TKBS-0012-2 Page 38 of 66

GLOSSARY

barites concrete

Concrete containing barium sulfate (BaSO4). 

calutron (California University Cyclotron)

An accelerator used to electromagnetically separate isotopes based on their mass.

supernatant

A highly radioactive liquid overlying material deposited by settling, precipitation, etc.; 

also called supernate.
Effective Date: 11/14/2003 Revision No. 00 Document No. ORAUT-TKBS-0012-2 Page 39 of 66

ATTACHMENT 2A

OAK RIDGE NATIONAL LABORATORY FACILITY INDEX

Facility 

ID Description

Old 

numbering

807 CS-137 EROSION/RUNOFF STUDY AREA

813 FIELD LABORATORY #1 TRAILER

814 Trailer

816 CESIUM PLOTS STUDY AREA

817 OZONE GENERATOR BUILDING

818 ATMOSPHERIC INSTRUMENT TRAILER

819 FARM IMPLEMENT STORAGE

820 CARBON DIOXIDE TANK

821 AMBIENT AIR STATION NO. 39

822 ESD/NOAA TRAILER

823 FREE AIR CARBON EXPERIMENT (FACE) COMPLEX

0823A FACE RING #1 SHED

0823B FACE RING #2 SHED

0823C FACE RING #3 SHED

0823D FACE RING #4 SHED

0823E FACE CO2 TANK/EVAPORATORS

830 White Oak creek embayment structure

853 White Oak Creek Below Dam

855 OPERATIONS BUILDING

857 Goat Building

858 SYCAMORE PLANTATION TRAILER

870 RACCOON CREEK MONITORING STA.

900 FIREARMS RANGE 745-A,-B

0900A FIRING RANGE STORAGE

0900B FIRING RANGE CANOPY

901 161 KV SUBSTATION 501-H

902 MAIN RESERVOIR 803

903 BETHEL VALLEY CHURCH

907 WALKER BRANCH WATERSHED LAB

910 BOOSTER PUMP STATION

926 1,500,000 STEEL WATER RESEVOIR

0926A VALVE HOUSE

0926B EMERGENCY GENERATOR

927 STORAGE BUILDING

929 ISH CREEK WEIR

932 WBW SOIL BLOCK 1

933 WBW SOIL BLOCK 2

934 WBW SUBSURFACE WEIR INSTRUMENT TRAILER

935 WBW SUBSURFACE WEIR

936 ESD TWIN TOWERS WALKER BRANCH

937 ATDD/NOAA RAIN GAUGE 2 BLDG.

940 INSTRUMENT BLDG 1

941 INSTRUMENT BLDG 2

0945A RAIN GAGE 1 SITE
Effective Date: 11/14/2003 Revision No. 00 Document No. ORAUT-TKBS-0012-2 Page 40 of 66

Attachment 2A (Continued)

Facility 

ID Description

Old 

numbering

0945B RAIN GAGE 2 SITE

0945C RAIN GAGE 3 SITE

0945D RAIN GAGE 4 SITE

0945E THROUGH-FALL EXPERIMENT SITE

0945F THROUGHFALL STORAGE BUILDING

946 KATIE'S KITCHEN WELL

950 WALKER BRANCH, EAST INSTRUMENT HOUSE

951 WALKER BRANCH, WEST INSTRUMENT HOUSE

952 WALKER BRANCH EAST WEIR

953 WALKER BRANCH WEST WEIR

954 REFUSE TRANSFER STATION

955 WALKER BRANCH STORAGE BLDG.

956 SPRING WATER PUMPHOUSE

957 SAMPLE STORAGE BUILDING

958 WATER WELL NO. 1

960 WATER WELL NO. 2

961 ORNL VISITOR OVERLOOK

963 WHITE OAK CREEK HEADWATERS MONITORING STATION

965 PARKING PASSENGER SHELTER

966 WEST ENTRY CONTROL FACILITY, POST 50

967 POWER CONDUCTOR ACCELERATED TEST FACILITY

1000 ENGINEERING OFFICE BUILDING 703-C

1001 SWSA #3 BURIAL GROUNDS

1005 LABORATORY FOR FUNCTIONAL AND COMPARATIVE GENOMICS

1055 WATER WELL NO. 9

1057 100-METER METEOROLOGICAL TOWER

1058 SUBSTATION NO. 7-2

1059 HEALTH EFFECTS INFORMATION OFFICE BUILDING

1060 ENVIRONMENTAL & LIFE SCIENCES LABORATORY FACILITY

1060COM 1060 COMMERCE PARK DRIVE

1061 HEALTH PROTECTION SERVICES OFFICE BUILDING

1062 WEST OFFICE BUILDING

1096 PASSENGER SHELTER, WEST PARKING LOT

111UNV 111 UNION VALLEY ROAD

115UNV RECEIVING, ACCEPTANCE, TESTING & STORAGE FACILITY

1503 ENVIRONMENTAL SYSTEMS LAB

1504 AQUATIC ECOLOGY LAB

1505 ENVIRONMENTAL SCIENCES LAB

1506 PLANT SCIENCES LAB

1507 LIFE SCIENCES DATA ANALYSIS OFFICE BUILDING

1508 AQUATIC STORAGE BUILDING

1509 ENVIRONMENTAL ENGINEERING OFFICE BUILDING

1510 AQUATIC STORAGE BUILDING 1

1511 AQUATIC STORAGE BUILDING 2

1512 AQUATIC STORAGE BUILDING 3
Effective Date: 11/14/2003 Revision No. 00 Document No. ORAUT-TKBS-0012-2 Page 41 of 66

Attachment 2A (Continued)

