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SEC Petition Evaluation Report 

Petition SEC-00189 

Report Rev #:0 Report Submittal Date: August 15, 2012 

Subject Expert(s): Michael Domal, Roger Halsey Ray Clark, Keith Varnado

Site Expert(s): N/A

Petition Administrative Summary

Petition Under Evaluation

Petition # Petition 

Type

Petition

Receipt Date

Qualification 

Date

DOE/AWE Facility Name

SEC-00189 83.13 July 18, 2011 October 11, 2011 Oak Ridge National Laboratory (X-10)

Petitioner-Requested Class Definition 

All contractor employees, subcontractor employees, and AEC employees who were monitored or should have 

been monitored for any of the various radionuclides and fission products present at the X-10 plant while working 

in all areas at the Oak Ridge National Laboratory (X-10) from January 1, 1943 through December 31, 1952.

Class Evaluated by NIOSH

All employees of the Department of Energy, its predecessor agencies, and their contractors and subcontractors 

who worked in any area at the Oak Ridge National Laboratory (X-10) in Oak Ridge, Tennessee, from January 1, 

1943 through July 31, 1955.

NIOSH-Proposed Class(es) to be Added to the SEC

All employees of the Department of Energy, its predecessor agencies, and their contractors and subcontractors 

who worked in any area at the Oak Ridge National Laboratory (X-10) in Oak Ridge, Tennessee, from June 17, 

1943 through July 31, 1955, for a number of work days aggregating at least 250 work days, occurring either 

solely under this employment, or in combination with work days within the parameters established for one or 

more other classes of employees in the Special Exposure Cohort.

Related Petition Summary Information 

SEC Petition Tracking #(s) Petition Type DOE/AWE Facility Name Petition Status

N/A N/A N/A N/A

Related Evaluation Report Information 

Report Title DOE/AWE Facility Name

N/A N/A

ORAU Lead Technical Evaluator: Michael Domal ORAU Peer Review Completed By: Michael Kubiak

Peer Review Completed By: [Signature on File] 8/16/2012

Timothy D. Taulbee Date

[Signature on File] 8/17/2012 SEC Petition Evaluation Reviewed By:

J. W. Neton Date

{Signature on File] 8/17/2012 SEC Evaluation Approved By:

Stuart L. Hinnefeld Date
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Evaluation Report Summary: SEC-00189 

Oak Ridge National Laboratory (X-10)

This evaluation report by the National Institute for Occupational Safety and Health (NIOSH) 

addresses a class of employees proposed for addition to the Special Exposure Cohort (SEC) per the 

Energy Employees Occupational Illness Compensation Program Act of 2000, as amended, 42 U.S.C.

§ 7384 et seq. (EEOICPA) and 42 C.F.R. pt. 83, Procedures for Designating Classes of Employees as 

Members of the Special Exposure Cohort under the Energy Employees Occupational Illness 

Compensation Program Act of 2000.

Petitioner-Requested Class Definition 

Petition SEC-00189 was received on July 18, 2011, and qualified on October 11, 2011. The petitioner 

requested that NIOSH consider the following class: All contractor employees, subcontractor 

employees, and AEC employees who were monitored or should have been monitored for any of the 

various radionuclides and fission products present at the X-10 plant while working in all areas at the 

Oak Ridge National Laboratory (X-10) from January 1, 1943 through December 31, 1952. 

Class Evaluated by NIOSH 

Based on its preliminary research, NIOSH expanded the petitioner-requested class. NIOSH evaluated 

the following class: All employees of the Department of Energy, its predecessor agencies, and their 

contractors and subcontractors who worked in any area at the Oak Ridge National Laboratory (X-10) 

in Oak Ridge, Tennessee, from January 1, 1943 through July 31, 1955. 

NIOSH-Proposed Class(es) to be Added to the SEC 

Based on its full research of the class under evaluation, NIOSH has defined a single class of 

employees for which NIOSH cannot estimate radiation doses with sufficient accuracy. The NIOSHproposed class includes all employees of the Department of Energy, its predecessor agencies, and their 

contractors and subcontractors who worked in any area at the Oak Ridge National Laboratory (X-10) 

in Oak Ridge, Tennessee, from June 17, 1943 through July 31, 1955, for a number of work days 

aggregating at least 250 work days, occurring either solely under this employment, or in combination 

with work days within the parameters established for one or more other classes of employees in the 

Special Exposure Cohort. 

Feasibility of Dose Reconstruction 

Per EEOICPA and 42 C.F.R. § 83.13(c)(1), NIOSH has established that it does not have access to 

sufficient information to: (1) estimate the maximum radiation dose, for every type of cancer for which 

radiation doses are reconstructed, that could have been incurred in plausible circumstances by any 

member of the class; or (2) estimate radiation doses of members of the class more precisely than an 

estimate of maximum dose. Information available from the site profile and additional resources is not 

sufficient to document or estimate the maximum internal and external potential exposure to members 

of the proposed class under plausible circumstances during the specified period. 
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NIOSH determined that radioactive materials did not arrive on site until June 17, 1943 at the 

earliest. Principal sources of internal and external radiation for members of the proposed class 

included exposures to plutonium, uranium, thorium, mixed fission products, and various 

cyclotron-related radionuclides. Principal sources of external radiation also included reactors that 

operated during the proposed class period. 

NIOSH determined in its evaluation that it did not locate sufficient data, including bioassay results 

and air monitoring concentrations, to estimate with sufficient accuracy the total internal dose from 

exposures to all the principal sources of internal radiation during the period from June 17, 1943 

through July 31, 1955. 

NIOSH found that it may be feasible to reconstruct internal doses to plutonium for employees 

during the period from January 1, 1944 through July 31, 1955. It may also be feasible to 

reconstruct the following internal exposures for a portion of the evaluation period: 

- Internal exposures to thorium from January 1, 1944 through December 31, 1947. 

- Internal exposures to uranium from January 1, 1949 through July 31, 1955. 

- Internal exposures to mixed fission products from January 1, 1950 through July 31, 1955. 

NIOSH has determined that cyclotron-related radionuclides produced at the nearby Y-12 Facility 

were processed at the ORNL facility during the period under evaluation. To allow 

cyclotron-related operations and exposures at the two sites to be collectively evaluated, NIOSH 

has reserved the evaluation of ORNL exposures to various radionuclides produced as a result of 

Y-12 cyclotron operations. 

The availability of ORNL (X-10) internal monitoring data is summarized in the following table. 

Summary Section: Available ORNL (X-10) Internal Monitoring Data

Internal Sources

Year

1943 1944 1945 1946 1947 1948 1949 1950 1951 1952 1953 1954 1955

Plutonium Air Bio Air Bioassay

Uranium No Data Bioassay

Thorium Air Data No Data Bio

Fission Products No Data Bioassay

Reactor/Cyclotron/Accelerator Reserved for a joint ORNL (X-10) and Y-12 evaluation

NIOSH found that external exposures could be reconstructed for all employees during the period 

from June 17, 1943 through July 31, 1955. 
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Prior to October 3, 1947, occupational medical X-rays were performed at Oak Ridge Hospital (an 

EEOICPA-covered site located on what was then the Clinton Engineering Works site). Starting 

October 3, 1947, occupational X-rays were performed on the ORNL site. Therefore, NIOSH has 

determined that it is applicable and feasible to reconstruct occupational medical X-ray exposures 

for ORNL (X-10) workers during period from June 17, 1943 through July 31, 1955. 

Pursuant to 42 C.F.R. § 83.13(c)(1), NIOSH determined that there is insufficient information to 

either: (1) estimate the maximum radiation dose, for every type of cancer for which radiation 

doses are reconstructed, that could have been incurred under plausible circumstances by any 

member of the class; or (2) estimate the radiation doses of members of the class more precisely 

than a maximum dose estimate. 

Although NIOSH found that it is not possible to completely reconstruct radiation doses for the 

proposed class, NIOSH intends to use any internal and external monitoring data that may become 

available for an individual claim (and that can be interpreted using existing NIOSH dose 

reconstruction processes or procedures). Therefore, dose reconstructions for individuals employed 

at ORNL (X-10) during the period from June 17, 1943 through July 31, 1955, but who do not 

qualify for inclusion in the SEC, may be performed using these data as appropriate. 

Health Endangerment Determination 

Per EEOICPA and 42 C.F.R. § 83.13(c)(3), a health endangerment determination is required because 

NIOSH has determined that it does not have sufficient information to estimate dose for the members 

of the proposed class. 

NIOSH did not identify any evidence supplied by the petitioners or from other resources that would 

establish that the proposed class was exposed to radiation during a discrete incident likely to have 

involved exceptionally high-level exposures, such as nuclear criticality incidents or other events 

involving similarly high levels of exposures. However, evidence indicates that some workers in the 

proposed class may have accumulated substantial chronic exposures through intakes of radionuclides, 

combined with external exposures to gamma, beta, and neutron radiation. Consequently, 42 C.F.R. § 

83.13(c)(3)(ii) requires NIOSH to specify that health was endangered for those workers covered by 

this evaluation who were employed for at least 250 aggregated work days either solely under this 

employment or in combination with work days within the parameters established for one or more 

other SEC classes. 
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Table of Contents 

1.0 Purpose and Scope ........................................................................................................................ 11

2.0 Introduction .................................................................................................................................. 11

3.0 SEC-00189 ORNL (X-10) Class Definitions ............................................................................... 12

3.1 Petitioner-Requested Class Definition and Basis ................................................................ 12

3.2 Class Evaluated by NIOSH ................................................................................................. 13

3.3 NIOSH-Proposed Class(es) to be Added to the SEC .......................................................... 14

4.0 Data Sources Reviewed by NIOSH to Evaluate the Class ........................................................... 14

4.1 Site Profile Technical Basis Documents (TBDs) ................................................................ 15

4.2 ORAU Technical Information Bulletins (OTIBs) and Procedures ..................................... 15

4.3 Facility Employees and Experts .......................................................................................... 16

4.4 Previous Dose Reconstructions ........................................................................................... 17

4.5 NIOSH Site Research Database .......................................................................................... 17

4.6 Documentation and/or Affidavits Provided by Petitioners ................................................. 17

5.0 Radiological Operations Relevant to the Class Evaluated by NIOSH ......................................... 18

5.1 ORNL Plant and Process Descriptions ................................................................................ 18

5.1.1 Major Facilities and Radionuclides of Concern ...................................................... 21

5.1.2 Reactors and Critical Assemblies ............................................................................ 27

5.1.3 Radiochemical Development Facility and Other Separations Facilities ................. 33

5.1.4 Radioactive Lanthanum Activities .......................................................................... 35

5.1.5 Isotope Production Areas ........................................................................................ 37

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

5.1.7 Waste Areas and Processes ..................................................................................... 42

5.2 Radiological Exposure Sources from ORNL Operations .................................................... 45

5.2.1 Internal Radiological Exposure Sources from ORNL Operations .......................... 45

5.2.1.1 Plutonium ................................................................................................. 45

5.2.1.2 Uranium (U-238, U-233, U-234, U-235) ................................................. 46

5.2.1.3 Fission and Activation Products (e.g., Sr-90, Cs-137, Zn-65, Co-60) ..... 46

5.2.1.4 Thorium (Th-232) ..................................................................................... 51

5.2.1.5 Exotic Radionuclides Produced by Reactor Neutron Irradiation and/or 

Accelerator Processes ............................................................................... 53

5.2.2 External Radiological Exposure Sources from ORNL Operations ......................... 53

5.2.2.1 Photon ....................................................................................................... 53

5.2.2.2 Beta ........................................................................................................... 54

5.2.2.3 Neutron ..................................................................................................... 54

6.0 Summary of Available Monitoring Data for the Class Evaluated by NIOSH ............................. 55

6.1 Available ORNL Internal Monitoring Data ........................................................................ 55

6.1.1 Personnel Monitoring for Plutonium (Pu-238, Pu-239, Pu-240, Pu-241) ............... 59

6.1.2 Personnel Monitoring for Uranium (U-238, U-233, U-234, U-235), ...................... 63

6.1.3 Personnel Monitoring for Fission and Activation Products .................................... 66
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6.1.4 Personnel Monitoring for Thorium ......................................................................... 67

6.1.5 Personnel Monitoring for Exotic Radionuclides ..................................................... 69

6.2 Available ORNL External Monitoring Data ....................................................................... 70

7.0 Feasibility of Dose Reconstruction for the Class Evaluated by NIOSH ...................................... 73

7.1 Pedigree of ORNL Data ...................................................................................................... 74

7.1.1 Internal Monitoring Data Pedigree Review ............................................................. 74

7.1.2 External Monitoring Data Pedigree Review ............................................................ 75

7.2 Evaluation of Bounding Internal Radiation Doses at ORNL (X-10) .................................. 76

7.2.1 Evaluation of Bounding Process-Related Internal Doses ........................................ 76

7.2.1.1 Urinalysis Information and Available Data .............................................. 76

7.2.1.2 Fecal Bioassay Data ................................................................................. 77

7.2.1.3 Airborne Levels ........................................................................................ 77

7.2.2 Evaluation of Bounding Ambient Environmental Internal Doses ........................... 78

7.2.3 Methods for Bounding Internal Dose at ORNL (X-10) .......................................... 78

7.2.4 Internal Dose Reconstruction Feasibility Conclusion ............................................. 81

7.3 Evaluation of Bounding External Radiation Doses at ORNL ............................................. 82

7.3.1 Evaluation of Bounding Process-Related External Doses ....................................... 82

7.3.2 Evaluation of Bounding Ambient Environmental External Doses .......................... 87

7.3.3 ORNL Occupational X-Ray Examinations ............................................................. 87

7.3.4 Methods for Bounding External Dose at ORNL ..................................................... 87

7.3.4.1 Methods for Bounding Operational Period External Dose ....................... 87

7.3.4.2 Methods for Bounding Ambient Environmental External Doses ............. 89

7.3.5 External Dose Reconstruction Feasibility Conclusion ............................................ 89

7.4 Evaluation of Petition Basis for SEC-00189 ....................................................................... 89

7.4.1 ORAUT-TKBS-012-5 ............................................................................................. 89

7.4.2 ORAUT-OTIB-0034 ............................................................................................... 90

7.4.3 ORAUT-OTIB-0018 ............................................................................................... 90

7.5 Summary of Feasibility Findings for Petition SEC-00189 .................................................. 91

8.0 Evaluation of Health Endangerment for Petition SEC-00189 ...................................................... 92

9.0 Class Conclusion for Petition SEC-00189 ................................................................................... 92

10.0 References .................................................................................................................................... 95

Attachment 1: Data Capture Synopsis ................................................................................................. 117
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Figures 

5-1: The Oak Ridge Reservation and Main DOE Facilities .................................................................. 24

5-2: Map of ORNL Outlying Areas ....................................................................................................... 25

5-3: Map of Oak Ridge National Laboratory in 1956 ........................................................................... 26

5-4: Cross-sectional Diagram of the LITR ............................................................................................ 28

5-5: Cross-section of the BSR Pool ....................................................................................................... 29

5-6: Cross-section of the HRE ............................................................................................................... 30

5-7: Building 7503 Layout .................................................................................................................... 31

5-8: Completed Tower Shielding Facility ............................................................................................. 32

5-9: Diagram of a Critical Experiments Assembly and Control Rooms ............................................... 33

5-10: ORNL Isotopes Production Flow ................................................................................................. 41

6-1: Bioassay Measurements for Plutonium Performed at ORNL, 1943-1959 ..................................... 63

6-2: Bioassay Measurements for Uranium Performed at ORNL, 1949-1959 ....................................... 65

6-3: Bioassay Measurements for Fission and Activation Products Performed at ORNL, 1950-1959 .. 67

6-4: Bioassay Measurements for Thorium Performed at ORNL, 1955-1959 ....................................... 69

Tables 

4-1: No. of ORNL Claims Submitted Under the Dose Reconstruction Rule ........................................ 17

5-1: Number of ORNL Workers by Year .............................................................................................. 19

5-2: Major ORNL Facilities and Radionuclides of Concern ................................................................. 22

5-3. Radioisotopes of Concern in Isotope Production Facilities ........................................................... 39

5-4: Isotopes Identified in ORNL Documents from 1943 through 1955 .............................................. 47

5-5: Principal Facilities with Internal Exposure Potential for Thorium during Evaluation Period ....... 51

5-6: Operational Timeline of Thorium and Related Processes, 1943-1955 .......................................... 52

5-7: Reactors at ORNL from 1943 through 1955 .................................................................................. 54

6-1: Available Bioassay Measurements for Plutonium Performed at ORNL, 1943-1959 .................... 62

6-2: Available Bioassay Measurements for Uranium Performed at ORNL, 1949-1959 ...................... 65

6-3: Bioassay Measurements for Fission and Activation Products Performed at ORNL, 1950-1959 .. 66

6-4: Bioassay Measurements for Thorium Performed at ORNL, 1955-1959 ....................................... 68

6-5: Number of Records by Year in ORNL Report from Exposure Database ...................................... 71

6-6: Types of Film Badges Used at ORNL from 1946 through 1955 ................................................... 72

7-1: ORNL Air Samples by Location (Electronic Database) ............................................................... 78

7-2: No. of Air Samples from Nine Weekly Reports (Aug48 through Apr49) ..................................... 78

7-3: Available ORNL (X-10) Internal Monitoring Data ....................................................................... 81

7-4: Summary of Feasibility Findings for SEC-00189 .......................................................................... 91
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SEC Petition Evaluation Report for SEC-00189

ATTRIBUTION AND ANNOTATION: This is a single-author document. All conclusions drawn from 

the data presented in this evaluation were made by the ORAU Team Lead Technical Evaluator: 

Michael Domal, MJW Corporation. The rationales for all conclusions in this document are explained 

in the associated text.

1.0 Purpose and Scope 

This report evaluates the feasibility of reconstructing doses for all employees of the Department of 

Energy, its predecessor agencies, and their contractors and subcontractors who worked in any area at 

the Oak Ridge National Laboratory (X-10) in Oak Ridge, Tennessee, from January 1, 1943 through 

July 31, 1955. It provides information and analyses germane to considering a petition for adding a 

class of employees to the congressionally-created SEC. 

This report does not make any determinations concerning the feasibility of dose reconstruction that 

necessarily apply to any individual energy employee who might require a dose reconstruction from 

NIOSH. This report also does not contain the final determination as to whether the proposed class 

will be added to the SEC (see Section 2.0). 

This evaluation was conducted in accordance with the requirements of EEOICPA, 42 C.F.R. pt. 83,

and the guidance contained in the Division of Compensation Analysis and Support’s (DCAS) Internal 

Procedures for the Evaluation of Special Exposure Cohort Petitions, DCAS-PR-004.1

2.0 Introduction 

Both EEOICPA and 42 C.F.R. pt. 83 require NIOSH to evaluate qualified petitions requesting that the 

Department of Health and Human Services (HHS) add a class of employees to the SEC. The 

evaluation is intended to provide a fair, science-based determination of whether it is feasible to 

estimate with sufficient accuracy the radiation doses of the class of employees through NIOSH dose 

reconstructions.2

 

42 C.F.R. § 83.13(c)(1) states: Radiation doses can be estimated with sufficient accuracy if NIOSH 

has established that it has access to sufficient information to estimate the maximum radiation dose, 

for every type of cancer for which radiation doses are reconstructed, that could have been incurred in 

plausible circumstances by any member of the class, or if NIOSH has established that it has access to 

sufficient information to estimate the radiation doses of members of the class more precisely than an 

estimate of the maximum radiation dose.

 

1

 DCAS was formerly known as the Office of Compensation Analysis and Support (OCAS). 

2

 NIOSH dose reconstructions under EEOICPA are performed using the methods promulgated under 42 C.F.R. pt. 82 and 

the detailed implementation guidelines available at http://www.cdc.gov/niosh/ocas. 
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Under 42 C.F.R. § 83.13(c)(3), if it is not feasible to estimate with sufficient accuracy radiation doses 

for members of the class, then NIOSH must determine that there is a reasonable likelihood that such 

radiation doses may have endangered the health of members of the class. The regulation requires 

NIOSH to assume that any duration of unprotected exposure may have endangered the health of 

members of a class when it has been established that the class may have been exposed to radiation 

during a discrete incident likely to have involved levels of exposure similarly high to those occurring 

during nuclear criticality incidents. If the occurrence of such an exceptionally high-level exposure has 

not been established, then NIOSH is required to specify that health was endangered for those workers 

who were employed for at least 250 aggregated work days within the parameters established for the 

class or in combination with work days within the parameters established for one or more other SEC 

classes. 

NIOSH is required to document its evaluation in a report, and to do so, relies upon both its own dose 

reconstruction expertise as well as technical support from its contractor, Oak Ridge Associated 

Universities (ORAU). Once completed, NIOSH provides the report to both the petitioner(s) and the 

Advisory Board on Radiation and Worker Health (Board). The Board will consider the NIOSH 

evaluation report, together with the petition, petitioner(s) comments, and other information the Board 

considers appropriate, in order to make recommendations to the Secretary of HHS on whether or not 

to add one or more classes of employees to the SEC. Once NIOSH has received and considered the 

advice of the Board, the Director of NIOSH will propose a decision on behalf of HHS. The Secretary 

of HHS will make the final decision, taking into account the NIOSH evaluation, the advice of the 

Board, and the proposed decision issued by NIOSH. As part of this decision process, petitioners may 

seek a review of certain types of final decisions issued by the Secretary of HHS.3

3.0 SEC-00189 ORNL (X-10) Class Definitions

The following subsections address the evolution of the class definition for SEC-00189, Oak Ridge 

National Laboratory (ORNL), also known as the X-10 Facility. When a petition is submitted, the 

requested class definition is reviewed as submitted. Based on its review of the available site 

information and data, NIOSH will make a determination whether to qualify for full evaluation all, 

some, or no part of the petitioner-requested class. If some portion of the petitioner-requested class is 

qualified, NIOSH will specify that class along with a justification for any modification of the 

petitioner’s class. After a full evaluation of the qualified class, NIOSH will determine whether to 

propose a class for addition to the SEC and will specify that proposed class definition. 

3.1 Petitioner-Requested Class Definition and Basis 

Petition SEC-00189 was received on July 18, 2011, and qualified on October 11, 2011. The petitioner 

requested that NIOSH consider the following class: All contractor employees, subcontractor 

employees, and AEC employees who were monitored or should have been monitored for any of the 

various radionuclides and fission products present at the X-10 plant while working in all areas at the 

Oak Ridge National Laboratory (X-10) from January 1, 1943 through December 31, 1952. 

 

3

 See 42 C.F.R. pt. 83 for a full description of the procedures summarized here. Additional internal procedures are 

available at http://www.cdc.gov/niosh/ocas. 
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The petitioner provided information and affidavit statements in support of the petitioner’s belief that 

accurate dose reconstruction over time is impossible for the ORNL (X-10) workers in question. 

NIOSH deemed the following information and affidavit statements sufficient to qualify SEC-00189 

for evaluation: 

The petition basis was the assertion that radiation exposures and radiation doses were not 

monitored, either through personal or area monitoring. It cited information from three 

ORAUT documents as the basis for the claim: 

ORAUT-TKBS-0012-5, ORNL Site - Occupational Internal Dose, was cited because it 

states that internal monitoring records are limited or do not exist for most radionuclides 

during this timeframe because internal monitoring as a form of personnel monitoring 

was just starting to be developed in the mid-to-late 1940s. As such, the petitioner 

indicates that the applicability for use of this document starts in 1947. 

ORAUT-OTIB-0034, Internal Dosimetry Coworker Data for X-10, was cited because it 

is only applicable starting in 1951 due to the lack of internal dosimetry data prior to 

1951. 

ORAUT-OTIB-0018, Internal Dose Overestimates for Facilities with Air Monitoring 

Programs, was cited because it is only applicable starting in 1953. 

Based on its ORNL research and data capture efforts, NIOSH determined that it has access to urine, 

fecal, air monitoring, film dosimeter badge, pocket dosimeter, and Neutron Track Emulsion Type A 

(NTA) film data for ORNL workers during the time period under evaluation. However, NIOSH also 

determined that bioassay and air monitoring records are not complete for all time periods or for all 

radionuclides. NIOSH concluded that there is sufficient documentation to support, for at least part of 

the requested time period, the petition basis that internal radiation exposures and radiation doses were 

not adequately monitored at ORNL, either through personal monitoring or area monitoring. The 

information and statements provided by the petitioner qualified the petition for further consideration 

by NIOSH, the Board, and HHS. The details of the petition basis are addressed in Section 7.4. 

3.2 Class Evaluated by NIOSH

Based on its research, NIOSH expanded the time period of the petitioner-requested class because 

NIOSH was unable to obtain the data necessary to estimate doses with sufficient accuracy until 

August 1, 1955. Therefore, NIOSH defined the following class for further evaluation: All employees 

of the Department of Energy, its predecessor agencies, and their contractors and subcontractors who 

worked in any area at the Oak Ridge National Laboratory (X-10) in Oak Ridge, Tennessee, from 

January 1, 1943 through July 31, 1955. 
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3.3 NIOSH-Proposed Class(es) to be Added to the SEC 

Based on its research of the class under evaluation, NIOSH has defined a single class of employees for 

which NIOSH cannot estimate radiation doses with sufficient accuracy. The NIOSH-proposed class 

to be added to the SEC includes All employees of the Department of Energy, its predecessor agencies, 

and their contractors and subcontractors who worked in any area at the Oak Ridge National 

Laboratory (X-10) in Oak Ridge, Tennessee, from June 17, 1943 through July 31, 1955, for a number 

of work days aggregating at least 250 work days, occurring either solely under this employment, or in 

combination with work days within the parameters established for one or more other classes of 

employees in the Special Exposure Cohort. The start date for the NIOSH-proposed class to be added 

to the SEC was changed from January 1, 1943 to June 17, 1943 because NIOSH obtained 

documentation showing that construction at the site did not start (i.e., ground-breaking) until February 

1943, and the first uranium slug shipment left Aluminum Company of America for the site on June 

17, 1943 (Alcoa, 1944). Thus, ORNL first had radioactive materials on site sometime after June 17, 

1943. 

4.0 Data Sources Reviewed by NIOSH to Evaluate the Class 

As is standard practice, NIOSH completed an extensive database and Internet search for information 

regarding ORNL (X-10). The database search included the DOE Legacy Management Considered 

Sites database, the DOE Office of Scientific and Technical Information (OSTI) database, the Energy 

Citations database, and the Hanford Declassified Document Retrieval System. In addition to general 

Internet searches, the NIOSH Internet search included OSTI OpenNet Advanced searches, OSTI 

Information Bridge Fielded searches, Nuclear Regulatory Commission (NRC) Agency-wide 

Documents Access and Management (ADAMS) web searches, the DOE Office of Human Radiation 

Experiments website, and the DOE-National Nuclear Security Administration-Nevada Site Officesearch. Attachment 1 contains a summary of ORNL documents. The summary specifically identifies 

data capture details and general descriptions of the documents retrieved. 

In addition to the database and Internet searches listed above, NIOSH identified and reviewed 

numerous data sources to determine information relevant to determining the feasibility of dose 

reconstruction for the class of employees under evaluation. This included determining the availability 

of information on personal monitoring, area monitoring, industrial processes, and radiation source 

materials. The following subsections summarize the data sources identified and reviewed by NIOSH. 
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4.1 Site Profile Technical Basis Documents (TBDs) 

A Site Profile provides specific information concerning the documentation of historical practices at 

the specified site. Dose reconstructors can use the Site Profile to evaluate internal and external 

dosimetry data for monitored and unmonitored workers, and to supplement, or substitute for, 

individual monitoring data. A Site Profile consists of an Introduction and five Technical Basis 

Documents (TBDs) that provide process history information, information on personal and area 

monitoring, radiation source descriptions, and references to primary documents relevant to the 

radiological operations at the site. The Site Profile for a small site may consist of a single document. 

As part of NIOSH’s evaluation detailed herein, it examined the following TBDs for insights into 

ORNL operations or related topics/operations at other sites: 

Technical Basis Document for the Oak Ridge National Laboratory – Introduction, ORAUTTKBS-0012-1; Rev. 0; August 11, 2004; SRDB Ref ID: 20132 

Oak Ridge National Laboratory – Site Description, ORAUT-TKBS-0012-2; Rev. 02; August 17, 

2007; SRDB Ref ID: 34367 

Oak Ridge National Laboratory – Occupational Medical Dose, ORAUT-TKBS-0012-3; Rev. 02; 

October 1, 2007; SRDB Ref ID: 35194 

Technical Basis Document for the Oak Ridge National Laboratory – Occupational Environmental 

Dose, ORAUT-TKBS-0012-4; Rev. 0; May 7, 2004; SRDB Ref ID: 20136a 

Oak Ridge National Laboratory – Occupational Internal Dose, ORAUT-TKBS-0012-5; Rev. 01; 

October 1, 2007; SRDB Ref ID: 35195 

Oak Ridge National Laboratory – Occupational External Dose, ORAUT-TKBS-0012-6; Rev. 01; 

September 10, 2007; SRDB Ref ID: 34945 

4.2 ORAU Technical Information Bulletins (OTIBs) and Procedures

An ORAU Technical Information Bulletin (OTIB) is a general working document that provides 

guidance for preparing dose reconstructions at particular sites or categories of sites. An ORAU 

Procedure provides specific requirements and guidance regarding EEOICPA project-level activities, 

including preparation of dose reconstructions at particular sites or categories of sites. NIOSH 

reviewed the following OTIBs as part of its evaluation: 

OTIB: Dose Reconstruction from Occupationally Related Diagnostic X-Ray Procedures, ORAUTOTIB-0006, Rev. 04; June 20, 2011; SRDB Ref ID: 98147

OTIB: Internal Dose Overestimates for Facilities With Air Sampling Programs, ORAUT-OTIB0018; Rev. 01; August 9, 2005; SRDB Ref ID: 19436
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OTIB: Technical Information Bulletin – External Coworker Dosimetry Data for the X-10 Site, 

ORAUT-OTIB-0021, Rev. 00; December 29, 2004; SRDB Ref ID: 19442 

OTIB: Internal Dosimetry Coworker Data for X-10, ORAUT-OTIB-0034; Rev. 00; December 13, 

2005; SRDB Ref ID: 20222

OTIB: Guidance on Assigning Occupational X-ray Dose Under EEOICPA for X-rays 

Administered Off Site, ORAUT-OTIB-0079, Rev. 00; January 1, 2011; SRDB Ref ID: 89563

4.3 Facility Employees and Experts

To obtain additional information, NIOSH interviewed eight current or former ORNL (X-10) 

employees in five interviews. 

Personal Communication, 2006, Personal Communication Regarding Activities in the ORNL 

Biology Buildings Located at Y-12; Interview by ORAU Team; April 12, 2006; SRDB Ref ID: 

22812 

Personal Communication, 2012a, Personal Communication with One Individual Regarding 

Thorium Operations at the X-10 Facility; Interview by ORAU Team; March 14, 2012; SRDB Ref 

ID: 109522

Personal Communication, 2012b, Personal Communication with Two Individuals Regarding 

Thorium Operations at the X-10 Facility; Interview by ORAU Team; March 22, 2012; SRDB Ref 

ID: 109819

Personal Communication, 2012c, Personal Communication with Three Individuals Regarding 

Radiation Monitoring at ORNL ( X-10); Interview by ORAU Team; June 13, 2012; SRDB Ref ID: 

116011

Personal Communication, 2012d, Personal Communication with One Individual Regarding 

Bioassay Sampling at ORNL; Interview by ORAU Team; June 14, 2012; SRDB Ref ID: 115274

Personal Communication, 2012e, Personal Communication with One Individual Regarding 

Reporting of Neutron Doses; Interview by ORAU Team; July 3, 2012; Ref ID: 115899
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4.4 Previous Dose Reconstructions 

NIOSH reviewed its NIOSH DCAS Claims Tracking System (referred to as NOCTS) to locate 

EEOICPA-related dose reconstructions that might provide information relevant to the petition 

evaluation. Table 4-1 summarizes the results of this review. (NOCTS data available as of July 10, 

2012) 

Table 4-1: No. of ORNL Claims Submitted Under the Dose Reconstruction Rule 

Description Totals

Total number of claims submitted for dose reconstruction 2036

Total number of claims submitted for energy employees who worked during the period under 

evaluation (January 1, 1943 through July 31, 1955). 1302

Number of dose reconstructions completed for energy employees who worked during the period

under evaluation (i.e., the number of such claims completed by NIOSH and submitted to the 

Department of Labor for final approval). 1074

Number of claims for which internal dosimetry records were obtained for the identified years in the 

evaluated class definition 236

Number of claims for which external dosimetry records were obtained for the identified years in the 

evaluated class definition 668

4.5 NIOSH Site Research Database

NIOSH also examined its Site Research Database (SRDB) to locate documents supporting the 

assessment of the evaluated class. As of the issuance of this report, there are 16,929 documents and 

subdocuments in the SRDB identified as pertaining to ORNL. These documents were evaluated for 

their relevance to this petition. The documents include historical background on monitoring, program 

descriptions, air monitoring data, urinalysis data, fecal data, film badge data, radiological control 

programs, medical monitoring, process materials, and process descriptions. 

4.6 Documentation and/or Affidavits Provided by Petitioners 

In qualifying and evaluating the petition, NIOSH reviewed the following documents submitted by the 

petitioners: 

Form B with Lecture Notes, Health Physics Training Lectures, 1948-49, AECU-817, Health 

Physics Division, Oak Ridge National Laboratory; September 29, 1950; Form B received on July 

18, 2011; DSA Ref ID: 114345 (Form B) 

Health Physics Division Quarterly Progress Report for Period Ending October 20, 1951, ORNL 

1174 Progress, Health Physics Division, Oak Ridge National Laboratory; 1951; DSA Ref ID: 

114348 (Progress Report, Oct1951a) 
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Oak Ridge National Laboratory – Occupational Internal Dose, ORAUT-TKBS-0012-5; Rev. 01; 

October 1, 2007; SRDB Ref ID: 35195

Internal Dose Overestimates for Facilities With Air Sampling Programs, ORAUT-OTIB-0018; 

Rev. 01; August 9, 2005; SRDB Ref ID: 19436

Internal Dosimetry Coworker Data for X-10, ORAUT-OTIB-0034; Rev. 00; December 13, 2005; 

SRDB Ref ID: 20222 

5.0 Radiological Operations Relevant to the Class Evaluated by 

NIOSH 

The following subsections summarize both radiological operations at the ORNL from January 1, 1943 

through July 31, 1955 and the information available to NIOSH to characterize particular processes and 

radioactive source materials. From available sources NIOSH has gathered some process and source 

descriptions, information regarding the identity of each radionuclide of concern, and limited 

information describing processes through which radiation exposures may have occurred and the 

physical environment in which they may have occurred. The information included within this 

evaluation report is intended only to be a summary of the available information. 

