ORAU TEAM

Dose Reconstruction

Project for NIOSH

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

Page 1 of 55

Document Title:

Site Profile for the Lawrence Berkeley 

National Laboratory

Document Number: ORAUT-TKBS-0049

Revision: 00

Effective Date: 08/07/2006

Type of Document: TBD

Supersedes: None

Subject Experts: Paul A. Szalinski, Baynard Turpin, James E. Turner, James East, Elizabeth A. 

Langille, and Bill R. Thomas 

Document Owner

Approval: Signature on File Approval Date: 07/19/2006

Paul A. Szalinski, TBD Team Leader

Approval: Signature on File Approval Date: 07/19/2006

John M. Byrne, Task 3 Manager

Concurrence: Signature on File Concurrence Date: 07/19/2006

Edward F. Maher, Task 5 Manager

Concurrence: Signature on File Concurrence Date: 08/04/2006

Kate Kimpan, Project Director

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

James W. Neton, Associate Director for Science

 New Total Rewrite Revision Page Change

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

REVISION AND DISCARD / DESTROY ALL COPIES OF THE PRIOR REVISION.
Document No. ORAUT-TKBS-0049 Revision No. 00 Effective Date: 08/07/2006 Page 2 of 55

PUBLICATION RECORD

EFFECTIVE 

DATE

REVISION 

NUMBER DESCRIPTION

08/07/2006 00 New site profile for the Lawrence Berkeley National Laboratory. First 

approved issue. Training required: As determined by the Task 

Manager. Initiated by Paul A. Szalinski.
Document No. ORAUT-TKBS-0049 Revision No. 00 Effective Date: 08/07/2006 Page 3 of 55

TABLE OF CONTENTS

SECTION TITLE

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

PAGE

5

1.0 Introduction ..............................................................................................................................7

 1.1 Purpose ...........................................................................................................................8

 1.2 Scope...............................................................................................................................8

2.0 Site Description........................................................................................................................8

3.0 Occupational Medical Dose.................................................................................................... 18

4.0 Occupational Environmental Dose ......................................................................................... 20

5.0 Occupational Internal Dose.................................................................................................... 24

6.0 Occupational External Dose................................................................................................... 38

References ........................................................................................................................................42

Glossary ............................................................................................................................................50
Document No. ORAUT-TKBS-0049 Revision No. 00 Effective Date: 08/07/2006 Page 4 of 55

LIST OF TABLES

TABLE TITLE

2-1 Area information and parameters.............................................................................................

PAGE

9

2-2 Magnitude of activities by area............................................................................................... 11

3-1 Summary of parameters and organ doses for 14- by 17-in. PA chest 

radiography............................................................................................................................19

3-2 Maximum organ doses by year for 14- by 17-in. PA chest radiography.................................. 19

4-1 External gamma and neutron radiation................................................................................... 22

4-2 Maximum site-wide annual median intakes via inhalation....................................................... 22

5-1 Internal dose control program (in vitro) ................................................................................... 25

5-2 Sample type (in vitro) ............................................................................................................. 26

5-3 Internal dose control program (in vivo) ................................................................................... 27

5-4 Detection limits in-vitro ........................................................................................................... 28

5-5 Detection limits in-vivo ........................................................................................................... 31

5-6 Units codes and description of units....................................................................................... 32

5-7 Radionuclides and fraction activity by facility.......................................................................... 33

6-1 LBNL dosimeter type, period of use, exchange frequency, MDL, and 

potential annual missed dose................................................................................................. 39

6-2 Selection of beta and photon radiation energies and percentages ......................................... 39

6-3 Selection of neutron radiation energies and percentages....................................................... 40

6-4 Recorded dose practices........................................................................................................ 40

6-5 Interpretation of reported data................................................................................................ 40

6-6 Adjustments to recorded dose................................................................................................ 41

6-7 Bias and uncertainty...............................................................................................................41
Document No. ORAUT-TKBS-0049 Revision No. 00 Effective Date: 08/07/2006 Page 5 of 55

ACRONYMS AND ABBREVIATIONS

AEC U.S. Atomic Energy Commission

AMAD activity median aerodynamic diameter

ANL-E Argonne National Laboratory-East

Bq becquerel

Ci curie

d day

DOE U.S. Department of Energy

dpm disintegrations per minute

EEOICPA Energy Employees Occupational Illness Compensation Program Act of 2000

ESE entrance skin exposure

F fast (solubility rate)

ft foot

HILAC heavy-ion linear accelerator

hr hour

HVL half-value layer

ICRP International Commission on Radiological Protection

in. inch

keV kiloelectron-volt, 1,000 electron-volts

KPA kinetic phosphorescence analysis

L liter

LANL Los Alamos National Laboratory

LBL Lawrence Berkeley Laboratory

LBNL Lawrence Berkeley National Laboratory

LLNL Lawrence Livermore National Laboratory

LRL Lawrence Radiation Laboratory

LRL-B Lawrence Radiation Laboratory Berkeley

m meter

M moderate (solubility rate)

MDA minimum detectable amount

MDL minimum detection limit

MeV megaelectron-volt, 1 million electron-volts

MFP mixed fission products

min minute

mR milliroentgen

mrem millirem

nCi nanocurie

NIOSH National Institute for Occupational Safety and Health
Document No. ORAUT-TKBS-0049 Revision No. 00 Effective Date: 08/07/2006 Page 6 of 55

pCi picocurie

PHA pulse height analysis

POC probability of causation

S slow (solubility rate)

TLD thermoluminescent dosimeter

U.S.C. United States Code

WB whole-body

WBC whole-body count

yr year

μm micrometer

§ section, sections
Document No. ORAUT-TKBS-0049 Revision No. 00 Effective Date: 08/07/2006 Page 7 of 55

1.0

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

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

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

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

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

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

INTRODUCTION

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

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

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

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

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

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

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

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

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

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

facility encompassed by EEOICPA.

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

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

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

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

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

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

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

determined in accordance with the POC [probability of causation[1]] guidelines established under 

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

derived:

• Radiation from naturally occurring radon present in conventional structures

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

[1] The U.S. Department of Labor is ultimately responsible under the EEOICPA for determining the POC.
Document No. ORAUT-TKBS-0049 Revision No. 00 Effective Date: 08/07/2006 Page 8 of 55

1.1 PURPOSE

This site profile provides technical basis information to be used to evaluate the total occupational 

radiation dose that can reasonably be associated with a worker’s radiation exposure at Lawrence 

Berkeley National Laboratory (LBNL). This dose results from exposure to external and internal 

radiation sources in LBNL facilities, to X-ray examinations performed for medical screening, and to 

onsite environmental releases. This site profile includes methods for estimating doses that could

have occurred while an employee was not monitored or was inadequately monitored as well as doses

that were missed due to analytical detection limits or incomplete or missing monitoring records (i.e., 

missed dose). 

This Site Profile can be a tool when performing dose reconstructions for LBNL workers. The 

Integrated Modules for Bioassay Analysis (IMBA) computer code is a tool useful for internal dose 

calculations. Information on measurement uncertainties is an integral component of the NIOSH

approach. This document describes how to evaluate uncertainty associated with LBNL exposure and 

dosimetry records

1.2 SCOPE

This site profile consists of a site description (Section 2.0), and discussions of occupational medical 

dose, occupational environmental dose, occupational internal dose, and occupational external dose

(Sections 3.0 to 6.0). 

2.0

This section describes major LBNL facilities and operations. LBNL was founded in 1931 on the 

University of California, Berkeley campus. It was originally known as the University of California 

Radiation Laboratory. In July 1945, LBNL moved from the Berkeley campus to a 134-acre site in the 

hills to the east. LBNL began defense work in 1941 when the National Defense Research Committee 

appointed Ernest O. Lawrence to study the potential military uses of 235U (Maroncelli and Karpin 

2002). Assignment of dose should begin in December 1941 when initial work enriching uranium with 

a cyclotron began.

SITE DESCRIPTION

LBNL is alternately referred to in reference documents as Berkeley Lab, Lawrence Radiation 

Laboratory (LRL), and Lawrence Radiation Laboratory, Berkeley (LRL-B). This document uses LBNL 

for consistency.