Facility 

ID Description

Old 

numbering

1513 AQUATIC STORAGE BUILDING 4

1514 AQUATIC STORAGE BUILDING 5

1515 AQUATIC STORAGE BUILDING 6

1542 GAS STORAGE FACILITY

1552 WATER MONITORING EQUIPMENT SHED

1553 SERVICE PIT FOR 1504

1554 Contractor Disposal Area

1556 EAST COOLING TOWER

1557 WEST COOLING TOWER

1558 NW TRIBUTARY MONITORING STATION

1559 BOAT SHED

1560 EAST GREENHOUSE

1561 WEST GREENHOUSE

1562 SCRAP METAL AREA

1563 SUBSTATION NO. 234-4

1566 FIRST CREEK MONITORING STATION

2000 SOLID STATE ANNEX 101-D

2001 INFORMATION CENTER COMPLEX 104-B

2003 PROCESS WATER CONTROL STATION

2007 CALIBRATION LAB

2008 ORNL WHOLE BODY COUNTER 719-B

2009 CAFETERIA WAREHOUSE 802

2010 ORNL CAFETERIA

2011 ELECTRIC & AC SERVICE CENTERS

2013 WEST MAINTENANCE SERVICE CENTER 719-A

2016 SECURITY PATROL HQ ANNEX 614-6

2016A PUMP STATION NO.1, CORE HOLE-8

2016B PUMP STATION NO. 2, CORE HOLE-8

2016C GROUND WATER COLLECTION AND TRANSFER, CORE HOLE-8

2017 EAST RESEARCH SERVICE SHOP

2018 ELECTRIC & AIR CONDITIONING SERVICE CENTER 717-C or 305

2019 LASER LABORATORY

2024 QUALITY ASSURANCE AND INSPECTION OFFICE BUILDING

2026 RADIOACTIVE MATERIALS ANALYTICAL LABORATORY (RMAL)

2026A Tank SE of Building 2026

2032 Manhole 240 Monitoring Station

2033 MEASUREMENTS & CONTROLS BUILDING

2034 Manhole 95 Monitoring Station

2061 STACK

2069 CHANGE HOUSE 708

2087 STORAGE I-E

2088 EMERGENCY GENERATOR BUILDING FOR 2000

2092 STORAGE

2093 ENVIROMENTAL STORAGE BUILDING

2097 COOLING TOWER FOR 2001
Effective Date: 11/14/2003 Revision No. 00 Document No. ORAUT-TKBS-0012-2 Page 42 of 66

Attachment 2A (Continued)

Facility 

ID Description

Old 

numbering

2098 SUBSTATION NO. 6-3

2099 Building 2026 monitoring control station

2101 LGWOD Health & Hygiene Support Building

2102 PCM TRAILER

2500 FIRE STATION AND PROTECTIVE SERVICES HEADQUARTERS 720

2506 P&E MAINTENANCE SHOP & SUPPORT BUILDING 717-B

2508 INSTRUMENTATION TRAILER, AT W-TANKS

2510 AIR COMPRESSOR BUILLDING

2517 HRDP/TRAINING 735-A

2518 FACILITIES AND OPERATIONS OFFICE BUILDING

2519 STEAM PLANT 801-D

2519A STANDBY EMERGENCY GENERATOR FOR 2519

2519C EMERGENCY GENERATOR, 2519

2521 SEWAGE TREATMENT PLANT

2521A SEWAGE TREATMENT AREATION BASIN

2521B EMERGENCY GENERATOR BUILDING

2521C SLUDGE DRYING BED

2521D AERATOR SHED

2521E CALGON TANK SHED

2521F SEWAGE DIGESTER BUILDING

2522 FUEL OIL TANK

2523 DECONTAMINATION LAUNDRY

2523A DECONTAMINATION LAUNDRY ANNEX

2525 P&E MACHINE SHOP FACILITY

2528 WHPP DEVELOPMENT FACILITY

2528A STORAGE TANK

2531 LLLW EVAPORATOR BUILDING

2532 HLW Storage Cooling Pump House

2533 CELL VENTILATION FILTER PIT FOR 2531 AND 2537

2534 OFF-GAS FILTER PIT FOR 2531 AND 2537

2535 Cooling Tower #1 for Building 2531

2536 COAL SAMPLE PREPARATION BUILDING

2537 EVAPRORATOR SERVICE TANK & CONTROL ROOM FOR 2531

2539 Cooling Tower Substation for 2531

2540 STEAM PLANT SUBSTATION

2543 EAST AERATION POND

2544 WEST AERATION POND

2545 SEWAGE TREATMENT FACILITY

2546 MONITORING BUILDING FOR 2545

2547 GENERAL MACHINE SHOP

2548 SLUDGE DRYING FACILITY

2549 STEAM PLANT STORAGE BUILDING

2555 250,000 FUEL OIL STORAGE FACILITY 717-I

2568 CELL VENT & OFF-GAS FILTER FOR 2531

2572 EMERGENCY GENERATOR FOR 2500 502 #9
Effective Date: 11/14/2003 Revision No. 00 Document No. ORAUT-TKBS-0012-2 Page 43 of 66

Attachment 2A (Continued)

Facility 

ID Description

Old 

numbering

2600 Bethel Valley Storage Tank 713-S

2609 SENTRY POST 3, WEST PORTAL

2621 WASTE OPERATIONS SUPPORT SHOP

2624 SWSA #1 Burial Grounds

2628 FIRE PROTECTION MAINTENANCE AND STORAGE BUILDING

2630 CASK COMPONENT DROP TEST FACILITY

2632 5000-KVA SUBSTATION

2636 WEST PRECIPITATOR

2637 EAST PRECIPITATOR

2638 STEAM PLANT SCALE HOUSE

2643 CHLORINATOR BUILDING

2644 COAL YARD RUNOFF TREATMENT PLANT

2645 EMERGENCY GENERATOR, COAL HANDLING

2646 SUBSTATION NO. 33-6

2648 FIRE TRAINING TOWER

2649 Transported Waste Receiving

2650 Evaporator Chemical Shed

2651 Emergency Generator, 2600 Area

2652A TRAILER, RADIOLOGICAL SURVEILLANCE

2652B TRAILER, RADIOLOGICAL SURVEILLANCE

2652C TRAILER, RADIOLOGICAL SURVEILLANCE

2653 COAL YARD BUILDING

2656 SEWAGE TREATED PLANT-WATER MONITOR STATION

2657 Manhole 243 Monitoring Station

2658 F-4005 Monitoring Station

2660 WASTE OPERATIONS SUPPORT FACILITY

2661 ORNL TRAINING BUILDING

2663 OZONE GENERATOR EQUIPMENT BUILDING

2664 SODIUM METABISULFITE BUILDING

3000 13.8 KV SUBSTATION

3001 OAK RIDGE GRAPHITE REACTOR, OGR 105

3002 OGR Filter House & Canal 114

3002A Drain Tank South of 3002

3003 SURFACE MODIFICATION AND CHARACTERIZATION FACILITY 115

3003A Drain Tank South of 3003

3005 Low Intensity Testing Reactor 106

3008 SECURITY PATROL STORAGE 103

3009 Pump House for Bldg 3010

3010 Bulk Shielding Reactor, BSR

3010A BULK SHIELDING REACTOR SUPPORT FACILITY. N. ANNEX

3012 ROLLING MILL 101-B

3017 QUALITY SERVICES DIVISION BUILDING

3018 OGR Exhaust Stack for 3003

3019A RADIOCHEMICAL DEVELOPMENT FACILITY 205

3019B HIGH LEVEL RADIATION ANALYTICAL LAB.
Effective Date: 11/14/2003 Revision No. 00 Document No. ORAUT-TKBS-0012-2 Page 44 of 66

Attachment 2A (Continued)