5.1 ORNL Plant and Process Descriptions 

The Oak Ridge National Laboratory is located on about 4470 acres of the 34,000-acre Oak Ridge 

Reservation in eastern Tennessee’s Anderson and Roane counties. The general area where the main 

ORNL facilities are now located was known as Bethel Valley, Kingston, Tennessee. In the latter part 

of 1942, the Army organized a new Manhattan Engineer District (MED) under the U.S. Army Corps 

of Engineers to manage the activities directed toward producing an atomic bomb. The Corps of 

Engineers started construction of a town and administrative office buildings in 1942 under the name 

Clinton Engineer Works (CEW). This was the area planned for the large-scale production activities 

required to produce an atomic bomb. The original plan called for all atomic bomb project activities to

be carried out at this site (Thompson, 1963).

The entire facility known as the Clinton Engineer Works was bounded by security fences from 

February 1943 through March 1949. Within the facility were the processing plants, known as K-25 

(for uranium enrichment), X-10 (for plutonium production), and Y-12 (for uranium enrichment). 

Each plant had its own security fence. (Each plant has been designated separately for the purposes of 

EEOICPA.) During this time, Roane Anderson Company managed, operated, and maintained for the 

CEW the residences, apartments, dormitories, guest houses, barracks, hutments, trailers, restaurants, 

cafeterias, buses, roads, streets, sidewalks, garbage and sewage disposal, heating plants, and more. 

However, Roane did not operate the processing plants and laboratories. The CEW gates came down 

in March 1949. This meant that people no longer needed a security clearance to enter the CEW, 

although clearances were still required to enter the plants and laboratories. The fences surrounding 

the processing plants remained. It was also in 1949 that privatization began of what today is known as 

the City of Oak Ridge. 
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DuPont agreed to accept the responsibility for the plutonium production plant, and because of this, 

also accepted responsibility for the design and construction of the pilot plant at CEW. Although the 

pilot plant was to be operated by the Metallurgical Laboratory of the University of Chicago, it was 

expected that DuPont would train personnel at the pilot plant for later assignment to the production 

facilities. Construction of the pilot plant started on February 1, 1943, the first plant construction in the 

CEW. Because of the location in the CEW, the name Clinton Laboratories was chosen for the pilot 

plant (Thompson, 1963). MED security required that the lab operator not be linked to these 

laboratories. Thus, a separate organization, the Clinton Laboratories, was created to obfuscate that 

link. In early 1947, those facilities were named the Clinton National Laboratory, which became the 

Oak Ridge National Laboratory on February 1, 1948. 

The main ORNL site is frequently known as "X-10." That name had its origins in late 1942 as a code 

name for the initial product of the Graphite Reactor and chemical processing plant at Oak Ridge (i.e., 

plutonium). ORNL and its predecessors have been operated, successively, by the University of 

Chicago's Metallurgical Laboratory (March 17, 1943 - June 30, 1945), the Monsanto Chemical 

Company (July 1, 1945 - February 29, 1948), divisions or subsidiaries of Union Carbide and Carbon 

Corporation and Union Carbide Corporation (March 1, 1948 - March 31, 1984), subsidiaries of Martin 

Marietta Company and Lockheed Martin Company (April 1, 1984 - March 31, 2000), and 

UT-Battelle, LLC, a partnership between the University of Tennessee and Battelle (April 1, 2000 - 

present) (Quist, 2000). 

For the period under evaluation, the ORNL workforce varied, ranging from approximately 953 

workers in 1943 to 4024 in 1955. A tabulation of workers compiled for an ORAU epidemiological 

study yielded widely-varied numbers, as indicated in Table 5-1. The database used for ascertaining 

the ORNL employment for 1943-1955 was the same database used by the ORAU Center for 

Epidemiological Research. (ORAU CER). 

Table 5-1: Number of ORNL Workers by Year

Gender

Year

1943 1944 1945 1946 1947 1948 1949 1950 1951 1952 1953 1954 1955

Female: 205 455 405 577 705 706 481 504 632 636 624 601 617

Male: 748 1891 1726 1926 2222 2211 1833 2484 2929 3128 3085 3243 3407

Total: 953 2346 2132 2504 2927 2917 2314 2988 3561 3764 3709 3844 4024

Source: ORAU CER database. ORAU CER was one of the three DOE epidemiological research centers that 

collected data on ORNL, including employment data which was used to determine when a person was employed. 

The original general purpose of the facilities that became ORNL was to provide the MED with its 

pilot plutonium-production plant. Those ORNL pilot facilities included a graphite-moderated, aircooled, natural-uranium, nuclear-fission reactor to produce plutonium and pilot-plant chemicalprocessing facilities for separating and purifying that plutonium. Subsequently, the large plutoniumproduction reactors and chemical facilities that were built at Hanford, Washington provided the 

plutonium for the atomic device tested at Alamogordo, New Mexico in July 1945, and for the atomic 

bomb dropped on Nagasaki, Japan in August 1945 (Quist, 2000). 
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The four specific original purposes of ORNL were: (1) to operate a small, graphite-moderated, 

air-cooled, natural-uranium-fueled, nuclear-fission reactor to produce small amounts of plutonium; (2) 

to operate a chemical pilot plant to separate plutonium from uranium and its fission products using the 

bismuth phosphate carrier process; (3) to operate a training school for technical personnel who would 

form the nucleus staff for operating Hanford's production plants; and (4) to perform research and 

development related to nuclear fission, nuclear reactors, and plutonium-separation processes. The 

first two items, the engineering scale-up of laboratory processes, were the most important purposes 

followed by (3) and then (4). A fifth purpose may have been to evaluate the health hazards from 

fission and fission-product radioactivity. The oldest ORNL facilities are the Graphite Reactor and the 

chemical-processing facilities. DuPont provided a total of 337 employees, all of whom were 

experienced in some phase of plant operations. Personnel who initially operated the Hanford plant 

were trained at those ORNL facilities (Quist, 2000; Thompson, 1963). 

Since operations began in 1943, ORNL’s mission has been research and development and production 

missions in support of the Department of Energy (DOE) and its predecessor agencies. Much of the 

earliest site work was devoted to the development and operation of the original graphite reactor which 

was designed as a pilot plant for the larger production reactors scheduled for the Hanford site. The 

graphite reactor was used to produce gram quantities of plutonium, and later, fission products 

(radioactive lanthanum and all other types of radioactive materials were separated in other ORNL site 

facilities). 

A large part of ORNL activities and operations has been research and development of chemical 

technologies for separation of materials from irradiated nuclear fuels and liquid waste streams. ORNL 

developed many of the solvent extraction processes adopted at U.S. plutonium production facilities, 

and at one time, the facility was a substantial provider of radioisotopes for industry and research. 

ORNL also produced stable isotopes using Calutrons at the Y-12 National Nuclear Security Complex. 

Isotope sales were eventually scaled back to only highly-specialized materials, such as Cf-252 from 

the High Flux Isotope Reactor, which was separated and packaged in the Radiochemical Engineering 

Development Center. 

Between 1944 and 1956, the Radioactive Lanthanum (RaLa) program was carried out at ORNL to 

produce large quantities of Ba-140/La-140 for use in weapons dynamic studies at the Los Alamos 

National Laboratory. The RaLa program involved dissolving short-decay uranium fuel slugs 

irradiated in either the ORNL Graphite Reactor or the production reactors at the Hanford site. 

The ORNL site was also used for developing new reactor technologies. Various reactor designs (pool, 

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

ORNL. They were then either scrapped or further developed elsewhere. Reactors operated by ORNL 

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

Shielding Reactor (BSR)/Pool Critical Assembly (PCA), ORNL Research Reactor (ORR), Tower 

Shielding Reactor (TSR), Health Physics Research Reactor (HPRR), Homogeneous Reactor 

Experiment (HRE), Aircraft Nuclear Propulsion (ANP) Program, the High Flux Isotope Reactor 

(HFIR), and the Molten Salt Reactor Experiment (MSRE). These reactor technologies and associated 

facilities are discussed later in this report. 
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In 1947, several ORNL divisions moved to the Y-12 complex (while remaining as ORNL divisions). 

These divisions were responsible for conducting research in biological sciences, production of stable 

isotopes, and engineering technology. 

The Oak Ridge Graphite Reactor, intended as a pilot plant for the larger plutonium production reactors 

at the Hanford site, achieved initial criticality on November 4, 1943. The Graphite Reactor served 

only briefly in its role as a pilot plant, and quickly became an essential tool for basic research and 

radioisotope production. The Graphite Reactor was the first of many reactors to operate at the site as 

the laboratory expanded its reactor research into a number of domains, including energy, propulsion 

systems, materials research, and radioisotope production. In addition, ORNL operated the Critical 

Experiments Facility (CEF) at the Y-12 site from mid-1950 until 1987. The CEF supported 

experiments with various reactor designs at ORNL and elsewhere. 

ORNL has operated several accelerators including the 86-inch cyclotron at the Y-12 complex, the Oak 

Ridge Isochronous Cyclotron, the Holifield Heavy Ion Research Facility, and the Oak Ridge Electron 

Linear Accelerator. Other smaller accelerators have also been used for such applications as dosimetry 

research and waste assay research. 

Waste-handling practices at ORNL evolved as the scope and duration of its mission expanded. 

Gaseous wastes were initially discharged via local stacks and vents before a centralized off-gas 

treatment system began operating in 1950. Liquid wastes were originally handled using a system of 

tank farms and settling basins to treat wastes before discharge into White Oak Creek. More liquid 

waste treatment facilities were added over time. A number of trenches, burial grounds, and Solid 

Waste Storage Areas have been at ORNL for the disposal of solid wastes. 

5.1.1 Major Facilities and Radionuclides of Concern 

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

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

building numbering nomenclature was changed to one with predominantly four digits. A March 1, 

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

Laboratory Building List (ORAUT-TKBS-0012-2), indicated a cross-linking from the old and new 

building numbering nomenclature at that time. Numbers 0000 through 5999 are located on the main 

plant site. Numbers 6000-7499 are further east of the main plant site in Bethel Valley, numbers 7500-

7999 are in Melton Valley, and the ORNL facilities in the Y-12 National Security Complex begin 

with the 9000 numbers. During the more than 60 years of site operations, facilities have been 

constructed, operated, decontaminated, and decommissioned based on need. 
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Table 5-2 shows the major ORNL facilities with their former and current building numbers as well as 

the associated radionuclides of concern. 

Table 5-2: Major ORNL Facilities and Radionuclides of Concern

(This table spans two pages)

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-16

3010 Bulk Shielding Reactor/Pool Critical 

Assembly

1951–1987 Volatile fission products, Na-24, N-16

3019 205 Pilot Plant (Solvent Extraction Facility) 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–circa 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, Cm242/244

3029 909 Source Development Laboratory 1952–late 1980s Fission/activation products

3030 908 Radioisotope Processing Building C circa 1950–late 

1980s

Fission/activation products

3031 907 Radioisotope Processing Building D circa 1950–late 

1980s

Fission/activation products

3032 906 Radioisotope Processing Building E circa 1950–late 

1980s

Fission/activation products

3033 905 Radioisotope Processing Building F, 

Radioactive Gas Processing Facility

circa 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, N16

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)
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Table 5-2: Major ORNL Facilities and Radionuclides of Concern

(This table spans two pages)

Current 

Building 

Number

Former 

Building 

Number

Facility Name or Description Dates of 

Operation Principal Radionuclides of Concern

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

3550 706-A Research Materials Preparation Facility 

(706 Chemistry Bldg)

1943-no end date 

known

Mixed fission products, uranics, TRU

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)

7500 Homogeneous Reactor Experiment, 

Homogeneous Reactor Test

1952–April, 1961 Mixed fission/activation products, uranyl 

sulfate

Source: ORAUT-TKBS-0012-2 
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Figure 5-1 shows a view of the Oak Ridge Reservation and main DOE facilities. 

Source: ChemRisk, 1993 

Figure 5-1: The Oak Ridge Reservation and Main DOE Facilities 
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Figure 5-2 shows a view of ORNL Outlying areas. 

Source: ChemRisk, 1993 

Figure 5-2: Map of ORNL Outlying Areas 
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Figure 5-3 shows a view of the ORNL site in 1956. 

Source: ORNL Site Map, 1955 

Figure 5-3: Map of Oak Ridge National Laboratory in 1956 
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5.1.2 Reactors and Critical Assemblies 

The Graphite Reactor (Pile) 

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

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

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

The reactor was designed to operate at a thermal power rating of 1,000 kW, but with subsequent 

modifications reached at least 4,400 kW. There were 7 ft. of concrete shielding between the reactor 

and the front wall of the shield that operators would work from (5 ft. of barites concrete with 1 ft. of 

structural concrete on each side as retaining walls). Natural uranium fuel slugs (4 in. long by 

approximately 1.1 in. in diameter) were loaded in the reactor by inserting them through holes in the 

front face into horizontal channels in the graphite matrix. Following irradiation, the slugs were 

pushed out the back side of the reactor into a water-filled transfer canal. (ORAUT-TKBS-0012-2) 

Low Intensity Test Reactor (LITR) 

The Materials Test Reactor (MTR) was designed by ORNL and built at the National Reactor Test Site 

in Idaho (now the Idaho National Laboratory). This was a high-power, enriched-uranium core cooled 

and moderated by ordinary water. 

In 1949, a full-scale mock-up of the MTR’s major components was built at ORNL in Building 3005 to 

check out mechanical and hydraulic operation and provide training for operators. After the mock-up 

was running, ORNL argued that it should be made critical with real fuel plus beryllium reflector 

elements, which would allow nuclear measurements and testing of instruments and controls. This was 

done, and in 1950, many low-power measurements for the final MTR design were made. In 1952, it 

was a small step to add shielding and a heat exchanger, thus providing the Laboratory with the 1500 

kW Low-Intensity Test Reactor (LITR). Later, after the addition of shielding and other modifications, 

the LITR was operated at 3 MW (Rosenthal, 2009).

Originally, LITR stood for the Low Intensity Training Reactor, and later, the Low Intensity Test 

Reactor. This reactor used MTR-type, enriched-uranium fuel elements and beryllium-reflector pieces 

in a 5-element x 9-element lattice with moderation and cooling provided by forced circulation of 

demineralized water. The reactor tank was surrounded with concrete block shielding. Control-rod 

drives were mounted on the top of the reactor tank. The reactor was flanked on the sides with two 

large rooms for housing experimental equipment. The beam holes opened into these rooms. Two 

higher levels around the tank, called the “midriff” and the “top level,” were enclosed to shelter the 

experiments and operating personnel (George, 1962). Figure 5-4 shows a diagram of the LITR. 
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Source: George, 1962 

Figure 5-4: Cross-sectional Diagram of the LITR 

Bulk Shielding Reactor (BSR) 

The BSR was originally a 10-kilowatt research reactor that was operated in the Bulk Shielding 

Facility, Building 3010. The reactor, a two-foot cube, was submerged in a pool 40 feet long, 20 feet 

wide and, at its deepest point, 27 feet deep. It was operated seventeen feet below the surface of the 

water shield (ORNL, 1958). 

The BSR achieved criticality on December 17, 1950 and was in operation through 1963. The reactor 

was known as the “Swimming Pool” reactor and served as the model for university, industry, and 

government research reactors. Figure 5-5 shows a diagram of the BSR. 
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Source: Rosenthal, 2009 

Figure 5-5: Cross-section of the BSR Pool 

Homogeneous Reactor Experiment (HRE) 

The Homogeneous Reactor Experiment was the first reactor prototype incorporating a circulating 

homogeneous aqueous fuel operating at high specific power and temperature with the reactor coupled 

to a steam turbine generator. The reactor was built for the purpose of demonstrating the feasibility of 

this concept; primarily, to show that the reactor was self-regulating and inherently stable. 

The reactor achieved criticality on April 15, 1952 and was in operation until April 1954. The reactor 

essentially consisted of an 18-inch diameter spherical core inside a 39-inch diameter reflector vessel, a 

circulating pump, and a heat exchanger where steam was produced for the operation of the turbine 

generator. The design conditions were 250°C temperature, 1000 psig pressure, and 1000 kilowatt 

reactor power. The material of construction was Type 347 stainless steel. A low pressure system 

contained dump tanks for the storage of fuel solution, an evaporator and condensate tanks for 

changing concentration, and recombiners for the decomposition gases released in the core. The fuel 

was a light water solution of UO2SO4 with a U-235 enrichment of 93 percent and the reflector was 

heavy water (Campbell, 1956; Visner, 1957). Figure 5-6 shows a diagram of the HRE. 
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Source: Rosenthal, 2009 

Figure 5-6: Cross-section of the HRE 

Aircraft Reactor Experiment (ARE) 

In 1953, ORNL erected Building 7503 to house the Aircraft Reactor Experiment (ARE) in Melton 

Valley about a half mile south of the ORNL main facilities complex. The entire reactor system was 

contained in three interconnected pits: one for the reactor, one for the heat exchangers and pumps, and 

the third for the fuel dump tanks. 

The ARE was an experiment to build and operate a high-temperature, low-power, circulating-fuel 

reactor using materials that would be amenable to a high-power aircraft-type reactor. The fuel was 

UF4 dissolved in molten salts, a mixture of sodium and zirconium fluorides. 

The reactor achieved criticality on November 3, 1954. The experiment was concluded on November 

12 when the reactor was shut down permanently. During its short run, the reactor logged a little over 

100 megawatt-hours and achieved a maximum power level of 2.5 megawatts (Meem, 1954; 

Rosenthal, 2009). Figure 5-7 shows a layout of Building 7503. 
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Source: Cottrell, 1955, pdf p. 239 

Figure 5-7: Building 7503 Layout 

Tower Shielding Reactor (TSR) 

In 1952, ORNL proposed to address air scattering and shielding problems arising from the 

development of a reactor-powered aircraft by hanging full-scale reactor and shield models high in the 

air. Approval was received and the Tower Shielding Facility (TSF) was built on Copper Ridge in a 

remote area south of the main laboratory area. The TSF (see Figure 5-8) was formed from four 

315-foot towers, separated by 200 feet in one dimension and 100 feet in the other. Cables attached to 

the towers could hoist the reactors and shields to 200 feet above the ground. The facility was operated 

from an underground building and a fence kept people and animals away. 

The first Tower Shielding Reactor (TSR) was essentially a BSR (bulk-shielding reactor). It was tested 

in a 12-foot diameter water-filled tank and in specially designed shield assemblies into which the core 

was lowered. When the core was in the tank, the reactor support system could rotate or move it to any 

position within a horizontal plane for measurements. Cooling was by forced convection. When 

testing began in 1954, the initial power limit was 100 kW, but permission was soon obtained for 

operation at up to 500 kW. When not in use, the reactor was stored in a deep pool between the towers 

(Rosenthal, 2009). 
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Source: Rosenthal, 2009 

Figure 5-8: Completed Tower Shielding Facility

Critical Experiments 

These were a series of three small reactor assemblies for testing enrichments, moderators, and 

reflector configurations that operated between 1945 and 1950 in Building 3019. After 1950, the 

Critical Experiments were moved to Y-12 (ORNL, 1967). 

The first configuration tested enriched uranium in a small reactor using an aluminum-water moderator 

and deuterium oxide, beryllium, and ordinary water reflectors (Mann, 1947). The assembly was later 

modified for a series of experiments using only beryllium reflectors by the removal of the liquid 

storage and piping systems. This assembly was placed on an aluminum floor supported by cast iron 

and had plates and cross bars installed to accurately position fuel tubes and control rods. This 

rearrangement included the installation of improved radiation monitoring equipment (Martin, 1948).

The assembly was further modified to test a more complex arrangement in support of the design of the 

MTR. It was used to measure the critical mass of a slab as a function of its geometry, the change in 

reactivity arising from holes through the reflectors and absorbers within these holes, gamma-produced 

heat in the reflector, the neutron flux through the core and reflector, and the effectiveness of control 

rods of various materials (ORNL, 1948). Figure 5-9 shows a diagram of the Critical Experiments. 
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Source: Mann, 1947 

Figure 5-9: Diagram of a Critical Experiments Assembly and Control Rooms 

5.1.3 Radiochemical Development Facility and Other Separations Facilities 

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 the uranium (precipitation, oxidation, and reduction); 

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

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

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

phosphate, reduction-oxidation [REDOX], Hexone-25, TBP [tributyl phosphate]-25, plutoniumuranium extraction [PUREX], fluoride volatility chemical process, and thorium extraction 

[THOREX]). (ORAUT-TKBS-0012-2)

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

present in the facility. This facility conducted much of the research and development operations for 

separations at the site. Several of the processes are described below (ORAUT-TKBS-0012-2). 

Bismuth Phosphate Process 

From 1943 until 1945, the Bismuth Phosphate Process took place in Building 3019 using the bismuth 

phosphate “co-precipitation” process to recover plutonium. Processing began in December 1943, 

using uranium irradiated at the Washington University cyclotron in St. Louis. By the end of 1944, 

this chemical pilot plant was processing one-third ton of Graphite Reactor uranium fuel per day. By 

the time operations ceased in early 1945, a total of 326 grams of plutonium had been separated from 

299 batches of irradiated uranium fuel slugs (ChemRisk, 1993).

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 involved the slugs being dissolved in acid in 

the initial cell. The remaining cells housed the equipment used in precipitating the plutonium from 

the dissolved fuel slugs and oxidation and reduction of the uranium. This batch process is based on 
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the fact that plutonium will co-precipitate with bismuth phosphate in the +4 valence state, but not in 

the +6 valence state. Aluminum cladding was dissolved away from the fuel elements using boiling 

sodium hydroxide solution. The bare uranium was then dissolved in concentrated aqueous nitric acid 

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

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

remained as a waste product. 

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

REDOX Process 

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

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

extracting uranium and plutonium from reactor fuel using solvents. 

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

PUREX Process 

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

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

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

Radionuclides of concern include: U-234, U-235, Pu-238, and mixed fission products. 

Fluoride Volatility Process 

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

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

molten salt. 

Radionuclides of concern include: U-234, U-235, Kr-85, Xe-133, Te-127, Te-129, I-131, Ru-103, 

Ru-106, and Pu-238.

THOREX Process 

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

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

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

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

cell, spreading it onto the street and the Graphite Reactor.

Radionuclides of concern include: Pu-238, Pu-239, U-233, Th-232, Th-233, Kr-85, Zr-95, Nb-95, 

Ru-103, Ru-106, I-131, I-132 (Te-132), Xe-133, Ba/La-140, Ce-141, Ce-144, and Pa-233. 
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Other Separations-Related Activities 

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

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

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

Flux Isotope Reactor were also developed and fabricated in this facility. Two additional and unique 

fuel-rod-loading techniques (vibratory compaction and slug injection) were also studied in the FCAF. 

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

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

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

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

irradiated in the Graphite Reactor included: 3026C, 3026D, 3505, 3515, and 3517. 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 

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

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

presence of residual fission products (Cs-137 and Sr-90) and uranic and transuranic radioisotopes. 

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

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

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

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

Tank Arrangement. It was used to extract radioisotopes of ruthenium, strontium, cesium, cerium, and 

other fission products (ORAUT-TKBS-0012-2). 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-inch-thick, walled concrete hot cell with a 2-ft-thick concrete roof was 

constructed. Numerous spills occurred in the building over the years, and the internal structure, 

particularly the concrete floor, was frequently soaked with contaminated waste. The building was 

posted as a high radiation area. Operations in Building 3515 were moved to Building 3517 in 1958. 

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

PUREX waste streams. A total of 1E+6 Ci of fission products were processed until building 

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

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

have been present in the waste as well as other fission products. 

5.1.4 Radioactive Lanthanum Activities 

During mid-1942, much research at the Metallurgical Laboratory at the University of Chicago was 

being directed at small-scale studies of various radioisotopes. While most of the radiological research 

was focused on the production of fissionable material for use in weapons manufacturing, some was 

conducted on other radioisotopes (i.e., activation and fission products) to determine their potential 

value to the war effort. While the Graphite Reactor was still being conceptualized by its designers, 

special attention was being given to barium, strontium, and lanthanum separation chemistry. Though 

initially-purified Ba-140 had little gamma activity, the activity of La-140 growing into the purified 
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Ba-140 created much interest due to the presence of a 1.6-MeV gamma emitted from La-140. 

Production activities were called the RaLa Project. In the fall of 1943, much of the Metallurgical 

Laboratory moved to ORNL to continue the research on fission products. This research was initiated 

at ORNL in Building 3550 (706-A) and soon (October 21, 1943) a request to construct a larger 

production facility was made. During the following year, Building 3026-C (originally 706-C) was 

designed and constructed with larger containers and equipment; the new facility’s initial production 

run began on September 10, 1944 (ORAUT-TKBS-0012-2). 

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

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

of product upon start-up. The 3026-C facility processed irradiated slugs from the Graphite Reactor. 

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

3,852 Ci in the building (Thompson, 1949). Multiple batches of irradiated slugs were dissolved to 

make up a completed run. The last run in Building 3026-C was conducted on May 28, 1945. 

After the second successful RaLa run in Building 3026-C, discussions were held indicating the need 

to further increase production rates. 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 (originally 706-D) was designed to process much larger 

(up to 1,000 Ci) amounts of radioactivity and was attached to the east end of the existing 3026-C 

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

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

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

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

(ORAUT-TKBS-0012-2).

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

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

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

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

1956 (ChemRisk, 1999; Thompson, 1949). The RaLa program was subsequently transferred to the 

Idaho Chemical Processing Plant. 

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

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

noble gases and radioiodines. Much of the iodine volatilized during the slug-dissolving process was 

effectively removed from the dissolver off-gas stream by the reflux condenser and chemical scrubber 

that were 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 too was routed to the 3039 stack (ORAUT-TKBS-0012-2). 
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5.1.5 Isotope Production Areas 

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 5-3 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, 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. 

Building 3028 

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

facility for Pm-147 (ORNL, 1997a).

Building 3029 

Building 3029 was constructed in 1952 to support the Isotopes Program (ORNL, 1997b). A small 

manipulator cell (now called Cell 4) and a system of remotely-operated barricades supported source 

fabrication of Ir-192. In addition, small Co-60 sources were fabricated. In 1955 and 1956, an 

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

of Co-60 sources fabricated in the facility diminished in the late 1950s. Major operations in Building 

3029 included Co-60, Cs-137, and Sr-90 source fabrication, and Ir-192 processing. A Co-60 storage 

and irradiation facility, called the Co-60 Garden, is below the floor of the east wing (Kuhaida, 1997). 

The exact dates of operation of this facility are unknown, but the program ended in the late 1980s. 

Building 3030 

Building 3030 was constructed in 1950 to produce and develop radioisotopes for industry, medicine, 

and research (ORNL, 1997c). The building contained a hot cell for processing irradiated cyclotron 

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

Fe-55, and Ir-192. These isotopes were processed primarily from irradiated targets from the HFIR 

(High Flux Isotope Reactor), ORR (Oak Ridge Reactor), and 86-inch Cyclotron. The exact dates of 

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

late 1980s.

Building 3031 

Building 3031 was constructed in 1950 as part of the Isotopes Program and used for storage, 

purification, processing, and dispensing radioisotopes that were processed primarily from irradiated 

targets from the HFIR, ORR, and 86-inch Cyclotron (ORNL, 1997d). The hot cell was used for the 

final separation of gadolinium (Gd-103). 
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Building 3032 

Building 3032 housed the analytical facility for radiochemical support of Isotopes Production 

activities (ORNL, 1997e). 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-inch Cyclotron. The exact dates of operation are unknown. The program it supported began 

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

Building 3033 

Building 3033 was used for processing C-14, Kr-85, and H-3. Processing of C-14 ended in 1975 

(ORNL, 1997f). 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 (Kr-85) for sale to 

private industries or used as feed to the thermal diffusion columns in Building 3026-C. The exact 

dates of operation are unknown. The program it supported began in the late 1940s. Processing of H-3 

ended in 1990. The last Kr-85 was produced in September 1989. 

Building 3033-A 

Building 3033-A 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 

(ORNL, 1997f). It also housed facilities for the fabrication of mono-energetic 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. All production operations ended in January 

1990.

Building 3034 

Building 3034 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 (ORAUT-TKBS-0012-2). 

Building 3038 

Building 3038 was used from 1949 until 1990 for radioisotope packaging, inspection, and shipping 

activities. 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 (the Alpha Handling Facility [AHF]) was used for 

the target fabrication. The center portion (3038-M) contained radioactive isotope shipping operations. 

The east end (3038-E) contained analytical chemistry laboratories that supported isotope shipping 

activities (DOE, 1996). The northwest corner (3038-W) contained a storage area and an isotope 

technology low-level laboratory. 
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Building 3118 

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 (ORAUT-TKBS-0012-2). 

Table 5-3. Radioisotopes of Concern in Isotope Production Facilities

Building name Building No. 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, Sr90, 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 

Source: ORAUT-TKBS-0012-2 
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5.1.6 ORNL Facilities at the Y-12 National Nuclear Security Complex 

NOTE: Radiation exposures received by ORNL (X-10) employees while located on the Y-12 Facility 

are not part of this ORNL (X-10) evaluation. Information in this section is meant to describe the 

radionuclides produced at the Y-12 facilities, but often transferred to ORNL (X-10) for processing and 

experimentation. Evaluation of ORNL cyclotron and accelerator operations on the Y-12 site is 

reserved for this evaluation report because such operations at both ORNL (X-10) and Y-12 will be 

addressed in a future combined evaluation effort.

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 

(ORAUT-TKBS-0012-2).

Space at Y-12 was used by the ORNL Research and Development divisions for several other projects. 

Three of the projects included the beta calutrons, the 86-inch cyclotron, and the 5-MeV Van de Graff 

Accelerator, all of which are briefly summarized below. Several of these projects involved the 

production and/or separation and purification of both stable and radioactive isotopes. Generally, the 

radioactive isotopes were produced in small quantities and/or had short half lives. 

Work performed at these facilities presented external and internal radiation exposure potential. At 

times, Y-12 workers supported efforts at the facilities and, in some cases, Y-12 employees were 

administratively transferred to ORNL. 

Figure 5-10 shows the productions flow between X-10, Y-12, and off-site locations. Certain 

radionuclides were produced at ORNL Graphite Reactor, the Cyclotron, and the Calutrons. Some 

materials containing these radionuclides were shipped off site, while other materials underwent further 

processing at X-10 before being shipped off site. Other source material was produced at the Low 

Intensity Test Reactor (ORNL) and off-site locations such as Hanford, University of Pittsburg, and 

Arco Idaho. 

A decision was made to reserve the radionuclides created by cyclotrons, accelerators, and reactors for 

this evaluation report due to the complexity and interdependency involved in transferring materials 

between two DOE-covered facilities (X-10 and Y-12). The operational complexity involved both the 

graphite pile (X-10) and the cyclotron (Y-12) and included the transfer of some manufactured 

radionuclides from Y-12 to X-10 for further processing while others were manufactured at Y-12, 

packed at Y-12, and shipped out of the Oak Ridge area from Y-12. An evaluation of potential 

exposures from these activities was being initiated for Y-12 when this interdependency was 

discovered; therefore, the decision was made to combine the Y-12 and X-10 radionuclide research 

efforts for a better understanding of the overall operations and also enhanced efficiency of evaluation. 

This planned evaluation of radionuclides produced by cyclotrons, accelerators, and reactors will 

commence following the issuance of this current evaluation report. 
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ORNL Isotopes Production Division

Exotic Radionuclides

Graphite 

Reactor Production Cyclotron Calutron

Chemical 

Separations

End Use

ORNL Labs

Onsite Offsite

X-10 Y-12

Y-12 Labs

Figure 5-10: ORNL Isotopes Production Flow 

Calutrons 

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. The initial primary location for the effort 

was Building 9731 (Calutron Pilot Plant) starting in 1946 (Savage, 1950; Wilcox, 1997). During the 

1950s, the Y-12 Beta calutrons (Building 9204-3) were used for the production, enrichment, and 

purification of an extensive list of stable and radioactive isotopes for worldwide medical research. 

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. 

Based on a series of about 30 progress reports produced by the Electromagnetic Research Division 

and subsequent organizations, it is evident that plutonium isotopic enrichment work was occurring in 

1952 and 1957. Documents also show that plutonium urinalyses were performed from 1952 through 

at least 1965, air monitoring was performed, and personnel protection was addressed through clothing 

and respiratory protection. Calutron facilities provided for double containment of the calutron(s) and 

glove-box handling of collection pockets (Progress Report, Dec1961; Progress Report, Oct1957).

86-inch Cyclotron 

The 86-inch cyclotron began operation in November 1950 and was used for isotope production and to 

perform radiation damage studies for the Nuclear Aircraft Project (Ball, 1971). As the world's largest 

fixed-frequency proton cyclotron, it produced a proton beam four times more intense than any other 

cyclotron. One of the original uses of the Oak Ridge 86-inch cyclotron was the production of Po-208 
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(Livingston, 1952; Progress Report, Jul-Oct1962; Johnson, 1994). Polonium was produced in the 

86-inch cyclotron as early as 1951 (ORNL, 1951). In 1952, internal revisions of the position and 

mounting of the ion source resulted in proton energy of 23 MeV. 

5-MeV Van de Graff Accelerator 

In the early 1950s, a 5-MeV Van de Graff accelerator operated for about one year in the east end of 

Building 9202-2 while a permanent structure was being built for the accelerator at the X-10 site. The 

5-Me V Van de Graff Accelerator was an X-10 project and the health physicists and all other workers 

involved with the Van de Graff were X-10 employees (ChemRisk, 1993; Progress Report, JanJun1951; Progress Report, Jul-Dec1951).

5.1.7 Waste Areas and Processes 

According to the ORNL Site Description TBD (ORAUT-TKBS-0012-2), waste-handling practices at 

ORNL evolved as the scope and duration of its mission expanded. Gaseous wastes were initially 

discharged via local stacks and vents before a centralized off-gas treatment system began operating in 

1950. Liquid wastes were originally handled using a system of tank farms and settling basins to treat 

wastes before discharge into White Oak Creek. More liquid waste treatment facilities were added 

over time. A number of trenches, burial grounds, and Solid Waste Storage Areas at ORNL have 

served as locations for disposal of solid wastes. 

The Central Exhaust Facility (Building 3039), built in 1950, 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 

that the system serves, any gaseous waste stream can contain TRU or fission product radioisotopes. 

Building operators, in their role as waste generators, are responsible for keeping radionuclides in the 

gaseous waste streams discharging to the Stack Ventilation System at levels that limit risk to the 

health and safety of the public and employees. This mitigation occurs through a combination of 

administrative controls, input controls, application of health physics procedures, and treatment of the 

gaseous waste stream before discharge to the Stack Ventilation System (usually by HEPA filters). 

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 (after the period under evaluation), disposal areas moved south of the Main Plant Area 

across Haw Ridge to Melton Valley. The following paragraphs describe the information available to 

NIOSH regarding the areas and amounts of radioactive materials present. 

The ORNL site was originally intended to operate for a short period to develop processes for use at 

other MED 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 off-site release. However, sediments in White Oak Creek and Lake contain radioactive 

materials that settled from the process liquids. 
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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-gallon underground gunite storage 

tanks placed in service in 1943. The farm 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. by 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 the 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) disposed of LLLWs deep in geological faults that are 

separate from sources of drinking water. 