Table 2-1 provides a general description of LBNL buildings and lists the radionuclides of concern. 

From the 1950s to the present, the laboratory has maintained its status as a major international center 

for physics research and has diversified its research program into almost every realm of scientific 

investigation. Along with its historical specialty of accelerator research and nuclear physics, the 

laboratory currently maintains divisions that investigate astrophysics, nuclear fusion, earth sciences, 

genomics, health physics, computer science, materials science, environmental science, and other 

areas. In addition, the laboratory is the site of a number of National User Facilities, including the 

Advanced Light Source, the National Center for Electron Microscopy, the National Energy Research 

Scientific Computing Center, the Energy Sciences Network, and the future Molecular Foundry. 

Table 2-2 lists the quantities of the radionuclides that workers could have encountered by area. This 

list is not intended as a complete radiological history, but rather as a discussion to familiarize dose 

reconstructors with the variety of radionuclides that have been used at LBNL.
Document No. ORAUT-TKBS-0049 Revision No. 00 Effective Date: 08/07/2006 Page 9 of 55

Table 2-1. Area information and parameters.

a

Building(s) Description Period Radionuclides usedb

1 (on campus) Donner Laboratory 1931 H-3, C-14, P-32, P-33, Sr-90, I-125, Th-232, U-238

2 (on campus) Advanced Materials 

Laboratory & Center for 

X-ray Optics (Formerly 

the Crocker Laboratory)

1931 N-13, O-15

3 Laboratory of Chemical 

Biodynamics (Calvin 

Laboratory)

H-3, C-14, P-32, S-35, P-33

4 & 5 Magnetic Fusion Energy H-3, C-14, P-32, S-35

6, 9, 10, and 

80

Advanced Light Source 

(formerly the 184 in.

cyclotron complex)

1940 to 

present

Be-7, Co-57, Co-58, Co-60, Ni-63, Fe-55, Fe-59, Mn-54, 

Na-2,2 Zn-65, Am-241, Am-243, Cm-246, Cm-248, 

Np-237, Pu-238, Pu-239, Pu-240, U-235, Tc-99, Pu-242, 

Pu-241, N-13, O-15, Na-24, Ar-41, Ni-57, Th-232

8 (on campus) Hearst Laboratory Am-241, U

10 Cell & Molecular Biology 

Research & Photography

1986 H-3, C-14, P-32, S-35, Cr-51

14 Accelerator & Fusion 

Research & Earth 

Sciences

H-3 

16 Magnetic Fusion Energy 

Laboratory

U-234, U-235, U-238

19 (on 

campus)

LeConte Hall Fe-55, Fe-59, Co-60, Au-198, Au-199, Hg-203, Ga-67, 

In-112, Ba-127, Cs-127, Ba-131, Cs-131, Cs-137, Sr-90

22 (on 

campus)

Latimer Hall C-14

26/76 Medical Services and 

Bioassay, Radiation and 

Analytical Measurements 

Lab

I-125, I-129, I-131, U-238, C-11, C-14, Be-7, F-18, P-32, 

S-35, U-232, Sr-90 Ac-228, Ag-108, Ba-133, Ce-144, Cm243, Am-241, Am-243, Br-76, Br-77, Cm-244, Bk-249, Cf249, Cf-250, Cm-245, Cm-246

31 (on 

campus)

Hesse Court Depleted U

36 (on 

campus)

2232 Piedmont Sr-90, Am-241, Na-24, Cl-36, K-42

38 (on 

campus)

Lewis Hall Co-57, Fe-59, Co-60, Sn-119, Gd-153

50B Physics Ag-106m, Au-194, Co-56, Co-57, Co-58, Co-60, Mn-52, 

Mn-54, Na-22, Ni-57, Re-184m, Sc-48, Se-75, Ta-182, 

v-48, Zn-65m Be-7, Ag-105

51 Contains the Bevatron & 

Bevalac

Be-7, Co-57, Co-58, Co-60, Fe-55, Fe-59, Mn-54, Na-22, 

Ni-63, Zn-65, Na-24, Ni-57, Ni-57, Cf-252, U, Am-241, 

Am-243, Ra-226, Bk-249

52 Magnetic Fusion Energy 

Laboratory

H-3, C-14, P-32, S-35, Am-241, Cf-250, Cm-243, Cm-248, 

Np-237, Pu-239, Pu-244, Th-229, Th-230, th-232, U-232, 

U-235, U-236, U-238, Pu-242

53 SuperHILAC (heavy-ion 

linear accelerator) 

Development

55/56 Research 

Medicine/Radiation 

Biophysics, Biomedical 

Isotope Facility

1964 H-3, C-14, F-18, P-32, I-131, Sr-90, Xe-127, Nb-95, 

Ru-103, Gd-153, Tl-201, I-123, I-125, Sn-113, Tc-99m, 

Co-57, Cr-51, Nb-95, O-15, Cu-64, Ce-141, N-13, Sr-85, 

Sc-46, C-11, Co-55,

56 Biomedical Isotope 

Facility

C-11, Co-55, Co-57, F-18, N-13, O-15, O-14, F-17 
Document No. ORAUT-TKBS-0049 Revision No. 00 Effective Date: 08/07/2006 Page 10 of 55

Table 2-1 (Continued). Area information and parameters.

Building(s) Description Period Radionuclides useda

57 (on 

campus)

Donner Pavilion P-32, Sr-82, Sr-85, Sr-90, I-125, I-131, In-111

58 & 58A Accelerator Research & 

Development

60 High Bay laboratory

62 Materials and Chemical 

Sciences

U-238

63 & 64 Accelerator & Fusion 

Research

P-32

70 and 70A Nuclear, Materials, 

Chemical, Life, and Earth 

Sciences

H-3, C-14, P-32, Fe-59, I-125, Sr-90, Th-232, Tc-99, 

Ce-141, Ce-144, Pa-233, Sm-153, Te-153m, Yb-169, 

Zn-65, Sc-46, Na-22, Na-24, S-35, Ca-45, Ca-49, Mn-54, 

Fe-59, Y-90, Rh-101, Ru-106, Sb-124, Ce-141, Tm-170, 

Cs-134, Eu-152 , Am-243, Bi-207, Sc-49, Co-60, Zr-88, 

Rb-86, Zr-95, Sb-122, Ta-182, Tl-204, Th-229, Yb-175, 

Ho-166m, Hf-175, Ac-227, Pa-233, Am-241, Cm-244, U233, U-234, U-235, U-238, Pu-238, Pu-239, Ra-226, Np237, Cf-249, Cf-252, Tb-161, Cm-248

71 HILAC 1957 to 

December 

23, 1992

Sc-46, Sc-49, Sr-90, Zr-88, Y-90, Zr-95, Tc-99, Sb-124, 

Tb-161, Tm-170, Yb-175, Ta-182, Tl-204, Th-229, Th-232, 

U-233, U-234, U-235, U-238

72 Health Physics 1961 P-32, Na-24, Ti-44, Cr-51 Mn-54, Co-58, Fe-59, Co-60, 

Cu-64, Zn-65, Br-82, Nb-95, Zr-95, Zr-97, Cd-113, Sb-122, 

Sb-124, Ba-133, Xe-133, Eu-152, Ta-182, Hg-194, Au-198, 

Bi-207, Ac-227, Th-228, Th-229, Pa-231, Th-232, U-238

73 Atmospheric Aerosol 

Research

H-3 

74 Research 

Medicine/Radiation 

Biophysics, Cell & 

Molecular Biology

H-3, C-11, N-13, C-14, O-15, F-18, P-32, S-35, Sc-46, Fe59, Cu-64, Sr-85, Nb-95, Tc-99m, Ru-103, I-123, I-125, I131, Tl-201, Pb-210, Th-232, U-233, U-234/235, U-238, 