Facility 

ID Description

Old 

numbering

3020 OFF GAS STACK FOR 3019

3023 NORTH TANK FARM 206

3025E IMET HOT CELL FACILITY

3025M SOLID STATE OFFICE & LABORATORY BUILDING 107

3026C Krypton-85 enrichment facility 706-C

3026D Metal segmenting hot cell facility 706-D

3027 SPECIAL NUCLEAR MATERIALS VAULT

3028 Alpha powder facility 910

3029 Source development lab 909

3030 Radioisotope Production Lab-C 908

3031 Radioisotope Production Lab-D 907

3032 Radioisotope Production Lab-E 906

3033 Radioactive gas process facility. 905

3033A Actinide fabrication facility annex

3034 RADIOISOTOPE AREA SERVICES 904

3036 RADIOISOTOPE MATERIAL SHIPPING AND PACKAGING 903

3037 CHEMICAL TECHNOLOGY OFFICES 901

3038 Radioisotopes Laboratory 902

3039 Central radioactive gas disposal facility 911

3042 Oak Ridge Research Reactor, ORR

3044 WEST COMPLEX FIELD SHOP

3047A RADIOISOTOPE DEVELOPMENT LABORATORY

3047B RADIOISOTOPES DEVELOPMENT LABORATORY

3074 INTERIM MANIPULATOR REPAIR FACILITY

3078 SEPTIC TANK FOR 3000 PUMP STA.

3080 SUPERCONDUCTIVITY LABORATORY

3082 DATA CONCENTRATOR 2, WOCC DAS

3083 Neutron flight tube building

3084 RIS SENSOR DEVELOPMENT, NORTH ANNEX

3085 Pump House for ORR

3086 COOLING TOWER NO.1 - ORR

3087 Heat Exchanger - ORR

3089 Cooling Tower No.2 - ORR

3091 FILTERS FOR 3019

3092 OFF-GAS SCRUBBER FACILITY

3093 Krypton Storage Cubicle

3095 REACTOR AREA EQUIPMENT BUILDING

3098 Filter facility-BSR

3099 Storage Pad between 3031&3032

3100 SOURCE & SPECIAL MATERIAL VAULT

3102 Heat Exchanger No.2 - ORR

3103 COOLING TOWER NO.3 - ORR

3104 WEST COMPLEX MAINTENANCE SHOP

3105 LGWOD HP OFFICE BUILDING

3106 CELL VENT FILTER FOR 4501,4505,AND 4507
Effective Date: 11/14/2003 Revision No. 00 Document No. ORAUT-TKBS-0012-2 Page 45 of 66

Attachment 2A (Continued)

Facility 

ID Description

Old 

numbering

3107 25-meter Target House

3108 FILTER HOUSE FOR BUILDING 3019

3109 Off-Gas Filters for ORR

3110 Filter House, Isotope area

3111 SECURITY POST 8A

3112 STORAGE BUILDING

3114 EFFICIENCY RESEARCH LABORATORY

3115 SOLID STATE OFFICES

3116 Nitrogen Cylinder Storage Bldg

3117 BSR Cooling Tower

3117A Sulfuric acid tank

3118 Radioisotope Production Lab-H

3119 BSR Heat Exchanger & Pump house

3121 CELL OFF-GAS FILTER HOUSE FOR 3019B

3123 DIESEL GENERATOR

3125 3039 Stack Area Emergency Generator

3126 Charcoal Filter (NOG) ORR

3127 PDS record storage

3129 PERSONNEL MONITORING STATION

3130 Waste Operation Control Center

3131 EMERGENCY GENERATOR

3132 EMERGENCY GENERATOR FOR 3127,3129,AND 3027

3133 BV valve box 1A

3135 SENTRY POST 8D, BLDG. 3019

3136 EQUIPMENT TEST FACILITY-3019

3137 SURFACE SCIENCE LAB

3138 ROOF THERMAL RESEARCH CENTER

3139 Cell Ventilation Filters-ORR

3140 CELL VENTILATION FILTERS FOR 3026

3144 ROOF RESEARCH CENTER

3145 LGWOD storage building

3146 EMERGENCY GENERATOR FOR 3020 STACK

3147 EFFICIENCY & RENEWABLE RESEARCH OFFICE BUILDING

3150 CERAMICS & THIN FILM LAB

3153 ENVELOPE SYSTEMS RESEARCH CTR.

3154 Manhole 112 Monitoring Building

3155 Manholes 114 & 234 Monitoring

3156 ENERGY DIVISION OFFICE BUILDING

3158 North CV duct monitoring bldg.

3159 South CV duct monitoring bldg.

3160 3019 MOTOR CONTROL CENTER #1 AND #2

3161 QSD STORAGE BUILDING

3162 QSD STORAGE

3163 WEST WEATHERPORT

3164 WEST WEATHERPORT
Effective Date: 11/14/2003 Revision No. 00 Document No. ORAUT-TKBS-0012-2 Page 46 of 66

Attachment 2A (Continued)

Facility 

ID Description

Old 

numbering

3500 I&C DIVISION OFFICES

3501 SEWAGE PUMPING STATION

3502 EAST RESEARCH SERVICE CENTER 706-HD

3502B DATA CONCEN 4 WOCC DAS 3502

3503 HIGH RAD. LEVEL CHEM. ENG. LAB 706-HB

3503A 3503 STORAGE PAD

3504 GEOSCIENCES LAB

3507 South Tank Farm 206

3508 I&C METROLOGY AND CALIBRATION

3513 Settling Basin 206

3515 Fission Prod Lab No. 1

3517 Fission Products Development Lab

3518 ACID NEUTRALIZATION PLANT

3518A LGWOD SPARE PARTS TRAILER

3523 EXPENSED BENCH STOCK BUILDING

3524 Equalization basin

3525 IRRADIATED FUELS EXAMINATION LABORATORY

3532 PAINT STORAGE SHED

3536 NITROGEN CYLINDER TANK STORAGE

3538 COOLING TOWER FOR 3525

3539 190 POND NO. 1, NORTH

3540 190 POND NO. 2, SOUTH

3541 ENGINEERING DEVELOPMENT LAB

3542 STORAGE BLDG. FOR 3506 & 3517

3543 MACES STORAGE BUILDING

3544 PROCESS WASTE TREATMENT PLANT

3544A ORNL WASTE WATER TREATMENT TRAILER

3544B Filter Press Building

3546 CCSD OFFICE BUILDING

3547 Cell Vent Roughing Filter for 3517

3548 CELL VENT FILTERS FOR 3517

3550 RESEARCH MATERIALS PREPARATION FACILITY 706-A

3550T INTERCOMPARISON STUDY DILUTIONS LAB.

