ORAU TEAM

Dose Reconstruction

Project for NIOSH

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

Page 1 of 80

Document Title:

Oak Ridge National Laboratory – Site 

Description

Document Number: ORAUT-TKBS-0012-2 

Revision: 01

Effective Date: 08/30/2006

Type of Document: TBD

Supersedes: Revision 00

Subject Expert: Kenneth Fleming

Document Owner

Approval: Signature on File Approval Date: 08/07/2006

Robert E. Burns, TBD Team Leader

Approval: Signature on File Approval Date: 08/08/2006

John M. Byrne, Task 3 Manager

Concurrence: Signature on File Concurrence Date: 08/07/2006

Edward F. Maher, Task 5 Manager

Concurrence: Signature on File Concurrence Date: 08/17/2006

Kate Kimpan, Project Director

Approval: Signature on File Approval Date: 08/30/2006

James W. Neton, Associate Director for Science

 New Total Rewrite Revision Page Change

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

REVISION AND DISCARD / DESTROY ALL COPIES OF THE PRIOR REVISION.
Document No. ORAUT-TKBS-0012-2 Revision No. 01 Effective Date: 08/30/2006 Page 2 of 80

PUBLICATION RECORD

EFFECTIVE 

DATE

REVISION

NUMBER DESCRIPTION

10/29/2003 00-A Draft Technical Basis Document for Oak Ridge National Laboratory -

Site Description. Initiated by Robert E. Burns.

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

08/30/2006 01 Constitutes a total rewrite as a result of biennial review. Approved 

issue of Revision 01. Text was revised to reflect recent construction 

and other site changes. In addition, the revision added guidance in 

Section 2.2.55 that maintenance workers should be evaluated using 

coworker data when appropriate, in response to comments received 

from the Worker Outreach Meeting with the Oak Ridge Atomic 

Trades and Labor Council on November 8, 2004. No further 

changes occurred as a result of internal formal review. Incorporates 

NIOSH formal review comments. This revision results in no change 

to the assigned dose and no PER is required. Initiated by Robert E. 

Burns.
Document No. ORAUT-TKBS-0012-2 Revision No. 01 Effective Date: 08/30/2006 Page 3 of 80

TABLE OF CONTENTS

SECTION TITLE

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

PAGE

6

2.1 Introduction ..............................................................................................................................9

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

2.1.2 Scope.........................................................................................................................10

2.2 Major Facility Descriptions ..................................................................................................... 11

2.2.1 Building 0816 Cesium Soil Test Plots.........................................................................13

2.2.2 Building 2000 (formerly 101-D) Metallurgy Laboratory................................................13

2.2.3 Building 2001 Information Center Complex ................................................................13

2.2.4 Building 2005 (formerly 706-B) Metallurgy Annex.......................................................13

2.2.5 Building 2024 Information Center Complex Annex .....................................................13

2.2.6 Building 2026 Radioactive Materials Analytical Laboratory......................................... 13

2.2.7 Building 3001 (formerly 105) Graphite Reactor Building (Clinton Pile)........................ 14

2.2.8 Building 3002 (formerly 114) Graphite Reactor Filter House....................................... 14

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

 Modification and Characterization Laboratory.............................................................14

2.2.10 Building 3004 (formerly 807) Water Demineralizer Facility ......................................... 14

2.2.11 Building 3005 (formerly 106) Low-Intensity Test Reactor............................................ 14

2.2.12 Building 3009 Bulk Shielding Facility Pumphouse ......................................................15

2.2.13 Building 3010 Bulk Shielding Reactor Facility.............................................................15

2.2.14 Building 3012 Rolling Mill ...........................................................................................15

2.2.15 Building 3018 Exhaust Stack (for Building 3003)........................................................15

2.2.16 Building 3019-A (formerly 205) Radiochemical Processing Pilot Plant........................ 15

2.2.17 Building 3019-B High Radiation Level Analytical Facility ............................................ 15

2.2.18 Building 3020 Exhaust Stack (for Building 3019)........................................................16

2.2.19 Building 3021 Fan House (Northeast of Building 3020) .............................................. 16

2.2.20 Building 3023 (formerly 206) North Tank Farm...........................................................16

2.2.21 Building 3025-E Physical Examination Hot Cells ........................................................17

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

 Processing and Chemical Separation Laboratory.......................................................17

2.2.23 Building 3027 Special Nuclear Materials Storage Vault .............................................. 17

2.2.24 Building 3028 (formerly 910) Alpha Powder Facility....................................................17

2.2.25 Building 3029 (formerly 909) Source Development Laboratory................................... 17

2.2.26 Building 3030 (formerly 908) Radioisotope Processing Building “C” ........................... 17

2.2.27 Building 3031 (formerly 907) Radioisotope Processing Building “D” ........................... 18

2.2.28 Building 3032 (formerly 906) Radioisotope Processing Building “E” ........................... 18

2.2.29 Building 3033 (formerly 905) Radioactive Gas Process Facility.................................. 18

2.2.30 Building 3033-A Actinide Fabrication Facility Annex ................................................... 18

2.2.31 Building 3034 Radioisotopes Services Building ..........................................................18

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

 Radioisotope Analytical and Packing Building ............................................................19

2.2.33 Building 3039 (formerly 911) Central Exhaust Stack (Radioisotope Area) .................. 19

2.2.34 Building 3042 Oak Ridge Research Reactor ..............................................................19

2.2.35 Building 3047 Radioisotopes Development Laboratory .............................................. 19

2.2.36 Building 3088 Bulk Shielding Reactor Facility Storage Building.................................. 19

2.2.37 Building 3093 Storage Enclosure ...............................................................................20
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2.2.38 Building 3098 Bulk Shielding Reactor Facility Filter House......................................... 20

2.2.39 Building 3099 (Building 3032) Storage Pad ................................................................20

2.2.40 Building 3101 Bulk Shielding Reactor Facility Storage ............................................... 20

2.2.41 Building 3117 Bulk Shielding Reactor Facility Cooling Tower ..................................... 20

2.2.42 Building 3118 Radioisotope Processing Building “H”.................................................. 20

2.2.43 Building 3119 Bulk Shielding Reactor Facility Heat Exchanger and 

 Pumphouse................................................................................................................20

2.2.44 Building 3504 Health Physics Waste Research Building............................................. 20

2.2.45 Building 3505 Metal Recovery Facility ........................................................................21

2.2.46 Building 3506 Waste Evaporator Facility ....................................................................21

2.2.47 Building 3507 (formerly 206) South Tank Farm ..........................................................21

2.2.48 Building 3508 Chemical Isolation Laboratory..............................................................21

2.2.49 Building 3515 Fission Product Pilot Plant ...................................................................22

2.2.50 Building 3517 Fission Products Pilot Plant ................................................................. 22

2.2.51 Building 3518 Acid Neutralization Plant ......................................................................23

2.2.52 Building 3525 High Radiological Level Examination Laboratory ................................. 23

2.2.53 Building 3544 Process Waste Treatment Facility........................................................23

2.2.54 Building 3597 Hot Storage Garden.............................................................................24

2.2.55 Building 4500 Central Research and Administration Facility....................................... 24

2.2.56 Building 4501 High Level Radiochemistry Laboratory................................................. 24

2.2.57 Building 4507 High Level Chemical Development Facility .......................................... 25

2.2.58 Building 4508 Metals and Ceramics Laboratory .........................................................25

2.2.59 Building 5505 Transuranium Research Laboratory.....................................................25

2.2.60 Building 6000 Holifield Radioactive Ion Beam Facility ................................................26

2.2.61 Building 6010 Oak Ridge Electron Linear Accelerator ................................................26

2.2.62 Building 7025 Tritium Target Facility...........................................................................26

2.2.63 Building 7500 Homogeneous Reactor Experiment Reactor Building .......................... 26

2.2.64 Building 7503 Molten Salt Reactor Experiment...........................................................26

2.2.65 Building 7602 Integrated Process Demonstration Facility........................................... 27

2.2.66 Building 7700 Tower Shielding Facility .......................................................................27

2.2.67 Building 7735 Dosimetry Applications Research Calibration Laboratory..................... 27

2.2.68 Buildings 7806, 7807, 7808, 7809, and 7810 Waste Pits and Trenches ..................... 28

2.2.69 Building 7852 Old Hydrofracture Facility.....................................................................28

2.2.70 Building 7900 High Flux Isotopes Reactor..................................................................28

2.2.71 Building 7920 Transuranic Processing Facility ...........................................................28

2.2.72 Building 7930 Thorium Uranium Recycle Facility (TURF)........................................... 29

2.2.73 Building 9204-3 Actinide Area (Electromagnetic Isotope Separation at 

 Y-12)..........................................................................................................................29

2.2.74 Solid Waste Storage Areas ........................................................................................29

2.3 ORNL Site Operations and Processes ................................................................................... 30

2.3.1 Early Operation of Graphite Reactor and Associated Facilities................................... 30

2.3.2 Radioactive Lanthanum Activities...............................................................................34

2.3.3 Isotope Production Areas ...........................................................................................35

2.3.4 Waste Areas and Processes ......................................................................................38

2.3.5 ORNL Facilities at the Y-12 National Nuclear Security Complex ................................ 40

2.3.6 Other Reactor Development and Operations..............................................................41

 2.3.6.1 Low-Intensity Test Reactor .......................................................................... 42

2.3.6.2 Critical Experiments Facility......................................................................... 42

2.3.6.3 Bulk Shielding Reactor/Pool Critical Assembly............................................. 43

2.3.6.4 Oak Ridge Research Reactor ...................................................................... 43
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2.3.6.5 Tower Shielding Facility ............................................................................... 44

2.3.6.6 Health Physics Research Reactor................................................................ 45

2.3.6.7 Homogeneous Reactor Experiment ............................................................. 45

2.3.6.8 Aircraft Nuclear Propulsion Experiment........................................................ 45

2.3.6.9 High Flux Isotope Reactor............................................................................ 45

2.3.6.10 Molten Salt Reactor Experiment .................................................................. 46

2.3.6.11 Spallation Neutron Source ........................................................................... 46

References ........................................................................................................................................47

Glossary ............................................................................................................................................52

ATTACHMENT 2A, OAK RIDGE NATIONAL LABORATORY FACILITY INDEX ............................... 53

ATTACHMENT 2B, FACILITY MAPS ................................................................................................73

ATTACHMENT 2C, MAJOR FACILITIES AND RADIONUCLIDES OF CONCERN ........................... 80

LIST OF TABLES

TABLE TITLE

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

PAGE

11

2-2 North Tank Farm contents...................................................................................................... 16

2-3 South Tank Farm contents..................................................................................................... 22

2-4 Sealed sources available at DOSAR Calibration Laboratory (Building 7735) ......................... 27

2-5 Radioisotopes of concern in isotope production facilities........................................................ 36

2-6 Radiation sources in Biological Sciences Division at Y-12...................................................... 41
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ACRONYMS AND ABBREVIATIONS

AEC U.S. Atomic Energy Commission

AHF Alpha Handling Facility

amu atomic mass unit

ANP aircraft nuclear propulsion

Bq Becquerel

BSR Bulk Shielding Reactor

CEF Critical Experiments Facility

cfm cubic feet per minute

Ci curie

cm centimeter

CRF Curium Recovery Facility 

d day

DOE U.S. Department of Energy

DOSAR Dosimetry Applications Research

EEOICPA Energy Employees Occupational Illness Compensation Program Act

FCAF Fuel Cycle Alpha Facility

ft foot

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

g gram

gal gallon

GCR gas-cooled reactor

HEPA high-efficiency particulate air

HFIR High Flux Isotope Reactor

HP health physics

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

lb pound

LITR Low-Intensity Test Reactor

LLLW low-level liquid waste

LLW low-level waste

m meter
Document No. ORAUT-TKBS-0012-2 Revision No. 01 Effective Date: 08/30/2006 Page 7 of 80

MED Manhattan Engineering District

MeV megaelectron-volt

mg milligram

mi mile

min minute

mL milliliter

mph miles per hour

mR milliroentgen

mrad millirad

mrem millirem

MSRE Molten Salt Reactor Experiment

MTR Materials Test Reactor

MV megavolt

MW megawatt

NIOSH National Institute for Occupational Safety and Health

NOAA National Oceanic and Atmospheric Administration

OGR Oak Ridge Graphite Reactor

ORELA Oak Ridge Electron Linear Accelerator

ORNL Oak Ridge National Laboratory

ORR ORNL Research Reactor or Oak Ridge Research Reactor

PCA Pool Critical Assembly

ppm parts per million

PUREX plutonium-uranium extraction

R roentgen

R&D research and development

RaLa radioactive lanthanum

REDC Radiochemical Engineering Development Center

REDOX reduction-oxidation

s second

SLLW solid low-level waste

SNAP Systems for Nuclear Auxiliary Power

SNS Spallation Neutron Source

SWSA Solid Waste Storage Area

TBP tributylphosphate

THOREX thorium extraction

TRU transuranic

TSF Tower Shielding Facility

TSR Tower Shielding Reactor

TURF Thorium Uranium Recycle Facility

U.S.C. United States Code

UCC Union Carbide Corporation

WAG Waste Area Grouping

WEF Waste Evaporator Facility
Document No. ORAUT-TKBS-0012-2 Revision No. 01 Effective Date: 08/30/2006 Page 8 of 80

WOCC Waste Operations Control Center

X-10 Oak Ridge National Laboratory

Y-12 Y-12 National Nuclear Security Complex

μCi microcurie

§ section
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2.1 INTRODUCTION

2.1.1

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

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

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

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

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

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

Purpose

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

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

employer facility” or a “Department of Energy [DOE] facility” as defined in the Energy Employees 

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

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

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

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

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

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

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

facility encompassed by EEOICPA.

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

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

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

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

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

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

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

determined in accordance with the POC [probability of causation1

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

premises, grounds, or operations covered by Executive Order No. 12344, dated February 1, 1982 (42 

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

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

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

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

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

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

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

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

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

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

derived:

] guidelines established under 

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

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

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

 

1 The U.S. Department of Labor is ultimately responsible under the EEOICPA for determining the POC. 
Document No. ORAUT-TKBS-0012-2 Revision No. 01 Effective Date: 08/30/2006 Page 10 of 80

• Radiation from naturally occurring radon present in conventional structures

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

2.1.2

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

to conduct research and development (R&D) and production missions in support of DOE and its 

predecessor agencies. (ORNL has also been known as X-10, Clinton Laboratories, and, briefly, 

Holifield National Laboratory.) Much of the earliest site work was devoted to the development and 

operation of the original plutonium production reactor and associated chemical separation facility to 

test the larger production reactors that were being built on the Hanford Site. The Graphite Reactor 

produced gram quantities of plutonium and later fission products [e.g., radioactive lanthanum (RaLa)]; 

other types of radioactive materials were separated in other site facilities. Waste control technologies 

during early site 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 exposures was progressing along with new technologies being 

discovered in radioisotope production. Much of the 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. Methods were later 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 immediate area and created locations in which 

incidents and spills occurred.

Scope

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

decontaminated, and decommissioned based on need. Many buildings that remain standing in the 

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

Attachment 2A lists buildings under the current numbering system along with applicable earlier

numbers.

Major historic operations and processes at ORNL include:

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

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

thorium from irradiated fuel

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

at Los Alamos National Laboratory

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

government and commercial use

In addition, ORNL developed new reactor technologies. The Laboratory tested different reactor 

designs (pool, pressurized-water, boiling-water, liquid-metal, gas-cooled) that were either scrapped or 

developed further elsewhere. Reactors operated at 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), Oak Ridge 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).
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In 1947, several ORNL divisions moved to Y-12. These divisions conducted research in biological 

sciences, the production of stable isotopes in the calutron units, and engineering technology.

2.2 MAJOR FACILITY DESCRIPTIONS

DOE and other agencies have used ORNL to test new ideas. Many of the earliest buildings changed

through various mission objectives. For example, Building 3019 was the original pilot plant facility for

separating plutonium from irradiated uranium slugs from the Graphite Reactor. The original bismuthphosphate separation process was inefficient and created a lot of waste. Subsequent chemical 

separations processes in Building 3019 better refined the dissolved material, leaving less final product 

in the waste stream.

DOE owns most of the land and facilities at ORNL. [Since the last revision of this document, several 

buildings have been constructed in the eastern portion of the main campus area with private, State of 

Tennessee, and Federal funding. These include the Laboratory for Comparative and Functional 

Genomics, the Center for Nanophase Materials Sciences, the Advanced Microscopy Laboratory, and 

the joint institutes for computational sciences, biological sciences, and neutron sciences. The 

Spallation Neutron Source (SNS) is under construction on Chestnut Ridge, north of the main campus 

with an estimated completion date in 2006.] 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 Oak Ridge National Laboratory. 

Period Operated by Name

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

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

1/1/1947 – 2/28/1948 AEC Clinton Laboratories

3/4/1948 Carbide & Carbon Chemicals Company, UCC 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 UCC, Nuclear Division Holifield National Laboratory

1976 – 3/31/1984 UCC, 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 site in Bethel Valley 

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

buildings have joint private funding sources, and are occupied by non-DOE contractors. Although 

maintenance is the responsibility of the owner, the individuals in the facilities in the ORNL Site 

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

internal dosimetry program as necessary.

The original building identification numbers from the 1940s were different from those in use today. At 

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

building numbering nomenclature 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.
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• 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.

• Numbers 2500 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 

location of the East Vehicle Gate (demolished in 2004).

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

location of the East Vehicle Gate.