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 Solid Waste Storage Areas on or near the Main Plant site 

(SWSA’s 1, 2, and 3). Solid wastes were later transported to Melton Valley where other landfills 

operated. The following paragraphs describe SWSAs 1 to 6. NOTE: SWSAs 5 and 6 were opened 

after the SEC evaluation period and are not included in this discussion. 

SWSA 1: 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 Sr-90, but 

no indication of Cs-137 or transuranic elements. 
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SWSA 2: 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, or Cs-137. Ground-water samples showed no detectable 

contamination; analyses included tritium, gross alpha, and gross beta. 

SWSA 3: Approximately 7 acres about 0.5 mi west of SWSA 1 and 0.6 mi west of the west ORNL 

entrance. SWSA 3 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, Sr-90, Sr-89, and H-3 contamination. 

SWSA 4: This location, covering approximately 23 acres, received waste from 1951 until 1959. 

SWSA 4 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 Sr-90, Ru-106, 

Cs-137, Co-60, Po-210, Pu-239, H-3, Sb-125, and trivalent rare earths. 
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5.2 Radiological Exposure Sources from ORNL Operations 

The following subsections provide an overview of the internal and external exposure sources for the 

ORNL class under evaluation. 

5.2.1 Internal Radiological Exposure Sources from ORNL Operations 

The diversity of operations at the ORNL (X-10) site makes it difficult for NIOSH to collect complete 

details of all ORNL internal exposure sources. Nevertheless, NIOSH has determined that the internal 

dose potential during the period under evaluation is associated with reactors, machine shops, 

accelerators, and other research and support activities as well as radioactive waste disposal. Although 

not all specific areas where waste materials were generated and buried are readily identifiable from 

the documents available to NIOSH, a potential for internal intakes from these activities is assumed to 

exist. 

Radionuclides with the widest application throughout ORNL facilities during the period under 

evaluation are: 

Plutonium (Pu-238, Pu-239, Pu-240, Pu-241) 

Uranium (U-238, U-233, U-234, U-235) 

Fission and activation products (e.g., Sr-90, Cs-137, Zn-65, Co-60) 

Thorium (Th-232) 

Exotic radionuclides (e.g., C-14, Ca-45, P-32, S-35, Ba-140/La-140, and others produced by 

reactor neutron irradiation and/or accelerator processes). 

5.2.1.1 Plutonium 

Plutonium exposure potential has existed at ORNL from the site’s inception to the present because of 

the numerous reactors, separations facilities, and accelerator facilities. Activities with the potential for 

plutonium intakes have occurred since 1944. Many facilities exhibited potential plutonium exposure 

during the period under evaluation, as shown in Table 5-2. Surveys, air samples, and bioassay 

samples for plutonium (via gross alpha analysis) were routinely performed, as indicated by the air 

sample database and confirmed by many available documents. Positive results have been noted for 

many samples within the documents (Monitoring, 1945-1990; Monitoring, Jan-Jul1949) and the air 

sample database (Monitoring, Jun1944-Dec1947).

There is no definitive historical information on the isotopic ratios of ORNL plutonium sources except 

for some documents from the period 1954-1956 related to using electromagnetic equipment. Other 

than the electromagnetic equipment areas, there is also no information available to NIOSH about how 

typical isotopic ratios varied with time and location. The dominant isotope (by activity) in most of the 

plutonium to which ORNL workers might have been internally exposed is Pu-239. Lab-scale 

separation activities (i.e., gram quantities) conducted in 1954 using electromagnetic equipment 

(calutrons) at the Y-12 location assigned to the stable isotopes program were noted in two reports 

(Bell, 1954; Martin, 1956). Various isotopic abundances were achieved for Pu-239, Pu-240, Pu-241, 
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and Pu-242. In December 1955, a seventh separation of the heavier plutonium isotopes from 

irradiated plutonium was completed with an estimated production of 1.0 gram of 85% Pu-240 and 160 

mg of Pu-241 (Progress Report, Dec1955). No other reports documented plutonium separation 

activities involving larger than gram-scale quantities. 

5.2.1.2 Uranium (U-238, U-233, U-234, U-235) 

Uranium exposure potential has existed at ORNL since the site’s inception to the present because of 

the numerous reactors, separations facilities, and accelerator facilities. Activities with the potential for 

uranium intakes have occurred since 1943. Many facilities have exhibited potential uranium exposure 

during the period under evaluation, as shown in Table 5-2. Surveys, air samples, and bioassay 

samples for uranium (via gross alpha analysis) were routinely performed, as indicated by many 

documents and the air sample database. Positive results have been noted for many samples within the 

documents available to NIOSH (Monitoring, 1945-1990; Monitoring, Jan-Jul1949) and the air sample 

database (Monitoring, Jun1944-Dec1947). 

ORNL uranium processes included (Brooksbank, 1994):

• Bismuth phosphate 

• REDOX 

• Hexone-25 

• TBP-25 

• PUREX 

• THOREX 

5.2.1.3 Fission and Activation Products (e.g., Sr-90, Cs-137, Zn-65, Co-60) 

Fission and activation product exposure potential has existed at ORNL since the site’s inception to the 

present because of the numerous reactors, separations facilities, and accelerator facilities. Many 

facilities have exhibited fission and activation product exposure potential during the period under 

evaluation, as shown in Table 5-2. Surveys, air samples, and bioassay samples for fission and 

activation products (via gross alpha and gross beta/gamma analysis) were routinely performed, as 

indicated by many available documents and database (Monitoring, 1945-1990).

Many of the electromagnetically-produced radionuclides generated at ORNL (i.e., at Y-12) were also 

fission and/or activation products. Table 5-4 identifies the produced radionuclides identified from 

1943 through 1955 in the various monthly reports, annual reports, and other relevant data capture 

documents. This listing of fission products does not include radioisotopes generated by reactor 

operations and fuel separations activities not specifically listed in the available documents but which 

would be expected to be present as early as 1943 when the Graphite Reactor became operational. 
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Table 5-4: Isotopes Identified in ORNL Documents from 1943 through 1955

(This tables spans four pages)

Isotope 1943 1944 1945 1946 1947 1948 1949 1950 1951 1952 1953 1954 1955

americium-241 X X

antimony-122

antimony-124 Z X X X X R

antimony-Be X X R R

antimony-125 R X R

argon-37 G G G G G

argon-41 G

arsenic-73 X X X X

arsenic-74 X X X

arsenic-76 X

arsenic-77 R

barium-131

barium-133 R R

barium-140 X X X X X R

beryllium-7 X X X X X X R

beryllium-9 X

bismuth-207 X

bismuth-210 Z R

boron-10 X X

bromine-82

cadmium-115 Z X X X X R R

cadmium-115m R R

calcium-45 X X X X X X X X R

carbon-14 X* X X X X X X X X R

cerium-141 X X X X X R

cerium-144 X X X X X X X R

cesium-134 X X R

cesium-137 X X X X X X X X R

chlorine-35 X

chlorine-36 X X X X X X X X R

chlorine-38 X

chromium-51 X X X X R

cobalt-56 X X X

cobalt-57 X X X X X R
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Table 5-4: Isotopes Identified in ORNL Documents from 1943 through 1955

(This tables spans four pages)

Isotope 1943 1944 1945 1946 1947 1948 1949 1950 1951 1952 1953 1954 1955

cobalt-58 X R

cobalt-60 X X X X X X X R

copper-64

europium-152-154 X X

europium-152 Z X

europium-154 X X X

europium-155 X X X X R

fission products X X X X X X R

Au198 X X

hydrogen-3 gas X X X X X X R

hydrogen-3 

zirconium X X R

indium-111 R

indium-114 X X X R R

iodine-125 X X X R

iodine-129 R

iodine-131 X X X X X X X X X R

iridium-192 X X X R

iron-55-59 X X X X X R R

iron-55 X X X X X X X X R

iron-59 X X X X X X X X R

krypton-85 G G

lanthanum-140 X X X X X X X X X X X

manganese-52 X X X

manganese-54 X X X X X R

mercury-203 X X X X X R

neodymium-147 X X X X R R

nickel-59 X

nickel-63 X X X X R R

nickel-65

niobium-95 X X X X X X X R

osmium-185 Z

osmium-191 Z

osmium-193 Z

phophorus-32 X X X X X X X X X R

polonium-208 X X
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Table 5-4: Isotopes Identified in ORNL Documents from 1943 through 1955

(This tables spans four pages)

Isotope 1943 1944 1945 1946 1947 1948 1949 1950 1951 1952 1953 1954 1955

polonium-210 Z Z

potassium-40 X X

potassium-42 Z X X R R

praesodymium-142

praesodymium-143 X X X X R R

promethium-147 X X X X X R

protactinium-233 X

rubidium-86 R

rhodium-102 X

rhodium-105 X

ruthenium-103 X X X X R R

ruthenium-106 X X X X X X X R

samarium-151 X X

samarium-153

scandium-46 Z X X X R

selenium-75 Z X X X X R

silver-110 Z R X R R

silver-111

sodium-22 X X X X X X R

sodium-24 X X X R

strontium-85 X X X X R

strontium-89 X X X X X X X X R

strontium-90 X X X X X X X R

sulfur-35 X X X X X X X X R

tantalum-182 Z X R R

technicium-99 X R R

terbium-160 X

thallium-204 Z X X X X R R

Tungsten-51 Z X

thorium-234 X X

tin-113 X X X X R

tungsten-185 Z X X X

tungsten-187 Z X R R

yttrium-88 X

yttrium-90 X
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Table 5-4: Isotopes Identified in ORNL Documents from 1943 through 1955

(This tables spans four pages)

Isotope 1943 1944 1945 1946 1947 1948 1949 1950 1951 1952 1953 1954 1955

yttrium-91 X X X X X X X X R

zinc-65 X X X X X X R R

zirconium-95 X X X X X X X R R

Ra:Be (radium-226) X

Rare Earth (gross) X X X X

Sources: See reference list below. 

* = carbon-14: First shipment of 1 mCi of C-14 in August 1946.

R = Notes listed in Annual Summary Report though not in Monthly reports. 

X = Notes listed in Monthly reports. (December 1946-December 1954) 

Z = Notes listed in 1948 Radioisotopes Catalog though not in Monthly Reports or identified on other reports. 

G = Notes inert gas, not an internal hazard

Data sources for Table 5-4 above include the following references: 

1947:

Progress Report, Jan1947

Progress Report, Feb1947

Progress Report, Mar1947a

Progress Report, Mar1947b

Progress Report, May1947

Progress Report, Jun1947

Progress Report, Jul1947

Progress Report, Aug1947

Progress Report, Nov1947

1948:

Progress Report, Feb1948

Progress Report, Jul1948

Progress Report, Aug1948

Progress Report, Oct1948

Progress Report, Nov1948

1949:

Progress Report, Feb1949

Progress Report, Apr1949

Progress Report, May1949

Progress Report, Jun1949

Progress Report, Sep1949

Progress Report, Dec1949

1950:

Progress Report, Jan1950

Progress Report, Mar1950

Progress Report, Apr1950

1951:

Progress Report, Feb1951

Progress Report, Apr1951

Progress Report, May1951

Progress Report, Jun1951

Progress Report, Jul1951

Progress Report, Aug1951

Progress Report, Sep1951

Progress Report, Oct1951b

Progress Report, Dec1951

1952:

Progress Report, Jan1952

Progress Report, Feb1952

Progress Report, Mar1952

Progress Report, Apr1952

Progress Report, May1952

Progress Report, Jun1952

Progress Report, Jul1952

Progress Report, Aug1952

Progress Report, Sep1952

Progress Report, Oct1952

Progress Report, Dec1952

1953:

Progress Report, Jan1953

Progress Report, Mar1953

Progress Report, Apr1953

Progress Report, May1953

Progress Report, Jun1953

Progress Report, Jul1953

Progress Report, Aug1953

Progress Report, Oct1953

Progress Report, Nov1953

Progress Report, Dec1953

1954:

Progress Report, Feb1954

Progress Report, Mar1954b

Progress Report, Jul1954

Progress Report, Aug1954

Progress Report, Sep1954

Progress Report, Oct1954

Progress Report, Nov1954

Progress Report, Dec1954

1957:

Seagren,1957
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5.2.1.4 Thorium (Th-232) 

Thorium exposure potential has existed at ORNL since 1944 because of the numerous laboratory 

facilities as well as fuel development and testing facilities. Some facilities have exhibited thorium 

exposure potential during the period under evaluation, as shown in Table 5-5. Initial thorium 

processing was performed in Building 3019 (Pilot Plant). Potential intakes may have resulted from 

basic thorium research, operations with nuclear fuel development operations, nuclear fuel separations 

activities, and laboratory activities. Surveys, air samples, and bioassay samples for thorium (via gross 

alpha analysis) were routinely performed, as indicated by the air sample database and many available 

documents. Positive results have been noted for many samples within the documents (Monitoring, 

1945-1990) and air sample database (Monitoring, Jun1944-Dec1947). Many documents were 

obtained related to the thorium processes and activities at the site. Limited documentation has been 

obtained regarding thorium bioassay prior to 1955. However, concerns associated with thorium alpha 

emissions and exposures cannot be limited by operational location during the period under evaluation. 

Thorium operations began in 1944 with lab-scale preparation and testing of thorium carbonate (the 

likely locations were 706A and 205). In 1946, test runs for the development of 23 (U-233) extraction 

from irradiated slugs occurred in 706A (the code word for U-233 at the time was 23). From 1947 

through around 1950, thorium extraction runs were performed in 706A and 706C. In 1948-1949, a 

pilot plant (the 23 Pilot Plant) was constructed in 706HB with thorium extraction runs occurring from 

1949-1950 through around 1955. In 1954, the Thorex Pilot Plant was installed in Building 205; it 

processed thorium from 1954 through the end of the period under evaluation. 

Table 5-5: Principal Facilities with Internal Exposure Potential for Thorium during Evaluation Period

Current 

Building 

Number

Former 

Building 

Number

Facility Name or Description Dates of Operation

Likely Potential Periods of 

Thorium Exposure During 

Evaluation Period

3001 105 Graphite Reactor Nov. 1943–Nov. 1963 1944-1955

3019 205 Pilot Plant Dec. 1943–present 

(partly inactive and pending 

D&D)

1946-1955

3026-C` 706-C Radiochemistry Laboratory 1944–circa 1997 1944-1955

3026-D 706-D Radiochemistry Laboratory (RaLa 

building from May 1945 until 

1958); Segmentation Facility

1945–(pending D&D) 1945-1955

3028 901 North Tanks Farm 1943-1986 1944-1955

3503 706-

HB

(23 Pilot Plant) 1949-1955

3550 706-A Research materials Preparations 

Facility

1943-no end date known 1944-1955

Misc --- Various other laboratory testing 

facilities

1943- no end date known 1944-1955

Misc --- Various storage facilities 1943-1978 1944-1955

Source: ORAUT-TKBS-0012-2 
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Table 5-6 presents a timeline of thorium and thorium-related activities from 1943-1955 derived from 

documents available to NIOSH. 

Table 5-6: Operational Timeline of Thorium and Related Processes, 1943-1955

Years Thorium and Related Processes

1943 - mid-1944 No evidence of thorium work or processes.

1944 Lab scale work on thorium carbonate. Preparation and irradiation of thorium carbonate for 

U-233 Program.

1946 Lab scale separation and purification of U-233 from solutions containing thorium nitrate.

mid-1946 Thorium slug removal from pile and processing.

1947 - 1950 Hexone-23 slug extraction process.

1948 - 1949 Constructed the 23 Pilot Plant.

1950 Approximately 1 Kg shipped to ORNL.

1951 - 1953 >2000 Kg annually shipped to ORNL.

1952 Approximately 2.76 Kg U-233 isolated from runs of 3689 Kg of Hanford irradiated thorium.

1952 - 1953 Interim 23 process work in Pilot Plant (mostly runs of Hanford irradiated thorium).

1953 >4000 Kg shipped to ORNL.

1953 - 1954 Thorex fuel blanket material processing. Thorex Pilot Plant installed in Building 3019 .

1954 Thorium purification studies initiated. Also began work on refining technology, separations 

from decay products, and fluoride reduction. Conducted thorium oxide blanket studies and 

pile irradiation of sample slurry. First Thorex cycle completed.

1955 Second Thorex cycle completed. Approximately 5000 lbs of ThO2 prepared and made ready 

for blanket studies.

1955 13073 Kg non-irradiated thorium processed and 6466 Kg irradiated thorium processed.

1955 Metallex lab scale studies. Larger scale runs conducted the following year.

1955-1960 Thorex processing of irradiated thorium metal (Hanford, SRS metal)

Sources: Booth, 1946; Brooksbank, 1994; Division Monthly reports 1951-1954 [see reference list preceding Table 5-4]; 

McCarley, 1956; Progress Report, Jan-Jul1946, pdf p. 188; Progress Report, Feb1947; Progress Report, May1954; 

Thompson, 1963; Thorium, 1944 
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5.2.1.5 Exotic Radionuclides Produced by Reactor Neutron Irradiation and/or Accelerator Processes 

ORNL built and operated cyclotrons and accelerators on the Y-12 site. These operations generated 

radionuclides (e.g., C-14, Ca-45, P-32, Ba-140/La-140, and others). NIOSH has access to data for 

these operations. However, this topic is reserved for this evaluation report because cyclotron and 

accelerator operations at both ORNL (X-10) and Y-12 will be addressed in a future combined 

evaluation effort. 

5.2.2 External Radiological Exposure Sources from ORNL Operations 

A great variety of radioactive nuclides were created, separated, processed, and used at ORNL. These 

can be broadly categorized into the groups of mixed fission products, activation products, and the 

uranium and thorium isotopes. 

5.2.2.1 Photon 

Photon exposure resulted from the mixed fission and activation products from the reactors and from 

isotopes produced at Y-12 (See Table 5-4). Exposure rates varied by building and by dates, but 

generally, exposure potential increased with time due to increased production and an increasing 

number of reactors on site. Examples of survey data have been located but are not complete for all 

locations for all time periods (Clark, 1944; Perry, 1947; Progress Report, Jan-Dec1947; Simons, 

1945). However, such surveys indicate the contemporary controls and enforcement of restricted areas. 

Direct photon exposure also resulted from workers in the proximity of the test and the research 

nuclear reactors. Exposure at the Graphite Reactor was monitored by routine surveys. Examples of 

these surveys have been located (Progress Report, Jan-Jul1946, pdf p. 6; Clifford, 1951). Survey data 

for other reactors have been located but are not complete for all reactors for all time periods 

(Exposure, 1951). Reactor operations began in 1943 with the Graphite Reactor and increased in 1951 

with the addition of the Low Intensity Test Reactor and the Bulk Shielding Reactor. Three additional 

reactors became operational in 1954: the Homogeneous Reactor Experiment, the Aircraft Reactor 

Experiment and the Tower Shielding Reactor. In addition, the three critical assemblies that comprised 

the Critical Reactor Experiments ran from 1945 through 1948. Although these were brought to 

critical levels and therefore would have created some level of exposure, they were operated from 

behind a 2-foot thick shield due to risk of a criticality accident (ORNL, 1967). Table 5-7 includes the 

names, locations, and operational lifetimes for all reactors existing from 1943 through 1955

(Campbell, 1956; Holland, 1970; ORNL, 1967; Progress Report, Dec1951; Progress Report, 

Mar1954a; Progress Report, Jun1954; Progress Report, Mar1955; Rosenthal, 2009). 
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Table 5-7: Reactors at ORNL from 1943 through 1955

Reactor Dates

Pile (Graphite Reactor)

Building 3001

1943 - 1963

Low Intensity Test Reactor (LITR)

Building 3005

1951 - 1968

Bulk Shielding Reactor (BSR)

Building 3010

1951 - 1987

Homogeneous Reactor Experiment (HRE-1)

Building 7500

1952 - 1954

Aircraft Reactor Experiment (ARE)

Building 3019

1954

Tower Shielding Reactor (TSR-I) 1954 - 1958

Critical Reactor Experiments

A series of three small reactors for testing enrichments, 

moderators, and reflector configurations

1946 - 1948

Source: Campbell, 1956, pdf p. 38; Mann, 1947; Martin, 1948; ORAUT-TKBS-0012-02; ORNL, 

1948; ORNL, 1958; ORNL, 1992; Progress Report, Jan1951; Progress Report, Dec1951; 

Progress Report, Mar1954a, pdf p. 15; Progress Report, Jun1954, pdf p. 150; Progress Report, 

Mar1955, pdf p. 13; Rosenthal, 2009; ORNL, 1952, pdf p. 7; AEC, 1960, pdf p. 552 

5.2.2.2 Beta 

Beta exposure resulted from the mixed fission and activation products from the reactors, and from 

isotopes produced at Y-12 (see Table 5-1). Exposure rates varied by building and by dates, but 

generally, exposure potential increased with time due to increased production and an increasing 

number of reactors on site. Examples of survey data have been located but are not complete for all 

locations for all time periods (Clark, 1944; Perry, 1947; Progress Report, Jan-Dec1947; Simons, 

1945). However, such surveys indicate the application of contemporary controls and the enforcement 

of restricted areas. 

5.2.2.3 Neutron 

ORNL workers may have been exposed to neutrons from neutron sources and from the existing 

nuclear reactors. An undated memo, which can be reasonably dated to circa 1951 from the 

operational statuses of the reactors mentioned, listed all sources of neutron exposure (Neutron 

Problems, unspecified). It stated that there were “12 PoBe” and “8 RaBe” neutron sources, ranging in 

strength from 0.4 to 12 curies. 

Reactors operating during the period under evaluation included those created as experimental facilities 

for measuring reactor kinetics, neutron irradiation, and shielding factors (e.g., the Graphite Reactor 

and the Bulk Shielding Reactor). 

In addition, in the Critical Reactor Experiments facility, three bench-scale critical assemblies were 

created to study design parameters for neutron reflectivity and criticality measurements. These 

assemblies were brought to critical levels for short periods and later disassembled. Although these 
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assemblies were brought to critical levels and produced neutrons, they were operated behind a 2-ft. 

shield due to concern of a criticality accident (ORNL, 1967). Table 5-7 lists all ORNL reactors in 

existence from 1943 through 1955. 

6.0 Summary of Available Monitoring Data for the Class Evaluated 

by NIOSH 

The following subsections provide an overview of the state of the available internal and external 

monitoring data for the ORNL class under evaluation. 

6.1 Available ORNL Internal Monitoring Data 

Data Description 

A large amount of raw bioassay data exists at the ORNL complex. These data were transcribed into 

an electronic database hosted on ORNL equipment and maintained by ORNL personnel. This 

database (Monitoring, 1945-1990) was queried for historical urinalysis records on October 30, 2003 

and was used by NIOSH for the ORNL Internal Technical Basis Document (ORAUT-TKBS-0012-5). 

A supplemental query was performed on December 12, 2003. These database queries were compiled 

into a single database (Monitoring, 1945-1990).

These queries requested information on the samples and the instrumentation used in the analysis. No 

personal information or individual dose results were requested or received. These database queries 

generated 66,204 records for the period 1945-1988. These records were compiled into a single 

database and data validation and comment fields were added to each record. Then the records were 

examined and classified according to usability for the ORNL Internal Technical Basis document 

MDA calculations (ORAUT-TKBS-0012-5). For consistency, and because they were previously 

examined, these data were used for this evaluation report. Duplicate records and unusable records 

(e.g., gross errors) were not included in this assessment. The database recovered 23913 records from 

1945 through 1959 (which includes most years of the period under evaluation). Of these, 22497 are 

clearly for urinalysis and 1416 are for fecal samples. These data were also cross-verified with a 1949 

Logbook containing plutonium urine sample data obtained through data capture (Monitoring, JanJul1949). The first samples identified are plutonium samples from 1945 through 1948. No bioassay 

samples in the database were prior to 1945. 

Although not included in the database or individual files, there are indications of ORNL urine sample 

results from as early as 1943 (Davis, 1954). This is discussed later in this report. The presentation of 

available internal monitoring data in this report (Section 6.1) also reflects data obtained from ORNL 

during multiple data capture trips conducted by NIOSH. 

A second set of data obtained by ORISE in 2011 was also evaluated (Monitoring, 1943-1959). This 

second data set of 23328 samples provided similar sample results as the 2003 data (Monitoring, 1945-

1990) but did not provide as comprehensive information on specific radionuclides, and thus, was not 

used in this evaluation. The 2011 set of bioassay results was obtained from the Oak Ridge Institute 

for Science and Education (ORISE) Center for Epidemiologic Research (CER) Dosimetry Database, 
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which contains urinalysis records from the ORNL site for the period 1943 to 1959. ORISE obtained 

this database from ORNL for an epidemiological study of site workers. Because the varied operations 

at ORNL involved exposure potential to many radionuclides, the database contains urinalysis data for 

numerous radionuclides. 

There are fairly extensive air monitoring records from 1944 through 1947 that are suitable for 

assigning estimates of exposure and dose. This is discussed later in this report. 

Overview 

The start-up of the Graphite Reactor and plutonium separation activities in late 1943 introduced the 

potential for personnel exposures from intakes of radioactive material. Laboratory operations 

involving radioactive materials increased over subsequent years as ORNL expanded its roles in 

radionuclide production and the development of chemical separations processes. Development of 

methods and techniques for internal monitoring (bioassay) was one of the many ORNL priorities in its 

early years of operation because such methods simply did not exist. 

Although ORNL used air sampling and radiological contamination monitoring programs as qualitative 

indicators of internal exposure, urinalyses for various internal contaminants did not begin at the site 

until about 1945, though possibly as early as 1943. A limited number of in vivo measurements appear 

to have begun at ORNL in 1959. ORNL maintained early tolerance levels for airborne contamination 

based on “product” (i.e., Pu-239) concentrations in the air (Wirth, 1946). These early tolerance levels 

for alpha and beta-gamma contaminants were 3E-11 and 1E-07 μCi/cm3respectively during the mid1940s. 

Isotope-specific analyses for in vitro samples did not become routine until 1989. Prior to that time, 

chemical methods were used to separate radioelements as well as practicable, and the materials were 

assayed in terms of total activity. The activity measured would later be assigned to a predominant 

nuclide. Thus, a result from the early years might indicate Sr-90, when in reality it includes Sr-89. 

The same is true for early plutonium results and results for transuranic materials. Thus, "associated" 

radionuclides are inherently included in such results. Process knowledge of radionuclides present in 

various work areas was used to assign nuclides to sample results. Division codes and building 

locations sometimes provide information on individual locations and specific radionuclides that were 

monitored. 

ORNL Bioassay Programs 

In Vitro Sampling and Analysis 

For much of ORNL’s operational history, health physics representatives, using professional judgment, 

designated personnel for participation in internal dosimetry monitoring (primarily urinalysis during 

the period under evaluation). 

ORNL has collected urine and fecal samples from individuals suspected of potential intakes from 

1945 (and possibly as early as 1943) to the present. Urine samples have been, and still are, the 

preferred method. The volume of sampling during the period under evaluation was relatively low and 
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assays were for uranium and plutonium. The processing of urine samples at the ORNL Urinalysis 

Building started in 1947 (Davis, 1954). At that time, analytical procedures were only available for 

uranium and plutonium and the number of collected samples was not extensive. During the early 

period when checks were made only for plutonium and uranium, the personnel in the urinalysis 

building used organizational charts for determining the personnel to be sampled and requests were 

also made through employees’ supervisors. At this time, this was considered a workable method 

because of the few people involved. During the mid-to-late 1940s, urine and fecal samples were 

collected in the early years of the bioassay program based on the Area Health Physicist’s knowledge 

of field conditions (e.g., known spills/incidents, air and contamination sample results, etc.). When the 

assay for fission products was instituted (~1950), the Health Physicist also determined which 

employees should be sampled. 

Although one plutonium bioassay for 1945 and four plutonium bioassays for 1946 were found in the 

database, and more than 100 plutonium bioassay samples were identified for successive years 

(Monitoring, 1945-1990), reports obtained by NIOSH during on-site data capture indicate plutonium 

bioassay monitoring occurring as early as 1943. One particular report noted that when operations 

started at Clinton Laboratories (now ORNL) in 1943, urine samples were sent to Argonne National 

Laboratory (ANL) in Chicago for processing (Davis, 1954). Another report indicated that plutonium 

urine sample analysis carried out at the Met Lab (ANL) started with the first weekly series on January 

1945 (Wirth, 1945a). Further data captures identified 164 plutonium urine samples taken from 

February 1945 through May 28, 1945 (Monitoring, Feb-Jun1945). No earlier samples have been 

identified. Further discussion is detailed later in this report. 

The ORNL database contains values for isotopic activities during times when isotope-specific 

analyses were not possible or routinely performed. In earlier years, the element of concern was 

extracted chemically from the biological sample and the total radioactivity of the element in the 

extract was measured. At some point after the extraction and sample count, the total sample activity 

was attributed to a specific radionuclide. Many of the isotopic assignments were based on process 

knowledge. 

In order to evaluate the effectiveness of the bioassay program, and as a possible basis for 

improvement, a study was conducted of all urinalysis samples submitted from July 2, 1953 to August 

23, 1954 (Davis, 1954b). The total number of samples was 1265. It was concluded that the method 

for the period seemed adequate and the recommendation was that the major emphasis be placed on 

obtaining samples for employees regularly working with radioactive materials and the schedule for 

sampling to be left at the discretion of the Health Physics area surveyor. It was further recommended 

that the surveyor, each year, select at random a number of employees who do not work regularly with 

radioactive materials and suggest that they submit a sample. 

In Vivo Sampling and Analysis 

Few in vivo measurements have been obtained by NIOSH for the period under evaluation. Reports 

noted thyroid counting results as early as 1946, 1948, and 1951 (Incident, Jan1951; Monitoring, 

Oct1948b; Progress Report, Jun1946). One report indicate that the whole-body counting (WBC) 

facility began operation in July 1959 (Progress Report, Jul1966), and other reports indicate a 

May-June 1960 date (Mani, 1983; Watts, 1995). Thus, it is likely that the WBC facility began limited 

operations in 1959. 
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The initial in vivo counter at ORNL used a 4-inch by 4-inch NaI (Tl) crystal and a tilted chair counting 

arrangement (Progress Report, Jul1961). Prior to February 27, 1961, in vivo counting had been 

restricted to checking individuals involved in known contamination incidents (Progress Report, 

Jul1961). From December 1962 to May 1965, a program to obtain baseline counts on essentially 

everyone with any significant potential for future exposure was accomplished (Mani, 1983).

ORNL has collected whole-body, lung, and wound counting data for employees since 1959. For the 

most part, in vivo counting was used until the late 1980s to confirm potential intakes from known 

incidents or intakes identified by the in vitro monitoring program. Although the Health Physics 

Division Annual Report for the period ending July 31, 1965 indicated that routine in vivo monitoring 

for all site radiological workers began in 1965, it appears that a formal program did not begin until the 

mid-to-late 1980s (Progress Report, Jul1965, pdf p. 251). 

Air Sample Data 

ORNL maintained early tolerance levels for airborne contamination based on “product” (i.e., Pu-239) 

concentrations in the air (Parker, 1944). These early tolerance levels for alpha and beta-gamma 

contaminants were 3E-11 and 1E-07 μCi/cm3, respectively, as early as 1944 and maybe 1943 

(Monitoring, Jun1944-Dec1947). The 3E-11 uCi/cm3

value for alpha was for prevention of deposition 

of 1 microgram of plutonium in the body (Wirth, 1946). For general safety and convenience, other 

alpha emitters were considered at the same activity level (Wirth, 1946). In addition, the laboratory 

later established tolerance levels for materials such as I-131 and noble gases. In practice, controls 

were established to attempt to maintain exposures at ten percent or less of tolerance levels. Controls 

were established requiring an approved respirator, combat mask, or air-line hood in any location 

where the concentration of airborne alpha emitters may be greater than 3E-11 uCi/cm3. Similar 

precautions were taken for airborne beta/gamma emitters (Wirth, 1946).

There are fairly extensive air-monitoring records identified in the 1944 through 1947 timeframe that 

are suitable for assigning estimates of exposure level and/or dose (Monitoring, Jun1944-Dec1947). 

Tolerance levels are well documented and there is strong evidence (i.e., memoranda and monthly 

reports) that exposure was controlled based on samples results (Progress Report, Jan-Dec1946, pdf pp. 

205, 330; Wirth, 1946). These memoranda include weekly reports on the airborne activity levels in 

various areas, as well as precautions taken or to be taken in the future (Monitoring, Jun-Nov1944; 

Monitoring, Aug1944). While exposure to greater concentrations was likely over short periods for 

some occupations, the overriding control goal was to limit the average exposure over longer 

timeframes. 

Based on interviews with former ORNL employees and the sample location descriptions, these air 

samples are believed to be representative of the breathing zone. Air samples were normally taken at 

head height with the intent of sampling a worker’s breathing zone to compare to tolerance levels. 

About one-half of these air samples had sample location descriptions that were noted as six inches 

from the hood or hood samples. Other samples were noted as being taken during assault mask use 

(possible breathing zone), were in unspecified locations in rooms or during activities, or were 

indeterminate. One report in 1944 indicated that, during an air contamination event, air samples were 

noted as being taken in front of a hood; however, on the following page, the sample locations were 

noted only as hood samples (Koval, 1945). In the electronic database, these samples were also 

identified only as hood samples. NIOSH considers this an indication that samples designated as hood 
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samples in the air sample database could be considered “breathing zone” air samples. Further 

discussion on air sample data is detailed later in this report. 

6.1.1 Personnel Monitoring for Plutonium (Pu-238, Pu-239, Pu-240, Pu-241) 

As discussed above, ORNL maintained early tolerance levels for airborne contamination based on 

“product” (i.e., Pu-239) concentrations in the air (Parker, 1944). The early tolerance levels for alpha 

contaminants were 3E-11 μCi/cm3

as early as 1944 and maybe 1943. The 3E-11 value for alpha was 

for prevention of deposition of 1 microgram of plutonium in the body (Wirth, 1946). For general 

safety and convenience, other alpha emitters were considered at the same activity level (Wirth, 1946). 

In practice, controls were established to attempt to maintain exposures at ten percent or less of 

tolerance levels. Controls were established to require an approved respirator, combat mask, or air-line 

hood in any location where the concentration of airborne alpha emitters may be greater than 3E-11 

uCi/cm3. 

One report dated June 28, 1945 (Wirth, 1945b) noted that approximately 40 employees of Clinton 

Laboratories have been working with varying quantities of plutonium. Also, a smaller group of 

perhaps 10 men who have been working in other fields of isolation of fission products may have had 

exposure to smaller quantities of plutonium. No other reports were identified that indicate the number 

of workers exposed to plutonium. 

Documented urinalysis results for total plutonium during the period from 1945 through 1959 have 

been obtained by NIOSH. The number of plutonium bioassay results from the records identified by 

NIOSH for the period under evaluation (and extended out through 1959) are shown in Table 6-1 and 

Figure 6.1. Limited or no bioassay data are available for 1943-1944. 