3584 SOLVENT OPERATIONS CONTAMINENT 713-UA

3587 MAIL SERVICES BUILDING

3592 COAL CONVERSION FACILITY

3594 WASTE MANAGEMENT STORAGE

3597 HOT STORAGE GARDEN

3598 EMERG. GENERATOR FOR 3500 AREA

3602 CYLINDER TANK STORAGE FOR 3525

3605 TSD STORAGE BUILDING

3606 SOUTH OFFICE ANNEX

3607 CASK STORAGE BUILDING

3608 Process waste treatment plant

3609 SUBSTATION NO. 25-1-C
Effective Date: 11/14/2003 Revision No. 00 Document No. ORAUT-TKBS-0012-2 Page 47 of 66

Attachment 2A (Continued)

Facility 

ID Description

Old 

numbering

3610 STORAGE BUILDING

3610A FLAMMABLE STORAGE

3613 Diversion box monitor station

3614 MH 190 monitoring station

3615 MH 235 monitoring station

3616 MH 149 monitoring station

3617 MH 229 monitoring station

3618 Pump. station, WC-10,11,12,13,14

3619 WHITE OAK CREEK GAUGING STATION

3620 HOT OFF GAS COLLECTION POT

3621 SPILL RESPONSE VEHICLE STORAGE FACILITY

3624 FLAMMABLE STORAGE FOR 3517

4000 13.8/2.4 KV SUBSTATION

4001 PUMPING STATION

4003 SWSA #2 BURIAL GROUNDS

4007 SECURITY AND COUNTERINTELLIGENCE OFFICE BUILDING

4500N CENTRAL RESEARCH & ADMINISTRATION BUILDING - NORTH

4500S CENTRAL RESEARCH & ADMINISTRATION BUILDING - SOUTH

4501 RADIOCHEMISTRY LABORATORY 4501

4503 STANDBY EMERGENCY GENERATOR FOR 4500N

4505 EXPERIMENTAL ENGINEERING 4501

4507 High Level Chemical Dev Lab

4508 METALS & CERAMICS LAB

4509 CENTRAL CHILLED WATER PLANT

4510 COOLING TOWER FOR 4509

4511 COOLING TOWER FOR 4509

4512 LABORATORY EMERGENCY RESPONSE CENTER

4513 HTML ELECTRICAL SUBSTATION

4514 GENERATOR - HTML

4515 HIGH TEMPERATURE MATERIALS LAB

4516 HTML COOLING TOWER

4521 COOLING TOWER FOR BLDG 4509

4556 Filter pit for bldg 4507

4557 SENTRY POST

4559 PASSENGER SHELTER

4560 4512 LIFT STATION

4561 FLAMMABLE STORAGE, 4509

5000 MAIN PORTAL BUILDING 4502

5002 SCIENCE & TECHNOLOGY PARTNERSHIPS OFFICE BUILDING

5100 JOINT INSTITUTE OF COMPUTER SCIENCE (JICS)

5500 HIGH VOLTAGE ACCELERATOR LAB 4503

5500A SOUTH OFFICE ANNEX

5505 TRANSURANIUM RESEARCH LAB

5507 CONTROLLED EXPERIM. ATMOSPHERE

5507A RDTE FACILITY
Effective Date: 11/14/2003 Revision No. 00 Document No. ORAUT-TKBS-0012-2 Page 48 of 66

Attachment 2A (Continued)

Facility 

ID Description

Old 

numbering

5510 ORG AND BIO MASS SPEC LAB

5510A QSD METROLOGY & INTERCOMPARISONS STUDIES LABS

5554 ELECTRICAL SUBSTATION FOR 5505

5600 COMPUTATIONAL SCIENCES BUILDING

5700 RESEARCH OFFICE BUILDING

5800 ENGINEERING TECHNOLOGY FACILITY

6000 HOLIFIELD RADIOACTIVE ION BEAM FACILITY (HRIBF)

6000B ATOMIC PHYSICS RESEARCH LAB

6001 COOLING TOWER FOR 6000

6005 GAS COMPRESSOR HOUSE FOR 6000

6007 DORMITORY FOR JIHIR

6008 JIHIR OFFICE/LAB FACILITY

6010 ORELA

6011 COMPUTATIONAL PHYSICS & ENGINEERING BUILDING

6012 COMPUTER SCIENCES RESEARCH

6013 CHEMICAL FEED SYSTEM ENCLOSURE

6014 COMPRESSOR BUILDING, 6001 FIRE PROTECTION SYSTEM

6016 OUTFALL 314 DECHLORINATION SYS

6025 COMPUTATIONAL PHYSICS & ENGR.

6551 WEST RESERVOIR ON HAW RIDGE

6552 EAST RESERVIOR ON HAW RIDGE

6553 STANDBY GENERATOR & VALVE PIT

6555 30M METEOROLOGICAL TOWER-B

6556-ST1 STORAGE TRAILERS

6556-ST2 FOREST MANAGEMENT STORAGE TRAILER

6556-ST3 STORAGE TRAILERS

6556-ST4 STORAGE TRAILERS

6556-ST5 STORAGE TRAILERS

6556-ST6 STORAGE TRAILERS

6556-ST7 STORAGE TRAILERS

6556-ST8 STORAGE TRAILERS

6556-ST9 STORAGE TRAILERS

6556A ER Field Operations Trailer

6556B ER Field Operations Trailer

6556C ER FIELD OPERATIONS TRAILER

6556D ER Field Operations Trailer

6556E ER FIELD OPERATIONS TRAILER

6556G ER Field Operations Trailer

6556J ER Trailer, Single Wide

6556K ER Trailer, Single Wide

6556L ER Field Operations Trailer

6556M ER Field Operations Trailer

6556Q FOREST MANAGEMENT TRAILER

6556R ER Field Operations Trailer

6556S ER FIELD OPERATIONS TRAILER
Effective Date: 11/14/2003 Revision No. 00 Document No. ORAUT-TKBS-0012-2 Page 49 of 66

Attachment 2A (Continued)

Facility 

ID Description

Old 

numbering

6556T ER Field Operations Trailer

6556U ENVIRONMENTAL MANAGEMENT OFFICE TRAILER

6556V ENVIRONMENTAL MANAGEMENT OFFICE TRAILER

6556X ENVIRONMENTAL MANAGEMENT OFFICE TRAILER

7000 SEPTIC TANK FOR 7000 AREA

7001 GENERAL STORES

7002 GARAGE & IRONWORKING SHOP

7003 WELDING & BRAZING SHOP

7005 LEAD SHOP

7006 STORAGE BUILDING

7007 PAINT SHOP

7009 CARPENTER SHOP

7010 DRY LUMBER STORAGE

7012 CENTRAL FABRICATION SHOP

7013 CHEMICAL REUSE BUILDING

7015 METAL STORAGE & CUTTING FACILITY

7018 BULK RECEIVING AND STORES BUILDING

7019 RRD WAREHUSE FACILITY - CAT C STORAGE

701SCA 701 SCARBORO ROAD

7020 INTERIM GROUNDS EQUIPMENT STORAGE BUILDING

7020AR HVAC DECONTAMINATION FACILITY

7020B TEMPORARY WASTE STORAGE FACILITY

7020C TEMPORARY WASTE STORAGE FACILITY

7020D OFFICE TRAILER-SWASA 6

7020E TEMPORARY WASTE STORAGE FACILITY

7020F HP OFFICE TRAILER

7021 FABRICATION EQUIPMENT STORAGE

7022 GAS CYLINDER STORAGE SHED

7025 TRITIUM TARGET PREP FACILITY

7026 METALS & CERAMICS STORAGE

7030 HEAVY EQUIP. STORAGE SHELTER

7031 FABRICATION STORAGE SHED

7033 LINE CREW FACILITY

7035 VACUUM ASBESTOS EQUIPMENT CLEANING FACILITY

7035A PAINT MIX BUILDING

7035B PAINT STORAGE

7035C EQUIPMENT STORAGE

7035D CAN DRYING FACILITY

7035E UTILITY MECHANICS STORAGE

7035F SHED STORAGE FACILITY

7037 COLD STORAGE FACILITY

7038 P&E TEMP. WASTE STORAGE PAD

7039 MATERIAL STAGING FACILITY

7040 GAS CYLINDER STORAGE

7041 STORAGE BUILDING
Effective Date: 11/14/2003 Revision No. 00 Document No. ORAUT-TKBS-0012-2 Page 50 of 66

Attachment 2A (Continued)