• Numbers 5000 to 5499 are north of Central Avenue, east of the location of the East Vehicle 

Gate, and west of Main Entrance Drive.

• Numbers 5500 to 5999 are south of Central Avenue, east of the location of the East Vehicle 

Gate, and west of the Swan Pond.

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

north of Haw Ridge.

• 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 9000 numbers. 

(The UT-Battelle team has begun reducing the number of facilities for which they are 

responsible on the Y-12 site.)

Attachment 2B contains maps of the main ORNL campus and subareas.

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

Laboratory Building List, indicated a cross-linking from the old and new building numbering 

nomenclature at that time (ORNL 1953). The Directorate provided a current ORNL building list for all 

facilities at the site (Parr et al. 2002). Attachment 2A contains the combined list.

The remainder of this section provides information on specific facilities for which information was 

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

following sections are summarized in Attachment 2C. Section 2.3 provides information on ORNL 

processes and programs.
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2.2.1

The 5-acre fenced 0816 site is part of the 0800 Environmental Research Area, an approximately 

50-acre, fescue-dominated field 330 ft north of the Clinch River at Clinch River Mile 20.5 (Tiner and 

Uziel 1994). The study area is about 1.3 mi south of the intersection of Bethel Valley Road and State 

Highway 95. A weapons fallout field study using 137Cs fused at high temperatures to silica sand 

particles (100 μCi/g) began in August 1968 using eight 33-ft-by-33-ft soil treatment plots. Four plots

were contaminated with about 2.2 Ci each and the other four were used as controls. The particles 

ranged in size from 88 μm to 177 μm in diameter and were spread over the plots to achieve an areal 

density of 72 g/m2

. A surface radiological investigation was conducted intermittently from July through 

September 1994 (Tiner and Uziel 1994). The highest exposure rate measurement documented in the 

report was 0.86 mR/hr. One soil sample indicated 9,000 ±400 pCi/g (dry wt.).

Building 0816 Cesium Soil Test Plots

2.2.2

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

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

enriched uranium. Facilities in the building included metal casting and fabrication equipment; 

laboratories for testing mechanical, chemical, and physical properties of uranium and fuel elements; 

and office space. The building had 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 LITR (LMERC 1997).

Building 2000 (formerly 101-D) Metallurgy Laboratory

2.2.3

During the 1950s, this building was used as the “main health physics facility.” In the latter part of the 

1950s, the Health Physics Division (including the Applied Health Physics, Dosimetry, and Radiation 

Physics groups) moved to Building 4500S (Auerbach 1992). The Ecology Group remained in 

Building 2001. 

Building 2001 Information Center Complex

2.2.4

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 in the building for compatibility with reactor materials in thermally driven test 

loops.

Building 2005 (formerly 706-B) Metallurgy Annex

2.2.5

Building 2024 (10,300 ft2

) was added between Buildings 2000 and 2001 to provide additional office 

and laboratory space to support early radiological operations in Building 2000 (LMERC 1997).

Building 2024 Information Center Complex Annex

2.2.6

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

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

The building has 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). It houses facilities designed to segregate low and high levels of radioactivity. In addition, it

Building 2026 Radioactive Materials Analytical Laboratory
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includes a radioactive liquid waste system that meets current regulatory requirements. It is equipped 

to handle the packaging and disposal of radioactive solid waste (Van Hoesen and Vogel 2001).

A personnel contamination incident occurred in Building 2026 on October 6, 2003, when a waste drain 

overflowed due to a clogged line. 

2.2.7

Section 2.3.1 describes the Graphite Reactor. 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 system resulted in the chronic release of 41Ar from 

the Building 3018 stack when the reactor was operating. In 1948, 41Ar releases totaled 540 Ci/d at 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)

2.2.8

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). Its purpose 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, which was constructed in 1948, operated until 1963.

Building 3002 (formerly 114) Graphite Reactor Filter House

2.2.9

The Graphite Reactor Fan House provided negative pressure and served as a passageway for filtered 

exhaust from the Graphite Reactor air filter building to the stack (Building 3018). It was in operation 

from 1948 to 1963. Information on operations at the Characterization Laboratory was not located.

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

and Characterization Laboratory

2.2.10

The Water Demineralizer Facility no longer exists, but was identified in an early building listing. 

Building 3004 supported operations for the LITR, but water from this facility apparently was also used 

in the Bulk Shielding Reactor pool (Rupp and Cox 1955). It was a four-story, wooden-framed building 

with wooden siding and approximately 1,600 ft2 of floor space (DOE 1996a). It provided 

demineralized water directly to Buildings 3001, 3002, 3010, and 3042, and by tanker truck to Building 

7702 at the Tower Shielding Facility (TSF). The original Water Treatment System was replaced by a 

mixed resin bed system and associated process equipment. The treatment equipment was on the 

first floor; treated water was pumped to a 10,000-gal holding tank on the fourth floor. Though there 

were no radiological operations in the building, low levels of residual radioactivity reportedly existed as 

a result of historical activities unrelated to water demineralization (DOE 1996a).

Building 3004 (formerly 807) Water Demineralizer Facility

2.2.11

The LITR facility consists of three buildings: the Low-Intensity Test Reactor Building (3005), the 

Water Demineralizer Facility (3004), and the Low-Intensity Test Reactor Water-to-Air Heat Exchanger 

(3077). The LITR consists of five cylindrical steel and aluminum tank sections with all but the lowest 

section above ground. It measures 70 ft by 62 ft by 57 ft. The LITR facility is northeast of the 

Graphite Reactor (Building 3001). Section 2.3.6.1 describes the LITR facility further.

Building 3005 (formerly 106) Low-Intensity Test Reactor
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2.2.12

Building 3009 consists of a single-story, single-room concrete block structure with about 156 ft2 of 

floor space. It is adjacent to the southwest side of the Bulk Shielding Reactor (Building 3010) below 

grade level (DOE 1996a). The only exposed exterior surface of the building is the west wall adjacent 

to the stairwell. The building originally supported the cooling system of the reactor bay pool in 

Building 3010. Though there were no radiological operations in the building, low levels of residual 

radioactivity reportedly exist under paint because of historical activities unrelated to pumping 

operations.

Building 3009 Bulk Shielding Facility Pumphouse

2.2.13

The BSR is a two-story, steel-frame building with corrugated metal siding, a footprint of approximately 

4,000 ft2

, and a total floor area of about 8,700 ft2. It was constructed in 1951, and operations ended in 

1987. The pool has internal dimensions of 40 ft by 20 ft. In addition to the pool, the building contains 

offices, instrument rooms, experiment rooms, and a small shop. Buildings 3004, 3009, 3088, 3098, 

3101, 3117, and 3119 were directly associated with the operation of the BSR. Section 2.3.6.3 

describes the BSR further.

Building 3010 Bulk Shielding Reactor Facility

2.2.14

Building 3012 was constructed in 1947 to fabricate MTR-type fuel plates. The building contained 

melting and casting, furnacing, and multipurpose rolling equipment. It provided fuel assemblies for 

several pool-type research reactors and conducted workability studies on tantalum, beryllium, and 

other metals (LMERC 1997). Before the rolling mill became available, preliminary work on MTR 

plates occurred in an annex to the Graphite Reactor (Building 3001).

Building 3012 Rolling Mill

2.2.15

Building 3018 is a 200-ft stack of steel-reinforced concrete used from 1943 until 1963 to vent exhaust 

from the Graphite Reactor. Section 2.3.1 describes the Graphite Reactor further.

Building 3018 Exhaust Stack (for Building 3003)

2.2.16

Building 3019-A was the original building that contained reprocessing cells and equipment to 

chemically dissolve irradiated fuel slugs and separate plutonium from solution. Irradiated slugs were 

received in Cell 1 on the east end of the building through an underwater canal from Building 3001, the 

Graphite Reactor. In Cell 1, a large tank was used to dissolve the cladding and slugs; the following 

four cells were designed for the large stainless-steel tanks, centrifuges, and piping needed for the 

successive oxidation-reduction cycles (Brooksbank, Patton, and Krichinsky 1994). The last cell was a 

spare for storing contaminated equipment. Section 2.3.1 describes several of the more important 

operations that occurred in Building 3019. After World War II, isotope production campaigns for 131I, 

32P, and 14C were conducted in the building’s hot cells (MMES 1994). 

Building 3019-A (formerly 205) Radiochemical Processing Pilot Plant

2.2.17

Building 3019-B is a concrete and masonry block building constructed in 1955 for separating, 

processing, and analyzing highly radioactive samples from ORNL programs, including those in 

Building 3019-A (LMES 1997a). It is physically attached to the west end of Building 3019-A. The 

samples handled in Building 3019-B included fission products, activation products, uranium, 

plutonium, and other transuranic (TRU) elements. From 1955 to 1958, the building primarily 

Building 3019-B High Radiation Level Analytical Facility
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supported the Thorium Extraction (THOREX) Program. [A remote sample withdrawal system was 

developed for the process system to decrease radiation exposure to operators and analytical 

chemists (MMES 1994).] From 1958 to 1960, analytical capabilities in the building supported 

programs from several ORNL divisions. These included the development of the Plutonium-Uranium 

Extraction (PUREX) Process and the development of the MTR. From 1960 through 1964, the building 

supported the Fluoride Volatility and Kilorod Programs. The Fluoride Volatility Process involved 

dissolving uranium in a fused fluoride bath by hydrofluorination and volatilizing it by fluorination. The 

Kilorod Program involved the preparation of about 1,000 Zircaloy-clad fuel rods containing 3% 233UO2

and 97% ThO2 to obtain information on radiation levels and personnel exposures. Many operations in 

Building 3019-B were transferred to Building 2026 in 1964, and the building was used only 

sporadically until 1976. In 1985, it was identified as a surplus contaminated facility.

The building area is more than 3,000 ft2

; the building contains a hot cell bank with seven work cells 

equipped with manipulators and a central storage cell. To the east of the cell bank is the operating 

room (Room 15), location of cell viewing windows and manipulator controls. To the west of the cell 

bank is the cell charging area (Room 14), which was a staging area for large items moving in or out of 

cells. A loading dock on the west end of the building was used to load and unload carriers and other 

equipment. Personnel external exposure averaged 30 mrem/wk during processing of short-lived 

isotopes (MMES 1994).

2.2.18

Building 3020 was initially used to exhaust Building 3019. The exhausts were later directed to the 

Building 3039 stack.

Building 3020 Exhaust Stack (for Building 3019)

2.2.19

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)

2.2.20

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

intersection of Central and Third Streets. It contained eight underground tanks (four gunite and four 

stainless steel) to accept wastes generated from chemical separations operations. Section 2.3 

describes the North Tank Farm further. Table 2-2 lists radioisotopes that could occur in the tanks.

Building 3023 (formerly 206) North Tank Farm

Table 2-2. North Tank Farm contents. 

Tank

Years of 

operation Radioisotopes of concern

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

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

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

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

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

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

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

W-15 1943 – 1958 Pu-238,239, Sr-90, Cs-137, Co-60, and H-3
Document No. ORAUT-TKBS-0012-2 Revision No. 01 Effective Date: 08/30/2006 Page 17 of 80

2.2.21

Building 3025-E, which was built in 1950, is 70% to 80% utilized. The literature indicates that this

facility handled more radioactive material in the early years and smaller quantities as the years 

progressed. 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 Low-Level Liquid Waste 

(LLLW) System was completed in 1998 (Van Hoesen and Vogel 2001).

Building 3025-E Physical Examination Hot Cells

2.2.22

The chemical separations facilities in Buildings 3026-C and –D processed 1-Ci to 100-Ci amounts of 

RaLa. However, it processed quantities of radioactivity much larger than those for which they were 

designed. After RaLa operations ended in 1956, operational areas in each facility were used for other 

operations. Section 2.3.2 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, 106Ru/Rh, 107Pd, 

147Pm, 137Cs, 140Ba/La, 90Sr, 85Kr, 188W, 191Os, 133Xe, actinides, uranium, 99Tc, 60Co, plutonium, and 3

H.

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

Chemical Separation Laboratory

2.2.23

The Special Nuclear Materials Storage Vault was built in 1980. It is used for storage of Security 

Category III radioactive materials. No material processing occurs in the building and two sealed 

barriers contain special nuclear materials at all times. The materials in the vault are inspected weekly. 

The building contains eight rooms and has an 18-in. concrete slab floor, reinforced 18-in. thick 

concrete walls, and a 10-in. reinforced concrete roof. It was designed to withstand 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 (Van Hoesen and Vogel 

2001).

Building 3027 Special Nuclear Materials Storage Vault

2.2.24

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

separation facility for 147Pm (LMES 1997b). It is on the northwest corner of Isotope Circle adjacent to 

the 3039 stack. The building is a four-story, steel-frame structure covered by aluminum siding; it has 

a four-story central section with one-story cell operation areas on the east and west sides. The first 

floor covers 4,000 ft2 and has seven cells in which various processes took place. The three upper 

levels contain laboratories for isotope and target fabrication production. Section 2.3.3 further 

describes Building 3028.

Building 3028 (formerly 910) Alpha Powder Facility

2.2.25

Building 3029, which was constructed in 1952 to support the Isotopes Program (LMES 1997c), is in 

the west-central area of Isotope Circle. It is a single-story, steel-frame structure covered by 

corrugated aluminum siding. It has a floor area of 3,000 ft2 and four cells where various processes 

took place. Section 2.3.3 further describes Building 3029. 

Building 3029 (formerly 909) Source Development Laboratory

2.2.26

Building 3030 was constructed in 1950 for the production and development of radioisotopes for use in 

industry, medicine, and research (LMES 1997d). It is a single-story, steel-frame structure covered by 

Building 3030 (formerly 908) Radioisotope Processing Building “C”
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corrugated aluminum siding. It has a floor area of 825 ft2, a manipulator-type hot cell on the middle of 

the east wall, two laboratory hoods in the northeast corner and center of the north wall, and a 

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

sides. All high-level work was conducted there. Section 2.3.3 describes Building 3030 further.

2.2.27

Building 3031 was constructed in 1950 for the production and development of radioisotopes for use in 

industry, medicine, and research (LMES 1997e). It is a single-story, steel-frame structure with a floor 

area of 825 ft2

, a manipulator-type hot cell, and two laboratory-type hoods in the northeast and 

northwest corners. The hot cell has 2-ft-thick barites concrete and 5 in. of steel armor plate. All highlevel work was conducted there. Section 2.3.3 describes Building 3031 further.

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

2.2.28

Building 3032 was constructed in 1950 to house the analytical facility for radiochemical support of 

Isotopes Production activities (LMES 1997f). It is a single-story, steel-frame structure covered by 

corrugated aluminum siding. It contains a laboratory with five hoods on the north side of the building 

and an office on the south side connected by an open passageway. No high-level work was 

conducted in this building, which operates at atmospheric pressure. Section 2.3.3 further describes 

Building 3032. 

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

2.2.29

Building 3033 was used to process 14C, 85Kr, and 3

H (LMES 1997g). Although the building 

construction date was not verified from site documentation, it apparently was constructed in 1950 

because both adjoining buildings (3032 and 3034) were constructed in 1950. It is a steel-frame 

structure covered with corrugated aluminum siding with about 1,200 ft2

 of floor space. The outer 

surface of the building was sealed by a “cocooning” process to make it as airtight as possible. 

Personnel and equipment entrances are gasketed. Three internal structures that enclosed/contained 

the equipment used to separate gaseous isotopes were in the building. Section 2.3.3 describes 

Building 3033 further.

Building 3033 (formerly 905) Radioactive Gas Process Facility

2.2.30

Building 3033-A is a metal structure with 242 ft2 of floor space constructed about 1960 by bridging the 

space between Buildings 3033 and 3034 and using their walls for support (LMES 1997g). The 

building was used primarily to house and contain facilities for the production, loading, welding, and 

decontamination of neutron dosimeter materials. It also housed operations to weigh milligram to gram 

quantities of actinide materials for research. In addition, a small area at the south end of the building 

was used to prepare 14C as barium carbonate from beryllium nitride targets which had been irradiated 

at Hanford (ORNL 1986). Personnel access is through gasketed airlock entries. Section 2.3.3 

describes Building 3033-A further. 

Building 3033-A Actinide Fabrication Facility Annex

2.2.31

Building 3034 houses the central electrical distribution station for the Isotopes Circle Area. It is a 

steel-frame structure covered with corrugated aluminum siding with about 825 ft2 of floor space. It 

was used as a field shop for the Plant and Equipment Division, served as a storage area and drop 

point for supplies for the isotope area, and has offices for the Maintenance Coordinator and the 

Building 3034 Radioisotopes Services Building
Document No. ORAUT-TKBS-0012-2 Revision No. 01 Effective Date: 08/30/2006 Page 19 of 80

Surveillance and Maintenance Supervisor for the area. No handling of radioactive materials occurred 

in this building. 

2.2.32

Building 3038, which has been in operation since 1949, was constructed to house all ORNL 

radioisotope shipping activities. It is a masonry structure divided into three sections by concrete brick 

interior walls. There is 7,250 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

2.2.33

The 3039 Stack Ventilation System, which was 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 Stack Ventilation System consists of seven collection systems, 

each with its own under- or above-ground ducting, fans, and controls. Five handle cell ventilation 

waste streams from limited-access areas and hot cells. The other two systems handle the off-gas 

from process equipment and laboratory experiments (Parr et al. 2002). Section 2.3.4 further 

describes the Central Exhaust Stack.