Pu-238, Am-241

75 Radioisotope Service & 

National Tritium Facility 

H-3, Sr-90, Th-232, Act. Products, C-11, C-14, F-18, I-125, 

I-129, I-131, P-32, S-35, Sr-90, U-232, Kr-81, Kr-85

75A Compact, Processing & 

Storage Facility

Th-232, Sr-90

76 C-11, C-14, F-18, I-125, I-129, I-131, P-32, S-35, Sr-90, U232, Am-241

84 H-3, C-14, P-32, S-35

85 Hazardous Waste 

Handling Facility

H-3, C-14, Sr-90, I-125, Th-232

88 88-in. Cyclotron Be-7, C-11, N-13, C-14, O-14, O-15, F-17, F-18, Na-21, 

Na-22, Na-24, P-32, S-35, Sc-46, Cr-51, Mn-54, Fe-55, 

Co-56, Co-57, Ni-57, Co-58, Fe-59, Co-60, Cu-60, Zn-62, 

Zn-63, Ni-63, Zn-65, Ge-71, Se-75, Br-76, Br-77, Kr-76, 

Kr-77, Kr-79, Y-88, Sr-90, Zr-95, Zr-97, U-238, Sc-93, Ac227, Am-241, Au-198, Cs-134, Cs-137, Gd-148, Eu-152, 

Eu-154, Pb-212, Np-237, Np-239, Th-229, Th-232, Pa233, Pu-238, Pu-239, Sb-124, Pa-231, Cf-249, Cf-252

934 Molecular and Cell 

Biology

H-3, P-32, S-35, C-14, I-125

977 Life Sciences and 

Physical Biosciences

H-3, P-32, P-33, S-35, C-14, Cd-109

a. Blank values indicate not applicable or data not available.

b. Particle size assumed as the default value of 5-μm activity median aerodynamic diameter (AMAD) because no site-specific data 

has been found.
Document No. ORAUT-TKBS-0049 Revision No. 00 Effective Date: 08/07/2006 Page 11 of 55

Table 2-2. Magnitude of activities by area. 

Building Radionuclides Activity (Ci)(a)

1, Room 159 K-42 0.001

F2-65 0.001

Zn-65 0.001

Sr-85 0.001

I-131 0.001

1, Room 212 Fe-59 0.001

1, Room 213 C-14 Trace

1, Room 216 C-14 0.005

P-32 0.03

Cr-51 0.01

Fe-55 0.01

Fe-59 0.01

Sr-90 0.02

Y-90 0.1

I-131 0.02

Hg-203 0.01

1, Room 227 P-32 0.05

I-131 0.25

1, Room 230 Ca-47 0.001

Zn-65 0.001

I-131 0.001

1, Room 261 P-32 0.5

I-131 0.001

1, Room 264 F-18 0.01

Fe-52 0.1

Ge-68 0.001

As-71 0.1

I-123 0.001

1, Room 271 Na-24 0.001

P-32 0.5

1, Room 308 C-14 0.005

1, Room 322 P-32 (b)

1, Room 326 P-32, P33 (b)

1, Room 330 H-3 Tracers

1, Room 361 P-32 (b)

1, Room 364 F-18 1 × 10-6

Fe-52 1 × 10-6

F2-59 1 × 10-6

Ga-68 1 × 10-6

As-71 1 × 10-6

I-131 1 × 10-6

Hg-203 1 × 10-6

1, Room 366 P-32, P33 (b)

1, Room 373 H-3, C-14, P-32, P33, S-35, I-125 (b)

1, Room 471 P-32 0.005

2, Room 101 & 

101A

Ca-45 Tracers

Sr-85 Tracers

Sr-90 Tracers

Am-241 Tracers

2, Room 102 Na-22 0.005

Ca-45 0.001

Sr-85 0.001

Sr-90 0.002

Eu-152/Eu-154 0.0015

Ac-227 0.003

Am-241 0.00015
Document No. ORAUT-TKBS-0049 Revision No. 00 Effective Date: 08/07/2006 Page 12 of 55

Table 2-2 (Continued). Magnitude of activities by area. 

Building Radionuclides Activity (Ci)(a)

2, Room 103 Ca-45 Tracers

2, Room 104 Sr-85 Tracers

2, Room 108 Sr-90 Tracers

2, Room 116 Am-241 Tracers

3, Room 120 C-14 0.01

3, 2nd floor lab H-3 5 × 10-6

C-14 5 × 10-6

P-32 5 × 10-6

3, Room 214 H-3 30

C-14 .05

varied Isotope storage

3, Room 250 C-14, P-32, P33, S-35 (a)

3, 3rd floor lab H-3 5 × 10-6

C-14 5 × 10-6

P-32 5 × 10-6

3, Room 318 H-3 Varied

C-14 0.03

P-32 Varied

3, Room 322 varied Calibration standards

3, Room 326 C-14 30

4 Cs-137 0.2 (July, 1963)(c)

5 Co-60 3,100 (1955) (c)

6 Am-241, Am-243, Cm-248, Eu-152, Eu-154, Np-237, Pu-239, Sr-90, 

Th-232, U-233, U(natural), U-235, U-238, Pu-241, Pu-242, Tc-99 

(b) 

8, Room 360 Am-241 0.0066

U 1 kg, various compounds

10 Cs-137 1,050 (1968) (c)

16, Room 101 U-234, U-235, U-238 (b)

19 (LeConte Hall) Co-60 0.02

19, Room 79 varied 0.01, experiment residues

Pb-197/Pb-209 1.5 (cyclotron target)

19, Room 81 varied 0.01, experiment residues

19, Room 86 Fe-55/Fe-59 1 (reactor capsule)

Ga-67 1.5 (cyclotron target)

In-112 2 (cyclotron target)

Ba-127/Cs-127 1.5 (cyclotron target)

Ba-131/Cs-131 24 (reactor capsule)

Au-198 1.5 (cyclotron target)

Au-199 1.5 (cyclotron target)

Hg-203 0.03

19, Room 405 Sr-90 0.001

Cs-137 0.001

22, Latimer Hall 

Room 710

C-14 Tracers

26, Rooms 6, 24, 

30, 31, and 32

Alpha, Am-241, Beta-Gamma, C-11, C-14, F-18, H-3, I-125, I-129, I131, P-32, S-35, U-232, Sr-90(b)

31, Hesse Court Depleted U 7 kg (gaseous conversion 

of UCl4 to UCl6

36, 2232 Piedmont

basement

Sr-90

Am-241

0.001

0.001

36, 2232 Piedmont

kitchen

Na-24

Cl-36

K-42

0.001

0.001

0.001

38, Lewis Hall Co-57/Co-60 0.02

Fe-59 0.025

Sn-119 0.0005

Gd-153 0.001
Document No. ORAUT-TKBS-0049 Revision No. 00 Effective Date: 08/07/2006 Page 13 of 55

Table 2-2 (Continued). Magnitude of activities by area. 

Building Radionuclides Activity (Ci)(a)

50 Ag-106m, Au-194, Co-56, Co-57, Co-58, Co-60, Mn-52, Mn-54, Na-22, 

Ni-57, Re-184m, Sc-48, Se-75, Ta-182, v-48, Zn-65m Be-7, Ag-105

(b)

50B, Room 6209 Ag-106m, Au-194, Co-56, Co-57, Co-58, Co-60, Mn-52, Mn-54, Na-22, 

Ni-57, Re-184m, Sc-48, Se-75, Ta-182, V-48, Zn-65, Be-7, Sc-46, Ag105

(b)

51 Be-7, Co-57, Co-58, Co-60, Fe-55, Fe-59, Mn-54, Na-22, Ni-63, Zn-65, 

Na-24, Ni-57, Ni-57, Cf-252, U, Am-241, Am-243, Ra-226, Bk-249

(b) 

52, Rooms 109 

and 111

Act Products, Am-241, Cf-250, Cm-243, Cm-248, Np-237, Pu-239, Pu244, Th-229, Th-230, Th-232, U-232, U-235, U-236, U-238, Pu-242(b) 

55 Sr-90 30 (spill - 1964) (c)

55, Room 116 H-3, C-14, Co-57, Cr-51, F-18, Gd-153, H-3, I-125, I-131, Nb-95, Ru103, Sn-113, Tc-99m, Tl-201 (b) 

55, Room 118 C-14, Co-57, Cr-51, F-18, Gd-153, H-3, I-125, I-131, Nb-95, Ru-103, 

Sn-113, Tc-99m, Tl-201 

(b)