Facility 

ID Description

Old 

numbering

7042 CORE STORAGE BUILDING

7043 PERSONNEL SHELTER-WEST OF 7000

7044 SUBSTATION 27-8, WEST OF 7003

7046 ESH&Q OFFICE TRAILER

7053 PERSONNEL SHELTER-NORTH

7055 GROUNDS EQUIPMENT STORAGE FACILITY

7057 SANDBLAST CLEANING FACILITY

7058 REGULATOR REPAIR FACILITY

7060 STEEL YARD

7061 ENVIRONMENTAL SURV. AND PROTECTION STORAGE

7062 CRANE INSPECTION CREW OFFICES

7063 EMERGENCY GENERATOR FOR 7003

7065 RIGGER EQUIPMENT STORAGE

7066 GROUNDS MAINTENANCE STORAGE

7067 TRAINING FACILITY

7069 GASOLINE SERVICE FACILITY

7069E UNDERGROUND STORAGE TANK

7069F UNDERGROUND STORAGE TANK

7070 STORAGE SHED

7071 LIQUID NITROGEN STORAGE TANK

7072 SENTRY POST 20B, 7000 AREA

7073 AIR MONITORING STATION

7074 SENTRY POST 20C, PED GATE 7012

7075 WASTE STORAGE BUILDING

7077 CRAFT SUPPORT OFFICE BLDG.

7077A RESERVATION SERVICES OFFICES

7078A Bechtel-Jacobs office trailer

7078B Bechtel Jacobs office trailer

7078C Bechtel Jacobs office trailer

7078D Bechtel Jacobs office trailer

7078E Bechtel Jacobs office support trailer

7078F Bechtel Jacobs office trailer

7078G SRINKLER CONTROL BUILDING

7078H SPRINKLER CONTROL BUILDING

7079 BOTTLE STORAGE BUILDING

7080 CARDBOARD COMPRESSOR

7081 PORTABLE GENERATOR STORAGE SHE

7082 SALT STORAGE BUILDING

7083 MODEL AIRPLANE SHOP

7085 90-DAY WASTE STORAGE

7086 FLAMMABLE GAS STORAGE

7089 FLAMMABLE STORAGE

7090 ELECTRICAL STORAGE WEST

7091 ELECTRICAL STORAGE EAST

7092 HUSTLER MOWER STORAGE
Effective Date: 11/14/2003 Revision No. 00 Document No. ORAUT-TKBS-0012-2 Page 51 of 66

Attachment 2A (Continued)

Facility 

ID Description

Old 

numbering

7093 PHYSICS DIVISION STORAGE 1

7094 PHYSICS DIVISION STORAGE 2

7095 PHYSICS DIVISION STORAGE 3

7096 ENVIRONMENTAL PROTECTION STORAGE

7097 CRANE AND ELEVATOR CREW OFFICE TRAILER

7098 TRANSPORTATION SERVICES OFFICE TRAILER

7099 PRESSURE REDUCING VALVE STATION

7500 Homogeneous reactor exp. facility.

7501 SEPTIC TANK

7502 Radioactive Waste Evaporator

7503 Molten Salt Reactor Experiment

7505 LGWOP MAINTENANCE SUPPORT OFFICE

7506 LGWOP Maintenance Support Shop

7507 Hazardous waste storage facility

7507W Mixed hazardous waste storage pad

7509 MSRE Office Building

7511 Filter Pit for 7503

7512 Stack for 7503

7513 Cooling Tower for 7503

7514 Filter House for 7503

7516 Field Service Shop - 7500 Area

7548 HAZARDOUS WASTE STORAGE SHED

7549 STORAGE

7553 PUMP HOUSE-TSF WATER SUPPLY 20035

7554 COOLING TOWER FOR 7500

7554A MK-FERGUSON TRAILER

7555 Diesel Generator House - 7503

7556 HRE settling pond

7557 Charcoal Absorber Pit for 7500

7558 Waste Evaporator Loading Pit

7559 Adsorber Valve Pit

7560 Waste Tank for 7500

7561 HRE decontamination pad/shed

7562 Waste Condensate Tank for 7500

7563 Circulator Pump Pit for 7500

7567 Central pump. station, tanks T1,T2

7568 SENTRY POST 19, HFIR AREA

7569 LLLW collection tank, WC-20

7571 30-METER METEOROLOGICAL TOWER

7572 CH-TRU waste storage facility

7574 Waste storage facility

7575 SWASA #7

7576 BULK CONTAMINATED SOIL FACILITY

7577 TRU STORAGE FACILITY

7578 CLASS 34 WASTE RETRIEVABLE STORAGE
Effective Date: 11/14/2003 Revision No. 00 Document No. ORAUT-TKBS-0012-2 Page 52 of 66

Attachment 2A (Continued)

Facility 

ID Description

Old 

numbering

7580 SOLID LOW LEVEL WASTE STAGING FACILITIES

7582 LGWOD SPARE PARTS STORAGE FAC.

7583A WASTE OPERATIONS SPARE PARTS STORAGE

7583B WASTE OPERATIONS SPARE PARTS STORAGE

7583C WASTE OPERATIONS SPARE PARTS STORAGE

7584 BJC OFFICE TRAILER

7600 CONTAINMENT BUILDING

7601 R&PS DIVISION OFFICE BUILDING

7602 Integrated process demo. facility.

7603 REMOTE OPERATIONS & MAINTENANCE

7603A FUEL OIL STORAGE TANKS

7604 UTILITY BUILDING

7605 STORAGE BUILDING

7606A ROBOTICS R&D LAB

7606B RESEARCH SVC-MAINTENANCE BLDG

7607 EGCR RIVER PUMP STATION

7608 PLASMA TORCH CUTTING DEMO. FAC

7609 STACK MONITORING HOUSE

7610 STORAGE HOUSE - R&PS

7611 SENTRY POST 30, R&PS COMPLEX

7613 WASTE RETENTION BASIN

7614 EXHAUST STACK

7615 REDC STORAGE

7616 SEPTIC TANK

7618 DIESEL GENERATOR FOR 7600

7619 COOLING TOWER

7621 HEADQUARTERS BLDG.

7623 BATHOUSE

7624 ROBOTICS STORAGE BUILDING

7630 LOW-RISK INACTIVE STORAGE FAC.

7631 LOW-RISK INACTIVE STORAGE FAC.

7632 LOW-RISK INACTIVE STORAGE FAC.

7633 LOW-RISK INACTIVE STORAGE FAC.

7651 Clean, used oil storage pad

7652 Hazardous Waste Storage Facility

7653 Chemical Waste Storage Facility

7654 Hazardous Waste Storage Facility

7658 Contractors landfill

7658A BECHTEL JACOBS OFFICE TRAILER

7658B BECHTEL JACOBS OFFICE TRAILER

7658C BECHTEL JACOBS OFFICE TRAILER

7658D BECHTEL JACOBS OFFICE TRAILER

7659 LEAKING OIS GAS CYLINDER AREA

7661 ELECTRICAL UTILITY BUILDING

7662 Emergency Generator
Effective Date: 11/14/2003 Revision No. 00 Document No. ORAUT-TKBS-0012-2 Page 53 of 66

Attachment 2A (Continued)