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

2.2.34

Building 3042, which was built to house the ORR, covers approximately 11,000 ft2

. It is a semiairtight, 

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 Oak Ridge Research Reactor

2.2.35

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

concrete block exterior and interior walls. It houses the Radioisotopes Development Laboratory and 

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. It is used for R&D and to 

produce radioisotopes. Radioactive materials handled include 90Sr (up to 100,000 Ci), with single 

sealed sources of 90Sr up to 350,000 Ci. Other radionuclides include 137Cs, 152,154Eu, 238Pu, 111mSn, 

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

Building 3047 Radioisotopes Development Laboratory

The facility was used for research, development, and production of radioisotopes. Past processing 

cannot be described specifically because of frequent changes not only in processes but also in 

materials, operation procedures and parameters, and program requirements. Special safety 

summaries and approved procedures were required for each new experiment and operation. Before 

an operation could begin, all pertinent paperwork had to be reviewed and approved. If a potential 

hazard was identified, additional reviews and approval were needed.

2.2.36

Building 3088 is a small (approximately 129 ft2 of floor space), single-story, single-room, steel-framed 

building with metal siding north of the BSR (DOE 1996a). It was reportedly used for general storage 

of equipment and miscellaneous materials during BSR operations. 

Building 3088 Bulk Shielding Reactor Facility Storage Building
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2.2.37

Building 3093 is a permanent krypton storage enclosure adjacent to Building 3033. It is a roofless, 

reinforced-concrete enclosure containing four charcoal-filled storage tanks. Although the tanks are 

now empty, irretrievable amounts of krypton remain absorbed in their charcoal linings (DOE 1996b).

Building 3093 Storage Enclosure

2.2.38

Building 3098 is a small (150 to 250 ft2 of floor space) single-story, single-room concrete structure 

housing HEPA filters for the BSR and ORR ventilation systems (DOE 1996a). It was constructed into 

the side of a hill about 200 yards south of the BSR, apparently for shielding purposes. Air from the 

BSR reactor bay exhausted through filters before discharge to the atmosphere through the Central 

Exhaust Stack (Building 3039).

Building 3098 Bulk Shielding Reactor Facility Filter House

2.2.39

Building 3099 is a concrete storage pad adjacent to the west side of Building 3032. It has been used 

for temporary storage of items including containerized radioactive materials and wastes.

Building 3099 (Building 3032) Storage Pad

2.2.40

Building 3101 is a small, single-story building west of the BSR with about 200 ft2 of floor space (DOE 

1996a). Half of this area was a storage room and the other half was a covered concrete pad storage 

area. It was used for storage of miscellaneous materials and equipment for BSR activities.

Building 3101 Bulk Shielding Reactor Facility Storage

2.2.41

Building 3117 is a small, single-story, wood-framed cooling tower east of the BSR (DOE 1996a). At 

present, it provides cooling water to BSR air conditioning units.

Building 3117 Bulk Shielding Reactor Facility Cooling Tower

2.2.42

Building 3118 was constructed in the early 1960s to enclose the space between Buildings 3030 and 

3031 and provide direct access through rear doors to the hot cells in each facility. In addition, it

provided general storage space, forklift charging and storage, temporary storage for hazardous and 

radiological waste, radiological shielding materials, and casks. The steel-frame structure is covered 

with corrugated aluminum siding.

Building 3118 Radioisotope Processing Building “H”

2.2.43

Building 3119 is a small, single-room, concrete-block structure with an approximately 667-ft2 footprint 

east of the BSR (DOE 1996a). It was used to support the BSR bay pool cooling system.

Building 3119 Bulk Shielding Reactor Facility Heat Exchanger and Pumphouse

2.2.44

Construction of Building 3504 was completed in 1951. This building housed large-scale laboratory 

investigations into waste disposal. Specifically, studies were conducted of methods to remove fission 

products from water prior to releasing it to the environment. This facility was sometimes referred to as 

the Waste Disposal Laboratory. 

Building 3504 Health Physics Waste Research Building
Document No. ORAUT-TKBS-0012-2 Revision No. 01 Effective Date: 08/30/2006 Page 21 of 80

2.2.45

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 using the PUREX process (Mostella 

1994). It was a two-story, steel-frame metal siding structure with numerous windows. It contained 

seven aboveground, high-density, reinforced concrete or concrete-block process cells (A through G), 

a canal, a dissolver room, and a dissolver pit. The building was used to recover uranium, plutonium, 

neptunium, and americium from waste solutions, scrap, and fuel elements. Its maximum capacity was 

450 kg of irradiated uranium per day, reached during processing of natural uranium fuel elements 

(MMES 1994). The basic design philosophy was that the equipment would be remotely operated and

directly maintained. Vulnerable pieces of equipment that would require frequent maintenance were 

“unit shielded” with lead to minimize personnel exposure. The exposure of maintenance personnel to 

radioactivity in 7 years of operation averaged 60 mrem/week (MMES 1994). Twenty-five processing 

campaigns were run through the facility, which was shut down and abandoned in 1960 due to lack of 

secondary containment (Mandry and Grisham 1994). The building apparently had no HEPA-filtered 

ventilation until the early 1980s (Mandry and Grisham 1994).

Building 3505 Metal Recovery Facility

2.2.46

Building 3506, the old Waste Evaporator Facility (WEF), which was constructed in 1949, housed the 

first liquid waste evaporator at ORNL (ATG 1996). The WEF received LLLW from laboratories and 

isotope processing areas for concentration. After the LLLW was processed, the condensate was 

transferred to the Process Waste System. The WEF was replaced by Building 2531 and later used as 

an experimental radioactive waste incinerator and an experimental facility for separating rare earth 

elements. In the 1980s, it was used as a changing room for personnel working in the North and South 

Tank Farm areas.

Building 3506 Waste Evaporator Facility

Building 3506 is approximately 32 ft by 23 ft and consists of three main areas: north cell, south cell, 

and main gallery. The north and south cells had concrete walls that were 2 ft and 3 ft thick, 

respectively, and extended to a below-grade depth of 6 ft. The concrete wall that separated the north 

and south cells was removed to produce a single cell area. The building originally included a second 

floor that provided access to the cells. The second floor and interior stairs leading into the cells were 

removed, but it is not clear when this occurred.

2.2.47

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

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

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

underground stainless-steel tanks. The tanks accepted wastes generated from chemical separations 

operations. Section 2.3.4 describes the South Tank Farm further. Table 2-3 lists radioisotopes that 

might have been present in the South Tank Farm tanks. 

Building 3507 (formerly 206) South Tank Farm

2.2.48

Building 3508 housed chemical separations operations to purify materials initially processed 

(extracted) in recovery operations in Building 3505. For instance, solvent extraction processes in 

Building 3505 would be followed by ion exchange procedures in Building 3508 to clean up separation 

products. Separations research, such as experiments in removing plutonium from uranyl sulfate 

solutions in support of the Homogeneous Reactor Experiment Program, was conducted in 1957.

Building 3508 Chemical Isolation Laboratory
Document No. ORAUT-TKBS-0012-2 Revision No. 01 Effective Date: 08/30/2006 Page 22 of 80

Table 2-3. South Tank Farm contents. 

Tank

Years of 

operation Radioisotopes of concern

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

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

and Cf-252

W-7 1943 – 1978 U-233, U-235, H-3, Co-60, Sr-90, Th-232, Pu-238/239, Cm-244,

Eu-152/154, and Cf-252

W-8 1943 – 1978 U-233, U-235, H-3, Co-60, Sr-90, Am-241, Pu-238/239, Cm-244,

Eu-152/154, and Cf-252 

W-9 1943 – 1978 U-233, U-235, H-3, Co-60, Sr-90, Am-241, Pu-238/239, Cm-244,

Eu-152/154, and Cf-252

W-10 1943 – 1978 U-233, U-235, H-3, Co-60, Sr-90, Am-241, Pu-238/239, Cm-244,

Eu-152/154, and Cf-252 

2.2.49

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

1948. The facility initially consisted of several tanks and associated equipment on a concrete pad 

(Mandry and Snedaker 1994). A concrete block wall was the only shielding. A canvas tent was later 

placed over the equipment. In 1952, the block wall was replaced with a 1.5-ft-thick poured concrete 

wall, and a 1-ft-thick concrete ceiling was added. A control room originally on the east side of the 

structure was moved to the southern end in 1952. The south cell was added in 1952, as was more 

shielding. 

Building 3515 Fission Product Pilot Plant

Operations in Building 3515 included extracting radioisotopes from waste liquids from on- and offsite 

activities. The predominant elements included ruthenium, strontium, cesium, and cerium. Operations 

in the building ended in 1958. Section 2.3.1 further describes Building 3515.

2.2.50

Building 3517 is a two-story, concrete-block structure with about 14,400 ft2 of floor space. It was 

completed in 1958. The operating area consisted of nine process cells, ten manipulator and service 

cells, four tank farm cells, a ventilation filter pit, filtration housings, and several service/pipe tunnels. 

The tank farm cells and service tunnels are underground adjacent to the northwest corner of the 

facility. Two cell ventilation facilities (Buildings 3547 and 3548) and a storage building (Building 3542) 

are associated with Building 3517 (DOE 1996b). This facility is also known as the Fission Products 

Development Laboratory (FPDL). 

Building 3517 Fission Products Pilot Plant

The FPDL was originally designed and constructed to separate kilocurie quantities of 137Cs, 90Sr, 

144Ce, and 147Pm from REDOX- and PUREX-type (liquid) waste streams. The facility was modified in 

1963 to allow production of megacurie amounts of 137Cs, 90Sr, and 144Ce primarily for use in the AEC’s 

Systems for Nuclear Auxillary Power (SNAP) program. At the conclusion of the program (1975), the 

facility was placed in standby, and initial decontamination efforts undertaken (ORNL 1986). Large 

quantities of 244Cm were stored in the building (DOE 1996b). A memo dated August 30, 1965, 

describes a contamination incident that occurred during unloading of a carrier containing strontium 

titanate (90SrTiO3) pellets (Burnett 1965). The incident occurred on July 7, 1965, so strontium titanate 

was handled in Building 3517 circa mid-1965.
Document No. ORAUT-TKBS-0012-2 Revision No. 01 Effective Date: 08/30/2006 Page 23 of 80

2.2.51

In 1957, a new process waste treatment plant was built. The plant had the capacity of 500,000 gal/d. 

It included an 800,000-gal equalization and hold-up basin that could store wastewater before 

treatment. A lime-soda softening process was used to remove strontium through coprecipitation. The 

neutralization plant could remove 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

2.2.52

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, equipment maintenance air lock 

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

housing 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 

tests 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 nonfuel, typically as experimental 

capsules) in shielded casks

• Transfer of material in and out of the hot cells

• Capsule disassembly

• Nondestructive and destructive testing of irradiated materials

• Packaging and shipment of irradiated materials (on or off the 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 property evaluations appropriate to the experimental 

objectives of a program.

2.2.53

The construction of Building 3544 was completed in 1957. This building housed a lime-soda softening 

process to precipitate strontium and cesium primarily (plus other unidentified isotopes) from liquid 

process wastes. It had a capacity of 500,000 gal/d (Auerbach 1992). The Process Waste Collection 

System consists of a series of underground pipes through which process wastewater flows from the 

Building 3544 Process Waste Treatment Facility
Document No. ORAUT-TKBS-0012-2 Revision No. 01 Effective Date: 08/30/2006 Page 24 of 80

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). Waste 

acceptance criteria administratively limit wastes that can be added to the process waste system to a 

total radionuclide concentration of the ingestion dose equivalent of 1 × 104Bq/L 90Sr. Chemicals are 

limited based on treatment system capabilities and effluent discharge permit limits. At strategic points 

throughout the collection system, manholes equipped with beta-gamma radiation monitors, pH 

monitors, and flow monitors are continuously monitored at the Waste Operations Control Center 

(WOCC) to enable personnel to detect unusual activity in the system (Van Hoesen and Vogel 2001).

2.2.54

Building 3597, which is an annex to Building 3503, was used to store fuel assemblies and other 

irradiated materials. Personnel working in this facility received accidental radiation exposures on 

August 10, 2004, when inadequate prejob scoping did not identify existing radiological hazards.

Building 3597 Hot Storage Garden

2.2.55

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

Built in the early 1950s, each building consists of a main area with four wings containing primarily 

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. A radioactive hot drain from 4500 South that is no longer in use connects the 

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

Building 4500 Central Research and Administration Facility

Work with radioactive materials in the Building 4500 complex consisted of initial small-scale R&D 

efforts on chemical separations processes prior to scaling up these processes in other facilities (such 

as Building 4507). A discussion with the individual at ORNL responsible for sampling and 

documenting radiological air effluents indicated that currently (2004) only six labs (comprising a total 

of eight hoods) are required to report radiological releases in ORNL’s annual stack report (Fleming 

2006). However, in earlier years additional laboratory areas within the 4500 complex were used for 

work involving radioactive materials. 

When evaluating potential exposures to employees, a caveat is appropriate for maintenance workers 

and those with similar duties. These individuals often worked on hot process drain lines, hood 

ventilation systems, and other systems and locations where they could have been exposed to 

significantly different radionuclide mixes and activities than workers performing routine tasks. Dose 

reconstructors should consider such nonroutine exposures for workers responsible for maintenance 

and similar activities, using coworker data as appropriate. In addition, although monitoring or other 

records for maintenance workers might indicate their assignment to a single or central work area, in 

reality they worked in many ORNL facilities. 

2.2.56

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

concrete and concrete block faced with transite, gypsum block, or steel paneling. The building, which

was constructed in 1952, has four floors. With the exception of the first floor, hallways and stairwells

provide interior access connections from Building 4501 to Building 4505. 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 outer part of this 

floor contains chemical and radiochemical laboratories and office space. On the second floor, 

Building 4501 High Level Radiochemistry Laboratory
Document No. ORAUT-TKBS-0012-2 Revision No. 01 Effective Date: 08/30/2006 Page 25 of 80

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 contains several 

exhaust stacks for ventilation systems. A process to convert 233U adsorbed on sodium-fluoride traps 

as part of MSRE design and development was conducted in the building.

2.2.57

The High Level Chemical Development Facility, which was constructed in 1957, housed chemical 

separations research on highly irradiated nuclear fuels. Small sections of irradiated fuel or prototype 

fuel elements would be dissolved for laboratory-scale process development research (ORNL 1962). 

The building consists of hot cell banks and associated charging and operating areas. Following its 

work with irradiated nuclear fuels, Building 4507 became the Curium Recovery Facility (CRF; MMES

1994), which tested TRU processes at high activity levels. Curium-242 was recovered from 

241AmO2-Al targets irradiated in the MTR and ORR. CRF operations resulted in the successful 

isolation of about 35 g of 243Am and 244Cm and 25 g of 242Cm.

Building 4507 High Level Chemical Development Facility

2.2.58

Building 4508 is immediately west of Building 4500 South. In the 1960s, the Interim Plutonium 

Laboratory (IPL) was assembled on the first floor within the Ceramics Laboratory. Placement of the 

IPL in Building 4508 was made possible by the secondary containment design. The IPL had highquality gloveboxes and a purge system that provided them 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 for synthesizing, pressing, and sintering pellets of these 

nitrides (LMERC 1997).

Building 4508 Metals and Ceramics Laboratory

In addition, Building 4508 housed the Fuel Cycle Alpha Facility (FCAF), which fabricated plutonium 

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

microspheres with pyrolytic carbon. In addition, special target materials for the HFIR were developed 

and fabricated. This facility was initially in the basement of Building 3019 before relocation to Building 

4508. Two unique fuel-rod-loading techniques – vibratory compaction and slug injection – were 

studied in the FCAF (LMERC 1997).

2.2.59

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 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, separated by a central corridor providing controlled access to each 

laboratory for transfer of radioactive materials. Offices occupy the north, west, and south perimeters 

of the building and are across a corridor from the laboratories. At present, the facility generates no 

radioactive liquid waste, 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, laboratory exhaust system, and glovebox exhaust system. Research 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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2.2.60

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 lowand high-energy acceleration tubes 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 that accelerates ions 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 began in August 1975. The first successful transmission of beam through the entire 

system occurred in May 1980.

Building 6000 Holifield Radioactive Ion Beam Facility

2.2.61

The Oak Ridge Electron Linear Accelerator (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, 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 target, they generate an intense 

flux of gamma rays. Thegamma ra ys produce ne utrons via (gamma, xn) reactions on the 

tantalum. The neutrons are moderated in the cooling water surrounding the target and travel to the 

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 neutron energy. The integrated flux is about 

0.8 × 1014 neutron/s at a power of 50 kW.

2.2.62

Building 7025 is a prefabricated metal-sided building acquired from the Tennessee Valley Authority as 

surplus property. Erected in 1968, it has a total floor area of 590 ft2 (LMES 1997h). It is about 1.4 mi 

northeast of the central ORNL campus to the east of the General Stores and buildings. It had a 26-ftlong, stainless-steel glovebox for titanium tritide target fabrication. The glovebox exhaust was 

unfiltered because no particulate radioactive material was present. The exhaust stream was 

monitored. In the late 1970s, a high-vacuum evaporator system moved from Building 3550 to Building 

7025 for the preparation of thin-film uranium and thorium oxide targets. The evaporator operated in a 

HEPA-filtered hood. According to LMES (1997h), only benchtop quantities of uranium and thorium 

were handled. The building had a forced exhaust system that ran continuously in combination with a 

forced air intake system to exhaust tritium gas that would have escaped from the glovebox line. The 

tritium and ThO2/UO2 operations ended in October 1989 and January 1990, respectively.