Urine samples for plutonium have been, and still are, the preferred bioassay monitoring method. As 

stated previously, NIOSH finds indication that some early Clinton Laboratories urine samples were 

sent to ANL in 1943 for processing (Davis, 1954). In the early years, the volume of sampling during 

this period was relatively low and assays were for uranium and plutonium. The processing of urine 

samples at ORNL at their Urinalysis Building started in 1947. At that time, analytical procedures 

were only available for uranium and plutonium and the number of samples collected was not 

extensive. During the early period when checks were made only for plutonium and uranium, the 

personnel in the urinalysis building used organizational charts for determining the personnel to be 

sampled and requests were also made through employees’ supervisors. At that time, this was 

considered a workable method because of the few people involved. In the mid-to-late 1940s, the 

sampling program made the Health Physicist in the field responsible for determining which employees 

should be sampled, scheduling the sampling, and handing out the request forms. Another report 

indicated that plutonium urine sample analysis carried out at the Met Lab (ANL) started with the first 

weekly series in February 1945, with the first 47 plutonium urine samples analyzed for Clinton 

Laboratory personnel in the period February 6, 1945 through March 14, 1945; plutonium analysis 

continued at the Met Lab for at least six months thereafter (Wirth, 1945a).
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One plutonium bioassay in 1945, and four plutonium bioassays for 1946, were found in the electronic 

database. Greater than 100 plutonium bioassay samples were identified in the years thereafter, reports 

from data capture indicate plutonium bioassay monitoring as early as 1943. Further NIOSH data 

capture identified the first 164 plutonium urine samples taken from February 1945 through May 28, 

1945 and include some control samples (Monitoring, Feb-Jun1945). These 1945 plutonium samples 

were not identified within the electronic database records or in the NOCTS-DOE records. Other 

reports (Monitoring, Feb-Mar1945; Whitaker, 1945) indicate potential sample cross-contamination 

issues with the initial 164 plutonium samples and some interference with the LaF3 carrier. Indications 

were that at least some of the samples were collected in the 706-A locker room (in the Chemistry 

Building which housed many extraction processes). Steps were taken around April 30, 1945 to 

minimize contamination issues, including Monday collections, required bathing, and a new location 

for sampling (i.e., in the 703-A Administration Building) (Monitoring, Feb-Jun1945). It is postulated 

that these 1943 to 1945 plutonium urine samples are not in the database because they precede the 

routine sampling program at the site; they were collected as part of a study to determine “the amount 

of plutonium, if any, that may be fixed in the bodies of any chemists at Clinton Laboratories” (Wirth, 

1945a). In a report dated January 31, 1947 (Progress Report, 1946-1956, pdf p. 7), a method for 

removing the lanthanum reagent in-growth was noted. (There was a naturally-occurring contaminant 

[possibly radium] in the reagent that could be interpreted as plutonium). The lab removed the alpha 

contaminant activity by a resin column extraction so that only 0.1 counts per minute per milligram 

remained and there was no appreciable alpha in-growth over a period of two weeks. Prior to this, 

precipitation methods largely removed the alpha contaminant in-growth in the reagent for only a few 

days. 

NIOSH data capture attempts have not identified other plutonium sample results after May 28, 1945 

through December 16, 1946, although indications are that several hundred plutonium urine bioassays 

were taken. More research and data capture is ongoing to obtain these results. One ORNL logbook 

was found for the period of January 1949 through July 1949 which contained over 150 plutonium 

urine bioassay sample results (Monitoring, Jan-Jul1949). The samples in the logbook were in 

sequential order starting with number 446, indicating earlier plutonium sample data exist. More data 

capture efforts are ongoing to locate the earlier logbooks. These January-July 1949 logbook 

plutonium samples were cross-verified with the electronic database records and the records located in 

the NOCTS-DOE records. The logbook plutonium samples were found in the database and NOCTSDOE records; however, uranium results also in the logbook were not found in the electronic database 

or NOCTS-DOE records. 

About 400 plutonium samples (four in December 1946, 188 in 1947, 191 in 1948, and about 25 in 

1949) were indicated in the database from December 16, 1946 through mid-January 1949 (when the 

logbook entries began). Given that 164 samples were indicated in the Met Lab data (in 1945) and that 

about 400 samples were indicated in the database (1946 through mid-January 1949), there appears to 

be more plutonium samples taken than the first sequential number in the 1949 logbook would 

indicate.
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Before 1989, ORNL did not routinely perform isotope-specific analyses for plutonium. Rather, the 

Laboratory separated plutonium as an element and analyzed it by proportional counting. Therefore, 

the historic plutonium analysis technique was unable to differentiate among the alpha-emitting 

isotopes Pu-238, Pu-239, and Pu-240. The default isotope for dose reconstruction using plutonium 

bioassays is Pu-239. One report on September 1, 1947 noted the use of calcium oxelate for the 

determination of plutonium (Progress Report, 1946-1956, pdf p. 21).

NIOSH’s current assignment of internal dose for potential exposures occurring from 1943 through 

1950 is based on a modified ORAUT-OTIB-0018 approach. ORAUT-OTIB-0018, Internal Dose 

Overestimates for Facilities with Air Sampling Programs, applies through 1950 and uses the ORNL 

plutonium tolerance level limit of 3E-11 μCi/mL (ORAUT-OTIB-0018). The ORNL co-worker 

study, ORAUT-OTIB-0034, is based on bioassay results and applies starting in 1951 (ORAUT-OTIB0034). The modified ORAUT-OTIB-0018 approach was developed based on air concentration limits. 

ORAUT-OTIB-0018 is considered to generally provide an overestimate for a number of reasons. 

Exposure at the maximum permissible air concentration is assumed for 40 hours per week, 50 weeks 

per year. While exposure to concentrations greater than the maximum permissible air concentration is 

likely over short periods for some occupations, the overriding control factor was to limit the average 

exposure over longer timeframes. In addition, the nuclide that results in the largest dose is assumed to 

comprise 100% of the intake; the list of possible nuclides includes some that are very unlikely to be 

present in significant quantities. During the early years of ORNL, several of the nuclides on the list 

were just being discovered or were yet to be discovered. The NIOSH-assigned nuclide might change 

from year to year to ensure that the largest possible dose is assigned in each year until the date of 

diagnosis. 

Although not included in the individual files, there are limited urine sample results from ORNL in 

1945 (i.e., 164 plutonium urine samples taken from February 1945 through May 28, 1945) 

(Monitoring, Feb-Jun1945). An analysis of the data indicates that the geometric mean of this 

distribution is somewhat large (1.7 pCi/1400 mL) and the fit to the results indicates that there are 

possibly two distributions. If this value is assumed to be due to a constant, chronic intake of Type M 

Pu-239 beginning in early 1944, an airborne concentration of 8.1 × 10-11 μCi/mL is indicated. This is 

almost three times larger than the tolerance level of 3 × 10-11 μCi /mL in effect at the time. If Type S 

is assumed, the airborne concentration is expected to be two orders of magnitude larger than the 

tolerance level. In a memorandum dated May 11, 1945, it was reported that the findings appeared to 

be above control levels, which resulted in a more rigid collection technique and system of collecting 

samples being implemented on April 25 (Monitoring, Feb-Apr1945). Results in the first two weeks of 

this more-rigid collection system were not substantially different from previous results, but samples in 

the subsequent, final four weeks of the study showed little detectable activity and include some 

control samples (Monitoring, Feb-Jun1945). The geometric mean before April 25, 1945 is 3.1 

pCi/day, while after this date it drops to 0.54 pCi/day. The arithmetic average of the results from 

April 25 through the end of the study is about 25% of the average during the previous weeks, and the 

average from the final four weeks is about 3% of the earlier weeks. These comparisons indicate that 

the ORNL concerns about the collection system before April 25 may have been justified. 
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In addition to the urine samples, 1483 alpha air-monitoring results were available for 1944 through 

1947 at ORNL (Monitoring, Jun1944-Dec1947). The two largest values, both many orders of 

magnitude larger than the tolerance level in use at the time, were excluded from the analysis because 

one appeared to be a miscalculation (based on the recorded alpha activity) and the other was collected 

inside a hot cell. Results were fit to a lognormal distribution. The geometric mean is 5% of the 

tolerance level applied in ORAUT-OTIB-0018, and the 95th percentile is equal to the tolerance level. 

Notes indicating that assault masks had been worn were present for just under 10% of the samples; 

many of the samples were collected inside of hoods. Given this information, ORAUT-OTIB-0018 

appears to be a reasonable upper bound because the 95th percentile of the air-monitoring results 

coincides with the value applied in that document. Assault masks were used in many situations and 

many of the results exceed the activity to which the individual would have been exposed because 

samples were collected inside of hoods. Conservativeness is built into ORAUT-OTIB-0018 by the 

inclusion of alpha emitters with large dose coefficients that were likely not present or present only in 

very small quantities. 

The number of identified plutonium bioassay results is presented in Table 6.1 and Figure 6-1. 

Table 6-1: Available Bioassay Measurements for Plutonium Performed at ORNL, 1943-1959

Year Pu-239 Urine Pu-239 Fecal Pu-238 Urine Gross Alpha 

Urine 

GA Fecal Total Pu and 

Gross Alpha

1943 0 0 0 0 0 0

1944 0 0 0 0 0 0

1945 165a 0 0 0 0 165

1946 4 0 0 0 0 4

1947 188 0 0 0 0 188

1948 191 0 0 0 0 191

1949 348 0 0 0 0 348

1950 311 0 3 0 0 314

1951 385 0 0 0 0 385

1952 760 0 4 0 0 764

1953 436 0 1 4 0 441

1954 868 2 4 93 0 967

1955 596 0 2 211 50 859

1956 651 1 2 38 0 692

1957 389 15 0 102 10 516

1958 370 0 5 318 6 699

1959 386 0 2 484 75 947

Source: Monitoring, 1945-1990; Monitoring, Jan-Jul1949 

a

 Includes 164 plutonium samples identified from data capture in 1945 not in database. 
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Source: Monitoring, 1945-1990; Monitoring, Jan-Jul1949

Includes 164 plutonium samples identified from data capture in 1945 but not in database. 

Figure 6-1: Bioassay Measurements for Plutonium Performed at ORNL, 1943-1959

6.1.2 Personnel Monitoring for Uranium (U-238, U-233, U-234, U-235), 

As discussed above, ORNL maintained early tolerance levels for airborne contamination based on 

“product” (i.e., Pu-239) concentrations in the air (Parker, 1944). The early tolerance levels for alpha 

were 3E-11 μCi/cm3

 as early as 1944 and maybe 1943 (Monitoring, Jun1944-Dec1947). For general 

safety and convenience, other alpha emitters were considered at the same activity level (Wirth, 1946). 

In practice, controls were established to attempt to maintain exposures at ten percent or less of 

tolerance levels. Controls were established to require an approved respirator, combat mask, or air-line 

hood in any location where the concentration of airborne alpha emitters may be greater than 3E-11 

uCi/cm3 (Wirth, 1946). 

Documented urinalysis results for total uranium during the period from 1949 through 1959 have been 

obtained by NIOSH. The number of uranium bioassay results recorded during the period under 

evaluation (and extended out through 1959) is shown in Table 6-2 and Figure 6-2. Limited or no 

bioassay data are available for 1943-1948. Urine samples for uranium have been, and still are, the 

preferred method. 

One report indicated that as of September 1, 1947, work continued on the development of a practical 

procedure for the routine determination of uranium in urine (Progress Report, 1946-1956, pdf p. 22). 

Another report dated February 28, 1949 (Progress Report, 1946-1956, pdf p. 79) noted a method for 

analyzing for uranium, developed to meet the need for a method sufficiently sensitive for monitoring 

significant body content of U-233, had been put into routine operation and during the last six months, 
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158 uranium analyses had been made on urine specimens. The volume of sampling during this period 

was relatively low and assays were for uranium and plutonium. As previously discussed, the 

processing of urine samples at ORNL at their Urinalysis Building started in 1947. At that time, 

analytical procedures were only available for uranium and plutonium and the number of samples 

collected was not extensive. During the early period when checks were made only for plutonium and 

uranium, the personnel in the urinalysis building used organizational charts for determining the 

personnel to be sampled and requests were also made through employees’ supervisors. At that time,

this was considered a workable method because of the few people involved. In the mid-to-late 1940s, 

the sampling program in use made the Health Physicist in the field responsible for determining which 

employees should be sampled, scheduling the sampling, and handing out the request forms. 

As previously noted, although 79 bioassays were found in the database for 1949 (starting August 5, 

1949) and more than 100 uranium bioassay samples were identified for years thereafter, reports 

obtained during data captures indicate uranium bioassay monitoring occurring as early as 1947 (Davis, 

1954b). Other weekly reports indicate uranium urine bioassay monitoring results beginning in August 

1948 (Weekly Report, Aug 28, 1948; Weekly Report, Sep 12, 1948; Weekly Report, Oct 17, 1948; 

Weekly Report, Nov 14, 1948; Weekly Report, Nov 28, 1948; Weekly Report, Dec 12, 1948; Weekly 

Report, Jan 16, 1949; Weekly Report, Feb 6, 1949; Weekly Report, Mar 27, 1949). One report 

(Progress Report, 1946-1956, pdf p. 79) ending in February 1949 indicated that in the last six months 

158 uranium analyses had been made on urine specimens. These 1948-1949 samples were not found 

in the database or in the NOCTS-DOE records. 

More research and data capture is ongoing to obtain these sample analysis results. One ORNL 

logbook was found for the period January through July 1949; it contains 151 uranium (U-233) urine 

bioassay sample results (i.e., prior to the data found in the electronic database) (Monitoring, 

Jan-Jul1949). Another logbook for the period May through August 1949 contains 88 uranium 

(U-233) urine bioassay sample results. The samples in the January-July logbook are in sequential 

order starting with number 446 and ending with sample 604, indicating earlier sample data may also 

exist. The May-August samples are in sequential order starting with number 605. More data capture 

efforts are ongoing in an attempt to locate the earlier logbooks. These logbook uranium samples were 

cross-verified with the electronic database records and the records located in the NOCTS-DOE 

records. The plutonium samples were found in the database and NOCTS-DOE records; however, 

uranium results in the logbook were not found in the electronic database or NOCTS-DOE records. 

Also, the logbook uranium results were for U-233 and most uranium samples found in the database 

were identified as U-238 (with one U-233 sample). 
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Before 1989, ORNL did not routinely perform isotope-specific analyses for uranium. Rather, the 

laboratory separated uranium as an element and analyzed it by proportional counting. Therefore, the 

historic uranium analysis technique was unable to differentiate among the alpha-emitting isotopes 

U-233, U-234, U-235, and U-238. The default isotope for dose reconstruction using uranium 

bioassays is U-234. 

Table 6-2: Available Bioassay Measurements for Uranium Performed at ORNL, 1949-1959

Year U-233 urine U238 urine U238 fecal U239 urine Total U

1949 240a 77 0 1 318

1950 44 131 0 0 175

1951 274 11 0 0 285

1952 170 625 0 0 795

1953 25 576 0 0 601

1954 33 830 0 0 863

1955 27 872 0 1 900

1956 27 887 1 1 916

1957 22 554 1 1 578

1958 0 896 1 1 898

1959 0 747 0 1 748 a

 Includes 239 uranium samples identified from data capture in 1949 not in database.

Source: Monitoring, 1945-1990; Monitoring, Jan-Jul1949; Monitoring May-Aug 1949

Source: Monitoring, 1945-1990; Monitoring, Jan-Jul1949; Monitoring May-Aug 1949 a

 Includes 239 uranium samples identified from data capture in 1949 not in database. 

Figure 6-2: Bioassay Measurements for Uranium Performed at ORNL, 1949-1959
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6.1.3 Personnel Monitoring for Fission and Activation Products 

As discussed above, tolerance levels for alpha and beta-gamma contaminants were 3E-11 and 1E-07 

μCi/cm3, respectively, as early as 1944 and maybe 1943 (Monitoring, Jun1944-Dec1947). For general 

safety and convenience, other alpha-emitters were considered at the same activity level (Wirth, 1946). 

In addition, the laboratory later established tolerance levels for materials such as I-131 and noble 

gases. In practice, controls were established to attempt to maintain exposures at ten percent or less of 

tolerance levels. Controls were established to require an approved respirator, combat mask, or air-line 

hood in any location where the concentration of airborne alpha emitters may be greater than 3E-11 

uCi/cm3and similar precautions were taken for airborne beta/gamma emitters based on 1E-7 uC/cm3

(Wirth, 1946). 

Documented urinalysis results for fission products during the period from 1943 through 1959 have 

been obtained by NIOSH. The number of fission product bioassay results recorded during the period 

under evaluation (and extended out through 1959) is shown in Table 6-3 and Figure 6-3. Limited or 

no bioassay data are available prior to 1950. 

Forty-eight (48) fission product bioassays were found in the database for 1950 and more than 300 

fission product bioassay samples (primarily cesium and strontium) were identified in successive years. 

Urine samples and in vivo counting for fission and activation products have been, and still are, 

generally the preferred method. One report indicated gross beta urine bioassay monitoring results as 

early as October 1948. (Weekly Report, Oct 17, 1948). One report dated January 15, 1950 indicates 

that an exploratory survey (urinalysis) for alkaline earth and rare earth beta-gamma emitting elements 

was made on 38 individuals (Progress Report, 1946-1956, pdf p. 127). Another report noted this 

exploratory survey, but noted that the rare earth analysis was to supplement the fission-product-inurine procedure already in place (Progress Report, Oct1950). Another report dated April 15, 1950 

indicates that an analysis procedure for strontium was in use (Progress Report, 1946-1956, pdf p. 

149). A survey of urinalyses for fission products conducted at ORNL during the last two years 

determined that where measurable amounts were found, it was due, in most cases, to radioisotopes of 

strontium (Progress Report, 1946-1956, pdf p. 257). 

Table 6-3: Bioassay Measurements for Fission and Activation Products 

Performed at ORNL, 1950-1959

Year Bioassays

1950 48

1951 364

1952 828

1953 844

1954 1271

1955 1063

1956 861

1957 659

1958 1975

1959 1980

Source: Monitoring, 1945-1990 
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Source: Monitoring, 1945-1990

NOTE: Does not include plutonium, uranium, and thorium bioassays. 

Figure 6-3: Bioassay Measurements for Fission and Activation Products Performed at ORNL, 1950-1959

6.1.4 Personnel Monitoring for Thorium 

As previously noted, there are fairly extensive air-monitoring records in the 1944 through 1947 

timeframe that are suitable for assigning estimates of exposure and/or dose. 

Approximately 1500 air sample results were identified in an electronic database (Monitoring, 

Jun1944-Dec1947). Based on interviews with former ORNL employees and the sample location 

descriptions, these air samples are believed to be representative of the breathing zone. Air samples 

were normally taken at head height with the intent of sampling a worker’s breathing zone to compare 

to tolerance levels. About one-half of these air samples had sample location descriptions which were 

noted as six inches from the hood or hood samples. Other samples were noted as during assault mask 

use (possible breathing zone), were in unspecified locations in rooms or during activities, or were 

indeterminate. There were 1141 alpha air samples noted in Building locations 706-A and 706-C from 

1944-1947 where much of the thorium-related processes occurred. More data capture efforts are 

ongoing to locate additional air sample information. It is postulated that this large number of air 

samples from the primary thorium-processing facilities would bound thorium exposure for the period 

1944-1946. This period coincides with the period in which primarily only lab-scale thorium processes 

occurred.
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Documented urinalysis results for thorium during the period from 1943 through 1959 have been 

obtained by NIOSH. One Th-232 urine sample was identified in 1950 and 1954, and others were 

identified from 1956 through 1959. Gross alpha fecal samples were identified starting in 1955. 

Th-232 fecal sampling started in 1955 (two samples) and more than 100 were identified in successive 

years. The number of thorium bioassay samples recorded during the period under evaluation (and 

extended out through 1959) is shown in Table 6-4 and Figure 6-4. As indicated, limited or no thorium 

bioassay monitoring results were identified from 1943 through 1953. 

Contemporary ICRP biokinetics models for thorium show that urine bioassay lacks the sensitivity to 

demonstrate compliance with regulatory limits, and therefore, urine bioassay is not used as part of a 

routine thorium bioassay program. However, it was determined that thorium bioassay monitoring 

began in 1955 via the gross alpha fecal samples in 1955 and Th-232 fecal samples from 1956 and 

thereafter. A NIOSH review of a 1959 procedure for preparing urine samples for gross alpha 

measurements indicates that thorium would be present in the samples (i.e., not separated out in the 

sample preparation). Fecal sample preparation would be similar to that of the urine for gross alpha. 

Given the timeline of thorium processes at ORNL, it is postulated that these 1955 gross alpha fecal 

samples were for thorium monitoring. 

The ORNL database contains values for isotopic activities during times when isotope-specific 

analyses were not possible or routinely performed. In earlier years, the element of concern was 

extracted chemically from the biological sample and the total radioactivity of the element in the 

extract was measured. At some point after the extraction and sample count, the total sample activity 

was attributed to a specific radionuclide. Many of the isotopic assignments were based on process 

knowledge. During the period 1955 to 1956, there was a transition from gross alpha fecal to Th-232 

fecal. 

Table 6-4: Bioassay Measurements for Thorium Performed at ORNL, 1955-1959

Year Gross Alpha fecal Th-232 fecal Th-232 urine Total

1955 50 2 0 52

1956 0 103 11 114

1957 10 118 14 132

1958 6 764 28 798

1959 75 217 7 299

Source: Monitoring, 1945-1990 
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Source: Monitoring, 1945-1990

Figure 6-4: Bioassay Measurements for Thorium Performed at ORNL, 1955-1959 

In vivo counting was implemented in 1959-1960 and would have been sensitive to thorium daughter 

products, but was not available during the period under evaluation. Later on, whole-body counting 

and chest counting were routinely used as part of the ORNL internal dosimetry program. 

Representative air sampling data have been requested for locations where un-encapsulated thorium 

was processed prior to 1960. ICRP 75, General Principles for the Radiation Protection of Workers, 

discusses the uses of area air sampling to establish trends and representative air sampling to quantify 

the extent of airborne contamination to which workers are likely to be exposed. The air sampling 

requirement specified in the August 1954 Test Authorization Number 3-138 suggests that the air 

sampling data will satisfy the "representative sampling" definition in ICRP 75, which states that 

representative sampling typically involves using fixed samplers at locations intended to be reasonably 

representative of the breathing zone of the workers. If air sample data are available as expected, then 

intake rates can be calculated based on an assumption of a default breathing rate and an appropriate 

occupancy factor in these areas using the air sample data. 

6.1.5 Personnel Monitoring for Exotic Radionuclides 

ORNL built and operated cyclotrons and accelerators on the Y-12 site. These operations generated 

radionuclides (e.g., C-14, Ca-45, P-32, Ba-140/La-140, and others). NIOSH has access to data for 

these operations. However, this topic is reserved for this evaluation report because cyclotron and 

accelerator operations at both ORNL (X-10) and Y-12 will be addressed in a future combined 

evaluation effort. 
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6.2 Available ORNL External Monitoring Data 

Copies of original documents containing film badge and pocket dosimeter results with dates between 

1944 and 1949 have been found. They can be found in the following references: 

1944:

Monitoring, Jan-Dec1944

Monitoring, Jan1944-Feb1950

Monitoring, Aug1944-Oct1945

1945:

Monitoring, May-Aug1945

1947:

Monitoring, Jan1947

Monitoring, Feb1947

Monitoring, Mar1947

Monitoring, Mar-Jun1947

Monitoring, Apr1947

Monitoring, May1947

Monitoring, Jun1947a

Monitoring, Jun1947b

Monitoring, Jul1947a

Monitoring, Jul1947b

Monitoring, Jul-Dec1947

Monitoring, Aug1947a

Monitoring, Aug1947b

Monitoring, Aug1947c

Monitoring, Sep1947a

Monitoring, Sep1947b

Monitoring, Oct1947a

Monitoring, Oct1947b

Monitoring, Nov1947a

Monitoring, Nov1947b

Monitoring, Dec1947a

Monitoring, Dec1947b

Monitoring, 1947-1948

1948:

Monitoring, Jan1948

Monitoring, Feb1948

Monitoring, Mar1948

Monitoring, Apr1948

Monitoring, May1948

Monitoring, Jun1948

Monitoring, Jul1948

Monitoring, Aug1948

Monitoring, Sep1948

Monitoring, Oct1948a

Monitoring, Nov1948

Monitoring, Dec1948

1949:

Monitoring, Jan1949

Monitoring, Jan-Apr1949

Monitoring, Jan-Dec1949

Monitoring, Feb1949

Monitoring, Mar1949

Monitoring, Apr1949

Monitoring, Apr-Jun1949

Monitoring, May1949

Monitoring, May-Dec1949

Monitoring, Jun1949

Monitoring, Jul1949

Monitoring, Jul-Aug1949

Monitoring, Aug1949

Monitoring, Sep1949

Monitoring, Oct1949

Monitoring, Nov1949

Monitoring, Dec1949

1951:

Monitoring, Feb-Apr1951

1989:

Ahmed, 1989

One document containing similar data for 1954 has been found (Monitoring, Jan-Dec1954). The 

above data include both photon and beta results and are associated with names or payroll numbers. 

Copies of original Weekly Neutron Film Reports for 1947, 1948, and 1949 have been found. These 

reports contain employee names and badge numbers along with the number of tracks observed for 

“Open Window,” “Shield,” and “Star Tracks” - with the greatest majority of the results listed as 

having zero tracks. These reports can be found in the following references: 

Progress Report, Aug-Dec1947

Progress Report, Dec1947-Feb1948

Progress Report, Feb-Apr1948

Progress Report, Apr-Jul1948

Progress Report, Jul-Sep1948

Progress Report, Sep-Oct1948

Progress Report, Oct-Dec1948

Progress Report, Dec1948-Apr1949

Progress Report, May-Jun1949

Progress Report, Apr-Jul1949

Progress Report, Jul-Sep1949

Progress Report, Sep1949-Jan1950

In addition, reports on specific incidents within the period of interest have been located that include 

names of the employees present and film badge results. These reports can be found in the following 

references: 

Incident, Jul1951

Incident, Oct1951

Incident, Nov1951

Monitoring, Jul1951

Incident, Jan1952

Incident, Mar1952

Incident, Apr1952

Incident, Aug1952

Incident, Sep1952

Incident, Apr-May1954

Incident, Dec1960

Incident, Apr1976

In response to a NIOSH request, a spreadsheet report from ORNL’s exposure database was provided 

by the site (Monitoring, 1943-1959b). The dates in the spreadsheet range from 1943 through 1959. It 

contains 45,447 rows for dates between 1943 and 1955. Each row has the name of the employee, 

either a five-digit or six-digit badge number, sample date, year, “Gamma_Exposure,” and 

“Beta_Exposure.” ORNL indicated that the field labeled “Gamma_Exposure” includes all assigned 
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neutron exposure results (Personal Communication, 2012e). Although an exact count of the 

individuals included may not be possible due to potential misspellings and name changes, the 

spreadsheet contains 8074 unique names. In the great majority of the results, a department code is 

also listed. Table 6-5 is a list of years, the count of distinct results (each with both a gamma and beta 

result), and the number of distinct names in the spreadsheet for those years. Note that the total of 

names by year is greater than the number of distinct names in the spreadsheet due to people working 

at the site for multiple years. 

Table 6-5: Number of Records by Year in ORNL Report from Exposure Database

Year Record Count No. of Names

1943 1345 857

1944 4117 2106

1945 2946 1747

1946 2674 1799

1947 3215 2266

1948 3793 2584

1949 2516 2039

1950 3442 2599

1951 4174 3086

1952 4355 3271

1953 3953 3158

1954 4536 3336

1955 4536 3471

--- Total = 46,928 ---

Source: Monitoring, 1943-1959b 

A comparison of the data in this spreadsheet with the data obtained in 2004 that formed the basis for 

ORAUT-OTIB-0021, External Coworker Dosimetry Data for the X-10 Site, shows that they are 

essentially the same. 

Type of dosimeter, frequency, and minimum reported dose are documented for all years. From 1943 

through June 1944, pocket ionization chambers were used on a daily basis. After June 1944, film 

badges were used. After 1951, dosimeters were used by all employees at the site. The pocket 

ionization chamber was read daily; the film badge was read weekly though 1951 and weekly for 

radiation workers through 1954. For non-radiation workers between 1951 and 1954, the film badge 

was read annually (Ahmed, 1989). Calibration data for 1953, 1954, and 1955 are documented 

(Gordon, 1986). 

The types of film badges used at ORNL are well documented (Davis 1954a; Parrish, 1982; Thornton, 

1961). During the period under evaluation, advances were made in both the type of filters used in film 

badges and the film types they contained to compensate for energy dependence, to extend the dose 

range, to minimize any interference, and to measure multiple radiation types in a single device. Of 
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particular interest was the development of the “ORNL Badge” in 1954, which combined the film 

badge with the identification badge (Davis 1954a, pdf p. 174). Table 6-6 lists the types of film badges 

used at ORNL between 1946 and 1955. 

Table 6-6: Types of Film Badges Used at ORNL from 1946 through 1955

Year Introduced Material Used in Construction Filters Films Used

1944 Tin Cd, W DuPont 552

1949 Stainless Steel Cd, W DuPont 552 and fine 

grained particle

1951 Stainless Steel Pb, Cd, Cu, Pl, W DuPont 552, NTA

1953 Plastic Pb, Cd, Cu, Pl, W DuPont 552, NTA

1954 Plastic Pb, Cd, Cu, Pl, W DuPont 553, NTA

Source: Adapted from Thornton, 1961, pdf p. 7 

Between 1944 and 1949, neutron dosimetry was conducted through the use of Eastman “Special 

Fine-Grain Particle Safety Film,” which recorded tracks from recoil protons resulting from incident 

neutrons. Thermal neutron exposure could be distinguished from fast through the use of a cadmium 

shield for a portion of the film (Bradley, 1945; Cheka, unspecified).

Neutron tolerance levels for the period (1650 /cm2-second for thermal and 266/cm2-second for fast) 

was measurable by these fine-grain films (Cheka, unspecified, Wirth, 1945c). The calibration data 

and conversion factors for the observed-tracks-per-field is documented (Cheka, unspecified). 

After 1950 and through 1954, NTA film was used for neutron dosimetry. 

A letter from 1951 states that a “film loaded finger ring” was in use and had been “for some years” 

(Hart, 1951). The minimum threshold of sensitivity was “0.3 r...when exposed to Radium gamma.” 

A March 12, 1948 summary of radiation protection requirements states that ring badges are required 

for certain types of work (Monitoring, Jul-Dec1947, pdf p. 5). 

Several documents provide the history of the research and development of the ORNL badges (Ahmed, 

1989; Davis 1954a, pdf p. 171; Parrish, 1982; Thornton, 1961). The report ORNL-3126, The ORNL 

Badge Dosimeter and Its Personnel Monitoring Applications, was published in 1961 and is the basis 

for much of the information in the current technical basis documents used by NIOSH to support dose 

reconstructions. 

These reports on the history of ORNL dosimetry also include information on the creation and use of 

NTA-type film badges, starting as early as 1949. In addition, many documents containing neutron 

exposure data have been located. 
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Some limited photon survey data have been found but they are incomplete for any location or time 

and only serve to show that such surveys were used to document levels in restricted areas. With the 

exception of the Graphite Reactor, no neutron survey data have been located for areas related to 

occupational exposure for the reactors or for the Critical Experiments. 

In 1946, gamma and thermal neutron surveys were made around the Graphite Reactor. Survey 

locations included the north and south faces of the reactor, locations near beam ports, and the 

“Operator Table” or “Operator Desk.” A total of 156 paired measurements have been located 

(Progress Report, Jan-Jul1946). 

The document, ORNL Historical X-ray Practices and Protocols (ORNL, post-2002), lists the specific 

X-ray equipment, procedures, and technique factors used at the site. It also states that prior to October 

3, 1947, all pre-employment X-rays, and presumably any routine annual X-rays, were performed at 

Oak Ridge Hospital. Oak Ridge Hospital is located on what was then the Clinton Engineering Works 

site and is EEOICPA-covered from 1943 to 1959. After October 3, 1947, X-rays were performed on 

the ORNL site. 

Details regarding the various analyses used and the associated minimum detectable activities are 

presented in the Technical Basis Document for the ORNL Site - Occupational External Dose (ORAUTKBS-0012-6). 

7.0 Feasibility of Dose Reconstruction for the Class Evaluated by 

NIOSH 

The feasibility determination for the class of employees under evaluation in this report is governed by 

both EEOICPA and 42 C.F.R. § 83.13(c)(1). Under that Act and rule, NIOSH must establish whether 

or not it has access to sufficient information either to estimate the maximum radiation dose for every 

type of cancer for which radiation doses are reconstructed that could have been incurred under 

plausible circumstances by any member of the class, or to estimate the radiation doses to members of 

the class more precisely than a maximum dose estimate. If NIOSH has access to sufficient 

information for either case, NIOSH would then determine that it would be feasible to conduct dose 

reconstructions. 

In determining feasibility, NIOSH begins by evaluating whether current or completed NIOSH dose 

reconstructions demonstrate the feasibility of estimating with sufficient accuracy the potential 

radiation exposures of the class. If the conclusion is one of infeasibility, NIOSH systematically 

evaluates the sufficiency of different types of monitoring data, process and source or source term data, 

which together or individually might assure that NIOSH can estimate either the maximum doses that 

members of the class might have incurred, or more precise quantities that reflect the variability of 

exposures experienced by groups or individual members of the class as summarized in Section 7.5. 

This approach is discussed in DCAS’s SEC Petition Evaluation Internal Procedures which are 

available at http://www.cdc.gov/niosh/ocas. 
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The next four major subsections of this Evaluation Report examine:

The sufficiency and reliability of the available data. (Section 7.1) 

The feasibility of reconstructing internal radiation doses. (Section 7.2) 

The feasibility of reconstructing external radiation doses. (Section 7.3) 

The bases for petition SEC-00189 as submitted by the petitioner. (Section 7.4) 

7.1 Pedigree of ORNL Data

This subsection answers questions that need to be asked before performing a feasibility evaluation. 

Data Pedigree addresses the background, history, and origin of the data. It requires looking at site 

methodologies that may have changed over time; primary versus secondary data sources and whether 

they match; and whether data are internally consistent. All these issues form the bedrock of the 

researcher’s confidence and later conclusions about the data’s quality, credibility, reliability, 

representativeness, and sufficiency for determining the feasibility of dose reconstruction. The 

feasibility evaluation presupposes that data pedigree issues have been settled. 

7.1.1 Internal Monitoring Data Pedigree Review 

NIOSH obtained both air sampling and bioassay results for the period under evaluation. Air sample 

results were received for 1944-47. Bioassay sample results were obtained starting in 1944. The 

bioassay results are urinalyses starting in 1945 and fecal sample results starting in 1955. 