Facility 

ID Description

Old 

numbering

7666 ENVIRONMENTAL EMER. RESPONSE

7666A TRAILER

7666B SPRINKLER CONTROL BUILDING

7667 Chemical detonation area

7668 Mixed Waste Storage Facility

7670 STORAGE TENT

7671 STORAGE

7672 PASSENGER SHELTER

7700 TOWER SHIELDING FACILITY (TSF) 20035

7701 TSF-POOL & PAD AREA 20035

7702 TSF-CONTROL HOUSE 20035

7703 TSF-HOIST HOUSE 20035

7704 TSF-CONTROL HOUSE NO. 2 20035

7705 TSF-PUMP HOUSE

7706 TSF-COOLER

7707 TSF-BATTERY HOUSE

7708 TSF-REACTOR SHIELD STORAGE

7709 HEALTH PHYSICS RES. REACTOR

7710 HPRR-DOSAR FACILITY

7711 Process Waste Basin for 7709

7712 DOSAR LOW ENERGY ACCELERATOR

7716 FILTER PUMP HOUSE MAIN. POOL

7720 Civil Defense Bunker

7735 RADIATION CALIBRATION LAB

7740 RADIO TRANSMITTER FACILITY

7740A MELTON HILL RADIO FACILITY

7740B EMERGENCY GENERATOR BUILDING

7740C MELTON HILL RADIO FACILITY

7750 FLOOR DRAIN COLLECTION TANK 20035

7751 SENTRY POST 22, TSF EXCLU. 20036

7755 DOSAR (HPRR) RESERVOIR

7756 METER HOUSE, HPM

7758 HFIR PARTS STORAGE

7759 CESIUM FOREST RESEARCH AREA

7800 SWSA #4 BURIAL GROUNDS

7802 SWSA #5 BURIAL GROUNDS

7802A Seep "C" Collection and Treatment Unit

7802B Seep D collection & treat. sys

7802C Deep monitoring well #1 bldg

7802D DEEP MONITORING WELL # 2 BLDG.

7802E SLUDGE REMOVAL TEST TANK

7802F Radiation monitoring equipment storage building

7802N SWAS 5 North Trench disposal area

7803 LAB TRAILER

7805 Waste Pit No.1
Effective Date: 11/14/2003 Revision No. 00 Document No. ORAUT-TKBS-0012-2 Page 54 of 66

Attachment 2A (Continued)

Facility 

ID Description

Old 

numbering

7807 Waste Pit No.3

7808 Waste Pit No.4

7809 Waste Trench No.5

7810 Chemical Waste Trench No.6

7810A Interim Non-reg. Waste Storage

7811 GEOSCIENCES STORAGE BUILDING

7811A PILOT PITS EXPERIMENTS AREA

7813 White Oak Creek Dam

7818 Waste Trench No.7

7821 Emergency Waste Basin

7822 SWSA #6 BURIAL GROUNDS

7822A High range disposal wells

7822J LLW Storage Pad

7823 LLW staging/storage facility

7823A Underground Storage Facility Well

7823B TEMP. WASTE STORAGE FACILITY

7823C TEMP. WASTE STORAGE FACILITY

7823D TEMP. WASTE STORAGE FACILITY

7823E TEMP. WASTE STORAGE FACILITY, TENT

7823F STORAGE SHED (SWSA 5)

7824 Waste examination and assay facility

7824A WEAF Support Facility Trailer

7826 TRU drum storage facility

7827 Shielded Dry Well Facility

7829 Shielded Dry Well Facility

7830 Melton valley storage facility

7830A Hazardous waste storage tank

7831 FIELD OFFICE & COMPACTOR FACIL

7831A SLLW storage building

7831C SLLW storage shed

7831D SWSA 5 storage pad

7833 Alpha Greenhouse Facility

7834 TRU drum storage facility

7835 SLUDGE WASTE POND

7841 CONTAMINATED EQUIPMENT STORAGE YARD

7841A WASTE STORAGE AREA OFFICE TRAILER

7842 Temp LLW storage facility

7842A LWSP II SOLIDIFIED WASTE STO.

7842B TEMP LLW STORAGE FACILITY

7842C TEMPORARY LLW STORAGE FACILITY, TENT

7844 ER STORAGE BUNKER

7846 White Oak Lake

7847 Vehicle/Personnel Monitoring Station

7848 EPICORE II STORAGE BUILDING

7849 WHITE OAK CRK WEIR & GAGING ST
Effective Date: 11/14/2003 Revision No. 00 Document No. ORAUT-TKBS-0012-2 Page 55 of 66

Attachment 2A (Continued)

Facility 

ID Description

Old 

numbering

7852 Old Hydrofracture Facility

7853 LGWOD storage building

7854 DRILLING EQUIPMENT STORAGE

7855 Concrete cask storage facility

7855A SWASA 5 EQUIPMENT TENT

7856 MVST Capacity Increase Project

7857 IWMF Monitoring Station

7858 WHITE OAK LAKE STORAGE BLDG.

7859 SAMPLE EQUIPMENT STORAGE BLDG.

7859A SAMPLE STORAGE BUILDINGS

7860 New Hydrofracture facility

7863 General Storage for 7860

7864 GAGING STATION - EAST SEEP

7865 GAGING STATION - WEST SEEP

7866 SAMPLING STATION - 7500 BRANCH

7867 WEIR - MELTON BRANCH

7868 SAMPLING STATION-WHITE OAK CK.

7869 STREAM FLOW MONITORING STA. #5

7870 RUBB STRUCTURE

7871 STREAM FLOW MONITORING STA. #3

7872 STREAM FLOW MONITORING STA. #4

7874 STORAGE BLDG. S.W. SWSA 4

7875 MONITORING STORAGE BLDG.

7876 Health Physics Office Trailer

7877 LLW Solidification Facility

7878 CH-TRU waste storage facility

7878A TEMPORARY WASTE STORAGE TENT

7878B EQUIPMENT STORAGE TENT

7879 TRU /LLLW staging storage facility

7880 WASTE PROCESSING FACILITY

7880A TRUPACT BUILDING

7880B WASTE PROCESSING FACILITY PERSONNEL BUILDING

7880C WASTE CHARACTERIZATION LABORATORY

7880D WASTE PROCESSING FACILITY CONTROL ROOM

7880E STEAM BOILER

7880F AIR COMPRESSOR

7880G SWITCHGEAR/TRANSFORMER, WASTE PROCESSING FACILITY

7880H DIESEL GENERATOR, WASTE PROCESSING FACILITY

7880I NDA TRAILER, WASYE PROCESSING FACILITY

7880J NDE TRAILER, WASTE PROCESSING FACILITY

7880K ACCESS CONTROL POINT, WASTE PROCESSING FACILITY

7880L DOE OFFICE TRAILER, WASYE PROCESSING FACILITY

7880M DOE OFFICE TRAILER, WASTE PACKAGING FACILITY

7880N CONSTRUCTION MANAGAGMENT, WASTE PACKAGING FACILITY

7880P BREAK FACILITY, WASTE PACKAGING FACILITY
Effective Date: 11/14/2003 Revision No. 00 Document No. ORAUT-TKBS-0012-2 Page 56 of 66