Building 7025 Tritium Target Facility

2.2.63

Section 2.3.6.7 describes the HRE Building.

Building 7500 Homogeneous Reactor Experiment Reactor Building

2.2.64

Section 2.3.6.10 describes the MSRE facility.

Building 7503 Molten Salt Reactor Experiment
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2.2.65

Building 7602 is a 15,841-ft2

, concrete-block and steel-frame structure built in 1963 as a fueling 

building for the Experimental Gas-Cooled Reactor (LMES 1997i). This project was terminated during 

construction in 1965 and the reactor (Building 7600) was never fueled. No nuclear fuel was handled. 

The building, which has three floors and three pits (F-14, solvent extraction, and dissolver), was idle 

until 1974, when the Liquid Metal Fast Breeder Reactor Fuel Cycle Program moved into its offices. It 

is not clear if radioactive materials were processed during this program. From 1981 to 1983, additions 

and modifications supported a collaborative fuel reprocessing program with the Japanese. From 1984 

through 1994, the building was used to test chemical separations processes, principally using 

PUREX. Tests used dummy fuel made from depleted and natural uranium. No spent nuclear fuel 

was processed in the building.

Building 7602 Integrated Process Demonstration Facility

2.2.66

Section 2.3.6.5 describes the Tower Shielding Facility.

Building 7700 Tower Shielding Facility

2.2.67

The Dosimetry Applications Research (DOSAR) Calibration Laboratory (CalLab) is a 2,800-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 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). A Pantak model HF320 

X-ray generator is available for reproducing National Institute of Science and Technology beam 

codes. Table 2-4 lists the sealed sources in the facility. The assay date for the radionuclide sources 

is November 4, 2005.

Building 7735 Dosimetry Applications Research Calibration Laboratory

Table 2-4. Sealed sources available at DOSAR Calibration Laboratory (Building 

7735). 

Radiation Source Dose rate

Source distance

(cm)

Beta Sr-90/Y 5,563 mrad/hr- 35

Beta Pm-147 8.1 mrad/hr (surface) 20

Beta Tl-204 5.9 mrad/hr 35

Beta Sr-90/Y 961 mrad/hr- 35

Beta Sr-90/Y 24,081 mrad/hr 35

Gamma Cs-137 991 mR/hr- 51

Gamma Cs-137 2,323 mR/hr 100

Neutron Cf-252 (bare) 79 mrem/hr 50

Neutron Cf-252 (bare) 19.8 mrem/hr 100

Neutron Cf-252 (poly-moderated) 9.3 mrem/hr- 50

Neutron Cf-252 (poly-moderated) 2.3 mrem/hr 100

Neutron Cf-252 (D2O-moderated) 53.1 mrem/hr

- 50

Neutron Cf-252 (D2O-moderated) 13.3 mrem/hr 100

Neutron Pu-238:Be 21.1 mrem/hr 100

X-ray Various beam qualities 2 to 300 R/hr 318
Document No. ORAUT-TKBS-0012-2 Revision No. 01 Effective Date: 08/30/2006 Page 28 of 80

2.2.68

About 1955, the ORNL ecology group constructed three unlined pits in Conasauga shale above White 

Oak Lake. The purpose of these pits was to test the sorptive properties of the shale for fission 

products. The three pits were designated Buildings 7806, 7807, and 7808. They received large 

volumes of “intermediate-level” radioactive wastes generated by fuel reprocessing studies in Building 

3019. Thousands of curies of 90Sr, 137Cs, 60Co, and 106Ru were poured directly into the pits. With the 

exception of 106Ru, this activity was retained in the soil immediately adjacent to the pits. High 

personnel exposures (external) rendered the pits too hazardous for continued use; they were filled 

and capped about 1960 (Auerbach 1992). These pits still exist. In place of the pits, covered trenches 

were built to distribute radioactive materials in liquid waste into the surrounding soils. These trenches 

were designated Buildings 7809 and 7810. 

Buildings 7806, 7807, 7808, 7809, and 7810 Waste Pits and Trenches

2.2.69

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

LLLW in shale formations at depths of more than 780 ft. Facilities required to support the waste 

disposal operations included a building containing a mixing cell, pump cell, and injection well cell; five 

underground tanks 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 cell had 1-ft-thick concrete walls and roofs of diamond-plated steel. The liquid 

waste tanks, 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 to about 100 to 200 mR/hr (AIMS and CDM 1996).

Building 7852 Old Hydrofracture Facility

2.2.70

Section 2.3.6.9 describes the HFIR facility.

Building 7900 High Flux Isotopes Reactor

2.2.71

Building 7920 is part of the Radiochemical Engineering Development Center (REDC). The mission of 

the REDC is to separate and purify TRU isotopes (primarily 252Cf) from 244Cm target material irradiated 

in the HFIR. The REDC consists of Building 7920 and Building 7930, both of which contain hot cells 

and gloveboxes for working with irradiated targets and separated products. The separation and 

purification processes occur in Building 7920. Products are prepared to customer specifications and 

packaged in Building 7930. Elements handled in the REDC include californium, berkelium, 

einsteinium, and fermium.

Building 7920 Transuranic Processing Facility

Building 7920 receives isotopes from the HFIR and processes them in preparation for fabrication into 

sealed sources. It contains radioanalytical laboratories and heavily shielded hot cells. The primary 

radiological hazard in Building 7920 is neutron exposure from 252Cf and other transcalifornium 

isotopes. Operating areas in Building 7920 include the following:

• The Control Room.

• Room 105, the Counting Room.

• Room 111, the Shielded Cave Area, which contains hot cells and gloveboxes.
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• Room 208, the Analytical Laboratory, is used to prepare samples for analysis. It contains 

gloveboxes, bench tops, fume hoods, etc.

• Room 211, the Alpha Lab, which contains glovebox banks.

• The Transuranium Decontamination Facility, which is a movable hot cell on top of the Building 

7920 hot cell bank used to move materials from hot cells into other containers.

• The Waste Transfer Area, where waste passes through a square tunnel going through the wall 

of process cubicle Number 10.

• The Limited Access Area, where waste generated in the process cubicles is placed in casks. 

Waste is placed in the casks as necessary by removing their covers using an overhead crane.

2.2.72

Building 7930 is in the HFIR (7900) area southeast of the main plant area (MMES 1994). (Limited 

information on this facility was located.) Constructed in the late 1960s, the facility was the focal point 

of the High Temperature Gas Reactor fuel cycle development and demonstration work, with 

collaborative efforts in solvent extraction work conducted by THOREX in Building 3019-B (MMES

1994). In 1968, it was equipped to prepare 233U fuel for the MSRE. Due to the amount of 232U in the 

feed (250 ppm), exposure rates from a 1-lb can of oxide measured 250 rem/hr at contact. This 

exposure rate made it necessary to handle the material remotely in cell G.

Building 7930 Thorium Uranium Recycle Facility (TURF)

TURF operations ended in 1980, leaving approximately 50,000 gal of TRU waste in the five 

underground storage tanks. This waste was transferred to the Melton Valley Storage Tanks for 

processing and disposal. Building 7930, which is still part of REDC, contains gloveboxes used in the 

finishing and packaging of isotopic sources produced in Building 7920.

2.2.73

These operations were housed in a small area (less than 5,000 ft2

) on the second floor of the east end 

of Building 9204-3 at the Y-12 National Security Complex. They consisted of the calutron operations 

area (2,700 ft2

), where actinide isotopes were separated, and the components wash and service area 

(1,800 ft2

), where actinide isotopes were removed from calutron receivers and the receivers were 

prepared for use. About 1962, this area was modified to separate actinide isotopes for research. This 

was new construction with the exception of the calutron. The actinide area operated continuously 

until the mid-1970s, when it was placed in standby. It operated again in the late 1970s to isolate 

242Pu, and was placed in standby again in 1980 (MMES 1995).

Building 9204-3 Actinide Area (Electromagnetic Isotope Separation at Y-12)

2.2.74

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

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

Solid Waste Storage Areas

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

indication of 137Cs or transuranic elements.

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

included uranium, plutonium, and 137Cs. Ground-water samples showed no contamination. 

Water sample analyses included tritium, gross alpha, and gross beta.
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3. Ground-water samples from the SWSA 3 area indicated small amounts of trivalent rare 

earths, 90Sr, 89Sr, and 3

H contamination.

4. Ground- and surface-water samples from the SWSA 4 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 samples from the SWSA 5 area 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 Ci 60Co; and 7,110 Ci 3

H. Water seepage has occurred in most of 

the 49 trenches. To decrease 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 ORNL SITE OPERATIONS AND PROCESSES

Section 2.2 describes 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., a fan house, filter house, stack, and other ancillary facilities were associated with Graphite 

Reactor operation). Section 2.3.1 discusses early operation of the Graphite Reactor, the Hot Pilot 

Plant (Building 3019), and 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 the bombardment of 238U with a cyclotron could produce 

plutonium, and Enrico Fermi had designed a graphite-moderated reactor that had achieved a selfsustaining, critical reaction, it was recognized that the production of plutonium in quantities great 

enough for weapons production could be attained only by 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 (MED) 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 4, 1943, to November 

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

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

testing. The reactor was designed to operate at a thermal power rating of 1,000 kW; however, with 

subsequent modifications it 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 from which operators would 

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

Witkowski 1955)]. Natural uranium fuel slugs (4 in. long by approximately 1.1 in. in diameter) were 
Document No. ORAUT-TKBS-0012-2 Revision No. 01 Effective Date: 08/30/2006 Page 31 of 80

inserted in the reactor 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 reactor.) 

Following irradiation, an operator standing at the front face used a long-handled rod to push the slugs 

out the back of the reactor. The irradiated slugs dropped into a water-filled transfer canal. The ORNL 

plutonium production mission was accomplished by the end of 1944 (MMES 1994).

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

highly contaminated concrete. A 1958 memorandum stated that most of the exposure to reactor 

operations personnel occurred during work adjacent to the transfer canal (Author unknown 1958). In 

1959, the water level was increased and steel plating was placed over the contaminated concrete. 

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

its former value” (Cox 1959a). 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 

decay of 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 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 prior to being 

submerged underwater. The impact would sometimes breach or further breach the aluminum 

cladding of the slugs, resulting in a release of particulate matter to the air. The large building 

ventilation fans would entrain these particles and exhaust them out the stack. Therefore, 

concentrations of gaseous wastes such as noble gases (41Ar and several xenon/krypton isotopes) and 

radioiodines were not filtered or quantified.

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

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

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

one that stored contaminated equipment from the other cells. The cell area was in a frame structure 

that contained the operating gallery and office areas. This facility, known as the Pilot Plant, was 

where new chemical separations processes were tested [e.g., bismuth phosphate, reduction-oxidation 

(REDOX), Hexone-25, tributylphosphate (TBP)-25, PUREX, fluoride volatility chemical process, and 

THOREX].

The first “hot run” to separate plutonium began on December 19, 1943. The first batch of irradiated 

fuel slugs were transferred from Building 3001 to the Building 3019 dissolver on December 20, 1943. 

On January 3, 1944, the first plutonium (1.54 mg) was shipped from ORNL to the Metallurgical

Laboratory at the University of Chicago (MMES 1994). By the end of January 1944, approximately 

one-third ton of irradiated fuel from the reactor was going through the Pilot Plant each day. By May 

1944, 30.737 g of purified plutonium had been shipped. [Purification of plutonium extracted in the 

Pilot Plant occurred in Building 3550 (originally 706-A).] Plutonium separation activities were placed 

on standby in January 1945 (Quist 2000). The final regular shipment in January 1945 brought the 

total to 289.438 g. Additional plutonium was reclaimed and purified during the process of shutting 

down and cleaning out the equipment, bringing the total amount of plutonium shipped to 326.390 g 

(MMES 1994). 
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Because of the variety of processes that took place in Building 3019, different radioisotopes were and 

are still present in the facility. At first, airborne emissions 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 sent to the large Central Exhaust Facility stack at Building 

3039 (Klima 1962). Arnold, Gresky, and Nichols (1961) described the types of materials likely to be 

exhausted through the filter. Historical and Programmatic Overview of Building 3019 (Brooksbank, 

Patton, and Krichinsky 1994) describes all processes that occurred in Building 3019. This facility 

conducted much of the R&D operations for chemical separations at the site. Several of the processes 

are described below.

• From 1943 until 1945, the Bismuth-Phosphate Process recovered plutonium from 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 dissolution of the slugs in acid in the initial cell. The remaining cells housed 

equipment used in precipitating plutonium from the dissolved fuel slugs and oxidation and 

reduction of the uranium. This batch process is based on the fact that plutonium will 

coprecipitate with bismuth phosphate in the +4 valence state but not in the +6 valence state. 

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

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

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

phosphate. The Bismuth-Phosphate Process could extract only plutonium; uranium remained 

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

fission products.

• The REDOX Process took place 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 from 1949 to 1960. The PUREX Process involved the use of 

TBP for solvent extraction. 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, 235U, 238Pu, and mixed fission products.

• The Fluoride Volatility Chemical 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 to separate 233U, 232Th, 233Th, and 233Pa from irradiated 

thorium metal and other fission products. In 1956 and 1957, 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 originally housed the FCAF in a basement area before its relocation to 

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

coating sol gel-derived microspheres with pyrolytic carbon. Special target materials for the 
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HFIR were developed and fabricated in this facility. Two additional and unique fuel-rodloading techniques – vibratory compaction and slug injection – were studied in the FCAF.

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

and South Tank Farm areas, facilities 3023 and 3507. At times, volatile gases were released from the 

head space of the tanks when liquids were being added. Section 2.3.4 contains more information on 

waste operations.

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

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

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

plutonium. The explosion also contaminated the Graphite Reactor and other buildings. King and 

McCarley (1960) indicated that environmental contamination was immediately fixed at buildings and 

grass with paint, asphalt on roads, and either paint or tar on 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 and McCarley 1960). A report 

issued August 25, 1961, indicated that decontamination efforts took place over an extended period 

and that approximately 141 g of plutonium were flushed from the cell area (Parrott 1961). Parrott

indicated that, although many entries were made to the cell area for decontamination efforts, none of 

the workers was overexposed to beta/gamma radiation and there was “no detectable increase in the 

body burden of plutonium of any individual involved” in the decontamination efforts. 

Other buildings in the Main Plant Area where radioisotopic separations occurred using slugs irradiated 

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

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 reprocessing of the irradiated fuel. A radiological 

survey in 1981 indicated that the facility had widespread residual fission products, 137Cs and 90Sr, and 

uranic and TRU radioisotopes were present. The building was demolished and removed from the site 

in about 2000.

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

used in the further separation of fission products from waste solutions from Building 3505. Building 

3515, which operated from 1948 to 1958, was originally known as the 106Ru tank arrangement. It was 

used to extract radioisotopes of ruthenium, strontium, cesium, cerium, and other fission products (BN 

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 built. Numerous spills occurred 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 

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; some uranic and TRU isotopes would have been 

present in the waste, as would other fission products.
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2.3.2

In mid-1942, radiological research was directed at small-scale studies of different radioisotopes in the 

Metallurgical Laboratory at the University of Chicago. While most of the research focused on the 

production of fissionable material for use in weapons manufacturing, some was 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, special attention was given to barium, strontium, and 

lanthanum separation chemistry. Although initially purified 140Ba had little gamma activity, 140La, which 

grew into the purified 140Ba, was of great interest due to its 1.6-MeV gamma ray and high specific 

activity. The program for the separation and production of radioactive lanthanum was 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 began in Building 3550 (706-A); on October 21, 1943, 

there was a request to construct a larger production facility. Building 3026-C (706-C) was constructed 

with larger containers and equipment in 1944, and the new facility was placed in operation; its initial 

production run began on September 10, 1944.

Radioactive Lanthanum Activities

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

constraints and unusual circumstances, at startup it was producing greater-than-100-Ci amounts. The 

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. (Multiple batches of 

irradiated slugs were dissolved to make up a completed run.) The last run in Building 3026-C was on

May 28, 1945. During the initial lower activity production runs, spills, plugged lines, low chemical 

yields (requiring dissolution of additional batches of slugs), and failed equipment affected the 

completion of runs (Thompson 1949).

After the second successful RaLa run in Building 3026-C, discussions indicated the need to increase 

production rates further. Although 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 (706-D), which was designed to process much larger (up to 1,000 Ci) 

amounts of radioactivity, was attached to the east end of the 3026-C facility. As with the construction 

of Building 3026-C, time constraints caused design and development work 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 completed in Building 3026-C. Building 3026-D processed much higher activities 

than those designed for the facility.