As discussed in Section 5.0, a database containing approximately 1500 air monitoring records from 

1944 through 1947 was reviewed and determined to be suitable for assigning internal dose estimates 

(Monitoring, Jun1944-Dec1947). The air monitoring records were gross alpha activity measurements, 

approximately 1100 of which were taken in Building 706-A where plutonium and thorium processing 

took place. The noted sample locations and descriptions indicate to NIOSH that these air samples 

adequately represent the breathing zone air concentrations. Based on interviews with former ORNL 

employees, air samples were normally taken at head height and were intended to be representative of 

what a worker might breathe because the results were compared to their established tolerance levels to 

determine if respiratory controls were needed. The sample results were commonly given in activity 

units (uCi/cm3

) and as a percent of the tolerance level (Monitoring, Jun1944-Dec1947). The alpha 

tolerance level was 3E-11 uCi/cm3

. The alpha tolerance level was put in place to prevent the 

inhalation and subsequent deposition of 1 microgram of plutonium in the body (Wirth, 1946). For 

general safety and convenience, other alpha emitters were considered at the same activity level (Wirth, 

1946). The air sampling protocol for monitoring alpha activity in air was reviewed by NIOSH and 

found to be sufficient for personnel monitoring and establishing controls. The volume of breathing 

zone air samples and the comparison to tolerance levels that was in place to control excessive 

inhalation of airborne radioactivity is indicative of an established air monitoring program. 
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Upon further review of the air monitoring records database, a corresponding reference document 

number was found for each data entry. The reference document numbers corresponded to documents 

contained within the ORNL Central Files. During data capture visits to ORNL, NIOSH specifically 

requested and reviewed documents and memos from the Central Files that were referenced in the air 

monitoring records database (Air Contamination, Nov1944; Air Contamination, Jan1945). All of the 

air sample data obtained from these documents and memos were found to be included in the database 

of air monitoring records, confirming that the database was accurately created using primary source 

documents. 

The air sampling database was determined to be sufficient to use as internal monitoring data. The 

database was created using primary source documents, contains a large volume of breathing zone air 

samples, and the samples were taken using an adequate air sampling protocol. 

A large amount of raw bioassay data exists at the ORNL complex. These data were transcribed into 

an electronic database hosted on ORNL equipment and maintained by ORNL personnel. This 

database (Monitoring, 1945-1990) was queried in 2003 for historical urinalysis records and generated 

66,204 records for the period 1945-1988 (ORAUT-TKBS-0012-5). These records were compiled into 

a single database and a data validation and comment field was added to each record. The records 

were then examined by NIOSH and classified according to usability and later used to develop the 

minimum detectable activities (MDAs) for various radionuclides detected in urine or fecal samples. 

These data were also cross-verified with a 1949 Logbook containing approximately 150 plutonium 

urine sample results obtained through data capture and found to be accurate (Monitoring, JanJul1949). A similar check with the electronic database was conducted against the dosimetry records 

of 16 former ORNL employees who worked during the 1940s. Bioassay results in their records were 

verified to be included in the electronic database. No records of urinalysis for uranium or fission 

products were found before 1949 and 1950, respectively. Duplicate records and unusable records 

(e.g., gross errors) were not included in this assessment. 

7.1.2 External Monitoring Data Pedigree Review 

Primary documentation and summary reports are available for both photon and beta exposure for 

individual workers (see Section 6.2 for references). In addition, NIOSH has almost 46,000 photon 

results and the same number of beta results for more than 9,000 individuals. Documents with neutron 

results for both fine-grain film and for NTA film are available for certain years with results listed by 

employee name, badge number, or both. 

Examples of calibration methods for beta on film (Hart, 1947a; Weeks, 1945) photon on film 

(Gupton, 1981; Monitoring, 1953-1970; Progress Report, Jul1955-Jan1956), neutron on film (Bradley, 

1945) and pocket dosimeters (Hart, 1947b) are available. 

For the great majority of claimants, their results can be expected to exist in one or more of the 

documents acquired by NIOSH from ORNL, or they may be obtained from ORNL. 

NIOSH has obtained sufficient data on workers for all years of the class under evaluation to estimate 

likely worker exposures using co-worker data. A co-worker study has been performed against the 

data and is presented in ORAUT-OTIB-0021, External Coworker Dosimetry Data for the X-10 Site. 
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For those workers who do not have exposure results and those results cannot be obtained from DOE, 

the results of the co-worker analysis in ORAUT-OTIB-0021 may be applied. 

7.2 Evaluation of Bounding Internal Radiation Doses at ORNL (X-10)

The principal sources of internal radiation doses for members of the class under evaluation include 

plutonium, uranium, thorium, and mixed fission products. The following subsections address the 

ability to bound internal doses, methods for bounding doses, and the feasibility of internal dose 

reconstruction. 

7.2.1 Evaluation of Bounding Process-Related Internal Doses 

The following subsections summarize the extent and limitations of information available for 

reconstructing the process-related internal doses of members of the class under evaluation. 

7.2.1.1 Urinalysis Information and Available Data 

As previously discussed in Section 7.1, there is an extensive urine bioassay database that NIOSH 

believes is sufficient for bounding internal radiation exposure estimates due to plutonium, uranium 

and mixed fission products. The earliest urine bioassay data contained in the database are for 

plutonium starting in 1947, uranium in 1949, and fission products in 1950 (Monitoring, 1945-1990). 

In addition to the bioassay database, approximately 150 plutonium urinalysis results from 1945 were 

located in documents in the ORNL Central Files (Monitoring, Feb-Jun1945). Although NIOSH 

believes sufficient data are currently available for bounding internal radiation exposures during 

specified time periods, NIOSH is continuing to pursue additional data. NIOSH will continue to 

evaluate as additional urine bioassay data become available and are compiled. 

The first urine bioassays for ORNL employees were for plutonium. An internal document describing 

the bioassay program at ORNL in the 1940s stated that urine bioassay analyses were performed on 

site at the ORNL facility starting in 1947 (Davis, 1954b). Prior to that, urine samples were collected 

and sent to the Met Lab in Chicago for analysis (Davis, 1954b). Procedures were developed in 1944 

and 1945 for the detection of plutonium in urine. Two such documents include: Methods of Analysis 

of Stools and Urine for Product (1944), and Procedures for the Detection of Plutonium in Human 

Urine (1945) (Russell, 1945; Stone, 1944). NIOSH evaluated radiochemistry and sample preparation 

in the latter procedure and determined that it was sufficient for detecting plutonium. The earliest urine 

bioassay sample results obtained by NIOSH were reported in 1945 for plutonium (Monitoring, 

Feb-Jun1945). Approximately 150 plutonium sample results were reported in 1945. These results 

were not included in the bioassay database, but were instead located in documents in the ORNL 

Central Files (Monitoring, Feb-Jun1945). All other plutonium sample results were obtained from the 

bioassay sample database. The bioassay database lists only four plutonium urine bioassay results in 

1946, but no fewer than 188 for each of the following years, with a maximum of 868 in 1954. 

Starting in 1948, the monthly Radiation Survey and Monitoring Section reports included results from 

the Body Fluid Analysis Group (Hart, Apr1949; Hart, May1949). The results included the number of 

samples taken and the target radionuclides. The Body Fluid Analysis Group appeared to be a newlyformed group and indicated an expanding area of personnel monitoring. The bioassay database 

continued to show increasing numbers and an expanding list of target radionuclides. The first 
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uranium bioassay results for uranium reviewed by NIOSH are from 1949 (Monitoring, 1945-1990). 

There were 77 results that year and several hundred in the following years. Urine bioassay results for 

mixed fission products appear in the bioassay database starting in 1950 with results for cesium and 

strontium (Monitoring, 1945-1990). 

7.2.1.2 Fecal Bioassay Data 

Fecal bioassay results first appeared in the bioassay database in 1955 with results for thorium. The 

sampling frequency appeared to be regular, with over 1300 fecal sample results for thorium reported 

from 1955-59 (Monitoring, 1945-1990). Fecal analysis procedures were developed in the mid-1940s, 

but a program with regular results did not appear to emerge until the mid-1950s. The radiochemistry 

and sample preparation procedures that were previously developed for fecal analysis (Stone, 1944) 

were reviewed by NIOSH and determined to be sufficient for analyzing for thorium. These data were 

also previously reviewed by NIOSH in the development of fecal bioassay minimum detectable 

activity (MDA) values for the ORNL Occupational Internal Dose TBD (ORAUT-TKBS-0012-5). 

Based on the quantity of fecal bioassays and the sampling and analysis procedures, NIOSH believes 

the fecal bioassay data are sufficient for establishing a bounding dose estimate for thorium. Although 

NIOSH believes sufficient data are currently available for bounding internal radiation exposures 

during specified time periods, NIOSH is continuing to pursue additional data. NIOSH will continue 

to evaluate as additional fecal bioassay data become available and are compiled. 

7.2.1.3 Airborne Levels 

As described in Section 7.1, there is extensive air monitoring data from 1944-47 (Monitoring, 

Jun1944-Dec1947). Approximately 1500 air sample results were recorded, with approximately 1100 

from Building 706-A, which is where thorium and plutonium processing activities took place. As 

described in Section 7.1.1, the samples were determined to be breathing zone samples which were 

analyzed for gross alpha, and are sufficient for establishing a bounding dose estimate for potential 

thorium intakes for the years 1944-47. 

NIOSH performed extensive research in an effort to locate air sampling data after 1947 but was 

unsuccessful. A regularly-generated report titled Report for the Radiation Survey and Monitoring 

Section listed air sample totals over a given time period, usually one week. Reports located in 1948 

and 1949 routinely listed air sample totals of approximately 200-250 per month (Hart, Apr1949; Hart, 

May1949). Individual air sample results from which these totals were generated could not be located. 

Tables 7-1 and 7-2 below illustrate the air sample data available in the electronic database as well as 

the summary data in the report series, Report for the Radiation Survey and Monitoring Section. Table 

7-1 shows the number of air samples taken in various locations from 1944 through 1947. As stated 

previously, there were approximately 1500 air sample results recorded during this time period. Table 

7-2 tabulates the results from nine weekly reports from August 1948 through April 1949. There were 

a total of 534 air samples taken, averaging approximately 60 per week. At that rate, there were 

approximately 3000 air samples taken per year, which is significantly more than the 1500 taken from 

1944 through 1947 – evidence of an expanding air-sampling program. It is clear that air sampling 

continued at an increased rate after 1947; however, only summary totals could be found, not the actual 

sample results. 
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Table 7-1: ORNL Air Samples by Location (Electronic Database)

Building 1944 1945 1946 1947

100 96 31 4

101 1

102 2

105 41 3 1

115 2 1 2

204 19 7 1

205 72 22 1

706-A 655 415 21 18

706-C 1 15 1 15

706-D 30 1 6

Source: Electronic database

Table 7-2: No. of Air Samples from Nine Weekly Reports (Aug48 through Apr49)

Building

105 205 706-A 706-C 706-D

No. of Air Samples 41 53 137 54 249

Source: Weekly Report, Aug 28, 1948; Weekly Report, Sep 12, 1948; Weekly Report, Oct 

17, 1948; Weekly Report, Nov 14, 1948; Weekly Report, Nov 28, 1948; Weekly Report, 

Dec 12, 1948; Weekly Report, Jan 16, 1949; Weekly Report, Feb 6, 1949; Weekly Report, 

Mar 27, 1949 

7.2.2 Evaluation of Bounding Ambient Environmental Internal Doses 

Because NIOSH has determined that it is not possible to completely reconstruct internal radiation 

doses for the period from June 17, 1943 through July 31, 1955, it is not necessary to fully evaluate 

environment internal doses for the period under evaluation. Consistent with the findings presented in 

this Section 7.0, NIOSH will include environmental internal doses, as appropriate, during assignment 

of nuclide-specific partial internal dose estimates for periods when dose reconstruction is considered 

feasible. 

7.2.3 Methods for Bounding Internal Dose at ORNL (X-10) 

The principal sources for internal radiation doses relative to this evaluation are plutonium, uranium, 

thorium, and fission products. The evaluation of doses from accelerator- or cyclotron-produced 

radionuclides is reserved because such operations at both ORNL (X-10) and Y-12 will be addressed in 

a future combined evaluation effort. Although NIOSH has determined that it does not have sufficient 

data, including bioassay or air monitoring results, to estimate with sufficient accuracy total internal 
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exposures to all the principal sources of internal radiation during the period, NIOSH believes that 

internal dose estimates can be made for each of the principal sources of internal radiation exposures 

for various time periods between June 17, 1943 and July 31, 1955. 

Plutonium 

The ORNL graphite reactor achieved criticality in December 1943, and plutonium production and 

processing followed starting in 1944. NIOSH obtained a database of approximately 1500 air samples, 

as discussed earlier in Section 7 (Monitoring, Jun1944-Dec1947). This database contained air 

samples from 1944 through 1947. Approximately 1100 of these air samples were taken in Building 

706-A, where plutonium and thorium processing took place. These air samples were analyzed for 

gross alpha activity, and therefore, the results include alpha-emitting radionuclides present in the air 

for the specified location (e.g., plutonium or thorium). Bounding dose estimates for potential internal 

plutonium intakes can be made by using the gross alpha air sample results taken in areas where 

plutonium-processing activities took place. These results sufficiently estimate the plutonium 

concentrations in the air that could have been inhaled by workers in the area. Dose estimates from 

potential plutonium intakes based on air samples results can therefore be made from 1944 to 1947. 

In addition, plutonium bioassay results are available starting in 1945 (Monitoring, Feb-Jun1945). In 

that year, approximately 150 samples were analyzed. There were only four plutonium bioassay results 

for 1946, but 188 samples in 1947, increasing to a maximum of 868 samples in 1954, and leveling to 

several hundred samples in 1955. Based on the quantity of plutonium bioassay samples, and the 

protocols that were in place at the time, NIOSH believes these results are sufficient for providing 

SEC-period dose estimates from potential plutonium intakes from 1945 through 1955. 

Therefore, NIOSH believes that, based on the available air sample data and urine bioassay data, 

internal doses due to plutonium can be estimated with sufficient accuracy for the period from January 

1, 1944 through July 31, 1955 (all years of the period under evaluation). NIOSH will continue to 

evaluate as further air and plutonium bioassay data become available and are compiled. 

Uranium 

The first bioassay results located for uranium are during 1949. They were analyzed on site and were 

included in the ORNL bioassay database. There are 77 sample results reported for 1949, and 

approximately 3000 between 1950 and 1955 (Monitoring, 1945-1990). The large number of uranium 

bioassay samples is indicative of a developed program and provides sufficient data for making 

bounding dose estimates from potential uranium intakes from 1949 through 1955. 

NIOSH has determined that it does not have sufficient data, including bioassay or air monitoring 

results, to estimate internal uranium doses with sufficient accuracy during the period June 17, 1943 

through December 31, 1948 (the period prior to uranium-specific bioassay data). With the availability 

of uranium bioassay data starting in 1949, NIOSH believes that it has adequate monitoring data to 

allow for sufficiently accurate estimation of internal uranium doses for workers during the period from 

January 1, 1949 through July 31, 1955. 
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Thorium 

NIOSH obtained a database of approximately 1500 air samples, as discussed earlier in Section 7 

(Monitoring, Jun1944-Dec1947). This database contained air samples from 1944 through 1947. 

Approximately 1100 of these air samples were taken in Building 706-A, where plutonium and thorium 

processing took place. These air samples were analyzed for gross alpha activity, and therefore, the 

results include alpha-emitting radionuclides present in the air for the specified location (e.g., 

plutonium or thorium). Bounding dose estimates for potential internal doses from thorium intakes can 

be made by using the gross alpha air samples results taken in areas where thorium processing 

activities took place. These results would sufficiently estimate the thorium concentrations in the air 

that could have been inhaled by workers in the area. Bounding dose estimates from potential thorium 

intakes based on the air samples results can therefore be made from 1944 to 1947. 

The first bioassay results for thorium are 51 fecal bioassay results starting in August 1955 

(Monitoring, 1945-1990). The thorium fecal bioassay program continued to expand in the following 

years with 103 results in 1956, 125 in 1957, and 770 in 1959. The thorium fecal bioassay program 

coincides with the rapidly developing thorium operations at ORNL (described in Section 5). The 

large number of thorium bioassay samples is indicative of a developed program and provides enough 

data for making bounding dose estimates from potential thorium intakes starting in August 1955. 

With the availability of air monitoring data through 1947, NIOSH believes that it has adequate 

monitoring data to allow for sufficiently accurate estimation of internal thorium doses for workers 

during the period from January 1, 1944 through December 31, 1947. NIOSH will continue to evaluate 

as further air data become available and are compiled. During the period 1948 through July 1955, 

NIOSH has no available thorium-related air or bioassay data until thorium-specific fecal sample 

results become available in August 1955. NIOSH has determined that it does not have sufficient data, 

including bioassay or air monitoring results, to estimate internal thorium doses with sufficient 

accuracy during the period from January 1, 1948 through July 31, 1955. 

Fission Products 

Bioassay results for fission products appeared in the ORNL bioassay database starting in 1950, with 

results for cesium and strontium (Monitoring, 1945-1990). There were 47 sample results reported in 

1950, 360 in 1951, and over 700 for each of the following years through 1955. The large number of 

fission product bioassay samples is indicative of a developed program and provides enough data for 

making bounding dose estimates from potential fission product intakes from 1950 through 1955. 

NIOSH has determined that it does not have sufficient data, including bioassay or air monitoring 

results, to estimate internal fission product doses with sufficient accuracy during the period January 1, 

1944 through December 31, 1949 (the period prior to cesium and strontium bioassay data). With the 

availability of cesium and strontium bioassay data starting in 1950, NIOSH finds that it has adequate 

monitoring data to allow for sufficiently accurate estimation of internal fission product doses for 

workers during the period from January 1, 1950 through July 31, 1955. 
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7.2.4 Internal Dose Reconstruction Feasibility Conclusion 

The evaluation concludes that it is not feasible for NIOSH to reconstruct with sufficient accuracy the 

internal doses at ORNL (X-10) from: 

uranium exposures during the period June 17, 1943 through December 31, 1948; 

thorium exposures during the period from January 1, 1948 through July 31, 1955; and 

fission product exposures during the period from January 1, 1944 through December 31, 1949.

Combining the periods above yields a summative time period for dose reconstruction infeasibilities of 

June 17, 1943 through July 31, 1955. Therefore, the NIOSH-recommended SEC class includes the 

period from June 17, 1943 through July 31, 1955. 

NIOSH believes that internal doses due to plutonium can be estimated with sufficient accuracy for the 

entire period from January 1, 1944 through July 31, 1955. NIOSH also believes that for some periods 

of time between June 17, 1943 and July 31, 1955, it is feasible to reconstruct doses for each of the 

other principal sources for internal radiation doses. However, there are no time periods between June 

17, 1943 and July 31, 1955 when total internal doses can be reconstructed for all principal sources of 

internal radiation dose. NIOSH will continue to evaluate as further data become available and are 

compiled. 

Although NIOSH found that it is not possible to completely reconstruct internal radiation doses for the 

period from June 17, 1943 through July 31, 1955, NIOSH intends to use any internal monitoring data 

that may become available for an individual claim (and that can be interpreted using existing NIOSH 

dose reconstruction processes or procedures). Dose reconstructions for individuals employed at 

ORNL (X-10) during the period from June 17, 1943 through July 31, 1955, but who do not qualify for 

inclusion in the SEC, may be performed using these data as appropriate. 

Table 7-3 shows the available internal monitoring data by internal exposure sources and year.

Table 7-3: Available ORNL (X-10) Internal Monitoring Data

Internal Sources

Year

1943 1944 1945 1946 1947 1948 1949 1950 1951 1952 1953 1954 1955

Plutonium Air Bio Air Bioassay

Uranium No Data (Infeasible) Bioassay

Thorium Air Data No Data (Infeasible) Bio

Fission Products No Data (Infeasible) Bioassay

Reactor/Cyclotron/Accelerator Reserved for a joint ORNL (X-10) and Y-12 evaluation
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7.3 Evaluation of Bounding External Radiation Doses at ORNL 

The principal source of external radiation doses for members of the evaluated class was a combination 

of direct exposure from reactors and from various fission products and production nuclides. See 

Section 5.0 for a discussion of the radionuclides that are known to have been present. 

The following subsections address the ability to bound external doses, methods for bounding doses, 

and the feasibility of external dose reconstruction. 

7.3.1 Evaluation of Bounding Process-Related External Doses

The section summarizes the extent and limitations of information available for reconstructing the 

process-related external doses of members of the class under evaluation. Primary documentation and 

summary reports are available for both photon and beta exposure for individual workers (see Section 

6.2 for references). In addition, NIOSH has almost 46,000 photon results and the same number of 

beta results for more than 9,000 individuals. In addition, NIOSH has previously completed a coworker study for ORNL, ORAUT-OTIB-0021, External Coworker Dosimetry Data for the X-10 Site.

Photon 

The external dosimetry data are sufficient to perform SEC-period dose reconstructions for photon 

exposures from all external gamma and X-ray sources present at ORNL for all workers in the class 

under evaluation. Specific data are available for many individuals. For any worker whose exposure 

results are not in NIOSH’s possession and cannot be obtained from DOE, the factors from the ORNL 

co-worker study (ORAUT-OTIB-0021) may be used. 

Beta 

The external dosimetry data are sufficient to perform SEC-period dose reconstructions for beta 

exposures from all external beta sources present at ORNL for all workers in the class under 

evaluation. Specific data are available for many individuals. For any worker whose exposure results 

are not in NIOSH’s possession and cannot be obtained from the DOE, the factors from the ORNL coworker study (ORAUT-OTIB-0021) may be used. 

Neutron 

Neutron exposures occurred from a variety of sources in distinct locations. Each circumstance will be 

described separately with a proposed bounding method. NIOSH believes that the data are sufficient to 

reconstruct SEC-period estimates of neutron exposures for the all members of the class under 

evaluation. 
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For the cases of potential neutron exposure, NIOSH will develop a ratio of neutron-to-photon 

exposure. It is known that some, if not all, results reported by ORNL may include ORNL-assigned 

neutron exposure. NIOSH’S N:P ratio method will be claimant-favorable for such ORNL data 

because it will overestimate neutron exposure in those cases in which an employee was assigned 

neutron exposure, and also in the case when an employee did not actually receive neutron exposure 

but only worked in the vicinity of a neutron source. 

Graphite Reactor 

Neutron and gamma surveys were performed early during the reactor’s operation around the locations 

of likely worker exposure (Progress Report, Jan-Jul1946). These results have been used to develop a 

neutron-to-photon ratio of 0.1. This ratio may be applied to the photon exposure results for 

employees. This is a conservative estimate because, during the history of the reactor, it is expected 

that gamma levels would have increased due to activation effects while, with the reactor aging, the 

neutron levels would not have increased, thus overestimating neutron exposure for later years. Note 

that the Graphite Reactor was the only reactor operating at ORNL prior to 1951. 

Low Intensity Test Reactor (LITR) 

The LITR was created as a full-scale mockup of the Materials Test Reactor (MTR). Although there 

are differences between the shielding of the two reactors, similarities (e.g., size, overall design, and 

fuel type) lead NIOSH to believe that an N:P ratio that has been developed for the MTR may be 

applied to the LITR for dose reconstruction of the neutron component. 

In a memo discussing a proposed increase in the operating power level of the LITR, a comparison is 

made between the LITR and the MTR: 

A comparison of the LITR with the MTR shows that only minor differences exist as far as safety is 

concerned. Major differences exist in the materials of construction, water system and shielding, 

but it is believed that these do not appreciably decrease the safety of the LITR. (Larson, 1953, pdf 

p. 4) 

Of the factors mentioned, the most significant issue related to the possible use of MTR data for LITR 

workers is the difference in shielding. The memo goes on to describe the difference between the two 

shields: 

The shield of' the LITR is composed mostly of unmortared concrete blocks with only the outer 

one-foot being mortared. While this is not as efficient as the MTR shield in that more thickness is 

required (because ordinary concrete instead of high density barytes concrete was used), it is 

satisfactory and appears to be generally sufficient for 3000 KW operation. (Larson, 1953, pdf p. 

5) 

The greatest difference appears to be the thicknesses needed to provide similar worker exposure 

levels. 
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In the technical basis document, Idaho National Laboratory and Argonne National Laboratory-West – 

Occupational External Dosimetry, an N:P ratio is developed based on the measured thermal and fast 

neutron dose equivalent rates and gamma dose rates at the MTR test floor (ORAUT-TKBS-0007-6). 

The calculated value is 0.58 + 0.48. Note that this document indicates that this value will 

overestimate exposure due to the likelihood of many employees receiving gamma exposure while not 

in the vicinity of the reactor. 

Bulk Shielding Reactor (BSR) 

The Bulk Shielding Reactor (BSR) was a swimming pool reactor with a pool that was 20 feet deep 

with the top of the reactor 16 feet below the surface. Measurements made within the BSR pool 

showed that the fast neutron flux decreased by six orders of magnitude within a distance of 120 cm of 

water (about 4 feet) (Eggen, 1960). The potential neutron flux at the surface (16 feet above the 

reactor) would be unmeasurable or zero. Typically, experiments were lowered into the pool to place 

them in the vicinity of the reactor. There were no beam holes or other significant pathways in the 

BSR design, so there would effectively be no neutron exposures to workers as a result of BSR 

operations. 

However, it is important to note that one experiment has been located during which the water level 

was lowered to a minimum of 30 centimeters over the reactor (Hungerford, 1954). There is nothing in 

the documentation of this experiment indicating that any personnel were in the vicinity of the water’s 

surface. However, many paired photon and neutron data were collected as part of the experiment. 

These data can be used should the need arise to develop an N:P ratio for such exposure. For all other 

cases, a value of zero is appropriate for neutron exposure from the Bulk Shielding Reactor.

Homogeneous Reactor Experiment (HRE) 

Although information exists on the power levels and shielding used, no survey data or neutron spectra 

have been located for the HRE or its successor, the Homogeneous Reactor Test (HRT). Due to the 

unique design of a homogenous reactor, it is not appropriate to use information gathered from other 

reactors to estimate neutron exposure data directly. For example, shielding was required for the fuel 

loop to account for the production of delayed neutrons after the fuel had left the central core. 

However, NIOSH has found that claimant data reported by ORNL for persons known to have worked 

at the HRE includes original NTA badge track results with data labels “OW” and “S”. 

The film badge in use during the operation of the HRE had an open window, an area shielded by 

cadmium, and several other shielding components. For personnel with a potential for neutron 

exposure, these badges contained both a film for photon and beta exposure, and a separate NTA film 

behind that (Thornton, 1961). The open window area allowed the full spectrum of neutrons (fast plus 

thermal) to impact the NTA film. Fast neutrons produced a visible track due to the scattering of a 

recoil proton resulting from the neutron impacting a hydrogen nucleus. 
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Thermal neutrons captured by nitrogen in the film created a track from the 584 KeV proton produced 

by the N14 (n,p) C14 reaction (Cheka, unspecified). This track is equivalent to one created by a recoil 

proton from a collision with a neutron with energy of greater than 1 MeV. The cadmium filter 

absorbed thermal neutrons and allowed the fast neutrons to pass through to the film. The net 

difference between the number of tracks under the shielded area and the number of tracks in the open 

window area provide the number of tracks created by thermal neutrons. Note that although NTA film 

has a well-established threshold for the measurement of proton recoil tracks from neutrons with 

energies below 0.5 MeV, this technique bypasses that limitation. 

NTA films were developed for potentially-exposed personnel, and the number of tracks per field of 

view for each area (shielded and open window) were recorded. These track data are available to 

NIOSH from the individual claimant requests that have been made to date. It is expected that further 

employee NTA results may be obtained from ORNL following identification of individuals who 

worked at the HRE. 

NIOSH believes that these data, combined with claimant gamma exposure data, may be used to 

develop an N:P ratio for worker neutron exposure at the HRE. 

Aircraft Reactor Experiment (ARE) 

The ARE was operational for a very short time in 1954. During November 3-8, during the “Low 

Power Run,” the ARE was brought to a maximum of 20 kilowatts; during November 8-12, during the 

“High Power Run,” it was brought to 2.5 megawatts. Operations were terminated after November 12 

(Cottrell, 1955). The reactor was shielded laterally by six feet of concrete. During the High Power 

Run, three layers of 2.5 feet thick concrete blocks were added over the reactor. 

During the Low Power Run, measurements were made in the reactor pit of the gamma, fast neutron, 

and thermal neutron levels when the reactor was at 2.7 watts. Readings were taken at the top center of 

the reactor and at the side at the mid-plane. These data may be used to develop a neutron-to-photon 

ratio that takes into account the concrete shielding between the reactor and the control room. 

Tower Shielding Reactor (TSR) 

No neutron data have been located for the TSR. However, paired neutron and photon data along with 

a neutron spectrum were measured for the second Tower Shielding Reactor, TSR-II. The TSR-II may 

be considered as an analog for the TSR because it used the same type of fuel plates and was a redesign 

of the TSR-I in a spherical shape (Rosenthal, 2009, pdf p. 64). The TSR-II was used in, and operated 

from, the same locations as the TSR-I and was operated under the same procedures (Hart, 1959). 

It was confirmed during an employee interview that no personnel were allowed within the fence or 

outside of the underground control facility during any reactor operations (Personal Communication, 

2012c). 
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In A Study of the Radiation Shielding Characteristics of Basic Concrete Structures at the Tower 

Shielding Facility, measurements of gamma, fast neutron, and thermal neutron levels were made for 

various thicknesses of concrete ranging from none to 20 inches thick. These measurements were 

made in two bunkers located approximately 700 feet from the reactor (Cain, 1964). Spectral 

information for the TSR-II may be found in Absolute Neutron Spectrum for the TSR-II (Maerker, 

1972) and in Low Energy Neutron Spectrum for TSR-II (Freestone, 1970). These data may be used to 

estimate an N:P ratio for employee exposure for personnel present in the underground control facility 

during TSR-I operation. 

Although the design for the TSR-II eventually allowed operation at 1 MW, it operated at 100 kW 

through 1970. The above measurements were made prior to 1964. The TSR-I operated initially at 

100 kW but was soon increased to 500kW (Rosenthal, 2009, pdf pp. 63, 64). Due to the 

proportionality of the production of neutrons and photons, the similar spectra expected from the use of 

the same fuel, and the use of the same facility (including the worker shielding), it is expected that the 

differences in power levels would not cause a significant difference in the neutron-to-photon ratios 

expected from the two reactors. 

Critical Reactor Experiments 

These experiments were operated at very low power levels, from zero to tenths of watts. They were 

performed for very short time periods at or near criticality for a maximum of 20 minutes. They were 

operated from behind a two-foot thick concrete wall with a water window of the same thickness. The 

shielding was designed as a precaution against criticality events. There were no criticality accidents. 

Neutron levels within and near the assemblies were monitored closely during each step of the 

experiments. 

The neutron exposure levels to employees would have been zero or unmeasurable. A value of zero 

neutron exposure is appropriate for work with the Critical Experiments. 

Neutron (α-n) Sources 

From 1989 through 1991, Pacific Northwest Laboratory performed measurements to characterize the 

response of the CEDS neutron TLDs to various workplace neutron spectra at ORNL and Y-12. The 

measurements consisted of characterization of workplace neutron fields using tissue-equivalent 

proportional counters, Bonner spheres, He3detectors, and other instruments (Battelle, Vol. 1; Battelle, 

Vol. 2; Battelle, Vol. 3; Battelle, Vol. 4).

These data, along with 2,694 dosimetry records with reported neutron exposures, have been analyzed 

for a variety of source locations and types. In ORAUT-TKBS-0012-6, there are N:P ratios based on 

both worker location and source type, including manufactured alpha-neutron sources. 

As the spectrum of these sources should be constant regardless of time period, it is appropriate to use 

these ratios for earlier workers. 
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7.3.2 Evaluation of Bounding Ambient Environmental External Doses 

For workers who were monitored with film badges and pocket dosimeters, any ambient environmental 

exposures would have been accumulated along with the occupational exposures. 

The Occupational Environmental Dose TBD applies to workers who were not monitored for external 

or internal radiation exposure (ORAUT-TKBS-0012-4). Environmental dose is that which workers 

could have received while being outdoors on the ORNL site from inhalation of radioactive materials 

in the air, direct radiation from airborne releases, or direct radiation in the vicinity of process buildings 

and waste-handling areas. ORAUT-TKBS-0012-4 provides a table of annual average airborne 

concentration and intake data for I-131, tritium, and particulate mixed fission products. The 

concentration data are derived from a combination of conservative assumptions of airborne releases 

and dispersion and onsite air-monitoring data. NIOSH considers this information sufficient to allow 

bounding of ambient environmental external dose for all members of the class who were not 

monitored with external radiation dosimetry. 

7.3.3 ORNL Occupational X-Ray Examinations 

Prior to October 3, 1947, occupational medical X-rays were performed at Oak Ridge Hospital (an 

EEOICPA-covered site located on what was then the Clinton Engineering Works site) (ORNL, post2002). Starting October 3, 1947, occupational X-rays were performed on the ORNL site. Therefore, 

NIOSH has determined that it is applicable and feasible to reconstruct occupational medical X-ray 

exposures for ORNL (X-10) workers during period from June 17, 1943 through July 31, 1955. 

7.3.4 Methods for Bounding External Dose at ORNL 

There is an established protocol for assessing external exposure when performing dose reconstructions 

(these protocol steps are discussed in the following subsections): 

Photon Dose 

Beta Dose 

Neutron Dose 

Medical X-ray Dose (as applicable per Section 7.3.3) 

7.3.4.1 Methods for Bounding Operational Period External Dose

Photon Dose 

NIOSH has determined that external photon dose may be reconstructed. 

The primary method is the use of individual records. Film badge frequencies and thresholds are 

known and documented. Missed dose may be applied using this information. Standard methods may 

be applied for missing data, and for employees with no exposure results, the ORNL co-worker study 

(ORAUT-OTIB-0021) may be used. For unmonitored radiation workers routinely exposed (i.e., those 

who were expected to have been monitored), a conservative estimate of their probable exposure may 

be based on the 95th percentile of all photon exposure results for that year. For unmonitored radiation 
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workers likely exposed to intermittent low levels of external radiation, the 50th percentile of all photon 

exposure results for that year provides a conservative estimate of their probable exposure. For 

unmonitored employees who were unlikely to have been exposed, the ambient environmental 

exposure may be assigned. 

Beta Dose 

NIOSH has determined that external beta dose may be reconstructed. 

The primary method is the use of individual records. Film badge frequencies and thresholds are 

known and documented. Missed dose may be applied using this information. Standard methods may 

be applied for missing data, and for employees with no exposure results, the ORNL co-worker study 

(ORAUT-OTIB-0021) may be used. For unmonitored radiation workers routinely exposed (i.e., those 

who were expected to have been monitored), a conservative estimate of their probable exposure may 

be based on the 95th percentile of all beta exposure results for that year. For unmonitored radiation 

workers likely exposed to intermittent low levels of external radiation, the 50th percentile of all beta 

exposure results for that year provides a conservative estimate of their probable exposure. For 

unmonitored employees who were unlikely to have been exposed, the ambient environmental 

exposure may be assigned. 

Neutron Dose 

NIOSH has determined that for each of the areas of neutron exposure, an N:P ratio exists or may be 

created. 