Attachment 2A (Continued)

Facility 

ID Description

Old 

numbering

7880Q RESTROOM FACILITY, WASTE PACKAGING FACILITY

7880R FWENC OPERATIONS TRAILER

7882 Emergency Generator for 7877

7883 CH-TRU waste storage bunker

7886 Interim waste storage pad #1

7887 SOLID LIQUID SEPARATOR

7888 CASK LOADING FACILITY

7891 SWASA OFFICE TRAILER

7892 STORAGE BUILDING, 7856 OPERATIONS

7893 PASSENGER SHELTER

7894 WAG 6 MONITORING STATION #3

7900 HIGH FLUX ISOTOPE REACTOR

7901 ELECTRICAL BUILDING FOR 7900

7902 COOLING TOWER FOR 7900

7903 7900 COOLING TOWER EQUIPMENT BUILDING

7904 SEWAGE TREATMENT PLANT - 7900

7905 RETENTION POND 1 FOR 7900

7906 RETENTION POND 2 FOR 7900

7907 TRU POND A

7908 TRU POND B

7910 RESEARCH REACTORS OFFICE BUILDING

7911 STACK FOR 7900

7911B MONITORING EQUIPMENT BLDG. FOR 7911

7911C INSTRUMENT SHED FOR 7911

7912 FAN SHED AND ELECTRICAL EQUIPMENT FOR 7900

7913 FILTER PIT FOR 7911 STACK

7914 EQUIP. & PARTS STORAGE BLDG.

7914A HFIR CARPENTRY SHOP

7915 OPERATIONS STORAGE BLDG.

7916 HFIR COOLING TOWER WATER TREATMENT

7917 RESEARCH REACTORS OFFICE BLDG.

7918 REDC OFFICE & TRAINING BUILDING

7920 RADIOCHEMICAL ENGINEERING DEVELOPMENT CENTER

7921 EMERGENCY GENERATOR FOR 7920

7922 BREECHING & FAN AREA AND ELEC EQ FOR 7920

7922A DATA CONCENTRATOR #6 FOR WOCC DAS

7923 REDC COOLING TOWER

7924 MATERIALS STORAGE TENT

7924A STORAGE BUILDING

7924B STORAGE BUILDING

7925A STORAGE BUILDING

7925B STORAGE BUILDING

7927 STORAGE TENT

7930 RADIOCHEMICAL ENGINEERING DEVLOPMENT CENTER

7930A FILTER PIT FOR 7930
Effective Date: 11/14/2003 Revision No. 00 Document No. ORAUT-TKBS-0012-2 Page 57 of 66

Attachment 2A (Continued)

Facility 

ID Description

Old 

numbering

7931 EMERGENCY GENERATOR FOR 7930

7932 WASTE SAMPLE BLDG. FOR 7930

7933 OFFICE TRAILER

7934 CH-TRU WASTE STORAGE FACILITY

7935 Equipment cleaning facility

7936 REDC STORAGE BUILDING

7939 STANDBY EMERGENCY GENERATOR FOR 7930

7947 MELTON BRANCH HEADWATER FLUME

7948 MELTON BRANCH MONITORING STATION

7949 MELTON BRANCH TRIBUTARY WEIR

7952 Melton Valley waste pump station

7953 PUMP HOUSE - HPRR WATERLINE

7953A RESEARCH REACTORS OFFICE TRAILER

7953B RESARCH REACTORS STORAGE TRAILER

7953C CONSTRUCTION TRAILER AT HFIR

7955 SENTRY POST 19B, HFIR ENTRY

7957 OFFICE TRAILER FOR 7920

7958 SENTRY POST 23, HPRR

7960 HIFR STORAGE BUILDING

7961 Melton Valley Collection Tanks

7962 NEUTRON USERS OFFICE & LAB

7964A RESEARCH REACTORS OFFICE TRAILER

7964B RESEARCH REACTORS OFFICE TRAILER

7964C RESEARCH REACTORS OFFICE TRAILER

7964D RESEARCH REACTORS OFFICE TRAILER

7964E RESEARCH REACTORS OFFICE TRAILER

7964F RESEARCH REACTORS OFFICE TRAILER

7964G HIFR OPS/CHANGE HOUSE

7964H SOLID STATE OFFICE TRAILER

7964I SOLID STATE OFFICE TRAILER

7965A CHEMICAL TECHNOLOGY OFFICE TRAILER

7965B CHEMICAL TECHNOLOGY OFFICE TRAILER

7965C CHEMICAL TECHNOLOGY OFFICE TRAILER

7966 LLW collection tank, 7920, 7930

7966A FILTER HOUSE, 7966

7967A MELTON BRANCH SUBSURFACE WEIR

7967B SUBSURFACE WEIR INSTRUMENT BUILLDING

7967C UNDERGROUND WEIR

7968 TRAILER

7969 HAZARDOUS MATERIAL ENCLOSURE

7970 NEUTRON SCIENCE SUPPORT BLDG.

7971 H.O.G. FILTER FACILITY

7975 WATER MONITORING STORAGE BLDG

7977 COLD SOURCE EQUIPMENT BLDG.

7977A COLD SOURCE LIQUID NITROGEN TANK
Effective Date: 11/14/2003 Revision No. 00 Document No. ORAUT-TKBS-0012-2 Page 58 of 66

Attachment 2A (Continued)