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

RaLa. The higher power levels of the Hanford reactors (in relation to those of the Graphite Reactor) 

meant production of much larger quantities of RaLa in a shorter time, even with shipping the slugs 

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

October 1956. The RaLa program was 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 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 off-gas stream by the reflux condenser and chemical scrubber in line before the gaseous 

waste went to the stack. Dissolver off-gas 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 was routed to the 3039 stack. In the later part of 1948, operations in Building 3026-D were a 
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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 during RaLa operations, the worst incident occurred at about 5:00 p.m. on April 29, 

1954. It was described as “the most serious accidental release of activity ever experienced in the 

history of the process” (Rupp and Witkowski 1955). Building 706-D logbooks indicate that 161 

Hanford slugs had been loaded in the dissolver and three batches had been processed successfully

during Run 56. After the third batch dissolution, liquid did not cover the slugs in the dissolver tank for 

approximately 28 hr and the slugs became thermally hot due to radioactive decay. When the fourth 

batch addition of acid was poured in the dissolver to initiate additional dissolution, a violent reaction 

forced dissolver solution up the slug-loading chute and solution addition lines. Air monitors 

immediately sounded an alarm indicating elevated airborne radioactive material. The investigation 

that followed indicated that individuals donned gas masks and evacuated the building quickly. The 

release lasted from 10 min to 2 hr before the scrubbers could recover and begin filtering radioiodine 

from the building. A letter from the Laboratory Shift Superintendent to the ORNL Director indicated,

“all people involved in the incident and later in the high level decontamination work are being given 

the standard HP [Health Physics] check including urine checks, etc.” (Stanley 1954). Radiation levels 

reached 100 R/hr on the third floor, but were reduced to 100 mR/hr by 7:00 a.m. the next day; air 

sample results did not exceed the tolerance level of 3.0 × 10-08 μCi/mL. A “preliminary check of film 

badge results” indicated that the highest measured exposure was approximately 1250 mR (hard) and 

4700 mrep (soft) (Stanley 1954).

ChemRisk (1999) contains detailed information on RaLa operations, source terms, emissions, and 

offsite radiation doses. This document provided 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, site facilities were built to produce other 

radioisotopes. Table 2-5 lists facilities involved in the ORNL isotope production program and

radioisotopes that would have been present. Building 3026-C was the initial facility for commercial 

isotope production at ORNL (Kuhaida and Parker 1997). Most of the other isotope production 

facilities were built in the early 1950s. Some facilities have not produced any material since the 

1960s, and some are used for storage. The following paragraphs contain information on several 

isotope production buildings. 

Isotope Production Areas

Building 3028 was constructed in 1950 to house the 131I processing facility and the separation facility 

for 147Pm (LMES 1997b). The 131I facility was converted to manipulator cells and expanded in the 

early 1960s to the Short-Lived Fission Product Facility, which operated until 1985. The 133Xe facility 

was added at that time and operated until 1980 to produce 133Xe, 131I, and 99Mo. Curium source 

fabrication began in 1964 to support Space Nuclear Systems. The process took place on the first 

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

was named the Alpha Powder Facility to support the full-cost-recovery isotopes program. In the late 

1970s, the target facility moved to Building 3038; the upper floors were occupied by Nuclear Medicine 

Research until 1988. 

Building 3029 was constructed in 1952 to support the Isotopes Program (LMES 1997c). A small 

manipulator cell (now called Cell 4) and a system of remotely operated barricades supported source 
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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 I-129, I-131, Se-79, Pd-107, Pm-147, Cs-137, 

Sr-90, actinides, Kr-85, U, Tc-99, Co-60, Pu, H-3

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

Pu-238

Source Development Laboratory 3029 Ir-192, Co-60, Cs-137, Sr-90, I-131, I-CH3131, 

C-14, Tc-99

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

nitrate, Sn-111, U-237, P-33, Ir-192, Ni-63, 

Pd-103

Radioisotope Production Laboratory–D 3031 Y-90, Gd-153

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

Co-56, Co-57, Au-198, Fe-55, Np-234, Se-75, 

Sr-90, Cs-137, Sn-111, U-237, P-33, Ir-192, 

Cm-244, Xe-131, I-131, Mo-99, Pm-147

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

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

actinide isotopes

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

Equipment Division support

Alpha Handling Facility 3038-AHF Cf-252, Cm-244, Am-241, Pu-238, U-234, 

Np-237, Pa-231, others

Isotope Materials Laboratory 3038-E Transuranics, Y-90, U-235, Pm-147, Sr-90, 

Cm-244, Am-241

Radioisotope Packaging and Shipping 

Facility

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

Ru-106, Cl-36

Isotope Technology Building 3047 C-14, Eu-152,154, Co-60, Gd-153, Am-241, 

Cm-242/243

Storage Cubicle 3093 Kr-85

Storage Pad 3099 N/A

Radioisotope Production Laboratory–H 3118 Not established

Fission Products Development Laboratory 3517 Sr-90, Cs-137, Ce-144, Pm-147, Ru-106, Tc-99, 

Co-60, Ir-192, U-235, Eu-152,154, Am-241

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

fabrication of 192Ir. In addition, small 60Co sources were fabricated. 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, which is between Cells 1 and 3, handled waste and served 

as a pass-through between the two cells. Major operations in Building 3029 included 60Co, 137Cs, and 

90Sr source fabrication and 192Ir processing. A 60Co storage and irradiation facility, called the 60Co 

Garden, is below the floor of the east wing (DOE 1996b). The exact dates of operation of this facility 

are unknown, but the program ended in the late 1980s.

Building 3030 was constructed in 1950 to produce and develop radioisotopes for industry, medicine, 

and research (LMES 1997d). The building contained a hot cell for processing irradiated cyclotron and 

reactor targets to produce, purify, and separate radioisotopes such as 56Co, 57Co, 198Au, 55Fe, 234Np, 

75Se, 90Sr, 111Sn, 237U, 33P, and 192Ir. These isotopes were processed primarily from irradiated targets 

from the HFIR, ORR, and 86-in. Cyclotron. There is 63Ni and 103Pd contamination in the facility. The 

exact dates of operation are not known. The program the facility supported began in the late 1940s 

and ended in the late 1980s.
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Building 3031 was constructed in 1950 as part of the Isotopes Program and used for storage,

purification, processing, and dispensing radioisotopes (LMES 1997e) that were processed primarily 

from irradiated targets from the HFIR, ORR, and 86-in. Cyclotron. The hot cell was used for the final 

separation of gadolinium (153Gd).

Building 3032 housed the analytical facility for radiochemical support of Isotopes Production activities 

(LMES 1997f). It has a laboratory with five hoods on the north side and an office on the south side 

connected by an open passageway. It was used for storage, purification, processing, and dispensing 

radioisotopes that were processed primarily from irradiated targets from the HFIR, ORR, and 86-in. 

Cyclotron. The exact dates of operation of this facility are unknown. 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 (LMES 

1997g). Radioactive gas processing of tritium and krypton took place in this facility. Bulk tritium 

shipments from the Savannah River Site were received, purified, loaded in shipping canisters, and 

shipped around the world. Krypton from Idaho was received and purified (85Kr) 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 unknown. The program it supported began in the late 1940s. Processing 

of 3

H ended in 1990. The last 85Kr was produced in September 1989.

Building 3033-A (LMES 1997g) housed facilities for the fabrication of ceramic oxide wires and the 

loading of these wires, oxide powder, or metal into small metal capsules for use as in-core reactor 

neutron dosimeters. It also housed facilities for the fabrication of monoenergetic gamma sources, 

weighing and packaging of milligram to gram quantities of actinide materials, preparation of nanogram 

to milligram actinide samples for alpha counting, decontamination of nuclear material shipping 

containers, and storage of radioactive materials. In the early 1980s, the 14C room was 

decontaminated and decommissioned, which included removal of the underground dissolver tank, and 

converted for storage. All production operations in the building ended in January 1990 because of 

funding problems. All stored special nuclear materials were transferred to other ORNL or DOE sites 

or disposed of as waste.

Building 3034 (ORNL 1997j) houses the electrical distribution system for the isotopes area and serves 

as a storage area and drop point for supplies. It also contains office space. No radioactive operations 

took place in the building; however, 1995 radiological surveys indicated several limited locations of 

elevated fixed beta/gamma contamination. An exhaust duct on the west wall of the second floor also 

indicated elevated beta/gamma measurements.

Building 3038 was used from 1949 until 1990 for packaging, inspection, and shipping activities for 

radioisotopes. It 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 was 10 ft 

deep. From 1968 until 1990, the western portion, referred to as the Alpha Handling Facility (AHF),

was used for the fabrication of targets. The center portion (referred to as 3038-M) contained 

radioactive isotope shipping operations. The east end (3038-E) contained analytical chemistry 

laboratories that supported isotope shipping activities (DOE 1996b). This area was converted to an 

isotope production and development facility, and was used in the late 1970s and early 1980s to 

support research activities involving plutonium alloys and compounds. In the mid-1980s, gloveboxes 

in this area were used for research on 147Pm doped crystals. The northwest corner (3038-W) 

contained a storage area and an isotope technology low-level laboratory. 
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Building 3118 was constructed to cover and enclose entries made in the hot cells in Buildings 3030 

and 3031. It was used as a temporary storage shed for drums and containers of hazardous and 

radiological waste, radioactive shielding materials, and casks.

Section 2.2.69 discusses the REDC, which produces TRU isotopes from target materials irradiated in 

the HFIR. 

2.3.4

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

been used. Early sites in or near the Main Plant Area accepted solid and liquid production wastes. In 

later years, disposal areas moved south of the Main Plant Area across Haw Ridge to Melton Valley. 

The following paragraphs describe the areas and amounts of radioactive materials present, if 

available.

Waste Areas and Processes

The ORNL site was originally to operate for a short period to develop processes for use at other 

Manhattan Project facilities. Because of this short-term focus, maintenance of much of the wastes 

was expected to be in consolidation areas. The North and South Tank Farms were established for 

temporary storage of liquid wastes. Processing included treatment and precipitation of solids and 

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

Creek. The holding areas treated the liquids and precipitated much of the radioactivity out of solution 

prior to offsite release. However, sediments in White Oak Creek and Lake contain radioactive 

materials that settled from the process liquids.

The North Tank Farm (Facility 3023), which was built in 1943, included four large concrete (gunite) 

underground tanks (W-1, W-2, W-3, and W-4) to store liquid chemical and radioactive wastes. In 

1950, four stainless-steel underground tanks (W-1A, W13, W-14, and W-15) were built in the same 

general area. An extensive underground piping system transported liquid waste from Buildings 3019 

and 3026 to the tanks.

The South Tank Farm (Facility 3507) is a series of six 170,000-gal underground gunite storage tanks 

placed in service in 1943. It was part of the LLLW system for collection, neutralization, storage, and 

transfer of aqueous radiological and chemical wastes generated at ORNL.

The Waste Holding Basin (Facility 3513) was built in 1944 by scooping a depression in the native clay 

and constructing earthen berms to contain the liquids. The unlined disposal area measured 220 ft 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. Water from the process waste treatment plant that had been treated with fly ash and 

lime was discharged to the holding basin before discharge to White Oak Creek. The basin was 

removed from service in 1976, but still contains water and contaminated sediments.

The contaminants in these three waste storage areas consisted of soluble and insoluble radioisotopes 

that flowed from the chemical separations areas. The liquid wastes were often treated with caustic 

material to increase the pH and prompt radioactive material to settle out. Once treated, liquid waste 

could be transferred to make room for additional waste. The treated waste liquid was initially pumped 

into White Oak Creek. Liquid wastes were later transported by truck to Melton Valley, where they 

were poured into pits and trenches in which the liquid evaporated and chemically combined with the 

soil. The Old Hydrofracture Facility (Building 7852, see Section 2.2.47) disposed of LLLWs deep in 

geological faults that are separate from sources of drinking water.
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There are additional underground storage tanks in the main plant area (thorium tanks, area 4500 

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

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

3). Solid wastes were later transported to Melton Valley where other landfills operated. The following 

paragraphs describe SWSAs 1 to 6:

• 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. Solid waste was buried in this area in 

trenches south of Incinerator Drive beginning in April 1944. More waste was added in 1944, 

but the site was abandoned later that year due to water accumulating in the trenches. The 

area contains only a small amount of solid radioactive waste because fissionable material was 

maintained in the main plant site. At the time of waste generation, site operations did not 

include isotope separation and concentration of waste. Analyses from ground-water wells 

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

• SWSA 2 is approximately 3.6 acres north of the location where the East Vehicle Gate existed, 

on the lower half of the hill adjacent to and west of the main parking lot. The site is not fenced 

or marked to identify its location. It was used from 1944 until 1946 for disposal of waste. 

Beta/gamma-contaminated solid waste was put in black drums and buried in trenches. Liquid 

waste contaminated with plutonium was put in stainless-steel drums and either buried in 

trenches or stored above ground in a ravine. Following closure of SWSA 2, the drums were 

removed and reburied in SWSA 3. Following drum removal between 1946 and 1949, the 

SWSA 2 hillside was bulldozed, backfilled, contoured, and seeded. Analyses of core samples 

indicated no contamination from uranium, plutonium, and 137Cs. Ground-water samples 

showed no detectable contamination; analyses included tritium, gross alpha, and gross beta.

• SWSA 3 is about 7 acres about 0.5 mi west of SWSA 1 and 0.6 mi west of the west ORNL

entrance. It opened in 1946 and received contaminated trash, laboratory equipment, and 

other materials. The drums from SWSA 2 were placed in this area. Alpha-contaminated 

waste was put in drums and placed in concrete-lined trenches on the northeast end of the 

burial ground. Later, as the burial ground 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 removal in 1979. 

Some items were moved to an area between SWSA 4 and the Chemical Waste Pits, while 

others were moved to SWSA 5 or 6 and buried. SWSA 3 closed in 1951. Ground-water

samples indicate small amounts of trivalent rare earths, 90Sr, 89Sr, and 3

H contamination.

• SWSA 4, which covers approximately 23 acres, received waste from 1951 until 1959. It is in 

Melton Valley on the south side of and at the foot of Haw Ridge, immediately west of White 

Oak Creek. Records about waste disposed of 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 more than 50 other agencies; Argonne National Laboratory, Knolls 

Atomic Laboratory, Mound Laboratory, and the General Electric Company (Evendale, Ohio) 

were principal generators. Surface- and ground-water samples indicate the presence of 

radioactive contamination. One well sample indicated alpha contamination while another 8 of 

16 well samples indicated beta/gamma contamination. Radioactive contaminants include 90Sr, 

106Ru, 137Cs, 60Co, 210Po, 239Pu, 3

H, 125Sb, and trivalent rare earths.
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• SWSA 5 is in Melton Valley north of Melton Branch and east of the confluence of White Oak 

Creek and Melton Branch. The 33-acre area opened in 1958 after space in SWSA 4 became 

limited. Low-level waste is stored in trenches in the larger southern section of the area, and 

TRU waste is stored in trenches in the northwest corner. Disposal of waste in SWSA 5 ended 

in 1975. Water seepage has filled the trenches, which were excavated with the long portions 

extending down the slope parallel to the hydraulic gradient of the water table. In 1975, 

underground dams were installed across two parallel trenches to reduce 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 area in more than 14 trenches in the TRU 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 waste and 235U for 

storage. The 68-acre area is in Melton Valley north of White Oak Lake, south of Lagoon Road 

and Haw Ridge, and immediately east of Highway 95. Beta/gamma and TRU 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 cell ventilation, off-gas 

scrubber, and waste systems. Because of the diversity of activities in the buildings the system 

serves, any gaseous waste stream can contain TRU or fission product radioisotopes. Building 

operators, as the waste generators, are responsible for keeping radionuclides in the gaseous waste 

streams that discharge to the Stack Ventilation System to levels that limit risk to the health and safety 

of the public and employees. This occurs 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 to the Stack Ventilation System.

2.3.5

Due to a moratorium on construction activities immediately after World War II, insufficient space at 

ORNL caused the Biological Sciences Division to move to space at the Y-12 National Nuclear 

Security Complex, which included Buildings 9207, 9208, 9210, 9211, 9220, 9224, 9743, 9767-3, 

9767-5, 9982 and several cooling towers. The Biological Sciences Division conducted 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 (which had 

been Biological Sciences Division) indicated that the type of radiological studies conducted in the 

building complex used sealed radioactive sources for direct exposures (Fleming 2003). They used

sealed sources that consisted of welded metal capsules. The greatest potential hazard was direct 

exposure to an unshielded capsule. This is unlikely to have presented a contamination hazard except 

in the event of a broken capsule weld. There is no information indicating that this type of accident 

ever occurred in these facilities. The source rooms had lead-lined walls and doors at all locations 

where there was a potential for personnel or public exposure. Procedures and safety interlocking 

devices minimized the potential for personnel to be exposed.

Radiation sources are no longer present in the Y-12 Biological Sciences facilities. Table 2-6 lists the 

sources used by the Biological Sciences Division at Y-12 over the last few decades.
Document No. ORAUT-TKBS-0012-2 Revision No. 01 Effective Date: 08/30/2006 Page 41 of 80

Table 2-6. Radiation sources in Biological Sciences Division at Y-12. 

Building Room

Radioactive 

source

Quantity 

(Ci)

Dose rate (at 

1 m, unshielded) 

(rad/hr)

Type of 

radiation Main irradiation use

9207 403A Cs-137

Cs-137

1,300

65

430

21.5

Gamma Mice, rats

Mice, rats

9207 4040 Cs-137 0.83 0.3 Gamma Mice, rats

9210 341 Cs-137 2.5 0.8 Gamma Mice

9779-2 Cs-137 80 26.5 Gamma Mice

9207 127 Co-60 3.75 5 Gamma Insects, mammalian tissue

9983-17 Trailer Cf-252 3.91 0.8 Neutrons and 

gamma

Mice, rats, mammalian 

tissue

Two other ORNL programs moved to the Y-12 site. The Stable Isotopes Program emerged at the end 

of World War II when site personnel 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 Isotope Program. One track of calutrons was modified with 

heavy iron yokes so individual sections could be operated to separate isotopes of different elements. 