Using the appropriate N:P ratio against the gamma exposure data will allow for a conservative 

bounding estimate of an employee’s likely neutron exposure. This method will be claimant-favorable 

because in the absence of individually applicable data, it will assign neutron exposures to employees 

who may have simply worked in those areas without actually being exposed to neutrons. The method 

will also be claimant-favorable in those cases in which neutron exposures were calculated by the 

ORNL site and added to the gamma results; for such employees, their neutron exposure will be 

overestimated. Note that the great majority of neutron exposure results reviewed in the original 

documents, although not complete for the time period, have values of zero. The levels of neutron 

exposures for most locations are expected to have been low due to the nature of the experimental 

activities. The risk of vastly overestimating neutron exposure using the N:P ratio is believed to be 

small.

Medical X-ray Dose 

The Occupational Medical Dose TBD (ORAUT-TKBS-0012-3) provides information on doses 

workers received from X-rays that were required as a condition of employment. These X-rays were 

included in pre-employment screenings, annual physical exams, and termination exams. These X-ray 

exams were initially performed at the hospital in Oak Ridge, where photofluorographic techniques 

appear to have been used. ORNL took over with its own X-ray equipment on October 3, 1947 and 

those examinations were conventional exposures. In 1959, Oak Ridge Hospital became what is now 

known as Methodist Medical Center of Oak Ridge. Oak Ridge Hospital is EEOICPA-covered from 

1943 to 1959. The current ORNL Medical Department provided a description of radiographic 
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procedures that have been used to conduct X-ray examinations for workers at the ORNL site (ORNL, 

post-2002, Table 3-2). This information indicates that from October 3, 1947 to the present, all 

medical X-rays for screening conducted onsite in the ORNL Medical area used conventional, 

radiographic (non-PFG) equipment. 

7.3.4.2 Methods for Bounding Ambient Environmental External Doses 

Workers who were monitored for external exposure would have been assigned results from methods 

that incidentally included any ambient environmental exposure. That is, radiation workers wore 

dosimetry while on site regardless of location. This is confirmed in reviewed documentation and 

through employee interviews. 

The methods proposed in the ORNL Occupational Environmental Dose TBD are adequate to bound 

ambient environmental external doses for those who may have not been monitored for external 

exposure (ORAUT-TKBS-0012-4). The TBD addresses the primary contributions to environmental 

exposures, the release points, the stack emissions, and their contribution to the average annual 

concentrations. The TBD makes conservative assumptions to assign exposures based on immersion at 

those concentrations. 

7.3.5 External Dose Reconstruction Feasibility Conclusion 

External dose for photon and beta exposure may be reconstructed for all members of the class under 

evaluation. External dose for neutron exposure may be reconstructed for all members of the class 

under evaluation. 

7.4 Evaluation of Petition Basis for SEC-00189 

The following subsections evaluate the assertions made on behalf of petition SEC-00189 for the Oak 

Ridge National Laboratory. 

7.4.1 ORAUT-TKBS-012-5 

SEC-00189: The X-10 technical basis document ORAUT-TKBS-0012-5, Oak Ridge National 

Laboratory Occupational Internal Dose, conducted by NIOSH/ORAU, states that internal monitoring 

records are limited or do not exist for most radionuclides during this timeframe because internal 

monitoring as a form of personnel monitoring was just starting to be developed in the mid to late 

1940’s. As such, the applicability for use of this TBD starts in 1947. 

In the course of this evaluation, NIOSH determined that internal monitoring was limited until the late 

1940s. Therefore, limited monitoring data exist for some of the primary sources of internal radiation 

exposure. The bioassay data used to develop the ORNL Occupational Internal Dose TBD included 

urinalysis results starting in 1947 (only four results were from 1946) (ORAUT-TKBS-0012-5). The 

TBD provides a methodology for estimating internal doses only for radionuclides where bioassay data 

are available. As described in this evaluation, NIOSH is recommending the period from June 17, 

1943 through July 31, 1955 for inclusion in the SEC. 
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7.4.2 ORAUT-OTIB-0034 

SEC-00189: The technical information bulletin, ORAUT-OTIB-0034, Internal Dosimetry Coworker 

Data for X-10, conducted by NIOSH/ORAU, is only applicable starting in 1951. It cites a lack of 

internal dosimetry data prior to 1951. 

Prior to 1951, there are bioassay data for plutonium, uranium, cesium, and strontium. However, 

starting in 1951, the ORNL bioassay program expanded to cover many other radionuclides. The 

applicability starting in 1951 is based on this more comprehensive bioassay program. As described in 

this evaluation, NIOSH is recommending the period from June 17, 1943 through July 31, 1955 for 

inclusion in the SEC. 

7.4.3 ORAUT-OTIB-0018 

SEC-00189: The technical information bulletin, ORAUT-OTIB-0018, Internal Dose Overestimates for 

Facilities with Air Monitoring Programs, conducted by NIOSH/ORAU, is only applicable starting in 

1953. 

The assertion that ORAUT-OTIB-0018, Internal Dose Overestimates for Facilities with Air 

Monitoring Programs, is only applicable in 1953 reflects the difficulties with estimating internal 

doses before 1953. As described in this evaluation, NIOSH is recommending the period from June 

17, 1943 through July 31, 1955 for inclusion in the SEC. 
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7.5 Summary of Feasibility Findings for Petition SEC-00189 

This report evaluates the feasibility for completing dose reconstructions for employees at the Oak 

Ridge National Laboratory (X-10) from January 1943 through July 1955. NIOSH found that the 

available monitoring records, process descriptions and source term data available are not sufficient to 

complete sufficiently accurate dose reconstructions for the evaluated class of employees. 

NOTE: The start date for the NIOSH-proposed class to be added to the SEC was changed from 

January 1, 1943 to June 17, 1943 because NIOSH obtained documentation showing that construction 

at the site did not start (i.e., ground-breaking) until February 1943, and the first uranium slug shipment 

left Aluminum Company of America for the site on June 17, 1943 (Alcoa, 1944). Thus, ORNL first 

had radioactive materials on site sometime after June 17, 1943. 

Table 7-4 summarizes the results of the feasibility findings at ORNL (X-10) for each exposure source 

during the time period January 1943 through July 1955. 

Table 7-4: Summary of Feasibility Findings for SEC-00189

January 1, 1943 through July 31, 1955

Source of Exposure Reconstruction Feasible Reconstruction Not Feasible

Internal X

- Pu X

(Jan 1, 1944 through Jul 31, 1955)

- U X

(Jan 1, 1949 through Jul 31, 1955)

X

(Jun 17, 1943 through Dec 31, 1948)

- Th X

(Jan 1, 1944 through Dec 31, 1947)

X

(Jan 1, 1948 through July 31, 1955)

- Fission Products X

(Jan 1, 1950 through Jul 31, 1955)

X

(Jan 1, 1944 through Dec 31, 1949)

- Reactor-, Cyclotron-, or 

 Accelerator-produced 

 Radionuclides

Reserved for a joint ORNL (X-10)

and Y-12 evaluation

Reserved for a joint ORNL (X-10)

and Y-12 evaluation

External X

(Jun 17, 1943 through Jul 31, 1955)

- Gamma X

- Beta X

- Neutron X

- Occupational Medical X-ray X

As of July 10, 2012, a total of 1302 claims have been submitted to NIOSH for individuals who 

worked at ORNL during the period under evaluation in this report. Dose reconstructions have been 

completed for 1074 individuals (~82%). 
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Although NIOSH found that it is not possible to completely reconstruct radiation doses for the 

proposed class, NIOSH intends to use any internal and external monitoring data that may become 

available for an individual claim (and that can be interpreted using existing NIOSH dose 

reconstruction processes or procedures). Therefore, dose reconstructions for individuals employed at 

ORNL during the period from June 17, 1943 through July 31, 1955, but who do not qualify for 

inclusion in the SEC, may be performed using these data as appropriate. 

8.0 Evaluation of Health Endangerment for Petition SEC-00189

The health endangerment determination for the class of employees covered by this evaluation report is 

governed by both EEOICPA and 42 C.F.R. § 83.13(c)(3). Under these requirements, if it is not 

feasible to estimate with sufficient accuracy radiation doses for members of the class, NIOSH must 

also determine that there is a reasonable likelihood that such radiation doses may have endangered the 

health of members of the class. Section 83.13 requires NIOSH to assume that any duration of 

unprotected exposure may have endangered the health of members of a class when it has been 

established that the class may have been exposed to radiation during a discrete incident likely to have 

involved levels of exposure similarly high to those occurring during nuclear criticality incidents. If 

the occurrence of such an exceptionally high-level exposure has not been established, then NIOSH is 

required to specify that health was endangered for those workers who were employed for a number of 

work days aggregating at least 250 work days within the parameters established for the class or in 

combination with work days within the parameters established for one or more other classes of 

employees in the SEC. 

This evaluation concluded that for some periods of time between June 17, 1943 and July 31, 1955, it 

is feasible to reconstruct doses for each of the principal sources for internal radiation doses. However, 

there are no time periods between June 17, 1943 and July 31, 1955 when doses can be reconstructed 

for all principal sources of internal radiation dose. NIOSH’s evaluation determined that it is not 

feasible to estimate radiation dose for members of the NIOSH-evaluated class with sufficient accuracy 

based on the sum of information available from available resources. Therefore, the resulting NIOSHproposed SEC class must include a minimum required employment period as a basis for specifying 

that health was endangered. 

9.0 Class Conclusion for Petition SEC-00189 

Based on its full research of the class under evaluation, NIOSH has defined a single class of 

employees for which NIOSH cannot estimate radiation doses with sufficient accuracy. The NIOSHproposed class to be added to the SEC includes all employees of the Department of Energy, its 

predecessor agencies, and their contractors and subcontractors who worked in any area at the Oak 

Ridge National Laboratory (X-10) in Oak Ridge, Tennessee, from June 17, 1943 through July 31, 

1955, for a number of work days aggregating at least 250 work days, occurring either solely under this 

employment, or in combination with work days within the parameters established for one or more 

other classes of employees in the Special Exposure Cohort. 
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NIOSH has carefully reviewed all material sent in by the petitioner, including the specific assertions 

stated in the petition, and has responded herein (see Section 7.4). NIOSH has also reviewed available 

technical resources and many other references, including the Site Research Database (SRDB), for 

information relevant to SEC-00189. In addition, NIOSH reviewed its NOCTS dose reconstruction 

database to identify EEOICPA-related dose reconstructions that might provide information relevant to 

the petition evaluation. 

These actions are based on existing, approved NIOSH processes used in dose reconstruction for 

claims under EEOICPA. NIOSH’s guiding principle in conducting these dose reconstructions is to 

ensure that the assumptions used are fair, consistent, and well-grounded in the best available science. 

Simultaneously, uncertainties in the science and data must be handled to the advantage, rather than to 

the detriment, of the petitioners. When adequate personal dose monitoring information is not 

available, or is very limited, NIOSH may use the highest reasonably possible radiation dose, based on 

reliable science, documented experience, and relevant data to determine the feasibility of 

reconstructing the dose of an SEC petition class. NIOSH contends that it has complied with these 

standards of performance in determining the feasibility or infeasibility of reconstructing dose for the 

class under evaluation. 
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10.0 References 

42 C.F.R. pt. 81, Guidelines for Determining the Probability of Causation Under the Energy 

Employees Occupational Illness Compensation Program Act of 2000; Final Rule, Federal 

Register/Vol. 67, No. 85/Thursday, p. 22,296; May 2, 2002; SRDB Ref ID: 19391 

42 C.F.R. pt. 82, Methods for Radiation Dose Reconstruction Under the Energy Employees 

Occupational Illness Compensation Program Act of 2000; Final Rule; May 2, 2002; SRDB Ref ID: 

19392 

42 C.F.R. pt. 83, Procedures for Designating Classes of Employees as Members of the Special 

Exposure Cohort Under the Energy Employees Occupational Illness Compensation Program Act of 

2000; Final Rule; May 28, 2004; SRDB Ref ID: 22001 

42 U.S.C. §§ 7384-7385 [EEOICPA], Energy Employees Occupational Illness Compensation 

Program Act of 2000, as amended 

AEC, 1960, Annual Report to Congress of the Atomic Energy Commission for 1959, U.S. Atomic 

Energy Commission; January 30, 1960; SRDB Ref ID: 40450 

Ahmed, 1989, Regarding Historical Dosimetry Documentation, correspondence to Jack Fix; Abu B. 

Ahmed; April 21, 1989: SRDB Ref ID: 109936 

Air Contamination, Nov1944, Product Contamination of the Air in Bldg. 706A, 10-30-44 – 11-4-44, 

memo from G. Koval to K. Z. Morgan; Rocky Flats Plant; November 8, 1944; SRDB Ref ID: 99204 

Air Contamination, Jan1945, Product Contamination of the Air in Bldg. 706A, Report of 1-15-45 – 1-

20-45, memo from G. Koval to K. Z. Morgan; Rocky Flats Plant; January 25, 1945; SRDB Ref ID: 

115034 

Alcoa, 1944, Accounts of T-Metal at Aluminum Company of America Processed for Clinton Engineer 

Works, Aluminum Company of America; November 20, 1944; SRDB Ref ID: 45916 

Auerbach, unspecified, A History of the Environmental Sciences Division of Oak Ridge National 

Laboratory, ORNL/M-2732; Stanley I. Auerbach, Oak Ridge National Laboratory (ORNL); date not 

specified; SRDB Ref ID: 32219 

Ball, 1971, The Electronuclear Division: A Backward Look; James Ball; Fall 1971; SRDB Ref ID: 

42092 

Battelle, Vol. 1, Dosimeter Response Characterization for Personnel Neutron Dosimetry, Volume 1 

Summary, Correspondence, and Reports; Battelle; unspecified date; SRDB Ref ID: 11927 

Battelle, Vol. 2, Dosimeter Response Characterization for Personnel Neutron Dosimetry, Volume 2 

Measurement Data; Battelle; unspecified date; SRDB Ref ID: 11938 
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Battelle, Vol. 3, Dosimeter Response Characterization for Personnel Neutron Dosimetry, Volume 3 

Dosimeter Processing Data; Battelle; unspecified date; SRDB Ref ID: 11966 

Battelle, Vol. 4, Dosimeter Response Characterization for Personnel Neutron Dosimetry, Volume 4 

Neutron Group Correction Factors; Battelle; unspecified date; SRDB Ref ID: 11976 

Bell, 1954, A 2800 Degrees Celsius Calutron Ion Source Unit and its Use in Separating the Isotopes 

of Pd, Pt, Ru, and Ir, ORNL 1767; W. A. Bell Jr., L. O. Love, and C. E. Normand; July 30, 1954; 

SRDB Ref ID: 103204 

Booth, 1946, Separation and Purification of U-233 from Solutions Containing Thorium Nitrate by 

Continuous Countercurrent Extraction in a Packed Column; C. F. Booth; September 15, 1946; SRDB 

Ref ID: 102206 

Bradley, 1945, Personnel Monitoring of Fast Neutron Exposure, correspondence to K. Z. Morgan; J. 

E. Bradley; SRDB Ref ID: 13813 

Brooksbank, 1994, Historical and Programmatic Overview of Building 3019, ORNL/TM-12720; R. 

E. Brooksbank, Sr., B. D. Patton, and A. M. Krichinsky; August 1994; SRDB Ref ID: 22706 

Cain, 1964, A Study of the Radiation Shielding Characteristics of Basic Concrete Structures at the 

Tower Shielding Facility, ORNL-3464; V. R. Cain; January 30, 1964; SRDB Ref ID: 115591 

Campbell, 1956, Decontamination of the Homogeneous Reactor Experiment, ORNL-1839; D. O. 

Campbell; May 22, 1956; SRDB Ref ID: 104060 

Cheka, unspecified, Neutron Monitoring by Means of “Special Fine Grain Alpha Emulstion Film”; J. 

S. Cheka; unspecified date; SRDB Ref ID: 50019 

ChemRisk, 1993, Oak Ridge Health Studies Phase I Report, Volume 2: Part A, Dose Reconstruction 

Feasibility Study, DOE/OR/21981-T3-Vol.2; ChemRisk; September 1993; SRDB Ref ID: 13188 

ChemRisk, 1999, Iodine-131 Releases from Radioactive Lanthanum Processing at the X-10 Site in 

Oak Ridge, Tennessee (1944-1956)-An Assessment of Quantities Released, Off-Site Radiation Doses, 

and Potential Excess Risks of Thyroid Cancer, Oak Ridge Health Studies Oak Ridge Dose 

Reconstruction Task 1 Report; ChemRisk; July 1999; SRDB Ref ID: 13218 

Clark, 1944, Survey of Separation Processes-Third Progress Report on Problem No. 285-ML-55-4, 

CN-2519; R. E. Clark; August 1, 1944; SRDB Ref ID: 98218 

Clifford, 1951, Neutron Exposures, correspondence to M. E. Ramsey; C. E. Clifford and R. L. Clark; 

April 27, 1951; SRDB Ref ID: 109802 

Cottrell, 1955, Operation of the Aircraft Reactor Experiment, ORNL-1845(Del.); W. B. Cottrell, H. E. 

Hungerford, J. K. Leslie, and J. L. Meem; September 6, 1955; SRDB Ref ID: 97566 
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Davis 1954a, Applied Health Physics Radiation Survey Instrumentation; D. M. Davis, E. D. Gupton, 

and J. C. Hart; January 1, 1954; SRDB Ref ID: 860 

Davis, 1954b, Review of Urinalysis Program, correspondence to J. C. Hart; D. M. Davis and A. D. 

Warden; November 3, 1954; SRDB Ref ID: 109515 

DCAS-PR-004, Internal Procedures for the Evaluation of Special Exposure Cohort Petitions, Rev. 1, 

National Institute for Occupational Safety and Health (NIOSH); Cincinnati, Ohio; April 15, 2011; 

SRDB Ref ID: 94768 

DOE, 1996, Removal Site Evaluation Report for the Isotope Facilities at Oak Ridge National 

Laboratory, Oak Ridge, Tennessee, DOE/OR/01-1501&D1; Department of Energy (DOE); approved 

July 29, 1996; SRDB Ref ID: 32226 

Eggen, 1960, Fast-Neutron Spectra and Dose-Rate Calculations; J. B. Eggen, R. L. French, and A. 

Reetz, Jr.; revised May 26, 1960; SRDB Ref ID: 115592 

Exposure, 1951, Exposure Rates at LITR; unspecified author; delivered November 21, 1951; SRDB 

Ref ID: 109493 

Form B, Form B with Lecture Notes, Health Physics Training Lectures, 1948-49, AECU-817, Health 

Physics Division, Oak Ridge National Laboratory; September 29, 1950; Form B received on July 18, 

2011; DSA Ref ID: 114345 

Freestone, 1970, The Low-Energy Neutron Spectrum of the ORNL Tower Shielding Reactor Beam, 

ORNL-TM-3098; R. M. Freestone, F. J. Muckenthaler, K. M. Henry, and C. E. Clifford; August 24, 

1970; SRDB Ref ID: 112448 

George, 1962, The Oak Ridge Research Reactor (ORR), The Low-Intensity Testing Reactor (LITR), 

and the Oak Ridge Graphite Reactor (OGR) As Experiment Facilities, ORNL-TM-279; Kenneth D. 

George; August 28, 1962; SRDB Ref ID: 79534 

Gordon, 1986, Footprint of the Andrex 5310 X-ray Unit in B-239, correspondence to Edward J. 

Leahy; Lisa E. Gordon; July 10, 1986; SRDB Ref ID: 15118 

Gupton, 1981, Methods and Procedure for Internal Radiation Dosimetry at ORNL, ORNL/TM-7923; 

E. D. Gupton; date published August 1981; SRDB Ref ID: 865 

Hart, 1947a, Calibration of Minometers; J. C. Hart; March 24, 1947; SRDB Ref ID: 90632 

Hart, 1947b, Calibration of Victoreen Pocket Meter; J. C. Hart; July 7, 1947: SRDB Ref ID: 90624 

Hart, Apr1949, Survey-Monitoring Weekly Report for the Week Ending April 10, 1949; J. C. Hart; 

week ending April 10, 1949; SRDB Ref ID: 115028 

Hart, May1949, Survey-Monitoring Section Report for the Week Ending May 22, 1949, Volume II, 

No. 21; J. C. Hart; week ending May 22, 1949; SRDB Ref ID: 115036 
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Hart, 1951, Finger Films Used at ORNL, correspondence to J. E. Law; J. C. Hart; December 17, 1951; 

SRDB Ref ID: 110035 

Hart, 1959, Description of the Tower Shielding Reactor II and Proposed Preliminary Experiments, 

ORNL-2747; L. B. Holland and C. E. Clifford; issued July 6, 1959; SRDB Ref ID: 112218 

Holland, 1970, Tower Shielding Reactor 11 Design and Operational Report: Vol 1-Description, 

ORNL-TM-2893, Vol. 1; L. B. Holland; October 7, 1970; SRDB Ref ID: 16546 

Hungerford, 1954, The Skyshine Experiments at the Bulk Shielding Facility, ORNL-1611; H. E. 

Hungerford; July 2, 1954; SRDB Ref ID: 114137 

ICRP 75, 1997, General Principles for the Radiation Protection of Workers, International 

Commission on Radiological Protection; 1997; publicly available; ICRP website: 

http://www.icrp.org/publication.asp?id=ICRP%20Publication%2075 

Incident, Jan1951, Thyroid Counts After Iodine Release in Building 706-D on January 11, 1951; 

incident on January 11, 1951; SRDB Ref ID: 104244 

Incident, Jul1951, Activity Hazard Incident Report Spill of Fission Products in Building 3515 on July 

23, 1951; incident on July 23, 1951; SRDB Ref ID: 104386 

Incident, Oct1951, Activity Hazard Incident Report Spill of Mixed Rare Earths in Building 3038 on 

October 8, 1951; incident on October 8, 1951; SRDB Ref ID: 104408 

Incident, Nov1951, Unusual Incident in Building 3001 on November 7, 1951, correspondence to A. D. 

Warden; R. L. Clark; November 9, 1951; SRDB Ref ID: 104424 

Incident, Jan1952, Incident Concerning Cobalt Carrier at Building 3036 on January 5, 1952, 

correspondence to J. C. Hart; A. D. Warden; February 5, 1952; SRDB Ref ID: 104445 

Incident, Mar1952, Exposure Received in Building 3019 on March 17, 1952, correspondence to A. D. 

Warden; D. E. Arthur; March 19, 1952; SRDB Ref ID: 104487 

Incident, Apr1952, Unusual Incident in Building 3503, correspondence to J. C. Hart; O. D. Teague; 

April 11, 1952; SRDB Ref ID: 104528 

Incident, Aug1952, Activity Hazard Incident Report of Incident in Pipe Tunnel Building 3019 on 

August 22, 1952; incident on August 22, 1952; SRDB Ref ID: 104407 

Incident, Sep1952, Unusual Incident in Building 3019 on September 18, 1952, correspondence to J. C. 

Hart and A. D. Warden; O. D. Teague; September 26, 1952; SRDB Ref ID: 104415 

Incident, Apr-May1954, Reports on Radiation Incident in Building 3026 on April 29, 1954; various 

reports by various authors; reports written between April 1954 and May 1954; SRDB Ref ID: 16541 
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Incident, Dec1960, Radiation Incident in 7500 High Bay Area on December 10, 1960; S. E. Beall; 

December 15, 1960; SRDB Ref ID: 99543 

Incident, Apr1976, Investigation Report on Krypton Release Oak Ridge National Laboratory April 2, 

1976; unspecified author; issued June 18, 1976; SRDB Ref ID: 99459 

Incidents, 1943-2011, Oak Ridge National Laboratory Incidents Database for Years from 1943 

through 2011; SRDB Ref ID: 107042 

Johnson, 1994, Oak Ridge National Laboratory-The First Fifty Years, select portions only; Leland 

Johnson and Daniel Schaffer; 1994; SRDB Ref ID: 11916 

Koval, 1945, Product Contamination of the Air in Building 706-A Report of 12-26-44 to 12-30-44, 

correspondence to K. Z. Morgan; G. Koval; January 2, 1945; SRDB Ref ID: 22943 

Kuhaida, 1997, Site Descriptions of Environmental Restoration Units at Oak Ridge National 

Laboratory, Oak Ridge, Tennessee, ORNL/ER-391; A. J. Kuhaida Jr. and A. F. Parker; issued 

February 1997; SRDB Ref ID: 936 

Larson, 1953, Operation of the LITR at Higher Power Levels, correspondence to Mr. Kenneth 

Kasschau; C. E. Larson; November 9, 1953; SRDB Ref ID: 114339 

Livingston, 1952, Production of Polonium 208-Final Report on Termination of Project, ORNL-1392; 

Robert S. Livingston and John A. Martin; August 1952; SRDB Ref ID: 11936 

Maerker, 1972, The Absolute Neutron Spectrum Emerging through a 15-1/4-In. Collimator from the 

TSR-II Reactor at the Tower Shielding Facility, ORNL-TM-4010; R. E. Maerker and F. J. 

Muckenthaler; December 1972; SRDB Ref ID: 112447 

Mani, 1983, Assessment of Oak Ridge National Laboratory Internal Dosimetry Data for the DOE 

Health and Mortality Study; Kolam V. Mani; 1983; SRDB Ref ID: 870 

Mann, 1947, Critical Experiments on a Small Reactor of Enriched U-235 with AI-H20 Moderator, 

and D2O, BE and H2o Reflectors; M. M. Mann and A. B. Martin; August 18, 1947; SRDB Ref ID: 

112439 

Martin, 1948, Further Critical Experiments on a Small Reactor of Enriched U-235 with AL-H2O 

Moderator and Beryllium Reflector, ORNL-79; A. B. Martin and M. M. Mann; September 16, 1948; 

SRDB Ref ID: 102168 

Martin, 1956, Electronuclear Research Division Catalog of the Isotopes of the Heavy Elements, 

ORNL-2141; J. A. Martin, F. N. Case, and V. O. Haynes; issued September 5, 1956; SRDB Ref ID: 

104069 

McCarley, 1956, Analysis of Thorex Pilot Plant Radiation Exposures During 1955, ORNL-2102; W. 

T. McCarley; issued November 5, 1956; SRDB Ref ID: 104020 
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Meem, 1954, Preliminary Report Operation of the Aircraft Reactor Experiment; J. L. Meem and Wm. 

B. Cottrell; November 30, 1954; SRDB Ref ID: 114418 

Monitoring, 1943-1959a, Oak Ridge National Laboratory In-Vitro Spreadsheet for 1943 through 

1959; 1943-1959; SRDB Ref ID: 107455 

Monitoring, 1943-1959b, Oak Ridge National Laboratory External Dosimetry Spreadsheet for 1943 

through 1959; 1943-1959; SRDB Ref ID: 107457 

Monitoring, Jan-Dec1944, Pocket Meter Monthly Reports for January 1944 through December 1944; 

monthly reports for January 1944 through December 1944; SRDB Ref ID: 110575 

Monitoring, Jan1944-Feb1950, Individual Radiation Records for Single Employee; dates ranging from 

January 1944 through February 1950; SRDB Ref ID: 109298 

Monitoring, Jun-Nov1944, Status Reports of Product Measurements in Air and Dust Studies for June 

1944 through November 1944; various dates between June 1944 and November 1944; SRDB Ref ID: 

22950 

Monitoring, Jun1944-Dec1947, Air Sample Data Summary Spreadsheet; Excel spreadsheet with dates 

ranging from June 1944 through December 1947; SRDB Ref ID: 115411 

Monitoring, Aug1944, Dust Surveys for the Week of July 24-29, 1944; dust survey results for various 

buildings and dates from July 24 through July 29, 1944; SRDB Ref ID: 114941 

Monitoring, Aug1944-Oct1945, Air Sample Results and Film Badge Results for August 1944 through 

October 1945; various dates ranging from August 1944 through October 29, 1945; SRDB Ref ID: 

5920 

Monitoring, Feb-Apr1945, Product in Urine; reported in correspondence from J. E. Wirth; samples 

taken on various dates from February 6, 1945 through March 18, 1945; SRDB Ref ID: 114350 

Monitoring, Feb-Jun1945, Urine Specimen Results for February through June1945; various dates 

from February through June 1945; SRDB Ref ID: 114346 

Monitoring, May-Aug1945, Film Badge Results for May 15, 1945 through August 21, 1945; various 

dated from May 15, 1945 through August 21, 1945; SRDB Ref ID: 5939 

Monitoring, 1945-1990, ORNL Bioassay for 1945-1990 MDAs, Access Database; 1945-1990; SRDB 

Ref ID: 99341 

Monitoring, Jan1947, Personnel Monitoring of Film Meter and pocket Meter Results for January 

1947; results throughout January 1947; SRDB Ref ID: 109910 

Monitoring, Feb1947, Personnel Monitoring of Film Meter and Pocket Meter Results for February 

1947; results throughout February 1947; SRDB Ref ID: 109912 
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Monitoring, Mar1947, Personnel Monitoring of Film Meter and Pocket Meter Results for March 

1947; results throughout March 1947; SRDB Ref ID: 109913 

Monitoring, Mar-Jun1947, Positive Film Exposures by Payroll Number Batch 18-29 for March 1947 

through June 1947; various dates throughout March 1947 through June 1947; SRDB Ref ID: 109898 

Monitoring, Apr1947, Personnel Monitoring of Film Meter and Pocket Meter Results for April 1947; 

results throughout April 1947; SRDB Ref ID: 109915 

Monitoring, May1947, Personnel Monitoring of Film Meter and Pocket Meter Results for May 1947; 

results throughout May 1947; SRDB Ref ID: 109917 

Monitoring, Jun1947a, Positive Film Exposures by Payroll Number for Week #26 in June 1947; Week 

#26 in June 1947; SRDB Ref ID: 109899 

Monitoring, Jun1947b, Personnel Monitoring of Film Meter and Pocket Meter Results for June 1947; 

results throughout June 1947; SRDB Ref ID: 109918 

Monitoring, Jul1947a, Positive Film Exposures by Payroll Number for July 1947; various dates 

throughout July 1947; SRDB Ref ID: 109900 

Monitoring, Jul1947b, Personnel Monitoring of Film Meter and Pocket Meter Results for July1947; 

results throughout July 1947; SRDB Ref ID: 109919 

Monitoring, Jul-Dec1947, Summary of Radiation Exposure Record of Employees for the Last Six 

Months of 1947; July-December 1947; SRDB Ref ID: 5473 

Monitoring, Aug1947a, N.P.U. List and Continuous Exposure Sheets for August, Week #31; Week 

#31 in August 1947; SRDB Ref ID: 109904 

Monitoring, Aug1947b, Personnel Monitoring of Film Meter and Pocket Meter Results for August 

1947; results throughout August 1947; SRDB Ref ID: 109921 

Monitoring, Aug1947c, Personnel Monitoring of Film Meter and Pocket Meter Results for Weeks 

#32-35 of August 1947; results for weeks #32-35 of August 1947; SRDB Ref ID: 109931 

Monitoring, Sep1947a, Positive Film Exposures by Payroll Number for September 1947; various 

dates throughout September 1947; SRDB Ref ID: 109928 

Monitoring, Sep1947b, Personnel Monitoring of Film Meter and Pocket Meter Results for September 

1947; results throughout September 1947; SRDB Ref ID: 109922 

Monitoring, Oct1947a, Positive Film Exposures by Payroll Number for October 1947; various dates 

throughout October 1947; SRDB Ref ID: 109901 

Monitoring, Oct1947b, Personnel Monitoring of Film Meter and Pocket Meter Results for October 

1947; results throughout October 1947; SRDB Ref ID: 109923 
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Monitoring, Nov1947a, Positive Film Exposures by Payroll Number for November 1947; various 

dates throughout November 1947; SRDB Ref ID: 109902 

Monitoring, Nov1947b, Personnel Monitoring of Film Meter and Pocket Meter Results for November 

1947; results throughout November 1947; SRDB Ref ID: 109925 

Monitoring, Dec1947a, Positive Film Exposures by Payroll Number for December 1947; various 

dates throughout December 1947; SRDB Ref ID: 109903 

Monitoring, Dec1947b, Personnel Monitoring of Film Meter and Pocket Meter Results for December 

1947; results throughout December 1947; SRDB Ref ID: 109927 

Monitoring, 1947-1948, Film Badge Reports for Various Dates from 1947 through 1948; various 

dates from 1947 through 1948; SRDB Ref ID: 4385 

Monitoring, Jan1948, Personnel Monitoring of Film Meter and Pocket Meter Results for January 

1948; results throughout January 1948; SRDB Ref ID: 109929 

Monitoring, Feb1948, Positive Film Exposures by Payroll Number for February 1948; various dates 

throughout February 1948; SRDB Ref ID: 109887 

Monitoring, Mar1948, Positive Film Exposures by Payroll Number for March 1948; various dates 

throughout March 1948; SRDB Ref ID: 109891 

Monitoring, Apr1948, Positive Film Exposures by Payroll Number for April 1948; various dates 

throughout April 1948; SRDB Ref ID: 109892 

Monitoring, May1948, Positive Film Exposures by Payroll Number for May 1948; various dates 

throughout May 1948; SRDB Ref ID: 109894 

Monitoring, Jun1948, Positive Film Exposures by Payroll Number for June 1948; various dates 

throughout June 1948; SRDB Ref ID: 109895 

Monitoring, Jul1948, Positive Film Exposures by Payroll Number for July 1948; various dates 

throughout July 1948; SRDB Ref ID: 109862 

Monitoring, Aug1948, Positive Film Exposures by Payroll Number for August 1948; various dates 

throughout August 1948; SRDB Ref ID: 109863 

Monitoring, Sep1948, Positive Film Exposures by Payroll Number for September 1948; various dates 

throughout September 1948; SRDB Ref ID: 109865 

Monitoring, Oct1948a, Positive Film Exposures by Payroll Number for October 1948; various dates 

throughout October 1948; SRDB Ref ID: 109866 

Monitoring, Oct1948b, Thyroid Counts for Various Dates throughout October 1948; dates ranging 

from September 27, 1948 through October 18, 1948; SRDB Ref ID: 110152 
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Monitoring, Nov1948, Positive Film Exposures by Payroll Number for November 1948; various dates 

throughout November 1948; SRDB Ref ID: 109867 

Monitoring, Dec1948, Positive Film Exposures by Payroll Number for December 1948; various dates 

throughout December 1948; SRDB Ref ID: 109868 

Monitoring, Jan1949, Positive Film Exposures by Payroll Number for January 1949; various dates 

throughout January 1949; SRDB Ref ID: 109869 

Monitoring, Jan-Apr1949, Statistical Summary of Personnel Monitoring for January 1949 through 

April 1949; weekly dates ranging from January 1949 through April 1949; SRDB Ref ID: 109890 

Monitoring, Jan-Jul1949, Plutonium Bioassay Log Book for January 1949 through July 1949; dates 

ranging from January-July 1949; SRDB Ref ID: 112219 

Monitoring, Jan-Dec1949, Film Badge Results for January through December 1949; dates ranging 

from January through December 1949; SRDB Ref ID: 4281 

Monitoring, Feb1949, Positive Film Exposures by Payroll Number for February 1949; various dates 

throughout February 1949; SRDB Ref ID: 109870 

Monitoring, Mar1949, Positive Film Exposures by Payroll Number for March 1949; various dates 

throughout March 1949; SRDB Ref ID: 109871 

Monitoring, Apr1949, Positive Film Exposures by Payroll Number for April 1949; various dates 

throughout April 1949; SRDB Ref ID: 109876 

Monitoring, Apr-Jun1949, Statistical Summary of Personnel Monitoring for April 1949 through June 

1949; weekly dates ranging from April 1949 through June 1949; SRDB Ref ID: 109893 

Monitoring, May1949, Positive Film Exposures by Payroll Number for May 1949; various dates 

throughout May 1949; SRDB Ref ID: 109872 

Monitoring, May-Aug1949, Uranium (U-233) Bioassay Log Book for May 1949 through August 

1949; dates ranging from May-August 1949; SRDB Ref ID: 116919 

Monitoring, May-Dec1949, Analysis of Health Physics Records of the J. A. Jones Construction 

Company Employees; result dates ranging from May 1949 through December 1949; SRDB Ref ID: 

4706 

Monitoring, Jun1949, Positive Film Exposures by Payroll Number for June 1949; various dates 

throughout June 1949; SRDB Ref ID: 109873 

Monitoring, Jul1949, Positive Film Exposures by Payroll Number for July 1949; various dates 

throughout July 1949; SRDB Ref ID: 109874 
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Monitoring, Jul-Aug1949, Statistical Summary of Personnel Monitoring for July 1949 through August 

1949; weekly dates ranging from July 1949 through August 1949; SRDB Ref ID: 109896 

Monitoring, Aug1949, Positive Film Exposures by Payroll Number for August 1949; various dates 

throughout August 1949; SRDB Ref ID: 109881 

Monitoring, Sep1949, Positive Film Exposures by Payroll Number for September 1949; various dates 

throughout September 1949; SRDB Ref ID: 109883 

Monitoring, Oct1949, Positive Film Exposures by Payroll Number for October 1949; various dates 

throughout October 1949; SRDB Ref ID: 109884 

Monitoring, Nov1949, Positive Film Exposures by Payroll Number for November 1949; various dates 

throughout November 1949; SRDB Ref ID: 109888 

Monitoring, Dec1949, Positive Film Exposures by Payroll Number for December 1949; various dates 

throughout December 1949; SRDB Ref ID: 109889 

Monitoring, Feb-Apr1951, Radiation Film Monitoring Issue Records for February 23, 1951 through 

April 17, 1951; dates ranging from February 23, 1951 through April 17, 1951; SRDB Ref ID: 4339 

Monitoring, Jul1951, Skin Contamination Results for July 1951 Spill Involving Sample Cone in 

Building 205; incident on July 1, 1951; SRDB Ref ID: 104208 

Monitoring, 1953-1970, Select Film Badge Calibration Data for 1953 through 1970; SRDB Ref ID: 

15188 

Monitoring, Jan-Dec1954, Personnel Monitoring Weekly Exposure Records from January 1954 

through December 1954; results for all weeks between January 1954 and December 1954; SRDB Ref 

ID: 109308 

Neutron Problems, unspecified, Neutron Problems at ORNL; unspecified author; unspecified date; 

SRDB Ref ID: 109494 

ORAUT-OTIB-0006, Dose Reconstruction form Occupational Medical X-Ray Procedures, Rev. 04; 

ORAU Team Dose Reconstruction Project for NIOSH; effective June 20, 2011; SRDB Ref ID: 98147 

ORAUT-OTIB-0018, Internal Dose Overestimates for Facilities with Air Sampling Programs, Rev. 