Facility 

ID Description

Old 

numbering

7980A HFIR STORAGE 1

7980B HFIR STORAGE 2

7980C HFIR STORAGE 3

7980D HIFR STORAGE 4

7980E HIFR STORAGE 5

7981A P&E/HFIR STORAGE 1

7981B P&E/HFIR STORAGE 2

7981C P&E/HFIR STORAGE

7982 TRU STAGING AREA STORAGE

7983 TRU FACILITY STORAGE BUILDING

7984 PASSENGER SHELTER

7985 P&E/HFIR STORAGE 4

7986 P&E/HIFR STORAGE 5

8520 RING INJECTION DUMP BUILDING

9201-2 FUSION ENERGY ADMINISTRATION & LABORATORY BUILDING

9204-1 ENGINEERING TECHNOLOGY

9204-3 ISOTOPE SEPARATIONS

9207 BIOLOGY BUILDING Y-12

9210 MAMMALIAN GENETICS Y-12

9211 CO-CARCINOGENSIS

9220 MOLECULAR BIOLOGY FACILITY

9224 MOLECULAR BIOLOGY FACILITY

9401-1 ENGINEERING TECHNOLOGY LABORATORY FACILITY

9409-15 COOLING TOWER

9422 LCTF COMPRESSOR

9610-2 FLAMMABLE BUILDING STORAGE BUILDING

9732-2 86-INCH CYCLOTRON COUNTING ROOM

9743-2 PIGEON QUARTERS Y-12

9767-6 UTILITIES - CONTROL CENTER

9767-7 FAN HOUSE FOR 9207

9770-2 RADIATION SOURCE Y-12

9983-FX ESD TRAILER

9999-01 MOTOR GENERATOR

9999-03 ELECTRICAL SWITCHGEAR AND RECTIFIER

9999-04 ELECTRICAL EQUIPMENT

9999-3 POWER SUPPLY

9999-4 ELECTRICAL EQUIPMENT

NTRC NATIONAL TRANSPORTATION RESEARCH CENTER

X185249 TRAILER-SWASA #6

X186600 TRAILER-7002 AREA
Effective Date: 11/14/2003 Revision No. 00 Document No. ORAUT-TKBS-0012-02 Page 59 of 66

ATTACHMENT 2B

MAJOR FACILITIES AND RADIONUCLIDES OF CONCERN

Current 

building 

number

Former 

building 

number

Facility name or 

description

Dates of 

operation

Principal radionuclides 

of concern

3001 105 Graphite reactor Nov. 1943 – Nov. 

1963

Mixed fission/activation 

products, natural uranium

3005 106 Low-Intensity Test 

Reactor (LITR)

1949 – Oct. 1968 Volatile fission products, 

24Na, 16N

3010 Bulk Shielding Reactor 

(BSR)/Pool Critical 

Assembly (PCA)

1951 - 1987 Volatile fission products, 24Na, 16N 

3019 205 Pilot Plant Dec., 1943 –

present 

(partly inactive and 

pending D&D)

Mixed fission/activation 

products, natural uranium, 

232Th, 233U, TRU (liquid 

forms)

3023 206 North Tank Farm 1943 - 1986 Mixed fission/activation 

products, natural uranium, 

232Th, 233U, TRU (liquid 

forms)

3026-C 706-C Radiochemistry Lab 

(original RaLa 

building); 85Kr 

enrichment facility

1944 – ca. 1997

(pending D&D)

Mixed fission products, 

131I, 85Kr (liquid and 

gaseous forms)

3026-D 706-D Radiochemistry Lab 

(RaLa building from 

May 1945 until 1958); 

Segmentation Facility

1945 - ??

(pending D&D)

Mixed fission products,

131I, 106Ru, noble gases 

(liquid and gaseous 

forms); uranics/TRU 

(segmentation facility)

3028 910 Radioisotope 

Processing Building 

A/Alpha Powder 

Facility

1950 - 1985 99Mo, 131I, 133Xe, 147Pm, 

242/244Cm

3029 909 Source Development 

Lab

1952 – late 1980s Fission/activation products

3030 908 Radioisotope 

Processing Building C

ca. 1950 – late 

1980s

Fission/activation products

3031 907 Radioisotope 

Processing Building D

ca. 1950 – late 

1980s

Fission/activation products

3032 906 Radioisotope 

Processing Building E

ca. 1950 – late 

1980s

Fission/activation products

3033 905 Radioisotope 

Processing Building F, 

Radioactive Gas 

Processing Facility

ca. 1950 – 1990 3H, 14C, 85Kr (gaseous 

forms)

3038 902 Isotope Research 

Materials 

Laboratory/Alpha 

Handling Facility

1949 - 1990 Fission/activation 

products, uranics, TRU

3042 ORNL Research 

Reactor (ORR)

March, 1958 – ca. 

1987

Volatile mixed fission 

products; 24Na, 16N

3047 Radioisotopes 

Development 

Laboratory

1962 - Fission products, 238Pu
Effective Date: 11/14/2003 Revision No. 00 Document No. ORAUT-TKBS-0012-2 Page 60 of 66

Attachment 2B (Continued)

3505 Metals Recovery 

Facility

1952 - 1960 Mixed fission products, 

uranics, TRU (liquid form)

3507 206 South Tank Farm 1943 - 1978 Mixed fission/activation 

products, natural uranium, 

232Th, 233U, TRU (liquid 

form)

3508 Alpha Isolation 

Laboratory

1952 – ca. 1976 TRU, 233U (gram 

quantities); mixed fission 

products

3515 Fission Product Pilot 

Plant (F3P)

1948 - 1958 Mixed fission products, 

uranics, TRU (liquid form)

3517 Fission Product 

Development 

Laboratory

1958 - 1975 Mixed fission products, 

uranics, TRU (liquid form)

3525 High Radiation Level 

Examination 

Laboratory

1963 – present Fission/activation products

4501 High Level 

Radiochemistry Lab

1951 – present 233U (OREX process)

4507 High-Level Chemical 

Development Facility

1957 - ??

(pending D&D)

Mixed fission products 

(liquid forms)

4508 Interim Plutonium 

Laboratory/Fuel Cycle 

Alpha Facility

1962 – present Uranics, TRU (nitride and 

oxide forms) 

7025 Tritium Target 

Preparation Facility

1967 - ??

(pending D&D)

3

H, ThO2, UO2, 90Sr, 137Cs, 

244Cm

7500 Homogeneous Reactor 

Experiment (HRE), 

Homogeneous Reactor 

Test (HRT)

1952 – April, 1961 Mixed fission/activation 

products, uranyl sulfate

7503 Molten Salt Reactor 

Experiment (MSRE)

1965 - 1969 Mixed fission products, 

232Th, 233U

7900/7920 High Flux Isotope 

Reactor/TRU Facility

1966 - present 252Cf, TRU, Dy/Ho-166, 

186Re, 117mSn, W/Re-188
Effective Date: 11/14/2003 Revision No. 00 Document No. ORAUT-TKBS-0012-02 Page 61 of 66

ATTACHMENT 2C

ORNL FACILITY MAPS
Effective Date: 11/14/2003 Revision No. 00 Document No. ORAUT-TKBS-0012-2 Page 62 of 66

Attachment 2C (Continued)
Effective Date: 11/14/2003 Revision No. 00 Document No. ORAUT-TKBS-0012-2 Page 63 of 66

Attachment 2C (Continued)
Effective Date: 11/14/2003 Revision No. 00 Document No. ORAUT-TKBS-0012-2 Page 64 of 66

Attachment 2C (Continued)
Effective Date: 11/14/2003 Revision No. 00 Document No. ORAUT-TKBS-0012-2 Page 65 of 66

Attachment 2C (Continued)
Effective Date: 11/14/2003 Revision No. 00 Document No. ORAUT-TKBS-0012-2 Page 66 of 66

Attachment 2C (Continued)