55, Room 120 H-3, C-11, C-14, Co-55, Co-57, Ce-141, Cu-64, F-18, I-123, I-125, I131, N-13, Nb-95, O-15, Ru-103, Sr-85, Tc-99m, Gd-153, Tl-201, Sc-46 (b)

55, Room 122 H-3, C-11, C-14, F-18, Ce-141, Cu-64, F-18, I-123, I-125, I-131, N-13, 

Nb-95, O-15, Ru-103, Sr-85, Tc-99m, Tl-201, Sc-46

(b)

55, Room 126 H-3, C-11, C-14, F-18, Ce-141, Cu-64, F-18, I-123, I-125, I-131, N-13, 

Nb-95, O-15, Ru-103, Sr-85, Tc-99m, Tl-201, Sc-46

(b) 

55, Room 128 H-3, C-11, C-14, F-18, Ce-141, Cu-64, I-123, I-125, I-131, N-13, Nb-95, 

O-15, Ru-103, Sr-85, Tc-99m, Tl-201, Sc-46, Co-55, Co-57, I-123, I125, I-131, Tc-99m, I-125, Gd-153, Sn-113

(b)

55, Room 134 C-11, C-14, Co-55, Co-57, F-18, H-3, I-123, I-125, I-131, Tc-99m, N-13, 

O-15, O-14, F-17, Ce-141, Cu-64, Nb-95, Ru-103, Sr-85, Tl-201, Sc-46, 

Cr-51, Gd-153, H-3, Sn-113, Tl-201

(b)

55, Room 136 C-14, F-18, H-3, I-125 (b)

55, Room 139 C-11, C-14, Cr-51, Co-55, Co-57, F-18, H-3, I-123, I-125, I-131, Tc99m, Ce-141, Cu-64, N-13, Nb-95, O-15, Ru-103, Sr-85, Tl-201, Sc-46(b) 

55, Room 139A C-11, C-14, Co-55, Co-57, F-18, H-3, I-123, I-125, I-131, Tc-99m, Ce141, Cu-64, N-13, Nb-95, O-15, Ru-103, Sr-85, Tl-201, Sc-46(b)

55, Room 151 C-11, C-14, Co-55, Co-57, F-18, H-3, I-123, I-125, I-131, Tc-99m, N-13, 

O-15, O-14, F-17, Ce-141, Cu-64, Nb-95, Ru-103, Sr-85, Tl-201, Sc-46, 

Cr-51, Gd-153, H-3, Sn-113, Tl-201

(b)

55, Room 200 C-11, Ce-141, Cu-64, F-18, I-123, I-125, I-131, N-13, Nb-95, O-15, Ru103, Sr-85, Tc-99m, Tl-201, Sc-46(b) 

56, Room 100 C-11, Co-55, Co-57, F-18, N-13, O-15, O-14, F-17 (b)

56, Room 101 C-11, Co-55, Co-57, F-18, N-13, O-15, O-14, F-17 (b)

57, Cowell 

Hospital, 3rd floor

Y-90 1 

57, Cowell 

Hospital, 4th floor

I-125 0.01

57, Cowell 

Hospital, 4th floor

I-131 0.001

62, Rooms 114 

and 145

U-238

64, Room 234 P-32 (b)

69, Room 150 Various activation products (b)

70 Cm-242/Pu-238

70, Room 103 Ce-141, Ce-144, Fe-59, H-3, P-32, Pa-233, Sm-153, Te-125m, Yb-169, 

Zn-65, Sc-46

(b)

70, Room 108C Ce-141, Ce-144, Fe-59, H-3, P-32, Pa-233, Sm-153, Te-125m, Yb-169, 

Zn-65, Sc-46

(b)

70, Room 114 U-238 (b)

70, Room 114A U-238 (b)

70, Room 133 Ce-141, Ce-144, Fe-59, H-3, P-32, Pa-233, Sm-153, Te-125m, Yb-169, 

Zn-65, Sc-46

(b)
Document No. ORAUT-TKBS-0049 Revision No. 00 Effective Date: 08/07/2006 Page 14 of 55

Table 2-2 (Continued). Magnitude of activities by area. 

Building Radionuclides Activity (Ci)(a)

70, Room 147 Am-241, Cf-250, Cm-243, Cm-248, Np-237, Pu-239, Pu-244, Th-229, 

Th-230, Th-232, U-232, U-235, U-236, U-238, Pu-242

(b)

70, Room 147A Am-241, Am-243, Cf-249, Cm-243, Cm-245, Cm-246, Cm-248, Co-60, 

Eu-152, Eu-154, Eu-155, Ni-65, Np-237, Np-239, Pa-233, Pu-238, Pu239, Pu-240, Pu-244, Ra-226, Ru-106, Th-229, Th-230, Th-232, U-232, 

U-232, U-233, U-235, U-238, Tc-99, Pa-231, Pu-242, Cm-244, Cs-137, 

Ni-63, Pu-241, Sr-90, U-236, Bk-249, Cf-250, U-234, Es-254, P-32, Na21, Na-22, Co-57, Cu-60, Na-22, Ni-57, Sc-93, Zn-62, Zn-63, Ac-227, 

Au-198, C-11, Cf-249, Cf-252, Co-56, Co-57, Co-58, Cr-51, Cs-134, 

Cs-137, Fe-55, Fe-59, Mn-54, Sb-124, Se-75, Zn-65, Be-7, Sc-46, Pa231

(b)

70, Room 203 Am-241, Am-243, Bi-207, Cf-249, Cf-252, Cm-248, Er-165, Er-169, 

Er-171, Es-253, Eu-152, Fm-257, Hf-172, Hf-175, Hf-181, Ho-166, 

Ho-166m, Na-22, Nb-95, Np-237, Pu-238, Pu-239, Ra-226, Rh-101, 

Rh-102, Ta-182, Tb-160, Th-229, Tm-170, U-233, U-235, U-238, Y-90, 

Zr-88, Zr-95, Cm-244, Mn-54, Sr-90, Tl-204, Bk-249, Es-254

(b) 

70, Room 209 Am-241, Am-243, Bi-207, Cf-249, Cf-252, Cm-248, Er-165, Er-169, 

Er-171, Es-253, Eu-152, Fm-257, Hf-172, Hf-175, Hf-181, Ho-166, 

Ho-166m, Na-22, Nb-95, Np-237, Pu-238, Pu-239, Ra-226, Rh-101, 

Rh-102, Ta-182, Tb-160, Th-229, Tm-170, U-233, U-235, U-238, Y-90, 

Zr-88, Zr-95, Cm-244, Mn-54, Sr-90, Tl-204, Bk-249, Es-254

(b)

70, Room 210 Am-241, Am-243, Bi-207, Cf-249, Cf-252, Cm-248, Er-165, Er-169, 

Er-171, Es-253, Eu-152, Fm-257, Hf-172, Hf-175, Hf-181, Ho-166, 

Ho-166m, Na-22, Nb-95, Np-237, Pu-238, Pu-239, Ra-226, Rh-101, 

Rh-102, Ta-182, Tb-160, Th-229, Tm-170, U-233, U-235, U-238, Y-90, 

Zr-88, Zr-95, Cm-244, Mn-54, Sr-90, Tl-204, Bk-249, Es-254

(b)

70A Co-60 9,800 (July, 1965) (c)

70A, Room 1103 C-11, C-14, H-3, P-32 (b)

70A, Room 1115 C-11, C-14, P-32, P-33 (b)

70A, Room 117A C-11, H-3 (b)

70A, Room 1121A C-11, H-3 (b)

70A, Room 1121B C-11, H-3 (b)

70A, Room 1129 Co-60, Ni-63, Ni-65, Sr-90, Tc-99, Cs-137, Eu-152, Eu-154, Eu-155, 

Am-241, Am-243, Bk-249, Cf-249, Cm-243, Cm-244, Cm-245, Cm-246, 

Cm-248, Cf-249, Cf-250, f-252, Es-254, Np-237, Np-239, Pa-231, Pa233, Pu-238, Pu-239, Pu-240, Pu-241, Pu-242, Pu-244, Ra-226, Ru106, Th-229, Th-230, Th-232, U-232, U-233, U-234, U-235, U-236, U238