In 1963, the ORNL Electromagnetic Isotope Separations Program was providing more than 250 highpurity highly enriched isotopes for use in 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. In late 1985, the Stable Isotope Program made over 229 isotopes available by direct sale or 

on a loan basis. At one time, this program was the largest DOE involvement with commercial 

markets. Stable isotopes were used in preparing specialty isotopes used in medical research, as 

tracers, and in a number of physics applications. Every year, the 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 1951, the ORNL Engineering Technology Division was split into two divisions – the ANP and 

Reactor Experimental Engineering Divisions. Later that year, both divisions moved to Y-12 (ANP to 

Building 9201-3 and the Reactor Experimental Engineering Division to Building 9204-1). There is little 

indication that these divisions used substantial amounts of radioactive materials. 

The ORNL CEF, also at Y-12, is discussed in Section 2.3.6.2.

2.3.6

In addition to the Graphite Reactor operations described in Section 2.3.1, facilities were built at ORNL 

to test reactor designs, train personnel, or test criticality configurations. This section discusses the 

following facilities:

Other Reactor Development and Operations

• Low-Intensity Test Reactor

• Critical Experiments Facility

• Bulk Shield Reactor/Pool Critical Assembly

• Oak Ridge Research Reactor

• Tower Shielding Facility

• Health Physics Research Reactor

• Homogeneous Reactor Experiment
Document No. ORAUT-TKBS-0012-2 Revision No. 01 Effective Date: 08/30/2006 Page 42 of 80

• Aircraft Nuclear Propulsion Experiment

• High Flux Isotope Reactor

• Molten Salt Reactor Experiment

In addition to routine elevated external exposures adjacent to these facilities, each facility was known 

to have incidents that provided increased external and internal exposures. The following sections 

provide information on the operation of these facilities.

2.3.6.1 Low-Intensity Test Reactor

The LITR (Building 3005) was originally built as a mockup of the MTR being built in Idaho. It was a 

pool-type reactor with beryllium reflectors on each side and water used as a reflector on the top and 

bottom. Reactor specifications indicate that there could be as many as 25 fuel elements in a slab 

arrangement, but at times 25 fuel elements were not in place (Cox 1958, 1959b, 1960a). (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. Maximum radiation leakage around the beam plugs reached 1 R/hr (Rupp and Cox 

1955). During operational testing, 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 checkout of instruments and controls of the MTR. 

It was also used as a training facility for MTR operators. LITR controls were collocated in the 

Graphite Reactor Building. ORNL and AEC later decided to modify and operate the reactor for 

experimental and training purposes. It operated at a power level of 3 MW.

The LITR operated from 1951 until October 1968. Experiments could be approved by one individual, 

and no written procedures were followed during the experiments (Stapleton 1993). A series of 

documents (Cox 1958, 1959b, 1960a) described several minor incidents that caused elevated 

external exposure rates as well as contamination in the pool waters and airborne contamination in the 

facility. The cotton cord filters used in the bypass filters had an operational life of approximately 6

weeks, and changes were required before disintegration. After 8 yr of satisfactory use, sintered 

stainless-steel filters replaced the cotton filters. The stainless steel filters failed after about 1 yr, 

possibly from the dissolution of nickel. In addition, high-exposure conditions were encountered when 

experimental beam ports were vacuumed to minimize the spread of contamination when removing

experiments. Radioactive particles were removed during vacuuming that caused exposure rates to 

exceed 10 R/hr at 4 in. Some contamination was dropped on blotter paper and on the floor, with 

exposure rates of 10 and 4 R/hr, respectively. The 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 (Building 9213) 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). The building was constructed in 1946 for 

storing highly enriched uranium processed at Y-12 prior to shipment off the site (Auerbach 1992). It 

began critical and near-critical experiments in August 1950 in support of upcoming reactor designs 

(e.g., ANP, liquid fuels, TSR-II, and HFIR). The facility, which has three assembly areas and a control 

room, was designed with safety features (water-filled windows and an intercom system) to minimize 

occupational exposures to personnel. It operated until March 1987 and shut down permanently in 

1992. Four incidents occurred:
Document No. ORAUT-TKBS-0012-2 Revision No. 01 Effective Date: 08/30/2006 Page 43 of 80

• 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 

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 terminated. 

The incident occurred in 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 overaddition 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 × 1017 fissions occurred. The incident occurred in the shielded 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 during assembly of enriched uranium 

metal that was paraffin-reflected. Two pieces of metal were brought together too quickly, 

which caused an excursion that yielded 1 × 1015 to 1 × 1016 fissions. There was 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 conducting radiation shielding experiments (Stapleton 1993) for the ANP Project. After the 

ANP Project, the facility was used by the Space Program to determine the effects of radiation on 

space capsules for the Mercury Project. In 1960, the Low-Temperature Irradiation Facility was 

installed to test the effects of radiation on metals and other materials at low temperatures. It also was 

used by a number of organizations for isotope production, materials irradiation, radiation shielding 

experiments, and training for reactor operators and students (DOE 1996a). It served as a model for 

university, industry, and government pool reactors. It began operating in 1951 for shielding 

experiments; in 1963, it was made available to the site as a general research reactor due to the 

shutdown of the Graphite Reactor. The BSR shut down in March 1987. It permanently shut down on 

September 10, 1991. Modifications to the reactor allowed it to run at a thermal power level of 2 MW 

when it was designated a general research reactor. The aluminum-clad, uranium-aluminum alloy fuel 

appears to have been highly enriched, similar to that used in the MTR.

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 other site reactors. 

The reactor controls were similar to those for the BSR. The PCA was used to train nuclear 

engineering students from around the country. It shut down in 1987 and has not operated since.

2.3.6.4 Oak Ridge 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 
Document No. ORAUT-TKBS-0012-2 Revision No. 01 Effective Date: 08/30/2006 Page 44 of 80

fuel. It was at one end of the pool. Though it initially operated at 20 MW, power levels up to 30 MW 

were reached in mid-1960. 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 powerproducing reactors. When operational, the ORR produced greater quantities of radioisotopes for 

research, medical, and industrial use than any reactor in the world. It contained the most advanced 

safety devices, including filters and scrubbers to minimize airborne releases. Reports indicate several 

releases from 1959 to 1961 (Cox 1959c, 1960b; Castro et al. 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 to measure fission-product gases from 

ceramic fuels (1960 to 1969)

• A molten salt test loop for the analysis of homogenous fuels (1959 to 1967)

• The maritime ship reactor test loop for testing structural materials and fuel pins for nuclear 

merchant ship applications (1959 to 1962)

• A pneumatic tube irradiation facility used to transfer irradiated samples from the ORR to a 

laboratory in Building 3001 (1968 to 1973)

• The GCR test loop to test new fuels for gas-cooled reactors (1960 to 1967)

• GCR Loop I for irradiation of unclad graphite fuel to study fission product releases (1962 to 

1963)

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 enabled testing of different 

shielding configurations. The TSF is on a knoll approximately 2.4 mi south-southeast of the ORNL 

main plant area. It enabled radiological measurements free of radiation scattering from the ground or 

enclosed structures. Four different reactor designs have been employed at the TSF. The original, 

TSR-I, was a box-shaped, 500-kW, MTR-type reactor. 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. It was replaced in 1960 with a spherically symmetric reactor (TSR-II) that operated at power 

levels up to 100 kW. The fourth reactor, the TSF-SNAP (Systems for Nuclear Auxiliary Power) 

reactor, was used at the facility at a power level 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 ft. Warning horns sound 3 min before the reactor is 

brought out of the shielded location. In addition, safety interlocks automatically shut the reactor down 

if a door or gate is open while the reactor is in the open (Stapleton 1993). There have been no known 

incidents at TSF. It is likely that external exposures to neutron and gamma radiations would have 

been present.
Document No. ORAUT-TKBS-0012-2 Revision No. 01 Effective Date: 08/30/2006 Page 45 of 80

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 built 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 DOSAR facility (Building 7709). When not in use, the reactor was 

stored in a steel and concrete vault below floor level. Ancillary buildings were behind a hill and 

approximately 900 ft from the reactor building. There were no occurrences in which the safety of 

personnel was compromised or in which a 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 was built between 1953 and 1956. HRE-2, sometimes referred to as the Homogeneous 

Reactor Test, was a homogeneous reactor that could produce electricity and act as a breeder reactor, 

irradiating 232Th source material to create 233U for use as reactor fuel. The reactor consisted of the 

core and the thorium blanket. It reached criticality in 1957 and operated at normal full power of 5 MW. 

After 16,295 MW-hr of operation, the reactor shut down in 1961 due to a hole 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 from October 30 until November 12, 1949, in an area of Melton 

Valley approximately 0.75 mi from the main ORNL site. The reactor operated for 221 hr at a 

maximum power output of 2.5 MW. The 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 

moderated and reflected the neutron flux. Liquid sodium was pumped through the bottom of the 

reactor shell for cooling. Radioactive releases were minimal with practically all gaseous fission 

products and probably other volatile fission products removed from the circulating fuel (Cottrell et al.

1955). Off-gas treatment was provided by nitrogen-cooled charcoal tanks used to hold up the 

gaseous wastes. Waste gas was released via the effluent stack when the wind speed was greater 

than 5 mph and the concentration was less than 0.8 μCi/mL. 

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. 

One of the principal purposes of the HFIR is the production of radioisotopes for research, medical, 

and industrial applications. Radioisotopes produced in the HFIR include transuranics (most notably 

252Cf), 192Ir, and 60Co. The HFIR is also used in materials research.
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In late 1986, the HFIR was shut down due to concerns over embrittlement of the reactor vessel. 

Following modifications, the HFIR restarted on April 18, 1989, and operated at low power levels 

(8.5 MW). The restart period revealed procedural inadequacies and the HFIR shut down again until 

January 1990. Full-power operation was reached on May 18, 1990 (Stapleton 1993).

The REDC, which operates in conjunction with the HFIR, includes the Transuranic Facility (Building 

7920) and the TURF (Building 7930). These facilities are described in Sections 2.2.69 and 2.2.70, 

respectively. 

2.3.6.10 Molten Salt Reactor Experiment

The MSRE (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. It was initially fueled with 235U, which was replaced with 233U in 

1968. In 1969, the reactor 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 (Berner, Tiner, and Gossley 1998). More 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. 

2.3.6.11 Spallation Neutron Source

The SNS site is on 80 acres of Chestnut Ridge about 2 mi northeast of the main ORNL site. The 

SNS, an accelerator-based neutron source, will provide neutron beams with up to 10 times more 

intensity than any other source in the world. Construction began in 1999 and is scheduled for 

completion in 2006.
Document No. ORAUT-TKBS-0012-2 Revision No. 01 Effective Date: 08/30/2006 Page 47 of 80

REFERENCES

AIMS (Advanced Integrated Management Services) and CDM Federal Programs Corporation, 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, March. 

Alexander, W. A., S. Huang, T. W. Oakes, H. M. Hubbard, and J. S. Eldridge, 1982, Radionuclide 

Characterization of Subsurface Soil on the Site of Building 3505 at Oak Ridge National 

Laboratory, ORNL/TM-8479, Union Carbide Corporation, Oak Ridge National Laboratory, Oak 

Ridge, Tennessee, December.

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, 

October 3. 

ATG (Allied Technology Group), 1996, HAZWOPER Project Documents for Demolition of the Waste 

Evaporator Facility, Building 3506, at Oak Ridge National Laboratory, Oak Ridge, ORNL/ER347, Oak Ridge National Laboratory, Oak Ridge, Tennessee.

Auerbach, S. I., 1992, A History of the Environmental Sciences Division of Oak Ridge National 

Laboratory, ORNL/M-2732, Martin Marietta Energy Systems, Oak Ridge National Laboratory, 

Oak Ridge, Tennessee.

Author unknown, 1958, “Information for Review of Graphite Reactor Operation,” intra-laboratory 

correspondence to distribution, Oak Ridge National Laboratory, Oak Ridge, Tennessee, 

December 3.

Berman, S. N., P. F. Tiner, and R. C. Gosslee, 1998, Environmental Health and Safety Plan for the 

Molten Salt Reactor Experiment Remediation Project at Oak Ridge National Laboratory, 

ORNL/ER-326/R1, Lockheed Martin Energy Systems, Oak Ridge National Laboratory, Oak 

Ridge, Tennessee, January.

BN (Bechtel National), 1994, Site Characterization Report for Building 3515 at Oak Ridge National 

Laboratory, Oak Ridge, Tennessee, ORNL/ER/Sub/87-99053/73, Oak Ridge National 

Laboratory, Oak Ridge, Tennessee, August.

Brooksbank, R. E. Sr., 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.

Burnett, T. J., 1965, Contamination Released in Loading Transfer, intra-laboratory correspondence, 

Oak Ridge National Laboratory, Oak Ridge, Tennessee, August 30.

Casto, W. R., A. R. Costner, Jr., J. A. Cox, C. D. Cagle, S. S. Hurt, III, L. E. Stanford, W. H. Tabor, 

and K. W. West, 1961, “Information for Review of ORR Operation,” intra-laboratory 

correspondence to distribution, Oak Ridge National Laboratory, Oak Ridge, Tennessee, 

December 20.
Document No. ORAUT-TKBS-0012-2 Revision No. 01 Effective Date: 08/30/2006 Page 48 of 80

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, Alameda, California, July.

Cottrell, W. B., H. E. Hungerford, J. K. Leslie, and J. L. Meem, 1955, Operation of the Aircraft Reactor 

Experiment, ORNL-1845, Carbide and Carbon Chemicals Company, Oak Ridge National 

Laboratory, Oak Ridge, Tennessee, August 22.

Cox, J. A., 1958, “Information for Review of LITR Operation,” intra-laboratory correspondence to 

distribution, Oak Ridge National Laboratory, Oak Ridge, Tennessee, December 9.

Cox, J. A., 1959a, “Information for Review of Graphite Reactor Operation,” intra-laboratory 

correspondence to distribution, Oak Ridge National Laboratory, Oak Ridge, Tennessee, 

November 6.

Cox, J. A., 1959b, “Information for Review of LITR Operation,” intra-laboratory correspondence to 

distribution, Oak Ridge National Laboratory, Oak Ridge, Tennessee, November 11.

Cox, J. A., 1959c, “Information for Review of ORR Operation,” intra-laboratory correspondence to 

distribution, Oak Ridge National Laboratory, Oak Ridge, Tennessee, November 19.

Cox, J. A., 1960a, “Information for Review of LITR Operation,” intra-laboratory correspondence to 

distribution, Oak Ridge National Laboratory, Oak Ridge, Tennessee, November 4.

Cox, J. A., 1960b, “Information for Review of Oak Ridge Research Reactor Operation,” intralaboratory correspondence to distribution, Oak Ridge National Laboratory, Oak Ridge, 

Tennessee, December 1.

DOE (U.S. Department of Energy), 1996a, Removal Site Evaluation Report on the Bulk Shielding 

Facility at Oak Ridge National Laboratory, Oak Ridge, Tennessee, DOE/OR/01-1516&D1, 

Oak Ridge Operations Office, Oak Ridge, Tennessee.

DOE (U.S. Department of Energy), 1996b, Removal Site Evaluation Report for the Isotope Facilities at 

Oak Ridge National Laboratory, Oak Ridge, Tennessee, DOE/OR/01-1501&D1, Oak Ridge 

Operations Office, Oak Ridge, Tennessee.

Fleming, K. N., 2003, “Activities that took place in the ORNL Biology Buildings located @ Y-12,” 

documented communication, Oak Ridge Associated Universities Team, Oak Ridge, 

Tennessee, ca August. [SRDB Ref ID: 22812]

Fleming, K. N., 2006, “ORNL Environmental Air Data,” documented communication, Oak Ridge 

Associated Universities Team, Oak Ridge, Tennessee, April 20. [SRDB Ref ID: 22813]

Holland, L. B., 1970, Tower Shielding Reactor II, Design and Operation Report: Vol. 1 – Description, 

ORNL-TM-2893, Vol. 1, Union Carbide Corporation, Oak Ridge National Laboratory, Oak 

Ridge, Tennessee, October 7.

King, L. J., and W. T. McCarley, 1960, "'Intercycle Evaporator Explosion, Building 3019,' and 

'Decontamination of Building 3019,' papers presented at a Chemical Technology Division 

Seminar, July 16", letter to J. C. Bresee, Union Carbide Nuclear Company, Oak Ridge 

National Laboratory, Oak Ridge, Tennessee, July 27.
Document No. ORAUT-TKBS-0012-2 Revision No. 01 Effective Date: 08/30/2006 Page 49 of 80

Klima, B. B., 1962, "Building 3019 Vessel Off-Gas Filter," ORNL Central Files 62-10-108, letter to J. 

C. Bresee, Union Carbide Nuclear Company, Oak Ridge National Laboratory, Oak Ridge, 

Tennessee, October 30. 

Kuhaida, A. J. Jr., and A. F. Parker, 1997, Site Descriptions of Environmental Restoration Units at 

Oak Ridge National Laboratory, Oak Ridge, TN, ORNL/ER-391, Advanced Sciences, Oak 

Ridge National Laboratory, Oak Ridge, Tennessee, February.

LMERC (Lockheed Martin Energy Research Corporation), 1997a, Metals and Ceramics Division 

History 1946-1996, ORNL/M-6589, Oak Ridge National Laboratory, Oak Ridge, Tennessee, 

September.

LMES (Lockheed Martin Energy Systems), 1997a, Final Deactivation Project Report on the High 

Radiation Level Analytical Facility, Building 3019B at Oak Ridge National Laboratory, Oak 

Ridge, Tennessee, ORNL/ER-420, Oak Ridge National Laboratory, Oak Ridge, Tennessee, 

September.