01; ORAU Team Dose Reconstruction Project for NIOSH; effective August 9, 2005; SRDB Ref ID: 

19436 

ORAUT-OTIB-0021, Technical Information Bulletin – External Coworker Dosimetry Data for the X10 Site, Rev. 00; ORAU Team Dose Reconstruction Project for NIOSH; December 29, 2004; SRDB 

Ref ID: 19442 

ORAUT-OTIB-0034, Internal Dosimetry Coworker Data for X-10, Rev. 00; ORAU Team Dose 

Reconstruction Project for NIOSH; effective December 13, 2005; SRDB Ref ID: 20222 
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ORAUT-OTIB-0079, Guidance on Assigning Occupational X-Ray Dose Under EEOICPA for X-Rays 

Administered Off Site, Rev. 00; ORAU Team Dose Reconstruction Project for NIOSH; effective 

January 3, 2011; SRDB Ref ID: 89563 

ORAUT-TKBS-0012-1, Technical Basis Document for the Oak Ridge National Laboratory – 

Introduction, Rev. 0; ORAU Team Dose Reconstruction Project for NIOSH; effective August 11, 

2004; SRDB Ref ID: 20132 

ORAUT-TKBS-0012-2, Oak Ridge National Laboratory - Site Description, Rev. 02; ORAU Team 

Dose Reconstruction Project for NIOSH; effective August 17, 2007; SRDB Ref ID: 34367 

ORAUT-TKBS-0012-3, Oak Ridge National Laboratory – Occupational Medical Dose, Rev. 02; 

ORAU Team Dose Reconstruction Project for NIOSH; effective October 1, 2007; SRDB Ref ID: 

35194 

ORAUT-TKBS-0012-5, Oak Ridge National Laboratory - Occupational Internal Dose, Rev. 01; 

ORAU Team Dose Reconstruction Project for NIOSH; effective October 1, 2007; SRDB Ref ID: 

35195 

ORAUT-TKBS-0012-6, Oak Ridge National Laboratory – Occupational External Dose, Rev. 01; 

ORAU Team Dose Reconstruction Project for NIOSH; effective September 10, 2007; SRDB Ref ID: 

34945 

ORNL, 1948, Critical Experiments for the High Flux Reactor, W-7405, eng 26; A. B. Martin and M. 

M. Mann; October 22, 1948; SRDB Ref ID: 102174 

ORNL, 1951, Production of Polonium 208, ORNL-1192; Oak Ridge National Laboratory (ORNL); 

December 8, 1951; SRDB Ref ID: 21979; NOTE: This is a sensitive document with Export 

Controlled Information 

ORNL, 1952, Homogeneous Reactor Project Quarterly Progress Report for Period Ending July 1, 

1952, Oak Ridge National Laboratory; September 2, 1952; SRDB Ref ID: 115786 

ORNL, 1958, The Bulk Shielding Reactor (The “Swimming Pool” Reactor); Oak Ridge National 

Laboratory (ORNL); June 1, 1958; SRDB Ref ID: 114437 

ORNL, 1962, A Safety Review of the Oak Ridge Critical Experiments Facility, ORNL-TM-349; Oak 

Ridge National Laboratory (ORNL); December 1962; SRDB Ref ID: 15646 

ORNL, 1967, A Safety Analysis of the Oak Ridge Critical Experiments Facility, ORNL-TM-349 Rev. 

1; Oak Ridge National Laboratory (ORNL); February 1967; SRDB Ref ID: 15655 

ORNL, 1992, A Brief History of the Research Reactors Division of Oak Ridge National Laboratory; 

Oak Ridge National Laboratory (ORNL); September 1992; SRDB Ref ID: 16542 

ORNL, 1997a, Final Deactivation Project Report on the Alpha Powder Facility, Building 3028, at 

Oak Ridge National Laboratory, Oak Ridge, Tennessee, ORNL/ER-399; Isotopes Facility 
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Deactivation Project of Oak Ridge National Laboratory (ORNL); issued April 1997; SRDB Ref ID: 

32218 

ORNL, 1997b, 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 (ORNL); issued May 1997; SRDB Ref ID: 32252 

ORNL, 1997c, 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 (ORNL); issued August 1997; SRDB Ref ID: 32263 

ORNL, 1997d, 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 (ORNL); issued August 1997; SRDB Ref ID: 32264 

ORNL, 1997e, 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 (ORNL); issued September 1997; SRDB Ref ID: 32265 

ORNL, 1997f, 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; issued September 1997; SRDB Ref ID: 32268 

ORNL, post-2002, ORNL Historical X-Ray Practices and Protocols; Oak Ridge National Laboratory 

(ORNL); written sometime after 2002; SRDB Ref ID: 10114 

ORNL Site Map, 1955, ORNL Family Days Flyer with ORNL Site Map, Oak Ridge National 

Laboratory, Oak Ridge, Tennessee; December 3-4, 1955; SRDB Ref ID: 8499 

Parker, 1944, Health and Protection June 1944, CN-1648; H. M. Parker, T. W. Bloss, and D. J. 

Rendell; June 1944; SRDB Ref ID: 99616 

Parrish, 1982, Evaluation of External Personnel Monitoring Devices and Data for Oak Ridge 

National Laboratory Epidemiological Study, ORNL/TM-2006/37; Bruce R. Parrish; 1982; SRDB Ref 

ID: 109937 

Peretz, 1982, Summary of the Radiological Characterization of Building 3505, X-OE-190; F. J. Peretz 

and J. F. Alexander; September 30, 1982; SRDB Ref ID: 22606 

Perry, 1947, Conditions in 105 and 115 Buildings as a Result of Slug Removal from Pile, 

correspondence to K. Z. Morgan; C. H. Perry; December 11, 1947; SRDB Ref ID: 22949 

Personal Communication, 2006, Personal Communication Regarding Activities in the ORNL Biology 

Buildings Located at Y-12; Interview by ORAU Team; April 12, 2006; SRDB Ref ID: 22812 

Personal Communication, 2012a, Personal Communication with One Individual Regarding Thorium 

Operations at the X-10 Facility; Interview by ORAU Team; March 14, 2012; SRDB Ref ID: 109522
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Personal Communication, 2012b, Personal Communication with Two Individuals Regarding Thorium 

Operations at the X-10 Facility; Interview by ORAU Team; March 22, 2012; SRDB Ref ID: 109819

Personal Communication, 2012c, Personal Communication with Three Individuals Regarding 

Radiation Monitoring at ORNL ( X-10); Interview by ORAU Team; June 13, 2012; SRDB Ref ID: 

116011

Personal Communication, 2012d, Personal Communication with One Individual Regarding Bioassay 

Sampling at ORNL; Interview by ORAU Team; June 14, 2012; SRDB Ref ID: 115274

Personal Communication, 2012e, Personal Communication with One Individual Regarding Reporting 

of Neutron Doses; Interview by ORAU Team; July 3, 2012; SRDB Ref ID: 115899 

Progress Report, Jan-Dec1946, Multiple Weekly Surveys for Weeks Ending January 1946 through July 

1946; various dates between January through December 1946; SRDB Ref ID: 22957, pdf pp. 6-334

Progress Report, 1946-1956, Health Physics Department Monthly and Quarterly Reports for 1946 

through 1956; various dates between 1946 through 1956; SRDB Ref ID: 13233 

Progress Report, Jun1946, Health Division Report for Month Ending June 30, 1946; J. E. Wirth; June 

30, 1946; SRDB Ref ID: 99622 

Progress Report, Jan1947, Operating Department Report for Month Ending January 31, 1947; A. G. 

Erdman, E. J. Witkowski, and L. B. Emlet; issued February 11, 1947; SRDB Ref ID: 116298 

Progress Report, Jan-Dec1947, Health Physics and Progress Reports for Oak Ridge National 

Laboratory for Various Dates throughout 1947; SRDB Ref ID: 22959 

Progress Report, Feb1947, Monthly Report of Operations for Monsanto Chemical Company Clinton 

Laboratories for the Month of February 1947, W-35-058-eng-71; Walter P. Leber; March 1, 1947; 

SRDB Ref ID: 88307 

Progress Report, Mar1947a, Monthly Report of Operations for Monsanto Chemical Company Clinton 

Laboratories for the Month of March 1947; Walter P. Leber; April 1, 1947; SRDB Ref ID: 88309 

Progress Report, Mar1947b, Operating Department Report for Month Ending March 31, 1947; F. R. 

Stuckey, E. J. Witkowski, and L. B. Emlet; issued April 11, 1947; SRDB Ref ID: 116299 

Progress Report, May1947, Monthly Report of Operations for Monsanto Chemical Company Clinton 

Laboratories for the Month of May 1947; James C. Stewart; June 1, 1947; SRDB Ref ID: 88310 

Progress Report, Jun1947, Monthly Report of Operations for Monsanto Chemical Company Clinton 

Laboratories for the Month of June 1947; James C. Stewart; July 25, 1947; SRDB Ref ID: 88312 

Progress Report, Jul1947, Monthly Report of Operations for Monsanto Chemical Company Clinton 

Laboratories for the Month of July 1947; James C. Stewart; unspecified date; SRDB Ref ID: 88314 
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Progress Report, Aug1947, Monsanto Chemical Company Clinton Laboratories Operating 

Department Report for Month Ending August 31, 1947; F. R. Stuckey, E. J. Witkowski, and L. B. 

Emlet; issued September 15, 1947; SRDB Ref ID: 116300 

Progress Report, Aug-Dec1947, Weekly Neutron Film Reports for August 23, 1947 through December 

20, 1947; various dates from August 23, 1947 through August 23, 1947; SRDB Ref ID: 110148 

Progress Report, Nov1947, Monthly Report of Operations for Monsanto Chemical Company Clinton 

Laboratories for the Month Ending November 30, 1947; F. R. Stuckey, E. J. Witkowski, A. F. Rupp, 

and L. B. Emlet; issued December 19, 1947; SRDB Ref ID: 97548 

Progress Report, Dec1947-Feb1948, Weekly Neutron Film Reports for December 20, 1947 through 

February 28, 1948; various dates from December 20, 1947 through February 28, 1948; SRDB Ref ID: 

110170 

Progress Report, Feb1948, Operating Division Report for Month Ending February 29, 1948; M. E. 

Ramsey, E. J. Witkowski, A. F. Rupp, and L. B. Emlet; issued March 10, 1948; SRDB Ref ID: 97614 

Progress Report, Feb-Apr1948, Weekly Neutron Film Report for February 28, 1948 through April 24, 

1948; various dates from February 28, 1948 through April 24, 1948; SRDB Ref ID: 110175 

Progress Report, Apr-Jul1948, Weekly Neutron Film Report for April 24, 1948 through July 9, 1948; 

various dates from April 24, 1948 through July 9, 1948; SRDB Ref ID: 110191 

Progress Report, Jul1948, Operations Division Report for Month Ending July 31, 1948; M. E. 

Ramsey, E. J. Witkowski, A. F. Rupp, J. A. Cox, and L. B. Emlet; issued August 13, 1948; SRDB Ref 

ID: 110005 

Progress Report, Jul-Sep1948, Weekly Neutron Film Report for July 3, 1948 through September 3, 

1948; various dates from July 3, 1948 through September 3, 1948; SRDB Ref ID: 110195 

Progress Report, Aug1948, Operations Division Report for Month Ending August 31, 1948; M. E. 

Ramsey, E. J. Witkowski, A. F. Rupp, J. A. Cox, and L. B. Emlet; issued September 24, 1948; SRDB 

Ref ID: 110006 

Progress Report, Sep-Oct1948, Weekly Neutron Film Report for September 4, 1948 through October 

29, 1948; various dates from September 4, 1948 through October 29, 1948; SRDB Ref ID: 110200 

Progress Report, Oct1948, Operations Division Report for Month Ending October 31, 1948; M. E. 

Ramsey, E. J. Witkowski, A. F. Rupp, J. A. Cox, and L. B. Emlet; date issued unspecified; SRDB Ref 

ID: 109940 

Progress Report, Oct-Dec1948, Weekly Neutron Film Report for October 23, 1948 through December 

27, 1948; various dates from October 23, 1948 through December 27, 1948; SRDB Ref ID: 110202 
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Progress Report, Nov1948, Operations Division Report for Month Ending November 30, 1948; M. E. 

Ramsey, E. J. Witkowski, A. F. Rupp, J. A. Cox, and L. B. Emlet; issued December 13, 1948; SRDB 

Ref ID: 109941 

Progress Report, Dec1948-Apr1949, Weekly Neutron Film Report for December 18, 1948 through 

April 8, 1949; various dates from December 18, 1949 through April 8, 1949; SRDB Ref ID: 110207 

Progress Report, Feb1949, Operations Division Report for Month Ending February 28, 1949; M. E. 

Ramsey, E. J. Witkowski, A. F. Rupp, J. A. Cox, and L. B. Emlet; issued March 31, 1949; SRDB Ref 

ID: 109944 

Progress Report, Apr1949, Operations Division Report for Month Ending April 30, 1949; M. E. 

Ramsey, E. J. Witkowski, A. F. Rupp, J. A. Cox, and L. B. Emlet; issued May 20, 1949; SRDB Ref 

ID: 109945 

Progress Report, Apr-Jul1949, Weekly Neutron Film Report for April 2, 1949 through July 2, 1949; 

various dates from April 2, 1949 through July 2, 1949; SRDB Ref ID: 110213 

Progress Report, May1949, Operations Division Report for Month Ending May 31, 1949; M. E. 

Ramsey, E. J. Witkowski, A. F. Rupp, J. A. Cox, and L. B. Emlet; issued June 15, 1949; SRDB Ref 

ID: 109942 

Progress Report, May-Jun1949, Weekly Neutron Film Reports for May 1949 through June 1949; 

various dates from May 1949 through June 1949; SRDB Ref ID: 28126 

Progress Report, Jun1949, Operations Division Report for Month Ending June 30, 1949; M. E. 

Ramsey, E. J. Witkowski, A. F. Rupp, J. A. Cox, and L. B. Emlet; issued July 27, 1949; SRDB Ref 

ID: 98247 

Progress Report, Jul-Sep1949, Weekly Film Neutron Reports for July 2, 1949 through September 30, 

1949; various dates from July 2, 1949 through September 30, 1949; SRDB Ref ID: 110221 

Progress Report, Sep1949, Operations Division Report for Month Ending September 30, 1949; M. E. 

Ramsey, E. J. Witkowski, A. F. Rupp, J. A. Cox, and L. B. Emlet; issued October 19, 1949; SRDB 

Ref ID: 109947 

Progress Report, Sep1949-Jan1950, Weekly Neutron Reports for September 24, 1949 through January 

6, 1950; various dates from September 24, 1949 through January 6, 1950; SRDB Ref ID: 110225 

Progress Report, Dec1949, Operations Division Report for Month Ending December 31, 1949; M. E. 

Ramsey, E. J. Witkowski, A. F. Rupp, J. A. Cox, and L. B. Emlet; issued February 13, 1950; SRDB 

Ref ID: 98246 

Progress Report, Oct1950, Health Physics Division Quarterly Progress Report for Period Ending 

October 20, 1950, ORNL 877; K. Z. Morgan; issued December 11, 1950; SRDB Ref ID: 10091 
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Progress Report, Jan1950, Operations Division Monthly Report for Month Ending January 31, 1950; 

L. B. Emlet; issued February 22, 1950; SRDB Ref ID: 109956 

Progress Report, Mar1950, Operations Division Monthly Report for Month Ending March 31, 1950; 

L. B. Emlet; issued April 21, 1950; SRDB Ref ID: 109957 

Progress Report, Apr1950, Operations Division Monthly Report for Month Ending April 30, 1950; L. 

B. Emlet; issued May 19, 1950; SRDB Ref ID: 79870 

Progress Report, Jan1951, Oak Ridge National Laboratory Status and Progress Report January 1951; 

W. E. Thompson; issued February 9, 1951; SRDB Ref ID: 101963 

Progress Report, Jan-Jun1951, Carbide and Carbon Chemicals Company Health Physics Progress 

Report for the Period January 1, 1951 through June 30, 1951, W-7405-eng-26; E. G. Struxness; 

December 15, 1951; SRDB Ref ID: 8602 pdf pp. 257-294 

Progress Report, Feb1951, Operations Division Monthly Report for Month Ending February 28, 1951; 

M. E. Ramsey; issued March 26, 1951; SRDB Ref ID: 109960 

Progress Report, Apr1951, Operations Division Monthly Report for Month Ending April 30, 1951; M. 

E. Ramsey; issued May 17, 1951; SRDB Ref ID: 110008 

Progress Report, May1951, Operations Division Monthly Report for Month Ending May 31, 1951; M. 

E. Ramsey; issued June 21, 1951; SRDB Ref ID: 110010 

Progress Report, Jun1951, Operations Division Monthly Report for Month Ending June 30, 1951; M. 

E. Ramsey; issued September 20, 1951; SRDB Ref ID: 110011 

Progress Report, Jul1951, Operations Division Monthly Report for Month Ending July 31, 1951; M. 

E. Ramsey; issued November 7, 1951; SRDB Ref ID: 110013 

Progress Report, Jul-Dec1951, Carbide and Carbon Chemicals Company Health Physics Progress 

Report for Period July 1, 1951 through December 31, 1951, W-7405-eng-26; E. G. Struxness; March 

15, 1952; SRDB Ref ID: 8602 pdf pp. 110-178 

Progress Report, Aug1951, Operations Division Monthly Report for Month Ending August 31, 1951; 

M. E. Ramsey; issued January 15, 1952; SRDB Ref ID: 110016 

Progress Report, Sep1951, Operations Division Monthly Report for Month Ending September 30, 

1951; M. E. Ramsey; issued January 18, 1952; SRDB Ref ID: 110019 

Progress Report, Oct1951a, Health Physics Division Quarterly Progress Report for Period Ending 

October 20, 1951; K. Z. Morgan; DSA Ref ID: 114348 

Progress Report, Oct1951b, Operations Division Monthly Progress Report for Month Ending October 

31, 1951; M. E. Ramsey; issued February 14, 1952; SRDB Ref ID: 110022 
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Progress Report, Dec1951, Operations Division Monthly Report for Month Ending December 31, 

1951; M. E. Ramsey; issued March 6, 1952; SRDB Ref ID: 110026 

Progress Report, Jan1952, Operations Division Monthly Report for Month Ending January 31, 1952; 

M. E. Ramsey; issued March 31, 1952; SRDB Ref ID: 110029 

Progress Report, Feb1952, Operations Division Monthly Report for Month Ending February 29, 1952; 

M. E. Ramsey; issued April 28, 1952; SRDB Ref ID: 110030 

Progress Report, Mar1952, Operations Division Monthly Report for Month Ending March 31, 1952; 

M. E. Ramsey; issued May 16, 1952; SRDB Ref ID: 110031 

Progress Report, Apr1952, Operations Division Monthly Report for Month Ending April 30, 1952; M. 

E. Ramsey; issued June 30, 1952; SRDB Ref ID: 110032 

Progress Report, May1952, Operations Division Monthly Report for Month Ending May 31, 1952; M. 

E. Ramsey; issued July 23, 1952; SRDB Ref ID: 110033 

Progress Report, Jun1952, Operations Division Monthly Report for Month Ending June 30, 1952; M. 

E. Ramsey; issued August 13, 1952; SRDB Ref ID: 110055 

Progress Report, Jul1952, Operations Division Monthly Report for Month Ending July 31, 1952; M. 

E. Ramsey; issued September 8, 1952; SRDB Ref ID: 110034 

Progress Report, Aug1952, Operations Division Monthly Report for Month Ending August 31, 1952; 

M. E. Ramsey; issued October 1952; SRDB Ref ID: 110056 

Progress Report, Sep1952, Operations Division Monthly Report for Month Ending September 30, 

1952; M. E. Ramsey; issued November 20, 1952; SRDB Ref ID: 110038 

Progress Report, Oct1952, Operations Division Monthly Report for Month Ending October 31, 1952; 

M. E. Ramsey; issued December 19, 1952; SRDB Ref ID: 110044 

Progress Report, Dec1952, Operations Division Monthly Report for Month Ending December 31, 

1952; M. E. Ramsey; issued February 21, 1953; SRDB Ref ID: 110045 

Progress Report, Jan1953, Operations Division Monthly Report for Month Ending January 31, 1953; 

M. E. Ramsey; issued March 4, 1953; SRDB Ref ID: 110046 

Progress Report, Mar1953, Operations Division Monthly Report for Month Ending March 31, 1953; 

M. E. Ramsey; issued May 11, 1953; SRDB Ref ID: 110048 

Progress Report, Apr1953, Operations Division Monthly Report for Month Ending April 30, 1953; M. 

E. Ramsey; issued June 28, 1953; SRDB Ref ID: 110049 

Progress Report, May1953, Operations Division Monthly Report for Month Ending May 31, 1953; M. 

E. Ramsey; issued July 15, 1953; SRDB Ref ID: 110050 
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Progress Report, Jun1953, Operations Division Monthly Report for Month Ending June 30, 1953; M. 

E. Ramsey; issued July 27, 1953; SRDB Ref ID: 110051 

Progress Report, Jul1953, Operations Division Monthly Report for Month Ending July 31, 1953; M. 

E. Ramsey; issued September 15, 1953; SRDB Ref ID: 110052 

Progress Report, Aug1953, Operations Division Monthly Report for Month Ending August 31, 1953; 

M. E. Ramsey; issued October 12, 1953; SRDB Ref ID: 110066 

Progress Report, Oct1953, Operations Division Monthly Report for Month Ending October 31, 1953; 

A. F. Rupp; issued sometime in 1953; SRDB Ref ID: 110084 

Progress Report, Nov1953, Operations Division Monthly Report for Month Ending November 30, 

1953; A. F. Rupp; issued January 15, 1954; SRDB Ref ID: 110088 

Progress Report, Dec1953, Operations Division Monthly Report for Month Ending December 31, 

1953; A. F. Rupp; issued February 11, 1954; SRDB Ref ID: 110089 

Progress Report, Feb1954, Operations Division Monthly Report for Month Ending February 28, 1954; 

A. F. Rupp; issued April 19, 1954; SRDB Ref ID: 110092 

Progress Report, Mar1954a, Aircraft Nuclear Propulsion Project Quarterly Progress Report for 

Period Ending March 10, 1954; R. C. Briant, W. H. Jordan, A. J. Miller, and A. W. Savolainen; April 

15, 1954; SRDB Ref ID: 103200 

Progress Report, Mar1954b, Operations Division Monthly Report for Month Ending March 31, 1954; 

A. F. Rupp; issued May 19, 1954; SRDB Ref ID: 110094 

Progress Report, May1954, Resume of Activities for the Month Ending May 20, 1954; G. W. Wunder; 

May 27, 1954; SRDB Ref ID: 81619 

Progress Report, Jun1954, Aircraft Nuclear Propulsion Project Quarterly Progress Report for Period 

Ending June 10, 1954; W. H. Jordan, A. J. Miller, and A. W. Savolainen; July 20, 1954; SRDB Ref 

ID: 103208 

Progress Report, Jul1954, Operations Division Monthly Report for Month Ending July 31, 1954; A. F. 

Rupp; issued August 9, 1954; SRDB Ref ID: 109962 

Progress Report, Aug1954, Operations Division Monthly Report for Month Ending August 31, 1954; 

A. F. Rupp; issued October 2, 1954; SRDB Ref ID: 109963 

Progress Report, Sep1954, Operations Division Monthly Report for Month Ending September 30, 

1954; A. F. Rupp; issued November 16, 1954; SRDB Ref ID: 109938 

Progress Report, Oct1954, Operations Division Monthly Report for Month Ending October 31, 1954; 

A. F. Rupp; issued December 22, 1954; SRDB Ref ID: 109970 
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Progress Report, Nov1954, Operations Division Monthly Report for Month Ending November 30, 

1954; A. F. Rupp; issued January 18, 1955; SRDB Ref ID: 110095 

Progress Report, Dec1954, Operations Division Monthly Report for Month Ending December 31, 

1954; A. F. Rupp; issued February 4, 1955; SRDB Ref ID: 110096 

Progress Report, Mar1955, Aircraft Nuclear Propulsion Project Quarterly Progress Report for Period 

Ending March 10, 1955; W. H. Jordan, S. J. Cromer, R. I. Strough, A. J. Miller, and A. W. 

Savolainen; issued April 21, 1955; SRDB Ref ID: 103364 

Progress Report, Jul1955-Jan1956, Applied Health Physics Semi-Annual Report for July 1955 through 

January 1956; J. C. Hart; post January 1956; SRDB Ref ID: 22545 

Progress Report, Dec1955, Oak Ridge National Laboratory Status and Progress Report-December 

1955, W-7405-Eng-26; F. T. Howard and W. H. Sullivan; issued December 9, 1956; SRDB Ref ID: 

103948 

Progress Report, Oct1957, Electronuclear Division Annual Progress Report for Period Ending 

October 1, 1957, ORNL-2434; R. S. Livingston; issued April 15, 1958; SRDB Ref ID: 11945 

Progress Report, Jul1961, Health Physics Division Annual Progress Report for Period Ending July 

31, 1961, ORNL-3189; K. Z. Morgan; October 24, 1961; SRDB Ref ID: 11564 

Progress Report, Dec1961, Electronuclear Division Annual Progress Report for Period Ending 

December 31, 1961, ORNL-3257; R. S. Livingston and A. Zucker; issued August 17, 1962; SRDB 

Ref ID: 11949 

Progress Report, Jul-Oct1962, Isotopes Development Center Progress Report for Reactor- and 

Cyclotron-Produced Isotopes for July-October 1962, ORNL-TM-463; T. A. Butler; issued April 1, 

1963; SRDB Ref ID: 11934 

Progress Report, Jul1965, Health Physics Division Annual Progress Report for Period Ending July 

31, 1965; K. Z. Morgan, W. S. Snyder, and E. G. Struxness; October 1965; SRDB Ref ID: 11567 

Progress Report, Jul1966, Health Physics Division Annual Progress Report for Period Ending July 

31, 1966, ORNL-4007; K. Z. Morgan, W. S. Snyder, and E. G. Struxness; October 1966; SRDB Ref 

ID: 11561 

Rosenthal, 2009, An Account of Oak Ridge National Laboratory’s Thirteen Nuclear Reactors, 

ORNL/TM-2009/181; Murray W. Rosenthal, Oak Ridge National Laboratory (ORNL); August 2009; 

SRDB Ref ID: 79408 

Russell, 1945, Procedure for the Detection of Plutonium in Human Urine, correspondence to S. T. 

Cantril; E. R. Russell; October 20, 1945; SRDB Ref ID: 114392 

Savage, 1950, Calutron Production of Stable Isotopes, 1946-1949, Inclusive; H. W. Savage; April 20, 

1950; SRDB Ref ID: 97985 
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Seagren, 1957, Radioisotope Production and Process Development Annual Report for 1956, ORNL2303; H. E. Seagren; issued June 10, 1957; SRDB Ref ID: 103912 

Simons, 1945, 706-D Hot Run #3 Health Report for Period July 12 through July 23, 1945; R. A. 

Simons; July 26, 1945; SRDB Ref ID: 22938 

Stone, 1944, Methods of Analysis of Stools and Urine for Product, correspondence to Dr. J. J. 

Nickson; R. S. Stone; June 13, 1944; SRDB Ref ID: 114302 

Thomas, 1967, Correction for Dead Space in Face Masks in Inhalation Studies; Jess W. Thomas; 

February 1967; SRDB Ref ID: 16555 

Thompson, 1949, Operations Division A History of the Radioactive Barium-Lanthanum Process and 

Production; W. E. Thompson; June 22, 1949; SRDB Ref ID: 16543 

Thompson, 1963, History of the Oak Ridge National Laboratory 1943-1963, first rough draft; W. E. 

Thompson; August 23, 1963; SRDB Ref ID: 877 

Thorium, 1944, Various Correspondence Regarding the Program on Thorium and 23; various 

authors; various dates throughout 1944; SRDB Ref ID: 8401 

Thornton, 1961, The ORNL Badge Dosimeter and Its Personal Monitoring Applications, ORNL-3126; 

W. T. Thornton, D. M. Davis, and E. D. Gupton; issued December 5, 1961; SRDB Ref ID: 8573 

Quist, 2000, A History of Classified Activities at Oak Ridge National Laboratory, ORCA-7; Arvin S. 

Quist; September 29, 2000; SRDB Ref ID: 32028 

Visner, 1957, Low-Power Criticality Experiments on the Homogeneous Reactor Experiment, W-7405-

eng-26; S. Visner and P. M. Wood; March 15, 1957; SRDB Ref ID: 103846 

Watts, 1995, Oak Ridge National Laboratory Internal Dosimetry Group In Vivo Monitoring Technical 

Basis Document, Rev. 0; J. R. Watts, J. M. Barber, J. A. Biggerstaff, and G. R. Rao; August 30, 1995; 

SRDB Ref ID: 11500 

Weekly Report, Aug 28, 1948, Report for Radiation Survey-Monitoring Section, Week Ending August 

28, 1948, Oak Ridge National Laboratory; August 31, 1948; SRDB Ref ID: 116276 

Weekly Report, Sep 12, 1948, Report for Radiation Survey-Monitoring Section, Week Ending 

September 28, 1948, Oak Ridge National Laboratory; September 14, 1948; SRDB Ref ID: 116277 

Weekly Report, Oct 17, 1948, Report for Radiation Survey-Monitoring Section, Week Ending October 

17, 1948, Oak Ridge National Laboratory; October 19, 1948; SRDB Ref ID: 116212 

Weekly Report, Nov 14, 1948, Report for Radiation Survey-Monitoring Section, Week Ending 

November 14, 1948, Oak Ridge National Laboratory; November 16, 1948; SRDB Ref ID: 116215 
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Weekly Report, Nov 28, 1948, Report for Radiation Survey-Monitoring Section, Week Ending 

November 28, 1948, Oak Ridge National Laboratory; November 30, 1948; SRDB Ref ID: 116219 

Weekly Report, Dec 12, 1948, Report for Radiation Survey-Monitoring Section, Week Ending 

December 12, 1948, Oak Ridge National Laboratory; December 14, 1948; SRDB Ref ID: 116278 

Weekly Report, Jan 16, 1949, Report for Radiation Survey-Monitoring Section, Week Ending January 

16, 1949, Oak Ridge National Laboratory; January 18, 1949; SRDB Ref ID: 116252 

Weekly Report, Feb 6, 1949, Report for Radiation Survey-Monitoring Section, Week Ending February 

6, 1949, Oak Ridge National Laboratory; February 8, 1949; SRDB Ref ID: 116255 

Weekly Report, Mar 27, 1949, Report for Radiation Survey-Monitoring Section, Week Ending March 

27, 1949, Oak Ridge National Laboratory; March 29, 1949; SRDB Ref ID: 116262 

Weeks, 1945, Beta Calibration of Film Meters, correspondence to K. Z. Morgan; L. H. Weeks; 

February 9, 1945; SRDB Ref ID: 13812 

Whitaker, 1945, Plutonium in Urine Samples, correspondence to Mr. Russell; M. D. Whitaker; April 

30, 1945; SRDB Ref ID: 114318 

Wilcox, 1997, An Overview of the History of Y-12; compiled by Wm. Jr. with a number of Y-12 

alumni; compiled 1997 and published April 1999; SRDB Ref ID: 8358 

Wirth, 1945a, Present Status of Relationship of Analyses of Plutonium in Urine to the Plutonium 

Hazard, correspondence; J. E. Wirth; May 28, 1945; SRDB Ref ID: 22936 

Wirth, 1945b, Request for Construction of a Laboratory for Analysis of Product in Urine, 

correspondence to M. D. Whitaker; J. E. Wirth; June 28, 1945; SRDB Ref ID: 114363 

Wirth, 1945c, Tolerance Values for Neutrons, Fast and Slow, correspondence to J. J. Nickson; J. E. 