(b) 

70A, Room 1145 Co-60, Ni-63, Ni-65, Sr-90, Tc-99, Cs-137, Eu-152, Eu-154, Eu-155, 

Am-241, Am-243, Bk-249, Cf-249, Cf-250, Cf-252, Cm-243, Cm-244, 

Cm-245, Cm-246, Cm-248, Cf-249, Es-254, Np-237, Np-239, Pa-231, 

Pa-233, Pu-238, Pu-239, Pu-240, Pu-241, Pu-242, Pu-244, Ra-226, 

Ru-106, Th-229, Th-230, Th-232, U-232, U-233, U-234, U-235, U-236, 

U-238, U(natural)

(b)

70A, Room 1145A Am-241, Am-243, Cf-249, Cm-243, Cm-245, Cm-246, Cm-248, Co-60, 

Eu-152, Eu-154, Eu-155, Ni-65, Np-237, Np-239, Pa-233, Pu-238, Pu239, Pu-240, Pu-241, Pu-244, Ra-226, Ru-106, Th-229, Th-230, Th232, U-232, U-232, U-233, U-235, U-236, U-238, Tc-99, Pa-231, Pu242, Cm-244, Cs-137, Ni-63, Pu-241, Sr-90, Bk-249, Cf-250, U-234, 

Es-254

(b) 

70A, Room 1145B Am-241, Am-243, Cf-249, Cm-243, Cm-245, Cm-246, Cm-248, Co-60, 

Eu-152, Eu-154, Eu-155, Ni-65, Np-237, Np-239, Pa-233, Pu-238, Pu239, Pu-240, Pu-241, Pu-244, Ra-226, Ru-106, Th-229, Th-230, Th232, U-232, U-232, U-233, U-235, U-236, U-238, Tc-99, Pa-231, Pu242, Cm-244, Cs-137, Ni-63, Pu-241, Sr-90, Bk-249, Cf-250, U-234, 

Es-254

(b)
Document No. ORAUT-TKBS-0049 Revision No. 00 Effective Date: 08/07/2006 Page 15 of 55

Table 2-2 (Continued). Magnitude of activities by area. 

Building Radionuclides Activity (Ci)(a)

70A, Room 1149 Am-241, Am-243, Cf-249, Cm-243, Cm-245, Cm-246, Cm-248, Co-60, 

Eu-152, Eu-154, Eu-155, Ni-65, Np-237, Np-239, Pa-233, Pu-238, Pu239, Pu-240, Pu-241, Pu-244, Ra-226, Ru-106, Th-229, Th-230, Th232, U-232, U-232, U-233, U-235, U-236, U-238, Tc-99, Pa-231, Pu242, Cm-244, Cs-137, Ni-63, Pu-241, Sr-90, Bk-249, Cf-250, U-234, 

Es-254

(b)

70A, Room 1151 Am-241, Am-243, Cf-249, Cm-243, Cm-245, Cm-246, Cm-248, Co-60, 

Eu-152, Eu-154, Eu-155, Ni-65, Np-237, Np-239, Pa-233, Pu-238, Pu239, Pu-240, Pu-241, Pu-244, Ra-226, Ru-106, Th-229, Th-230, Th232, U-232, U-232, U-233, U-235, U-236, U-238, Tc-99, Pa-231, Pu242, Cm-244, Cs-137, Ni-63, Pu-241, Sr-90, Bk-249, Cf-250, U-234, 

Es-254

(b)

70A, Room 1159A Am-241, Am-243, Cf-249, Cm-243, Cm-245, Cm-246, Cm-248, Co-60, 

Eu-152, Eu-154, Eu-155, Ni-65, Np-237, Np-239, Pa-233, Pu-238, Pu239, Pu-240, Pu-241, Pu-244, Ra-226, Ru-106, Th-229, Th-230, Th232, U-232, U-232, U-233, U-235, U-236, U-238, Tc-99, Pa-231, Pu242, Cm-244, Cs-137, Ni-63, Pu-241, Sr-90, Bk-249, Cf-250, U-234, 

Es-254

(b)

70A, Room 1159B Am-241, Am-243, Cf-249, Cm-243, Cm-245, Cm-246, Cm-248, Co-60, 

Eu-152, Eu-154, Eu-155, Ni-65, Np-237, Np-239, Pa-233, Pu-238, Pu239, Pu-240, Pu-241, Pu-244, Ra-226, Ru-106, Th-229, Th-230, Th232, U-232, U-232, U-233, U-235, U-236, U-238, Tc-99, Pa-231, Pu242, Cm-244, Cs-137, Ni-63, Pu-241, Sr-90, Bk-249, Cf-250, U-234, 

Es-254

(b) 

70A, Room 1165 Am-241, Am-243, Cf-249, Cm-243, Cm-245, Cm-246, Cm-248, Co-60, 

Eu-152, Eu-154, Eu-155, Ni-65, Np-237, Np-239, Pa-233, Pu-238, Pu239, Pu-240, Pu-241, Pu-244, Ra-226, Ru-106, Th-229, Th-230, Th232, U-232, U-232, U-233, U-235, U-236, U-238, Tc-99, Pa-231, Pu242, Cm-244, Cs-137, Ni-63, Pu-241, Sr-90, Bk-249, Cf-250, U-234, 

Es-254

(b)

70A, Room 1165A Am-241, Am-243, Cf-249, Cm-243, Cm-245, Cm-246, Cm-248, Co-60, 

Eu-152, Eu-154, Eu-155, Ni-65, Np-237, Np-239, Pa-233, Pu-238, Pu239, Pu-240, Pu-241, Pu-244, Ra-226, Ru-106, Th-229, Th-230, Th232, U-232, U-232, U-233, U-235, U-236, U-238, Tc-99, Pa-231, Pu242, Cm-244, Cs-137, Ni-63, Pu-241, Sr-90, Bk-249, Cf-250, U-234, 

Es-254

(b) 

70A, Room 2211 Am-241, Am-243, Cf-249, Cm-243, Cm-245, Cm-246, Cm-248, Co-60, 

Eu-152, Eu-154, Eu-155, Ni-65, Np-237, Np-239, Pa-233, Pu-238, Pu239, Pu-240, Pu-241, Pu-244, Ra-226, Ru-106, Th-229, Th-230, Th232, U-232, U-232, U-233, U-235, U-236, U-238, Tc-99, Pa-231, Pu242, Cm-244, Cs-137, Ni-63, Pu-241, Sr-90, Bk-249, Cf-250, U-234, 

Es-254

(b)

70A, Room 2215 Am-241, Am-243, Cf-249, Cm-243, Cm-245, Cm-246, Cm-248, Co-60, 

Eu-152, Eu-154, Eu-155, Ni-65, Np-237, Np-239, Pa-233, Pu-238, Pu239, Pu-240, Pu-241, Pu-244, Ra-226, Ru-106, Th-229, Th-230, Th232, U-232, U-232, U-233, U-235, U-236, U-238, Tc-99, Pa-231, Pu242, Cm-244, Cs-137, Ni-63, Pu-241, Sr-90, Bk-249, Cf-250, U-234, 

Es-254

(b)

70A, Room 2217 Am-241, Am-243, Cf-249, Cm-243, Cm-245, Cm-246, Cm-248, Co-60, 

Eu-152, Eu-154, Eu-155, Ni-65, Np-237, Np-239, Pa-233, Pu-238, Pu239, Pu-240, Pu-241, Pu-244, Ra-226, Ru-106, Th-229, Th-230, Th232, U-232, U-232, U-233, U-235, U-236, U-238, Tc-99, Pa-231, Pu242, Cm-244, Cs-137, Ni-63, Pu-241, Sr-90, Bk-249, Cf-250, U-234, 

Es-254

(b) 
Document No. ORAUT-TKBS-0049 Revision No. 00 Effective Date: 08/07/2006 Page 16 of 55

Table 2-2 (Continued). Magnitude of activities by area. 