LMES (Lockheed Martin Energy Systems), 1997b, Final Deactivation Project Report on the Alpha 

Powder Facility, Building 3028, at Oak Ridge National Laboratory, Oak Ridge, Tennessee, 

ORNL/ER-399, Oak Ridge National Laboratory, Oak Ridge, Tennessee, April.

LMES (Lockheed Martin Energy Systems), 1997c, Final Deactivation Project Report on the Source 

Development Laboratory, Building 3029, Oak Ridge National Laboratory, Oak Ridge, 

Tennessee, ORNL/ER-400, Oak Ridge National Laboratory, Oak Ridge, Tennessee, May.

LMES (Lockheed Martin Energy Systems), 1997d, Final Deactivation Report on the Radioisotope 

Production Lab-C, Building 3030, at Oak Ridge National Laboratory, Oak Ridge, Tennessee, 

ORNL/ER-408, Oak Ridge National Laboratory, Oak Ridge, Tennessee, August.

LMES (Lockheed Martin Energy Systems), 1997e, Final Deactivation Report on the Radioisotope 

Production Lab-D, Building 3031, at Oak Ridge National Laboratory, Oak Ridge, Tennessee, 

ORNL/ER-409, Oak Ridge National Laboratory, Oak Ridge, Tennessee, August.

LMES (Lockheed Martin Energy Systems), 1997f, Final Deactivation Report on the Radioisotope 

Production Lab-E, Building 3032, at Oak Ridge National Laboratory, Oak Ridge, Tennessee, 

ORNL/ER-414, Oak Ridge National Laboratory, Oak Ridge, Tennessee, September.

LMES (Lockheed Martin Energy Systems), 1997g, Final Deactivation Report on the Radioactive Gas 

Processing Facility, Building 3033, and the Actinide Fabrication Facility, Building 3033A, at 

Oak Ridge National Laboratory, Oak Ridge, Tennessee, ORNL/ER-419, Oak Ridge National 

Laboratory, Oak Ridge, Tennessee, September.

LMES (Lockheed Martin Energy Systems), 1997h, Final Deactivation Report on the Tritium Target 

Facility, Building 7025, at Oak Ridge National Laboratory, Oak Ridge, Tennessee, ORNL/ER406, Oak Ridge National Laboratory, Oak Ridge, Tennessee, August.

LMES (Lockheed Martin Energy Systems), 1997i, Final Deactivation Report on the Integrated Process 

Demonstration Facility, Building 7602, Oak Ridge National Laboratory, Oak Ridge, Tennessee, 

ORNL/ER-418, Oak Ridge National Laboratory, Oak Ridge, Tennessee, September.
Document No. ORAUT-TKBS-0012-2 Revision No. 01 Effective Date: 08/30/2006 Page 50 of 80

LMES (Lockheed Martin Energy Systems), 1997j, Final Deactivation Report on the Radioisotope Area 

Services, Building 3034, at Oak Ridge National Laboratory, Oak Ridge, Tennessee, 

ORNL/ER-415, Oak Ridge National Laboratory, Oak Ridge, Tennessee, September.

Mandry, G. J., and R. W. Grisham, 1994, Decontamination Project for Cell G of the Metal Recovery 

Facility at Oak Ridge National Laboratory, Oak Ridge, Tennessee, ORNL/ER-219, Allied 

Technology Group, Freemont, California, February.

Mandry, G. J., and W. Snedaker, 1994, Decontamination and Decommissioning of the Fission 

Product Pilot Plant at the Oak Ridge National Laboratory, CONF-9404313-1, Martin Marietta 

Energy Systems, Oak Ridge National Laboratory, Oak Ridge, Tennessee.

MMES (Martin Marietta Energy Systems), 1994, The ORNL Chemical Technology Division, 1950–

1994, ORNL/M-2733/R1, Oak Ridge National Laboratory, Oak Ridge, Tennessee, October.

MMES (Martin Marietta Energy Systems), 1995, Work Plan for the Isotopes Facilities Deactivation 

Project at Oak Ridge National Laboratory, ORNL/ER-249/R1, Oak Ridge National Laboratory, 

Oak Ridge, Tennessee, May.

Mostella, W. B. Jr., 1994, Level III Baseline Risk Evaluation for Building 3505 at Oak Ridge National 

Laboratory, Oak Ridge, Tennessee, ORNL-6846, Martin Marietta Energy Systems, Oak Ridge 

National Laboratory, Oak Ridge, Tennessee, December.

ORNL (Oak Ridge National Laboratory), 1953, Oak Ridge National Laboratory Building List, Oak 

Ridge National Laboratory, Oak Ridge, Tennessee.

ORNL (Oak Ridge National Laboratory), 1962, Building 4507 High Level Chemical Development 

Facility – Hazards Evaluation, Vol. 10, ORNL/TM-321, Oak Ridge, Tennessee.

ORNL (Oak Ridge National Laboratory), 1986, The ORNL Surplus Facilities Management Program 

Maintenance and Surveillance Plan for Fiscal Year 1984, ORNL/TM-10268, Oak Ridge, 

Tennessee.

Parr, P. D., A. R. Medley, R. J. Forbes, and P. E. Cox, 2002, ORNL Land and Facilities Plan, 

ORNL/TM-2002/1, 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, Union Carbide Corporation, Oak Ridge National Laboratory, Oak Ridge, 

Tennessee, August 25.

Quist, A. S., 2000, A History of Classified Activities at Oak Ridge National Laboratory, ORCA-7, Oak 

Ridge Classification Associates, Oak Ridge, Tennessee, September 29.

Rupp, A. F., and J. A. Cox, 1955, Operation of the ORNL Graphite Reactor and the Low-Intensity Test 

Reactor - 1954, ORNL-1866, Union Carbide Nuclear Company, Oak Ridge National 

Laboratory, Oak Ridge, Tennessee, September 16.

Rupp, A. F., and E. J. Witkowski, 1955, RaLa Production – 1954, Central Files 55-1-211, Union 

Carbide Nuclear Company, Oak Ridge National Laboratory, Oak Ridge, Tennessee.
Document No. ORAUT-TKBS-0012-2 Revision No. 01 Effective Date: 08/30/2006 Page 51 of 80

Stanley, W. M., 1954, “Area Contamination on April 29, 1954,” inter-company correspondence to C. E. 

Larson, Carbide and Carbon Chemicals Company, Oak Ridge National Laboratory, Oak 

Ridge, Tennessee, April 30.

Stapleton, D. R., 1993, A Brief History of the Research Reactors Division of Oak Ridge National 

Laboratory, ORNL/M-2342, Martin Marietta Energy Systems, Oak Ridge National Laboratory, 

Oak Ridge, Tennessee.

Thompson, W. E. Jr., 1949, A History of the Radioactive Barium-Lanthanum Process and Production, 

ORNL-246, Carbide and Carbon Chemicals Corporation, Oak Ridge National Laboratory, Oak 

Ridge, Tennessee, June 22.

Tiner, P. F., and M. S. Uziel, 1994, Surface Radiological Investigations at the 0816 Site, Waste Area 

Grouping 13, Oak Ridge National Laboratory, Oak Ridge, Tennessee, ORNL/ER-291, Martin 

Marietta Energy Systems, Oak Ridge National Laboratory, Oak Ridge, Tennessee, December.

Van Hoesen, S. D., and H. R. Vogel, 2001, Facility Environmental Vulnerability Assessment, 

ORNL/TM-2001/123, Oak Ridge National Laboratory, Oak Ridge, Tennessee.
Document No. ORAUT-TKBS-0012-2 Revision No. 01 Effective Date: 08/30/2006 Page 52 of 80

GLOSSARY

barites concrete

Concrete containing barium sulfate (BaSO4).

calutron (California University Cyclotron)

An accelerator used for the electromagnetic separation of isotopes based on their mass.

supernatant

A highly radioactive liquid overlying material deposited by settling, precipitation, etc.; also 

called supernate.
Document No. ORAUT-TKBS-0012-2 Revision No. 01 Effective Date: 08/30/2006 Page 53 of 80

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

Environmental Sciences Division/National Oceanic and Atmospheric 

Administration (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 Station

900 Firearms Range 745-A,-B

0900A Firing Range Storage

0900B Firing Range Canopy

901 161 kilovolt (kV) Substation 501-H

902 Main Reservoir 803

903 Bethel Valley Church

907 Walker Branch Watershed Laboratory

910 Booster Pump Station

926 1,500,000 gal Steel Water Reservoir

0926A Valve House

0926B Emergency Generator

927 Storage Building

929 Ish Creek Weir

932 Walker Branch Watershed (WBW) Soil Block 1

933 WBW Soil Block 2

934 WBW Subsurface Weir Instrument Trailer

935 WBW Subsurface Weir

936 Environmental Sciences Division (ESD) Twin Towers Walker Branch

937

Atmospheric Turbulence and Diffusion Division (ATDD)/NOAA Rain Gauge 2 

Building

940 Instrument Building 1

941 Instrument Building 2

0945A Rain Gauge 1 Site

0945B Rain Gauge 2 Site

ATTACHMENT 2A

OAK RIDGE NATIONAL LABORATORY FACILITY INDEX

Page 1 of 20
Document No. ORAUT-TKBS-0012-2 Revision No. 01 Effective Date: 08/30/2006 Page 54 of 80

Facility 

ID Description

Old 

numbering

0945C Rain Gauge 3 Site

0945D Rain Gauge 4 Site

0945E Through-Fall Experiment Site

0945F Through-Fall 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 Building

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 Solid Waste Storage Area (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 (COM)

1061 Health Protection Services Office Building

1062 West Office Building

1096 Passenger Shelter, West Parking Lot

111UNV 111 Union Valley (UNV) Road

115UNV Receiving, Acceptance, Testing & Storage Facility

1503 Environmental Systems Laboratory

1504 Aquatic Ecology Laboratory

1505 Environmental Sciences Laboratory

1506 Plant Sciences Laboratory

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

1513 Aquatic Storage Building 4

1514 Aquatic Storage Building 5

1515 Aquatic Storage Building 6

ATTACHMENT 2A

OAK RIDGE NATIONAL LABORATORY FACILITY INDEX

Page 2 of 20
Document No. ORAUT-TKBS-0012-2 Revision No. 01 Effective Date: 08/30/2006 Page 55 of 80

Facility 

ID Description

Old 

numbering

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 Northwest 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 and Air Conditioning (AC) Service Centers

2013 West Maintenance Service Center 719-A

2016 Security Patrol Headquarters 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 and AC Service Center 717-C or 305

2019 Laser Laboratory

2024 Quality Assurance and Inspection Office Building

2026 Radioactive Materials Analytical Laboratory

2026A Tank Southeast of Building 2026

2032 Manhole (MH) 240 Monitoring Station

2033 Measurements and Controls Building

2034 MH 95 Monitoring Station

2061 Stack

2069 Change House 708

2087 Storage Building

2088 Emergency Generator Building for 2000

2092 Storage Building

2093 Environmental Storage Building

2097 Cooling Tower For 2001

2098 Substation No. 6-3

2099 Building 2026 monitoring control station

2101 Liquid and Gaseous Waste Operations Department (LGWOD) Health and

Hygiene Support Building

2102 Personnel Contamination Monitor Trailer

ATTACHMENT 2A

OAK RIDGE NATIONAL LABORATORY FACILITY INDEX

Page 3 of 20
Document No. ORAUT-TKBS-0012-2 Revision No. 01 Effective Date: 08/30/2006 Page 56 of 80

Facility 

ID Description

Old 

numbering

2500 Fire Station And Protective Services Headquarters 720

2506 Plant and Equipment (P&E) Maintenance Shop and Support Building 717-B

2508 Instrumentation Trailer at W-Tanks

2510 Air Compressor Building

2517 Personnel Development Offices 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 Aeration 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 Waste Handling and Packaging Plant Development Facility

2528A Storage Tank

2531 Liquid Low-Level Waste (LLLW) Evaporator Building

2532 High-Level Waste 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 Evaporator Service Tank and 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 gal Fuel Oil Storage Facility 717-I

2568 Cell Ventilation and Off-Gas Filter for 2531

2572 Emergency Generator for 2500 502 #9

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

ATTACHMENT 2A

OAK RIDGE NATIONAL LABORATORY FACILITY INDEX

Page 4 of 20
Document No. ORAUT-TKBS-0012-2 Revision No. 01 Effective Date: 08/30/2006 Page 57 of 80

Facility 

ID Description

Old 

numbering

2632 5000-kV 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 MH 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 and 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 (LITR) 106

3008 Security Patrol Storage 103

3009 Pump House for Building 3010

3010 Bulk Shielding Reactor (BSR)

3010A BSR Support Facility, North 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 Laboratory

3020 Off-Gas Stack for 3019

3023 North Tank Farm 206

3025E Irradiated Material Examination and Testing (IMET) Hot Cell Facility

3025M Solid State Office and 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

ATTACHMENT 2A

OAK RIDGE NATIONAL LABORATORY FACILITY INDEX

Page 5 of 20
Document No. ORAUT-TKBS-0012-2 Revision No. 01 Effective Date: 08/30/2006 Page 58 of 80

Facility 

ID Description

Old 

numbering

3029 Source Development Laboratory 909

3030 Radioisotope Production Laboratory-C 908

3031 Radioisotope Production Laboratory-D 907

3032 Radioisotope Production Laboratory-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 Station

3080 Superconductivity Laboratory

3082 Data Concentrator 2, Waste Operations Control Center (WOCC) Data 

Acquisition System DAS

3083 Neutron Spectrometer Station 1

3084 Neutron Spectrometer Station 2

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 and 3032

3100 Source and Special Material Vault

3102 Heat Exchanger No. 2 – ORR

3103 Cooling Tower No. 3 – ORR

3104 West Complex Maintenance Shop

3105 LGWOD Health Physics (HP) Office Building

3106 Cell Vent Filter for 4501, 4505, and 4507

3107 25-meter Target House

3108 Filter House for Building 3019

3109 Process 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 Building

ATTACHMENT 2A

OAK RIDGE NATIONAL LABORATORY FACILITY INDEX

Page 6 of 20
Document No. ORAUT-TKBS-0012-2 Revision No. 01 Effective Date: 08/30/2006 Page 59 of 80

Facility 

ID Description

Old 

numbering

3117 BSR Cooling Tower

3117A Sulfuric Acid tank

3118 Radioisotope Production Laboratory-H

3119 BSR Heat Exchanger and Pump House

3121 Cell Off-Gas Filter House for 3019b

3123 Diesel Generator

3125 3039 Stack Area Emergency Generator

3126 Normal Off-Gas (Charcoal) Filter Pit for ORR

3127 Plutonium Storage Vault

3129 Personnel Monitoring Station

3130 Waste Operation Control Center

3131 Emergency Generator

3132 Emergency Generator for 3127, 3129, and 3027

3133 Bethel Valley (BV) Valve Box 1A

3135 Sentry Post 80, Building 3019

3136 Equipment Test Facility – 3019

3137 Surface Science Laboratory

3138 Roof Thermal Research Center

3139 Cell Ventilation (CV) Filters – ORR

3140 CV Filters for 3026

3144 Roof Research Center

3145 LGWOD Storage Building

3146 Emergency Generator for 3020 Stack

3147 Efficiency and Renewable Research Office Building

3150 Ceramics and Thin Film Laboratory

3153 Envelope Systems Research Center

3154 MH 112 Monitoring Building

3155 MHs 114 and 234 Monitoring

3156 Energy Division Office Building

3158 North CV Duct Monitoring Building

3159 South CV Duct Monitoring Building

3160 3019 Motor Control Center #1 and #2

3161 Quality Services Division (QSD) Storage Building

3162 QSD Storage

3163 West Weatherport

3164 West Weatherport

3500 Instrumentation and Controls (I&C) Division Offices

3501 Sewage Pumping Station

3502 East Research Service Center 706-HD

3502B Data Concentrator 4, WOCC DAS 3502

3503 High Radiation Level Chemical Engineering Laboratory 706-HB

3503A 3503 Storage Pad

3504 Waste Research Building/Geosciences Laboratory

3505 Metal Recovery Facility

3507 South Tank Farm 206

3508 I&C Metrology and Calibration

ATTACHMENT 2A

OAK RIDGE NATIONAL LABORATORY FACILITY INDEX

Page 7 of 20
Document No. ORAUT-TKBS-0012-2 Revision No. 01 Effective Date: 08/30/2006 Page 60 of 80

Facility 

ID Description

Old 

numbering

3513 Settling Basin 206

3515 Fission Products Laboratory No. 1

3517 Fission Products Development Laboratory

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 Laboratory

3542 Storage Building for 3506 and 3517

3543 Maces Storage Building

3544 Process Waste Treatment Plant

3544A ORNL Waste Water Treatment Trailer

3544B Filter Press Building

3546 Computing and Computational Sciences Directorate (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 Laboratory

3584 Solvent Operations Contaminant 713-UA

3587 Mail Services Building

3592 Coal Conversion Facility

3594 Waste Management Storage

3597 Hot Storage Garden

3598 Emergency Generator for 3500 Area

3602 Cylinder Tank Storage for 3525

3605 Treatment, Storage, and Disposal (TSD) Storage Building

3606 South Office Annex

3607 Cask Storage Building

3608 Process Waste Treatment Plant

3609 Substation No. 25-1-C

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 Pumping Station, WC-10, 11, 12, 13, 14