Wirth; January 9, 1945; SRDB Ref ID: 13791 

Wirth, 1946, General Rules and Procedures Concerning Activity Hazards; J. E. Wirth; declassified 

August 20, 1946; SRDB Ref ID: 79654 
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Attachment 1: Data Capture Synopsis 

Table A1-1: Data Capture Synopsis for ORNL (X-10)

Data Capture Information General Description of Documents Captured Date 

Completed

Uploaded

To SRDB

Primary Site/Company Name: Oak Ridge National 

Laboratory (ORNL); DOE 1943-Present

Alternate Site Names: 

Clinton Laboratories

Holifield National Laboratory 

Operating Contractor Names: 

E.I. DuPont for the University of Chicago

Monsanto Chemical Company

Carbide & Carbon Chemicals Company

Union Carbide Corporation

Martin Marietta

Lockheed Martin

UT-Battelle 

Physical Size of the Site: 4470 Acres, 150 Buildings in 

1943. By 1951 there were approximately 270 numbered 

facilities, including buildings and ancillary structures, such 

as stacks.

Site Population: World War II Era: 1513 Employees

Currently: Approximately 4600 Employees 

 

Medical records, nuclear accident dosimetry, health physics periodic 

reports, film badge data, personnel monitoring for fast neutrons, 

building lists, hot run reports, health and safety reports, dust studies, 

radiation surveys including neutron surveys, urinalysis results, 

remediation reports, site and division histories, incident investigations, 

operational reports, exposure reports, division reports, isotope 

production in the 86 inch cyclotron, isotope inventories, Aircraft 

Nuclear Propulsion reports, site vicinity environmental reports, waste 

disposal reports, activity hazard reports, personnel contamination 

reports, bioassay reports, reactor reports, airborne radioactivity and air 

monitoring reports, Health Department reports, bioassay methods 

reports, and neutron dosimetry reports. NOTE: NIOSH and the ORAU 

Team are awaiting the release of additional Central Files (CF) reports 

which are being scanned at ORNL, Monsanto (MON) reports being 

scanned at ORNL, an index of radiological survey reports, and title lists 

for reports by selected ORNL authors.

OPEN 1,448

State Contacted: NA NOTE: Contacting the state was not considered necessary since ORNL 

is an active DOE site and cooperated with relevant data collection.

12/08/2011 0

Ames Laboratory Reference to shipments of uranium from the Ames Laboratory to 

ORNL.

10/18/2005 1

Argonne National Laboratory - East Material transfers to ORNL, ORNL's use of vacuums in Pu 

decontamination, reactor planning meeting minutes, promethium 

incident reports, radiation hazard meetings, clearance procedures, 

investigation reports, and urinalysis records.

07/06/2012 11

Auxier and Associates Health physics manuals. 05/14/2004 3
SEC-00189 08-15-12 ORNL (X-10) 

118 of 131

Table A1-1: Data Capture Synopsis for ORNL (X-10)

Data Capture Information General Description of Documents Captured Date 

Completed

Uploaded

To SRDB

Battelle Memorial Institute, King Avenue Battelle's procurement of thorium for ORNL and ORNL's performance 

evaluation of Battelle's bioassay program.

09/30/2011 2

Brookhaven National Laboratory Environmental monitoring, ORNL's providing radioisotopes for cancer 

research, the 1992 DOE annual exposure report, waste disposal reports, 

1947 AEC rules concerning radiation hazards, progress in implementing 

the DOE Radcon Manual, ambient air monitoring facilities at DOE 

facilities, a comparison of exposures at DOE accelerators, and BNL's 

intention to perform dosimetry intercomparisons with ORNL.

11/18/2008 12

Cincinnati Public Library Manhattan Engineer District (MED) and Atomic Energy Commission 

(AEC) histories, an internal dosimetry article, an automatic beta 

spectrometer, and 1955 ORNL radiation control action levels. 

12/06/2011 9

Claimant Provided A waste pond incident dose reconstruction, a waste solution 

contamination incident dose reconstruction, a FOIA request, and 

documents provided by a Linde Ceramics Plant claimant. 

01/31/2011 6

Colorado Mesa University Tomlinson Library The decontamination of the ORNL Thorex Pilot Plant and uranium 

extraction from Dakota lignites. 

04/19/2011 2

Curtiss-Wright, Cheswick, PA An ORNL individual exposure history report. 04/29/2009 1

Department of Labor / Paragon ORNL remedial action documents and surveys from New York sites, a 

thorium slug report, a complex-wide low-level mixed waste report, and 

the Li(B) ingot preparation report.

01/23/2012 33

DOE The definition of weapons-usable U-233. 06/18/2008 1

DOE Albuquerque Operations Office The hazard level classifications of nonreactor nuclear facilities. 04/15/2010 1

DOE Environmental Measurements Laboratory Development of urinalysis to estimate uranium body burden, 

occupational exposures to airborne uranium at feed materials facilities, 

and a discussion of criticality alarms.

01/21/2011 4

DOE Germantown Excerpts from the Manhattan District history, a thoria report, U-233 

recovery and supply reports, uranium recovery from phosphoric acid, a 

beryllium history, and meeting reports.

03/07/2011 17

DOE Legacy Management - Grand Junction Office ORNL remedial action reports and surveys from various sites, 

electromagnetic separation of isotopes, analysis and handling of 

radioactive scrap, Oak Ridge area environmental surveys, disposition of 

Aircraft Nuclear Propulsion Project equipment, Elza Gate surveys and 

remedial action documents, division reports, material transfers, bioassay 

records, tritium work for the Savannah River Site, jacketing of slugs, 

uranium handling rules, a U-233 status report, thorium reports, an 

ORNL subcontractor list, and budget reviews. 

08/30/2011 167
SEC-00189 08-15-12 ORNL (X-10) 

119 of 131

Table A1-1: Data Capture Synopsis for ORNL (X-10)

Data Capture Information General Description of Documents Captured Date 

Completed

Uploaded

To SRDB

DOE Legacy Management - Morgantown Environmental reports, Fernald material transfers and thorium work, 

recycled uranium processing, thorium processing, a 1950 study of 

uranium in urine of ORNL personnel, appraisals of ORNL's 

occupational medicine program, and Pu-242 tracer data. 

12/01/2011 71

DOE Legacy Management - MoundView (Fernald 

Holdings, includes Fernald Legal Database)

Mound reports from Monsanto's tenure as the ORNL operating 

contractor, epidemiology studies, ORNL summaries of occurrence 

reports, trip reports, conference reports, material transfers, thorium 

research, permissible polonium concentrations, criticality dosimetry, 

material control documents, and a 1947 neutron film badge report.

05/13/2010 71

DOE Legacy Management - Westminster Office The 1987 preliminary environmental survey report which identifies 

ORNL as performing sampling and analysis in support of the survey.

03/15/2012 1

DOE Oak Ridge Operations Office 1952 Building 3019 radiation reports, 1955 Thorex Pilot Plant radiation 

exposure report, Tiger Team reports, industrial hygiene reports, 

dosimetry reports, uranium and plutonium urine controls, environmental 

reports, and dosimetry records of 16 former ORNL workers.

07/13/2012 47

DOE Oak Ridge Operations Office Public Reading Room Material accountability reports and thorium processing. 04/08/2011 10

DOE Oak Ridge Operations Records Holding Task Group Organizational charts, building lists, film badge reports, researchers 

notes, progress reports, material requirements and transfers, Np-237 

processing, thorium processing reports, 1945 urine analyses, and 

ORNL's transuranic capabilities. 

04/05/2011 53

DOE Office of Scientific and Technical Information 

(OSTI)

Progress reports, trip reports, histories, film badge studies, thyroid 

counts, maps with building numbers, personnel monitoring records, 

neutron film calibration, air sample analyses, health physics reports, 

health physics instruments, environmental reports, source term data, 

urinalysis results, health physics facility appraisals, meeting minutes, 

diagnostic x-ray equipment, incident reports, procedures, film badge 

calibrations, reactor studies, pocket dosimeter logs, and ambient air 

sample results.

03/19/2012 600

[Name redacted] Report from the 1985 workshop on radiobiological effectiveness of 

neutrons.

08/13/2003 1

Federal Records Center (FRC) - Atlanta 1949 film badge data, film badge issue record, fallout monitoring, hood 

effluent contamination, treatment and disposal of waste liquors, tritium

information, and 1951 revision of building names and numbers. 

02/26/2007 14

Federal Records Center (FRC) - Chicago Aircraft Nuclear Propulsion Project personnel exposures and ORNL 

inspections of ANP work areas.

09/30/2008 4
SEC-00189 08-15-12 ORNL (X-10) 

120 of 131

Table A1-1: Data Capture Synopsis for ORNL (X-10)

Data Capture Information General Description of Documents Captured Date 

Completed

Uploaded

To SRDB

Federal Records Center (FRC) - Dayton Health Physics Division reports, radiological characterizations, site 

map, spent fuel surveys, waste disposal report, and personnel exposure 

data.

03/20/2006 14

Federal Records Center (FRC) - Denver Photodosimetry Evaluation Book Volume IV, Pu-244 recovery at 

Savannah River Site, and ORNL's revision to downblending monitoring 

equipment installation issues.

02/01/2012 3

Federal Records Center (FRC) - Kansas City Personnel exposure reports. 03/06/2009 3

Federal Records Center (FRC) - San Bruno 1946 radioactive materials rules and procedures, accelerator hazards, air 

sampling equipment and procedures, fuels and materials development 

programs, and corrective action plan for tritium facilities.

01/31/2006 5

Feed Materials Production Center (FMPC) Th-230 content of thorium inventories, ORNL summaries of occurrence 

reports, and trip reports.

03/14/2007 6

Feed Materials Production Center (FMPC) / SC&A Description of the 1968 Oak Ridge mobile in vivo laboratory. 06/26/2003 1

General Electric, Evendale, OH An affidavit documenting material transfers from General Electric, 

Evendale to ORNL.

09/24/2010 1

General Electric, Vallecitos, CA A summary of neutron dosimetry intercomparison studies. 05/18/2007 1

Hagley Museum and Library Trip reports, criticality incident report, history of Clinton Engineer 

Works, loading of L Reactor with enriched slugs, and Hanford histories 

with ORNL references. 

10/01/2010 38

Hanford Hanford reports mentioning material transfers to and from ORNL and 

ORNL trips and visitors, Y-12 health physics reports, an ORNL 

contamination scoping survey, evaluations of internal exposures, 

historical radionuclide release from Oak Ridge Operations Office 

facilities, material transfers and accountability, Np-237 recovery 

studies, and thorium fuel processing studies.

01/25/2012 88

Idaho National Laboratory (INL) ORNL's supplying U3O8 for the BORAX IV Reactor, ORNL's 

development of INL's ICPP processes, and report of an ORNL tritium 

release.

04/04/2012 3

Indiana Department of Homeland Security Report of an ORNL survey of the Joslyn Manufacturing and Supply 

site.

07/05/2012 1

Interlibrary Loan Environmental levels of radioactivity reports, a retrospective exposure 

assessment, the production of transuranium elements, thorium 

production, a nuclear criticality safety course, TLD studies, problems 

with using sphere ratios to determine albedo correction factors, and 

proceedings of the 1993 incineration conference.

05/29/2012 29

Internet ORNL's design of Operation Henre at the Nevada Test Site. 12/17/2007 1
SEC-00189 08-15-12 ORNL (X-10) 

121 of 131

Table A1-1: Data Capture Synopsis for ORNL (X-10)

Data Capture Information General Description of Documents Captured Date 

Completed

Uploaded

To SRDB

Internet - Defense Technical Information Center (DTIC) Neutron counting and dosimetry, radiation hazards, plutonium 

stabilization plans, fallout studies, Defense Nuclear Facilities Safety 

Board reports, reactor core physics, waste classification, and a shielding 

study of the Tower Shielding Facility.

07/20/2012 38

Internet - DOE DOE handbook for airborne releases and environmental assessment of 

the Building 3019 shutdown.

12/04/2008 2

Internet - DOE Comprehensive Epidemiologic Data 

Resource (CEDR)

No relevant documents identified. 12/05/2011 0

Internet - DOE Environmental Management Chapter 3 of Linking Legacies, radioactive wastes. 10/28/2007 1

Internet - DOE Legacy Management Considered Sites Elza Gate survey and report, a fuel materials report, irradiation of 

Bismuth-209 for the production of Polonium-210 at the Dayton Project, 

the ORNL survey of Bethlehem Steel, and Tonawanda area progress 

reports.

05/05/2012 8

Internet - DOE National Nuclear Security Administration 

(NNSA) - Nevada Site Office

No relevant documents identified. 02/17/2010 0

Internet - DOE OpenNet Human radiation studies and interviews, United States Transuranium 

Registry reports, AEC semiannual reports to Congress, progress reports, 

Advisory Committee for Biology and Medicine meeting minutes, 

environmental release reports, summary histories, Mound purchase 

order status reports, and a Mound site release package.

05/05/2012 49

Internet - DOE Office of Scientific and Technical 

Information (OSTI)

Thorium metallurgy report, remedial action reports, U-233 research, 

fuels research, and a dosimeter intercomparison at the Health Physics 

Research Reactor.

12/18/2009 22

Internet - DOE OSTI Energy Citations Environmental reports, thorium processing, decontamination proposals 

and reports, carbide fuel development, Cm-244 bioassay, and 

radioactive waste shipments.

04/24/2012 27

Internet - DOE OSTI Information Bridge Reports to Congress, waste inventory databases, fuels and materials 

reports, environmental reports, histories, lists of AEC isotope 

customers, radiation protection for the isochronous cyclotron, 

operational reports, research reports, thorium reports, division reports, 

fuel cycle conference proceedings, Pu-238 fuel reports, characterization 

of Cassini power source welds, and reactor reports.

06/28/2012 238

Internet - Environmental Protection Agency ORNL's 2006 user's guide to the dose and risk calculation software. 05/19/2008 1
SEC-00189 08-15-12 ORNL (X-10) 

122 of 131

Table A1-1: Data Capture Synopsis for ORNL (X-10)

Data Capture Information General Description of Documents Captured Date 

Completed

Uploaded

To SRDB

Internet - Google Decommissioning reports, operational reports, division reports, 

environmental reports, reports to Congress, trip reports, histories, lists 

of DOE radioisotope customers, epidemiological reports and public 

health assessments, waste stream reports, neutron dosimetry, accident 

investigation reports, descriptions of animal studies, and environmental 

remediation plans. 

06/09/2012 512

Internet - Hanford Declassified Document Retrieval System 

(DDRS)

Hanford reports mentioning material transfers to and from ORNL and 

ORNL trips and visitors.

09/01/2010 26

Internet - Health Physics Journal Design and dosimetry for an Sr-90-Y-90 irradiation facility, a 

radioiodine environmental model, report on an ORNL fast neutron 

survey meter, a review of emission sources, missing dose from the 

ORNL mortality study, and fast neutron spectra and dose rate 

calculations.

06/20/2012 6

Internet - Journal of Occupational and Environmental 

Hygiene

See Cincinnati Public Library and Interlibrary Loan. 12/05/2011 0

Internet - Massachusetts Department of Environmental 

Protection

A reference to ORNL's inspections and surveys at the Ventron site. 04/19/2012 1

Internet - National Academies Press (NAP) The 2005 National Research Council report on accelerating the 

treatment of radioactive wastes at DOE sites and an analysis of cancer 

risks in populations near nuclear facilities.

03/27/2012 2

Internet - NIOSH A report on beryllium contamination at covered facilities under 

EEOICPA and the Evaluation Report for Special Exposure Cohort 

petition SEC-00152.

01/09/2012 2

Internet - NRC Agencywide Document Access and 

Management (ADAMS) 

ORNL QA program, licensing correspondence, transuranic waste 

issues, spent fuel and radioactive waste inventories, weapons-usable 

waste storage reports, environmental impact statements, material 

transfer records, methods for estimating fugitive emissions, and NRC 

oversight of the DOE.

03/27/2012 52

Internet - ORNL Library Operations reports, division reports, histories, hazard evaluations and 

reports, electromagnetically enriched isotopes inventory reports, 

Aircraft Nuclear Propulsion Project reports, research reports, shielding 

reports, reactor handbooks and manuals, slug preparation, radiation 

surveys, reactor reports, instrument development, solvent extraction 

reports, neutron studies, Thorex Pilot Plant exposure analysis, and 

remedial action reports.

07/06/2012 636
SEC-00189 08-15-12 ORNL (X-10) 

123 of 131

Table A1-1: Data Capture Synopsis for ORNL (X-10)

Data Capture Information General Description of Documents Captured Date 

Completed

Uploaded

To SRDB

Internet - University of Hawaii, Manoa, Technical Report 

Archive and Image Library

An areal survey of ORNL and surrounding areas, and an evaluation of 

radiation protection afforded by typical Oak Ridge dwellings.

11/08/2007 2

Internet - US Army Corps of Engineers / FUSRAP A report referencing material transfers between ORNL and the Dayton 

Project. 

05/08/2012 1

Internet - US Transuranium and Uranium Registries No relevant documents identified. 02/17/2010 0

Lawrence Berkeley National Laboratory (LBNL) LBNL bioassay cards, post 1983. 05/23/2007 1

Lawrence Berkeley National Laboratory (LBNL) / SC&A LBNL's forecast for transuranium elements and epidemiological studies 

of Oak Ridge radiation workers.

07/22/2009 2

Lawrence Livermore National Laboratory (LLNL) Plutonium-beryllium source safety testing, a hazards control progress 

report, an Np-237 incident sample sent to ORNL, ORNL's 

intercomparison study including LLNL, and a DOE accelerator report. 

06/12/2009 5

Los Alamos National Laboratory (LANL) Excursions at the Critical Experiments Laboratory, waste disposal 

issues, disposal of weapons-usable material, material transfers to 

ORNL, special work permits, and americium oxide production.

03/09/2012 18

Los Alamos National Laboratory (LANL) / ORNL Human studies project compiled correspondence. 12/08/2007 1

Massachusetts Department of Public Health ORNL measurements of states' background radiation levels, ORNL 

responses to questions regarding Ventron, and ORNL's environmental 

assessment for Nuclear Metals' license renewal.

04/11/2012 4

Metals & Controls Corporation Confirmation that Metals & Controls supplied fuel elements to ORNL. 08/24/2004 1

Missouri Department of Natural Resources A plutonium storage working group report, interviews regarding 

material transfers, and St. Louis area environmental impact statements.

10/03/2008 4

Mound Museum Mound technical reports and newsletters referring to ORNL and the 

index to Mound Laboratory notebooks.

02/01/2012 23

National Archives and Records Administration (NARA) -

Atlanta

Dosimetry studies, dosimetry results and calibrations, incident 

investigations, radiation/contamination surveys, air sample results, 

thorium and U-233 reports, reactor operating safety limits, employee 

medical information, proposals for new labs, newspaper articles, 

progress reports, Aircraft Nuclear Propulsion Project reports, and 

Aircraft Reactor Experiment reports.

08/18/2011 191

National Archives and Records Administration (NARA) -

Atlanta / SC&A

Correspondence from 1955 on decontamination of gloves and a report 

of 14 cans of high-level scrap shipped from Pinellas to ORNL.

04/16/2004 2

National Archives and Records Administration (NARA) -

College Park

Tolerance levels, researchers notes, material balance report, sample 

analyses, Monsanto monthly reports, betatron records, and thorium 

research planning.

08/19/2010 33
SEC-00189 08-15-12 ORNL (X-10) 

124 of 131

Table A1-1: Data Capture Synopsis for ORNL (X-10)

Data Capture Information General Description of Documents Captured Date 

Completed

Uploaded

To SRDB

National Archives and Records Administration (NARA) -

Kansas City

Facility decontamination history, decommissioned facility survey 

program, 1977 listing of contaminated facilities, and TLD issue sheets 

and exposure reports.

07/16/2008 6

National Institute for Occupational Safety and Health 

(NIOSH)

Human radiation studies interviews, histories, organization charts, 

Worker Outreach meeting minutes and sign-in sheets, a listing for Oak 

Ridge in Sandia National Laboratories WebDose tables, research 

reactor reports, and health physics problems from thorium.

07/06/2012 43

National Institute for Occupational Safety and Health 

(NIOSH) / SC&A

Highly enriched uranium and plutonium working group reports. 02/16/2006 6

National Technical Information Service (NTIS) Progress reports on the feasibility study of correlating morbidity and 

mortality to occupational radiation exposure.

08/21/2006 2

Nevada Test Site The Nevada Test Site (NTS) Environmental Impact Statement which 

identifies ORNL as a generator of waste stored at NTS.

10/01/2003 3

New Jersey Department of Environmental Radiation ORNL remedial action documents and surveys from the Middlesex site. 01/30/2008 3

New York State Archives AEC Process Development minutes and reports from 1952-1954. 03/21/2012 2

Nuclear Regulatory Commission Public Document Room Transportation reports, waste disposal reports, stable cesium iodide 

chemistry, a trip report, ORNL reports for the NRC, and an evaluation 

of radionuclide geochemical information.

05/21/2012 14

Oak Ridge Gaseous Diffusion Plant (K-25) 1958 radiation protection training programs. 06/09/2005 1

Oak Ridge Institute for Science and Education Data validation for the Oak Ridge mortality study and chelation DTPA 

data for DOE employees.

08/06/2009 13

Oak Ridge Library for Dose Reconstruction Environmental reports, incident reports, radioactive material releases, 

waste disposal analyses and periodic reports, internal dosimetry 

methods and procedures, operations reports, reactor reports and 

descriptions, Health Physics Division reports, radioactive effluent 

reports, RALA reports, hazards evaluations, radiation dosimetry 

computer codes, assays of dissolver solutions, researcher notebooks, 

and 1946 air monitoring procedures.

08/15/2011 870

Oak Ridge Public Library Histories, photographs, public affairs articles, and procedures. 11/18/2010 10

ORAU Team Technical basis documents, annual DOE radiation exposure reports, 

incident reports, ORAU Team Technical Information Bulletins, 

documented communications, ORNL dosimetry procedures, instrument 

evaluation summaries, and an evaluation of electret ionization chambers 

for alpha surface contamination screening. 

07/10/2012 121
SEC-00189 08-15-12 ORNL (X-10) 

125 of 131

Table A1-1: Data Capture Synopsis for ORNL (X-10)

Data Capture Information General Description of Documents Captured Date 

Completed

Uploaded

To SRDB

Paducah Gaseous Diffusion Plant Radionuclide releases and reduction program, Np-237 contamination of 

magnesium fluoride, environmental reports, film badge calibrations, and 

the study of plutonium and fission products. 

10/06/2006 12

R. S. Landauer No relevant documents identified. 04/26/2012 0

Reactive Metals, Inc. A compilation of radionuclide releases from DOE facilities as of 1987. 08/17/2006 1

Rocky Flats Plant The 2003 Dose Reconstruction Project external dosimetry technical 

basis document.

09/24/2003 1

S. Cohen & Associates (SC&A) Progress reports, documents from BWXT Y-12, recycle uranium report, 

trip reports, and an interview.

08/14/2009 43

SC&A / Idaho National Laboratory (INL) Material transfer and accountability reports. 06/24/2010 109

SC&A / Los Alamos National Laboratory (LANL) A 1948 LANL progress report detailing RALA discussions with ORNL. 06/24/2010 1

SC&A / Santa Susana Field Laboratory A trip report from a 1967 tritium symposium. 06/24/2010 1

Sandia National Laboratories, New Mexico Bioassay and whole body count data, health physics reports, Ross 

Aviation shipments, and shielding analysis for the Sandia Engineering 

Reactor Facility.

01/26/2012 47

Santa Susana Field Laboratory A 1992 report questioning the adequacy of HEPA testing procedures at 

the High Flux Isotope Reactor.

12/19/2007 1

Savannah River Site Dosimetry visitor cards with ORNL personnel, irradiations performed 

for ORNL, classified reports receiving logs, thorium processing, SRS 

progress reports, decontamination of the ORNL Separations Pilot Plant, 

material disposal, and thorium and U-233 accountability data.

03/19/2012 103

Science Applications International Corp (SAIC) Radiation exposure summaries. 09/02/2004 9

Southern Illinois University, Edwardsville, IL A history of ORNL classified activities, the 1969 isotope user's guide, 

thorium operations, St. Louis area radiological activities, Oak Ridge site 

description, transcript of Day Two, and the fifty-sixth meeting of the 

ABRWH.

10/29/2008 14

United States Enrichment Corporation Radioactive waste threshold limit report review, an individual exposure 

history, and a U.S. Navy radioactive waste report.

10/06/2006 3

University of Colorado Norlin Library AEC/ERDA workshops on neutron dosimetry and a cost/benefit study 

of a formal safety program. 

04/10/2006 3

University of Iowa ORNL's 2000 radiological survey of the Iowa Ordnance Plant. 07/01/2003 1

University of Rochester Radiation Safety Unit Material transfers and neutron shielding for cyclotron targets. 09/26/2008 6

University of Tennessee Hodges Library Health Physics and Health Department reports, internal dosimetry 

studies, training program and reports, histories, K.Z. Morgan lectures 

and presentations, procedures, incident reports, notices to employees, 

bioassay analyses, and area and personnel monitoring reports.

10/11/2011 386
SEC-00189 08-15-12 ORNL (X-10) 

126 of 131

Table A1-1: Data Capture Synopsis for ORNL (X-10)

Data Capture Information General Description of Documents Captured Date 

Completed

Uploaded

To SRDB

Unknown Environmental program reports, site histories, procedures, health 

physics manual, radiation accident assessments, finding aids, a 

mortality study, environmental monitoring reports, contaminant 

releases, personnel monitoring procedures and reports, ORNL 

involvement with and surveys of other facilities, Health Physics 

Division reports, operational progress reports, personnel neutron 

dosimetry characterization, site surveys, site aerial survey, I-131 

releases, summary of radioactive releases, and the 1973 Mancuso 

report. 

02/10/2011 209

Westinghouse Site (United Nuclear Corporation), Hematite, 

MO

Material transfers, an ORNL citation regarding in vivo counting, and 

the ORNL Thorium Ceramics Data Manual.

04/09/2009 3

Wyeth Insurance An American Cyanamid article citing the development of the INL 

chemical recovery process at ORNL.

02/29/2008 1

Y-12 Neutron spectra and dosimetry, enriched uranium urinalysis procedures, 

Y-12 radiation protection standards, 86 inch cyclotron run sheets, and 

efficiency calibrations in the Mobile Body Counter.

03/30/2011 23

Y-12 / ORNL Plutonium, uranium, polonium, and tritium urinalysis reports, health 

physics reports, and high bioassay investigations.

05/14/2012 222

Y-12 / SC&A Medical examination reports, environmental data, radiation exposure 

data, and Y-12 specifications for recycle material transfers.

07/28/2010 4

TOTAL 6,992
SEC-00189 08-15-12 ORNL (X-10) 

127 of 131

Table A1-2: Databases Searched for ORNL (X-10)

Database/Source Keywords / Phrases Hits Selected

NOTE: Database search terms employed for each of the databases listed below are available in 

the Excel file called “Oak Ridge National Laboratory, Rev 01 (83.13) 07-30-12”

Defense Technical Information Center (DTIC)

https://www.dtic.mil/

COMPLETED 09/06/2011

See Note above 6,989 28

DOE CEDR

https://www.orau.gov/cedr

COMPLETED 12/05/2011

See Note above 57 1

DOE Hanford DDRS

http://www2.hanford.gov/declass/

COMPLETED 02/17/2010

See Note above 0 0

DOE NNSA - Nevada Site Office

www.nv.doe.gov/main/search.htm

COMPLETED 02/17/2010

See Note above 12,568 1

DOE OpenNet

http://www.osti.gov/opennet/advancedsearch.jsp

COMPLETED 08/20/2010

See Note above 5,676 5

DOE OSTI Energy Citations

http://www.osti.gov/energycitations/

COMPLETED 08/20/2010

See Note above 92 0

DOE OSTI Information Bridge

http://www.osti.gov/bridge/advancedsearch.jsp

COMPLETED 08/20/2010

See Note above 79,762 30

Google

http://www.google.com

COMPLETED 02/17/2010

See Note above 129,329,043 234

HP Journal

http://journals.lww.com/health-physics/pages/default.aspx

COMPLETED 12/05/2011

See Note above 613 6

Journal of Occupational and Environmental Health 

http://www.ijoeh.com/index.php/ijoeh

COMPLETED 12/05/2011

See Note above 7 2
SEC-00189 08-15-12 ORNL (X-10) 

128 of 131

Table A1-2: Databases Searched for ORNL (X-10)

Database/Source Keywords / Phrases Hits Selected

National Academies Press

http://www.nap.edu/

COMPLETED 02/17/2010

See Note above 513 0

NRC ADAMS Reading Room

http://www.nrc.gov/reading-rm/adams/web-based.html

COMPLETED 08/26/2010

See Note above 11,183 21

U.S. Transuranium & Uranium Registries 

http://www.ustur.wsu.edu/

COMPLETED 02/17/2010

See Note above 22 0

Table A1-3: DTIC Documents Requested for ORNL (X-10)

Document Number Document Title Requested

Date

Received

Date

ORNL-1277?

Ref ID: 13233

Nuclear Health Physics Dated 6/12/1952 12/02/2011 01/19/2012

ORNL-989 Biological Effects of Radiation Dated 8/10/1951 12/02/2011 NA - Could 

not locate

ORNL-66 Power Pile Division Quarterly Report For March, April, May 1948 

Dated 6/8/1948

12/02/2011 NA -

Cannot 

obtain; 

document is 

confidential
SEC-00189 08-15-12 ORNL (X-10) 

129 of 131

Table A1-4: Interlibrary Loan Documents Requested for ORNL (X-10)

Document Number Document Title Requested

Date

Received

Date

NA

Ref ID: 109315

Alpha-Gamma-Neutron Facilities papers presented at Hot Laboratory 

Symposium of the American Nuclear Society National Meeting, 

November 26-28, 1962

02/06/2012 02/06/2012

NA

Ref ID: 109320

Transuranium Elements papers presented at the American Nuclear 

Society National Meeting, June 18-21, 1962

02/06/2012 02/06/2012

NA 

Ref ID: 109318

Performance of Mechanical Equipment for Dejacketing Spent SRE 

Core 1 Fuel presented at the American Nuclear Society National 

Meeting, November 26-28, 1962

02/06/2012 02/06/2012

NA

Ref ID: 106142

Task- and Time-Dependent Weighting Factors in a Retrospective 

Exposure Assessment of Chemical Laboratory Workers; Journal of 

Occupational and Environmental Hygiene, 2007, Volume 4(2):71-79

12/05/2011 12/28/2011

NA

Ref ID: 104937

Action Levels for Radiation Control at Oak Ridge National Laboratory; 

American Industrial Hygiene Association Journal, 1965, Volume 

26(2):165-171

12/05/2011 12/06/2011

NA

Ref ID: 101466

The Application of External and Internal Radiation Exposure Limits 

from American Industrial Hygiene Association Quarterly Vol. 16:307-

323 Dated December 1955

08/29/2011 09/06/2011

NA

Ref ID: 100982

High Resolution Automatic Beta Spectrometer from Review of 

Scientific Instruments Vol. 26:959-962 Dated October 1955

08/29/2011 08/30/2011

NA

Ref ID: 100981

Developments in Internal Dose Determinations from Nucleonics Vol.

12(6):32-39 Dated June 1954

08/29/2011 08/30/2011

ORNL-547

Ref ID: 92980

Neutron Monitoring by Means of Nuclear Track Film (NTA) 02/25/2011 02/25/2011
SEC-00189 08-15-12 ORNL (X-10) 

130 of 131

Table A1-5: OSTI Documents Requested for ORNL (X-10)

Document Number Document Title Requested

Date

Received

Date

ORNL-3225 Preparation and Fabrication of ThO2 Fuels Dated June 5, 1962 by D. E. 

Ferguson, et al.

02/16/2012

ORNL-3385 Status and Progress Report for Thorium Fuel Cycle Development for 

Period Ending December 1962 dated June 1963 by D. E. Ferguson, et 

al.

02/16/2012

ORNL-390

Ref ID: 105444

Activation Analysis of the Rare Earths Dated 11/30/1949 12/02/2011 12/12/2011

ORNL-1155

Ref ID: 105442

Monitoring of Liquids for Radioactivity Dated 3/11/1952 12/02/2011 12/12/2011

AECD-2996, ORNL-732

Ref ID: 105443

Decontamination And Corrosion Resistance Properties Of Selected 

Laboratory Surfaces Dated January 1951

12/02/2011 12/12/2011

CF-51-3-78(Del)

Ref ID: 110829

A Survey of Homogeneous Reactor Chemical Processing 11/22/2011 06/01/2012

ORNL/TM-6429

Ref ID: 109997

Alternate Fuel Cycle Technologies/Thorium Fuel Cycle Technology 

Programs. Quarterly Report for Period 1 April--30 June 1978

11/22/2011 03/09/2012

DOE/HTGR-86-062; ORNL/TM-10056

Ref ID: 110827

Application of ENDF Data to the AVR Reactor with Highly Enriched 

Uranium Fuel and Thorium Feed

11/22/2011 03/26/2012

ORNL/TM-7089

Ref ID: 110001

Consolidated Fuel Reprocessing Program. Progress Report, July 1-

September 30, 1979

11/22/2011 03/09/2012

ORNL/TM-7536

Ref ID: 110813

Evaluation of Alternate Extractants to Tributyl Phosphate. Phase I 11/22/2011 03/26/2012

ORNL/TM-6953

Ref ID: 110825

Summary of the Radiological Assessment of the Fuel Cycle for a 

Thorium-Uranium Carbide-Fueled Fast Breeder Reactor

11/22/2011 03/26/2012

ORNL/TM-7108

Ref ID: 110002

Thorex Solvent Extraction Studies with Irradiated HTGR Fuel: Series I 11/22/2011 03/09/2012

ORNL/TM-6719

Ref ID: 110000

Consolidated Fuel Reprocessing Program. Progress Report, October 1--

December 31, 1978

11/22/2011 03/09/2012

ORNL-4278

Ref ID: 94817

Safety Analysis for the Thorium-Uranium Recycle Facility 11/22/2011 11/29/2011

ORNL/TM-12720

Ref ID: 22706

Historical and Programmatic Overview of Building 3019 11/22/2011 11/29/2011
SEC-00189 08-15-12 ORNL (X-10) 

131 of 131

Table A1-5: OSTI Documents Requested for ORNL (X-10)

Document Number Document Title Requested

Date

Received

Date

AECU-817

Ref ID: 77415

Lecture Notes Health Physics Training Lectures, 1948-1949 11/30/2009 12/18/2009

ORNL-TM-2334

Ref ID: 77086

Radiation Survey and Dosimeter Intercomparison Study at the Health 

Physics Research Reactor, 1968

8/18/2009 10/06/2009