Building Radionuclides Activity (Ci)(a)

70A, Room 2217B Am-241, Am-243, Cf-249, Cm-243, Cm-245, Cm-246, Cm-248, Co-60, 

Eu-152, Eu-154, Eu-155, Ni-65, Np-237, Np-239, Pa-233, Pu-238, Pu239, Pu-240, Pu-241, Pu-244, Ra-226, Ru-106, Th-229, Th-230, Th232, U-232, U-232, U-233, U-235, U-236, U-238, Tc-99, Pa-231, Pu242, Cm-244, Cs-137, Ni-63, Pu-241, Sr-90, Bk-249, Cf-250, U-234, 

Es-254

(b)

70A, Room 2229A Am-241, C-14, Fe-59, Np-237, Pb-210, Pu-238, Th-232, U-233, U-238, 

U-234/235

(b)

70A, Room 2229B Am-241, C-14, Fe-59, Np-237, Pb-210, Pu-238, Th-232, U-233, U-238, 

U-234/235

(b) 

70A, Room 4419 Kr-81, Kr-85 (b)

70A, Room 4429 Pb-205, Th-229, Th-232, U-233, U-238 (b)

70A, Room 4429A Pb-205, Th-229, Th-232, U-233, U-238 (b)

70A, Room 4429C Pb-205, Th-229, Th-232, U-233, U-238 (b)

70A, Room 4459 Th-228, Th-230, U(natural), U-234, U-235, U-238, Tc-99 (b)

70A, Room 4463 Th-228, Th-230, U(natural), U-234, U-235, U-238, Tc-99 (b)

71, Cave B (b) (b)

71, Cave N (b) (b)

72, Room 102 U-238 (b)

72, Room 112A U-238 (b)

72, Room 128 P-32, Na-21, Na-22, P-32, Co-57, Cu-60, Na-22, Ni-57, P-32, Sc-93, 

Zn-62, Zn-63, Ac-227, Am-241, Au-198, C-11, Cf-249, Cf-252, Co-56, 

Co-57, Co-58, Co-60, Cr-51, Cs-134, Cs-137, Eu-152, Eu-154, Fe-55, 

Fe-59, Mn-54, Na-22, Np-237, Np-239, P-32, Pa-233, Pu-238, Pu-239, 

Sb-124, Se-75, Zn-65, Be-7, Sc-46, Pa-231

(b)

72, Room 137 P-32, Na-21, Na-22, P-32, Co-57, Cu-60, Na-22, Ni-57, P-32, Sc-93, 

Zn-62, Zn-63, Ac-227, Am-241, Au-198, C-11, Cf-249, Cf-252, Co-56, 

Co-57, Co-58, Co-60, Cr-51, Cs-134, Cs-137, Eu-152, Eu-154, Fe-55, 

Fe-59, Mn-54, Na-22, Np-237, Np-239, P-32, Pa-233, Pu-238, Pu-239, 

Sb-124, Se-75, Zn-65, Be-7, Sc-46, Pa-231

(b) 

72C, Rooms 155, 

163, 169, 171, and 

173

U-238 (b)

73, Room 109 H-3 (b)

74 Co-60/P-32/Cs-137 1,500 (1962 & 1968) (c)

74, Room 144A Th-232, U(natural), U-238, Tc-99 (b)

74, Room 2011 Am-241, C-14, Fe-59, Np-237, Pb-210, Pu-238, Th-232, U-233, U-238, 

U-234/235

(b)

74, Room 238C H-3, O-32, P35 (b)

74, Rooms 265 

and 265A

P-32 (b)

74, Room 285 C-11, Ce-141, Cu-64, F-18, I-123, I-125, I-131, N-13, Nb-95, O-15, Ru103, Sr-85, Tc-99m, Tl-201, Sc-46(b)

74, Room 312 C-11, C-14, H-3, P-32 (b)

74, Room 330 C-11, C-14, H-3, P-32 (b)

74, Room 330A C-11, C-14, H-3, P-32 (b)

74, Room 344 C-11, C-14, H-3, P-32 (b)

74, Room 350 C-11, C-14, H-3, P-32 (b)

74D, Room 1 C-11, Ce-141, Cu-64, F-18, I-123, I-125, I-131, N-13, Nb-95, O-15, Ru103, Sr-85, Tc-99m, Tl-201, Sc-46(b)

75 Cs-137 30 (March, 1967) (c)

75, Room 103, 107 

and Storage 

Locker

H-3 (b) 

75, Room 109 H-3, activation products (b)

75, Room 113 H-3, activation products (b)

75, Room 127 Alpha, Am-241, Beta-Gamma, C-11, C-14, F-18, H-3, I-125, I-129, I131, P-32, S-35, U-232, Sr-90(b)
Document No. ORAUT-TKBS-0049 Revision No. 00 Effective Date: 08/07/2006 Page 17 of 55

Table 2-2 (Continued). Magnitude of activities by area. 

Building Radionuclides Activity (Ci)(a)

75D, Room 101B Act Products, Various, Kr-81, Kr-85 (b)

76, Room 135 and 

Storage Locker

Am-241, C-11, C-14, F-18, H-3, I-125, I-129, I-131, P-32, S-35, U-232, 

Sr-90

(b) 

84. Room 101 P-32 (b)

84. Room 153 C-14, H-3, P-32 (b)

84. Room 155 H-3, P-32, S-35 (b)

84. Room 157 H-3, P-32, S-35 (b)

84. Room 161 H-3, P-32, S-35 (b)

84. Room 175 H-3, P-32, S-35 (b)

84. Room 201 P-32 (b)

84. Room 220 P-32 (b)

84. Room 263 P-32, C-14, H-3 (b)

85, Room MW1 Alpha, Beta-Gamma, C-14, H-3 (b)

85, Room MW2 Alpha, Beta-Gamma, C-14, H-3 (b)

85, Room MW3 Alpha, Beta-Gamma, C-14, H-3 (b)

85, Room MW4 Alpha, Beta-Gamma, C-14, H-3 (b)

85, Room MW5 Alpha, Beta-Gamma, C-14, H-3 (b)

85, Room MW6 Alpha, Beta-Gamma, C-14, H-3 (b)

85, Room MW7 Alpha, Beta-Gamma, C-14, H-3 (b)

85, Room MW8 Alpha, Beta-Gamma, C-14, H-3 (b)

85, Room RW1 Alpha, Beta-Gamma, C-14, H-3 (b)

85, Room RW2 Alpha, Beta-Gamma, C-14, H-3 (b)

85, Room 

Scintillation Vial 

Room

Alpha, Beta-Gamma, C-14, H-3 (b)

85, Room Staging 

Area

Alpha, Beta-Gamma, C-14, H-3 (b) 

88, Room 134 Ac-227, Act Products, Am-241, Cf-249, Cf-252, Gd-148, Pb-212, Th228, Th-229, Th-232, U(natural), mixed fission products (MFP), 

Various, Actinide Tracers, Gamma Tracers

(b) 

88, Room 135 H-3, C-11, N-13, Na-22, Be-7, O-14, Ne-19, Ne-18, Br-76, Br-77, Kr-76, 

Kr-77, Kr-79, P-32, Na-21, Na-22, P-32, Co-57, Cu-60, Na-22, Ni-57, P32, Sc-93, Zn-62, Zn-63, Ac-227, Am-241, Au-198, C-11, Cf-249, Cf252, Co-56, Co-57, Co-58, Co-60, Cr-51, Cs-134, Cs-137, Eu-152, 

Eu-154, Fe-55, Fe-59, Mn-54, Na-22, Np-237, Np-239, P-32, Pa-233, 

Pu-238, Pu-239, Sb-124, Se-75, Zn-65, Be-7, Sc-46, Pa-231

(b)

88, Cave 0 Be-7, C-11, C-14, F-17, F-18, N-13, Na-22, O-14, O-15, Br-76, Br-77, 

Kr-76, Kr-77, Kr-79, Ne-19, Ne-18 

(b)

88, Cave 1 C-11, N-13, Na-22, Be-7, O-14, Ne-19, Ne-18, Ac-227, Act Products, 

Am-241, Cf-249, Cf-252, Gd-148, Pb-212, Th-228, Th-229, Th-232, 

U(natural), MFP, Various, Actinide Tracers, Gamma Tracers

(b)