3619 White Oak Creek Gauging Station

3620 Hot Off-Gas Collection Pot

ATTACHMENT 2A

OAK RIDGE NATIONAL LABORATORY FACILITY INDEX

Page 8 of 20
Document No. ORAUT-TKBS-0012-2 Revision No. 01 Effective Date: 08/30/2006 Page 61 of 80

Facility 

ID Description

Old 

Numbering

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 and Administration Building – North

4500S Central Research and Administration Building – South

4501 Radiochemistry Laboratory 4501

4503 Standby Emergency Generator for 4500N

4505 Experimental Engineering 4501

4507 High Level Chemical Dev Laboratory

4508 Metals and Ceramics Laboratory

4509 Central Chilled Water Plant

4510 Cooling Tower for 4509

4511 Cooling Tower for 4509

4512 Laboratory Emergency Response Center

4513 High Temperature Materials Laboratory (HTML) Electrical Substation

4514 Generator – HTML

4515 HTML

4516 HTML Cooling Tower

4521 Cooling Tower for Building 4509

4556 Filter Pit for Building 4507

4557 Sentry Post, No. 7B

4559 Passenger Shelter

4560 4512 Lift Station

4561 Flammable Storage, 4509

5000 Main Portal Building 4502

5002 Science and Technology Partnerships Office Building

5100 Joint Institute of Computer Science

5500 High Voltage Accelerator Laboratory 4503

5500A South Office Annex

5505 Transuranium Research Laboratory

5507 Controlled Experiment Atmosphere

5507A Research, Development, Testing, and Evaluation Facility

5510 Analytical Massspectrometry Laboratory

5510A QSD Metrology and Intercomparisons Studies Laboratories

5554 Electrical Substation for 5505

5600 Computational Sciences Building

5700 Research Office Building

5800 Engineering Technology Facility

6000 Holifield Radioactive Ion Beam Facility

6000B Atomic Physics Research Laboratory

6001 Cooling Tower for 6000

6005 Gas Compressor House for 6000

6007 Dormitory for Joint Institute for Heavy Ion Research JIHIR

6008 JIHIR Office/Laboratory Facility

ATTACHMENT 2A

OAK RIDGE NATIONAL LABORATORY FACILITY INDEX

Page 9 of 20
Document No. ORAUT-TKBS-0012-2 Revision No. 01 Effective Date: 08/30/2006 Page 62 of 80

Facility 

ID Description

Old 

Numbering

6010 Oak Ridge Electron Linear Accelerator

6011 Computational Physics and Engineering Building

6012 Computer Sciences Research

6013 Chemical Feed System Enclosure

6014 Compressor Building, 6001 Fire Protection System

6016 Outfall 314 Dechlorination System

6025 Computational Physics and Engineering

6551 West Reservoir on Haw Ridge

6552 East Reservoir on Haw Ridge

6553 Standby Generator and 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 Environmental Restoration (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

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 and Ironworking Shop

7003 Welding and Brazing Shop

7005 Lead Shop

7006 Storage Building

7007 Paint Shop

7009 Carpenter Shop

7010 Dry Lumber Storage

7012 Central Fabrication Shop

ATTACHMENT 2A

OAK RIDGE NATIONAL LABORATORY FACILITY INDEX

Page 10 of 20
Document No. ORAUT-TKBS-0012-2 Revision No. 01 Effective Date: 08/30/2006 Page 63 of 80

Facility 

ID Description

Old 

numbering

7013 Chemical Reuse Building

7015 Metal Storage and Cutting Facility

7018 Bulk Receiving and Stores Building

7019 Research Reactors Division Warehouse Facility – Category C Storage

701SCA 701 Scarboro Road (SCA)

7020 Interim Grounds Equipment Storage Building

7020AR Heating, Ventilation, and Air-Conditioning (HVAC) Decontamination Facility

7020B Temporary Waste Storage Facility

7020C Temporary Waste Storage Facility

7020D Office Trailer – SWSA 6

7020E Temporary Waste Storage Facility

7020F HP Office Trailer

7021 Fabrication Equipment Storage

7022 Gas Cylinder Storage Shed

7025 Tritium Target Preparation Facility

7026 Metals and Ceramics Storage

7030 Heavy Equipment 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 Temporary Waste Storage Pad

7039 Material Staging Facility

7040 Gas Cylinder Storage

7041 Storage Building

7042 Core Storage Building

7043 Personnel Shelter – West of 7000

7044 Substation 27-8, West of 7003

7046 Environment, Safety, Health and Quality Office Trailer

7053 Personnel Shelter – North

7055 Grounds Equipment Storage Facility

7057 Sandblast Cleaning Facility

7058 Regulator Repair Facility

7060 Steel Yard

7061 Environmental Surveillance 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

ATTACHMENT 2A

OAK RIDGE NATIONAL LABORATORY FACILITY INDEX

Page 11 of 20
Document No. ORAUT-TKBS-0012-2 Revision No. 01 Effective Date: 08/30/2006 Page 64 of 80

Facility 

ID Description

Old 

numbering

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, Pedestrian Gate 7012

7075 Waste Storage Building

7077 Craft Support Office Bldg.

7077A Reservation Services Offices

7078A Bechtel-Jacobs Company (BJC) Office Trailer

7078B BJC Office Trailer

7078C BJC Office Trailer

7078D BJC Office Trailer

7078E BJC Office Support Trailer

7078F BJC Office Trailer

7078G Sprinkler Control Building

7078H Sprinkler Control Building

7079 Bottle Storage Building

7080 Cardboard Compressor

7081 Portable Generator Storage Shed

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

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 Experiment (HRE) Facility

7501 Septic Tank

7502 Radioactive Waste Evaporator

7503 Molten Salt Reactor Experiment (MSRE)

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

ATTACHMENT 2A

OAK RIDGE NATIONAL LABORATORY FACILITY INDEX

Page 12 of 20
Document No. ORAUT-TKBS-0012-2 Revision No. 01 Effective Date: 08/30/2006 Page 65 of 80

Facility 

ID Description

Old 

numbering

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 – Tower Shielding Facility (TSF) Water Supply 20035

7554 Cooling Tower for 7500

7554A Morrison-Knudson (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 Pumping Station, Tanks T1, T2

7568 Sentry Post 19, High Flux Isotope Reactor (HFIR) Area

7569 LLLW Collection Tank, WC-20

7571 30-Meter Meteorological Tower

7572 Contact Handled, Transuranic (CH-TRU) Waste Storage Facility

7574 Waste Storage Facility

7575 SWSA 7

7576 Bulk Contaminated Soil Facility

7577 Transuranic (TRU) Storage Facility

7578 Class 34 Waste Retrievable Storage

7580 Solid Low Level Waste Staging Facilities

7582 LGWOD Spare Parts Storage Facility

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 Robotics and Process Systems (R&PS) Division Office Building

7602 Integrated Process Demonstration Facility

7603 Remote Operations and Maintenance

7603A Fuel Oil Storage Tanks

7604 Utility Building

7605 Storage Building

7606A Robotics Research and Development (R&D) Laboratory

7606B Research Service-Maintenance Building

7607 Experimental Gas-Cooled Reactor (EGCR) River Pump Station

7608 Plasma Torch Cutting Demonstration Facility

7609 Stack Monitoring House

7610 Storage House – R&PS

7611 Sentry Post 30, R&PS Complex

ATTACHMENT 2A

OAK RIDGE NATIONAL LABORATORY FACILITY INDEX

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Facility 

ID Description

Old 

numbering

7613 Waste Retention Basin

7614 Exhaust Stack

7615 Radiochemical Engineering Development Center (REDC) Storage

7616 Septic Tank

7618 Diesel Generator for 7600

7619 Cooling Tower

7621 Headquarters Building

7623 Bathhouse

7624 Robotics Storage Building

7630 Low-Risk Inactive Storage Facility

7631 Low-Risk Inactive Storage Facility

7632 Low-Risk Inactive Storage Facility

7633 Low-Risk Inactive Storage Facility

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 BJC Office Trailer

7658B BJC Office Trailer

7658C BJC Office Trailer

7658D BJC Office Trailer

7659 Leaking Gas Cylinder Area

7661 Electrical Utility Building

7662 Emergency Generator

7666 Environmental Emergency 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 TSF 20035

7701 TSF – Pool and 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 Research Reactor (HPRR)

7710 HPRR-DOSimetry Applications Research (DOSAR) Facility

7711 Process Waste Basin for 7709

7712 DOSAR Low Energy Accelerator

7716 Filter Pump House Maintenance Pool

ATTACHMENT 2A

OAK RIDGE NATIONAL LABORATORY FACILITY INDEX

Page 14 of 20
Document No. ORAUT-TKBS-0012-2 Revision No. 01 Effective Date: 08/30/2006 Page 67 of 80

Facility 

ID Description

Old 

numbering

7720 Civil Defense Bunker

7735 Radiation Calibration Laboratory

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 Exclusion Area 20036

7755 DOSAR (HPRR) Reservoir

7756 Meter House

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 and Treatment System

7802C Deep Monitoring Well #1 Building

7802D Deep Monitoring Well # 2 Building

7802E Sludge Removal Test Tank

7802F Radiation Monitoring Equipment Storage Building

7802N SWSA 5 North Trench Disposal Area

7803 Laboratory Trailer

7805 Waste Pit No. 1

7806 Waste Pit No. 2

7807 Waste Pit No. 3

7808 Waste Pit No. 4

7809 Waste Trench No. 5

7810 Chemical Waste Trench No. 6

7810A Interim Non-regulated 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 Low Level Waste (LLW) Storage Pad

7823 LLW Staging/Storage Facility

7823A Underground Storage Facility Well

7823B Temporary Waste Storage Facility

7823C Temporary Waste Storage Facility

7823D Temporary Waste Storage Facility

7823E Temporary Waste Storage Facility, Tent

7823F Storage Shed (SWSA 5)

7824 Waste Examination And Assay Facility

7824A Waste Examination Assay Facility (WEAF) Support Facility Trailer

7826 TRU Drum Storage Facility

ATTACHMENT 2A

OAK RIDGE NATIONAL LABORATORY FACILITY INDEX

Page 15 of 20
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Facility 

ID Description

Old 

numbering

7827 Shielded Dry Well Facility

7829 Shielded Dry Well Facility

7830 Melton Valley Storage Facility

7830A Hazardous Waste Storage Tank

7831 Field Office and Compactor Facility

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 Temporary LLW Storage Facility

7842A Liquid Low-Level Waste Solidification Project (LWSP) II Solidified Waste 

Storage

7842B Temporary 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 Creek Weir and Gauging Station

7852 Old Hydrofracture Facility

7853 LGWOD Storage Building

7854 Drilling Equipment Storage

7855 Concrete Cask Storage Facility

7855A SWSA 5 Equipment Tent

7856 Melton Valley Storage Tank (MVST) Capacity Increase Project

7857 Monitoring Station

7858 White Oak Lake Storage Building

7859 Sample Equipment Storage Building

7859A Sample Storage Buildings

7860 New Hydrofracture Facility

7863 General Storage for 7860

7864 Gauging Station – East Seep

7865 Gauging Station – West Seep

7866 Sampling Station – 7500 Branch

7867 Weir - Melton Branch

7868 Sampling Station – White Oak Creek

7869 Stream Flow Monitoring Station 5

7870 RUBB Structure

7871 Stream Flow Monitoring Station 3

7872 Stream Flow Monitoring Station 4

7874 Storage Building Southwest SWSA 4

7875 Monitoring Storage Building

7876 Health Physics Office Trailer

ATTACHMENT 2A

OAK RIDGE NATIONAL LABORATORY FACILITY INDEX

Page 16 of 20
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Facility 

ID Description

Old 

numbering

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 NonDestructive Assay (NDA) Trailer, Waste Processing Facility

7880J NonDestructive Examination (NDE) Trailer, Waste Processing Facility

7880K Access Control Point, Waste Processing Facility

7880L DOE Office Trailer, Waste Processing Facility

7880M DOE Office Trailer, Waste Packaging Facility

7880N Construction Management, Waste Packaging Facility

7880P Break Facility, Waste Packaging Facility

7880Q Restroom Facility, Waste Packaging Facility

7880R Foster Wheeler Environmental Corporation (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 SWSA Office Trailer

7892 Storage Building, 7856 Operations

7893 Passenger Shelter

7894 Waste Area Grouping (WAG) 6 Monitoring Station 3

7900 HIFR

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 Building for 7911

7911C Instrument Shed for 7911

7912 Fan Shed And Electrical Equipment for 7900

7913 Filter Pit for 7911 Stack

ATTACHMENT 2A

OAK RIDGE NATIONAL LABORATORY FACILITY INDEX

Page 17 of 20
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Facility 

ID Description

Old 

numbering

7914 Equipment and Parts Storage Building

7914A HFIR Carpentry Shop

7915 Operations Storage Building

7916 HFIR Cooling Tower Water Treatment

7917 Research Reactors Office Building

7918 REDC Office and Training Building

7920 REDC

7921 Emergency Generator for 7920

7922 Breeching and Fan Area and Electrical Equipment 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 Thorium-Uranium Recycle Facility (TURF)/REDC

7930A Filter Pit for 7930

7931 Emergency Generator for 7930

7932 Waste Sample Building 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 Research 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 and Laboratory

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 Operations/Change House

ATTACHMENT 2A

OAK RIDGE NATIONAL LABORATORY FACILITY INDEX

Page 18 of 20
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Facility 

ID Description

Old 

numbering

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 Building

7967C Underground Weir

7968 Trailer

7969 Hazardous Material Enclosure

7970 Neutron Science Support Bldg.

7971 Hot Off-Gas (H.O.G.) Filter Facility

7975 Water Monitoring Storage Building

7977 Cold Source Equipment Building

7977A Cold Source Liquid Nitrogen Tank

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 and Laboratory Building

9204-1 Engineering Technology

9204-3 Isotope Separations

9207 Biology Building Y-12

9210 Mammalian Genetics Y-12

9211 Co-Carcinogenesis

9220 Molecular Biology Facility

9224 Molecular Biology Facility

9401-1 Engineering Technology Laboratory Facility

9409-15 Cooling Tower

9422 Large Coil Test Facility (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

ATTACHMENT 2A

OAK RIDGE NATIONAL LABORATORY FACILITY INDEX

Page 19 of 20
Document No. ORAUT-TKBS-0012-2 Revision No. 01 Effective Date: 08/30/2006 Page 72 of 80

Facility 

ID Description

Old 

numbering

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 – SWSA 6

X186600 Trailer – 7002 Area

ATTACHMENT 2A

OAK RIDGE NATIONAL LABORATORY FACILITY INDEX

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ATTACHMENT 2B 

FACILITY MAPS

Page 1 of 7 
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ATTACHMENT 2B 

FACILITY MAPS

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ATTACHMENT 2B 

FACILITY MAPS

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ATTACHMENT 2B 

FACILITY MAPS

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ATTACHMENT 2B 

FACILITY MAPS

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ATTACHMENT 2B 

FACILITY MAPS

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ATTACHMENT 2B 

FACILITY MAPS

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Document No. ORAUT-TKBS-0012-2 Revision No. 01 Effective Date: 08/30/2006 Page 80 of 80

ATTACHMENT 2C 

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 1949 – Oct. 1968 Volatile fission products, Na-24, N

3010 Bulk Shielding Reactor/Pool Critical 

Assembly

1951 – 1987 Volatile fission products, Na-24, N-16

3019 205 Pilot Plant Dec., 1943 – present 

(partly inactive and 

pending D&D)

Mixed fission/activation products, natural 

uranium, Th-232, U-233, TRU (liquid forms)

3023 206 North Tank Farm 1943 – 1986 Mixed fission/activation products, natural 

uranium, Th-232, U-233, TRU (liquid forms)

3026-C 706-C Radiochemistry Laboratory (original 

RaLa building); Kr-85 enrichment 

facility

1944 – ca. 1997

(pending D&D)

Mixed fission products, I-131, Kr-85 (liquid and 

gaseous forms)

3026-D 706-D Radiochemistry Laboratory (RaLa 

building from May 1945 until 1958); 

Segmentation Facility

1945 – ??

(pending D&D)

Mixed fission products, I-131, Ru-106, noble 

gases (liquid and gaseous forms); uranics/TRU 

(segmentation facility)

3028 910 Radioisotope Processing Building A/

Alpha Powder Facility

1950 – 1985 Mo-99, I-131, Xe-133, Pm-147, Cm-242/244

3029 909 Source Development Laboratory 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 H-3, C-14, Kr-85 (gaseous forms)

3038 902 Isotope Research Materials 

Laboratory/Alpha Handling Facility

1949 – 1990 Fission/activation products, uranics, TRU

3042 Oak Ridge Research Reactor March, 1958 – ca. 

1987

Volatile mixed fission products; Na-24, N-16

3047 Radioisotopes Development Laboratory 1962 – present Fission products, Pu-238

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, Th-232, U-233, TRU (liquid form)

3508 Alpha Isolation Laboratory 1952 – ca. 1976 TRU, U-233 (gram quantities); mixed fission 

products

3515 Fission Product Pilot Plant 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 Laboratory 1951 – present U-233 (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)

H-3, ThO2, UO2, Sr-90, Cs-137, Cm-244

7500 Homogeneous Reactor Experiment, 

Homogeneous Reactor Test

1952 – April, 1961 Mixed fission/activation products, uranyl sulfate

7503 Molten Salt Reactor Experiment 1965 – 1969 Mixed fission products, Th-232, U-233

7920/ 

7930

Radiochemical Engineering 

Development Center

1966 – present Cf-252, TRU, Dy/Ho-166, Re-186, Sn-117m, 

W/Re-188