88, Cave 2 Ac-227, Act Products, Am-241, Cf-249, Cf-252, Gd-148, Pb-212, Th228, Th-229, Th-232, U(natural), MFP, Various, Actinide Tracers, 

Gamma Tracers

(b) 

88, Cave 3 H-3, C-11, C-14, P-32, P-33 (b)

88, Cave 4 H-3, C-11, C-14, P-32, P-33 (b)

88, Cave 4C Act Products, Be-7, C-11, C-14, F-17, F-18, N-13, Na-22, O-14, O-15 (b)

88, Cave 4C roof Ac-227, Act Products, Am-241, Cf-249, Cf-252, Gd-148, Pb-212, Th228, Th-229, Th-232, U(natural), MFP, Various, Actinide Tracers, 

Gamma Tracers

(b) 

88, Cave Roofs Act Products, Be-7, C-11, C-14, F-17, F-18, N-13, Na-22, O-14, O-15, 

Ne-19, Ne-18

(b)

88, East Alley Br-76, Br-77, Kr-76, Kr-77, Kr-79 (b)

88, East alley 

mezzanine

Br-76, Br-77, Kr-76, Kr-77, Kr-79, Ac-227, Act Products, Am-241, Cf249, Cf-252, Gd-148, Pb-212, Th-228, Th-229, Th-232, U(natural), 

MFP, Various, Actinide Tracers, Gamma Tracers

(b)
Document No. ORAUT-TKBS-0049 Revision No. 00 Effective Date: 08/07/2006 Page 18 of 55

Table 2-2 (Continued). Magnitude of activities by area. 

Building Radionuclides Activity (Ci)(a)

88, East alley niche C-11, N-13, Na-22, Be-7, O-14, Ne-19, Ne-18, Ac-227, Act Products, 

Am-241, Cf-249, Cf-252, Gd-148, Pb-212, Th-228, Th-229, Th-232, 

U(natural), MFP, Various, Actinide Tracers, Gamma Tracers

(b)

88, Entire Vault 

roof

Act Products, Be-7, C-11, C-14, F-17, F-18, N-13, Na-22, O-14, O-15, 

Br-76, Br-77, Kr-76, Kr-77, Kr-79

(b)

977, Room 205 H-3, P-32, P-33, S-35 (b)

977, Room 240 H-3, P-32, S-35 (b)

977, Room 285 C-14, Cd-109, H-3, P-32, S-35 (b)

a. Maximum quantity present in the building.

b. No quantity and/or isotope information available. 

c. Date used where indicated in the historical documents.

3.0

Table 3-1 gives the entrance skin exposure (ESE) and organ doses for PA chest radiography at 

different times at LBNL. For the early times through March 1975, the assigned doses are the default 

values given by (ORAUT 2005). Calculated doses for the later times are based on measurements of 

the ESE and other factors with the LBNL equipment. The earliest document found (de Castro and 

Thomas 1975) reports results from a survey of the Picker radiographic X-ray unit conducted on March 

19, 1975. The report states, “At a typical chest technique of 86 kV, 200 mA, large spot, 1/30 sec, 72 

inches [= 183 cm], the direct beam exposure was 7 mR”. Collimation is described as “satisfactory”, 

and the filtration is “assumed sufficient”. For the PA view, if one assumes a chest thickness of 26 cm 

and allows 5 cm for the thickness of the cassette, then the implied source-to-skin distance (SSD) is 

183 cm – 31 cm = 152 cm. It follows from the measurement that the skin-entrance exposure is (7 

mR)(183/152)2 = 10. mR. These data are consistent with subsequent survey results reported through 

1986 for this X-ray machine (de Castro 1977a, de Castro 1977b, Vaughan 1982, de Castro 1983, de 

Castro and Hill 1984, de Castro 1986). This unit was in use until its replacement by a new machine 

about September 28, 1987 (Bradfield 1987). The change was made to a Picker model BGX 625R 

stationary, general-purpose system, manufactured in 1987 (Thomas 1991, Bradfield-Montoya 1994). 

Based on available documents, these two Picker machines apparently served in succession for 

making medical X rays at LBNL, dating back to at least 1975. Chest x rays were discontinued at 

LBNL, and the second Picker machine was removed by about the end of 1993. No policy statements 

providing records of frequency were found. In the absence of other information, an annual 

frequency should be assumed. 

OCCUPATIONAL MEDICAL DOSE

Under an interagency agreement, the second Picker system was given a thorough inspection by the 

Food and Drug Administration (FDA) on February 23, 1989 (Goldstein 1989). All components were 

found to operate within applicable federal or manufacturer’s specifications. The measured exposure 

for a routine chest X ray was 11.2 mR with the technique of 300 mA at 84 kVp in the automatic 

exposure control mode. No significant problems were incurred in the operations. Regular control 

procedures were conducted to monitor performance over the years. Over time, the skin-entrance 

exposure measured in subsequent surveys remained close to 10 mR. Allowing a conservative factor 

of approximately two, the value ESE = 20 mR is used to estimate organ doses for all times after 

March 1975. 

In Table 3-2, the data from Table 3-1 are presented as the maximum organ doses in any calendar 

year. Following (ORAU 2005a), an uncertainty of ±30% at one sigma is estimated for an individual 

ESE or organ dose.
Document No. ORAUT-TKBS-0049 Revision No. 00 Effective Date: 08/07/2006 Page 19 of 55

Table 3-1. Summary of parameters and organ doses for 14- by 17-in. PA chest radiography.

a,b,c

Period Frequency Applicability

PA chest 

ESE (mR)

Organ doses (rem) from 14- by 17-in. PA chest radiography

Thyroid Ovaries Testes Lungs Breast Uterus

Bone 

marrow

Pre-1970 Unknown Unknown 200 3.48E-02 2.50E-02 5.00E-03 9.02E-02 9.80E-03 2.50E-02 1.84E-02

1970-3/75 Unknown Unknown 100 3.20E-03 1.00E-04 1.00E-06 4.51E-02 4.90E-03 1.30E-04 9.20E-03

4/75-1979 Unknown Unknown 20 6.40E-04 2.00E-05 2.00E-07 9.02E-03 9.80E-04 2.60E-05 1.84E-03

1980-1993 Unknown Unknown 20 1.56E-03 1.04E-04 2.00E-07 1.35E-02 2.32E-03 1.04E-04 3.56E-03

Period

Organ doses (rem) from 14- by 17-in. PA chest radiography

Eye/brain

Liver/gall 

bladder/spleen

Urinary 

bladder

Colon/ 

rectum Thymus Esophagus Stomach

Bone 

surface Remainder Skin

Pre-1970 6.40E-03 9.02E-02 2.50E-02 2.50E-02 9.02E-02 9.02E-02 9.02E-02 9.02E-02 9.02E-02 2.70E-01

1970-3/75 3.20E-03 4.51E-02 1.00E-04 1.00E-04 4.51E-02 4.51E-02 4.51E-02 4.51E-02 4.51E-02 1.35E-01

4/75-1979 6.40E-04 9.02E-03 2.00E-05 2.00E-05 9.02E-03 9.02E-03 9.02E-03 9.02E-03 9.02E-03 2.70E-02

1980-1993 1.56E-03 1.35E-02 1.04E-04 1.04E-04 1.35E-02 1.35E-02 1.35E-02 1.35E-02 1.35E-02 2.80E-02

a. Values for the pre-1970 and the 1970-3/1975 periods are taken from Table 6-5 of (ORAU 2005a). 

b. The default values (ORAUT 2005) for beam quality of 2.5 mm Al HVL prior to 1980 and 4.0 mm Al HVL for subsequent years are assumed.

c. No policy statement on LBNL frequency was found. In the absence of other information, the assumption of an annual frequency is reasonable.

Table 3-2. Maximum organ doses by year for 14- by 17-in. PA chest radiography. 

Year

Organ doses (rem) from 14- by 17-in. PA chest radiography

Maximum 

thyroid

Maximum 

ovaries

Maximum 

testes

Maximum 

lungs

Maximum 

breast

Maximum 

uterus

Maximum bone 

marrow

Maximum 

eye/brain

Pre-1970 3.48E-02 2.50E-02 5.00E-03 9.02E-02 9.80E-03 2.50E-02 1.84E-02 6.40E-03

1971-1975 3.20E-03 1.00E-04 1.00E-06 4.51E-02 4.90E-03 1.30E-04 9.20E-03 3.20E-03

1976-1979 6.40E-04 2.00E-05 2.00E-07 9.02E-03 9.80E-04 2.60E-05 1.84E-03 6.40E-04

1980-1993 1.56E-03 1.04E-04 2.00E-07 1.35E-02 2.32E-03 1.04E-04 3.56E-03 1.56E-03

Year

Organ doses (rem) from 14- by 17-in. PA chest radiography

Maximum 

liver/gall 

bladder/spleen

Maximum

urinary 

bladder

Maximum 

colon/rectum

Maximum 

thymus

Maximum 

esophagus

Maximum 

stomach

Maximum bone 

surface

Maximum 

remainder

Maximum 

skin

Pre-1970 9.02E-02 2.50E-02 2.50E-02 9.02E-02 9.02E-02 9.02E-02 9.02E-02 9.02E-02 2.70E-01

1970-1975 4.51E-02 1.00E-04 1.00E-04 4.51E-02 4.51E-02 4.51E-02 4.51E-02 4.51E-02 1.35E-01

1976-1979 9.02E-03 2.00E-05 2.00E-05 9.02E-03 9.02E-03 9.02E-03 9.02E-03 9.02E-03 2.70E-02

1980-1993 1.35E-02 1.04E-04 1.04E-04 1.35E-02 1.35E-02 1.35E-02 1.35E-02 1.35E-02 2.80E-02
Document No. ORAUT-TKBS-0049 Revision No. 00 Effective Date: 08/07/2006 Page 20 of 55

4.0

Occupational environmental dose results from releases or direct radiation as a result of facility 

operations. Inhalation of environmental radionuclides results in internal dose to the whole body or 

body organs. The site profile analysis determined the internal dose for workers outside the facilities 

from air concentrations from releases from stacks and individual buildings. Unmonitored workers 

could have been exposed to occupational doses internally from onsite releases to the air. 

OCCUPATIONAL ENVIRONMENTAL DOSE

The site profile preparers reviewed site environmental reports for data that would be useful in 

reconstructing ambient radiation levels. Ambient radiation dose rates include natural background 

radiation and sources at the facility. 

The laboratory used and created small amounts of radioactive material, created localized radiation 

areas with machines (X-ray machines and accelerators), and produced tritiated materials for wide 

distribution to other research facilities. Nuclear reactions were studied in the accelerators, which 

started on the site in the early 1930s as small devices (bench top) and progressed to large specially 

built buildings with controls and shielding. Workers and technicians who had access to the 

accelerators and experimental rooms had the highest risk and were therefore monitored for radiation 

exposure.

LBNL was involved in much of the discovery of the radiological properties of materials, and 

awareness of the hazards grew with each step in size and power of accelerator. Those working with 

the machines were monitored by state-of-the-art methods for internal and external dose. The LBNL 

hillside site is small. The distance from the accelerators to the maximum exposed member of the 

public was less than 1,500 m. Documentation of the site boundary impact began in the mid-1950s

and continues today.

Tritium was used in large quantities in the National Tritium Labeling Facility, which began operation in 

the early 1980s. Releases and doses to the personnel and public were well documented over the 

course of operations and continue today after shutdown. Potable water has always been supplied

from off the site by the local utility.

Methods of measuring deposition and air concentrations have varied over the years in terms of 

technique and locations. A cursory review shows long-term interest in fallout. Fallout and naturally 

occurring radioactive materials dominate any deposition from onsite releases and resuspension. 

Radionuclides were either created on the site or purchased, and the large variety created an 

extensively diverse source term. However, except for tritium and accelerator-induced byproducts, 

these nuclides were present only in small quantities needed for research. Laboratories at LBNL were 

some of the first to use hoods and airflow to control exposure to hazardous material.

Interviews with the dosimetry staff indicated that every monitored worker has a dosimetry file that is 

accessible today. Those who were not monitored would have been exposed to external radiation 

from outside the well-designed shield walls and from releases through ventilation systems. In 

addition, these facilities were always being improved and were operated on an intermittent schedule. 

Concepts of long-term steady-state exposure are not consistent with the nature of this facility.

Table 4-1 lists the maximum external gamma and neutron radiation measurements in millirem per 

year. There is not sufficient data available to provide measured uncertainty. The values reported in 

the table are those documented in the annual LBNL environmental reports. Early interest was the 
Document No. ORAUT-TKBS-0049 Revision No. 00 Effective Date: 08/07/2006 Page 21 of 55

maximum possible dose from surveys (usually during accelerator runs) and analysis. In later years 

with better monitoring, improved shielding and the development of ALARA policy, the reported doses 

fell dramatically. The annual average measurements, as opposed to the maximum values, were at 

50% of max or less. In order to generate the likely value and uncertainty, it would be reasonable to 

use 75% of the maximum value, and 25% of the maximum as the uncertainty as an estimate of 

unmonitored dose. Table 4-2 lists the maximum site-wide annual median intakes in Becquerel's per 

year via inhalation. Water supplies are offsite from East Bay Municipal Utility District, and no 

indication of soil contamination exceeding a background level has been found, so there would have 

been no doses from intakes from soil and drinking water. LBNL attributes gross alpha results to Th232 and gross beta results to Sr-90 for the purposes of dose calculation; these assumptions should 

be made here. Thorium as representative of naturally occurring alpha emitters. Strontium as 

representative of the beta component of fall out. By using these nuclides in the calculations, the 

resulting doses would not under estimate the actual doses.

Missing data is filled in with estimates as explained below and are based on the available maximum 

observed values gleaned from the annual environmental reports.

Alpha -- Reported alpha concentrations appear to be independent of operational effects of the lab and 

relatively constant over time. Therefore, a good representation of the alpha concentrations and intake 

is the average of all the measurements, which results in intake of 0.43 Bq per year.

Beta -- Principle contributor to the gross beta concentrations is fallout from atmospheric nuclear 

weapons testing. The later years of missing data were assigned a value of 10 Bq/y for gross beta 

intake. This represents a modest overestimate of the intake. The early years prior to 1961 were 

estimated to be reduced at a rate that would bring the intake in 1939 to values close to most recent 

observations. This would account for the gradual rise in beta due to weapons testing, and the effects 

(if any) of increased nuclide inventory on site, and increasing power of accelerators.

Tritium – Tritium releases, concentrations, and subsequent intake are related to accelerator and 

National Tritium Labeling Facility (NTLF) operations. Annual data are available from 1974 through 

2003. The value for 2004 (2500 Bq/y) was chosen to conform with the trend in the proceeding years 

and average ratio to C-14 (see C-14 discussion). The early years, prior to 1974, were trended down 

back to 1939 to values consistent with recent measurements which are the lowest values observed. 

The assumption that the site Tritium concentration before operations began, was no better than the 

lowest observed concentrations. This is consistent with the trend of accelerator development and to 

the operation of the NTLF.

Carbon-14 – C-14 releases, concentrations, and intakes are related to accelerator operations. The 

average ratio of C-14 to Tritium in the years both were reported is 0.155. When one data point is 

missing, this value is used to estimate the missing data in the later years. In years before 1974, a 

trend identical to the Tritium estimates was employed.

All estimates were limited to no more than two significant digits.
Document No. ORAUT-TKBS-0049 Revision No. 00 Effective Date: 08/07/2006 Page 22 of 55

Table 4-1. External gamma and neutron radiation.

a,b,c

Year 

Dose 

(mrem/yr) Reference

1959 810 Patterson (1962)

1960 650 Patterson (1962)

1961 450 Patterson (1962)

1962 312 LRL (1963)

1963 173 Lichliter (1964)

1964 113 Patterson (1965)

1965 74.6 Patterson (1966)

1966 124 LRL (1967)

1967 76 LRL (1968)

1968 132 LRL (1969)

1969 291 Kelly (1970)

1970 173 LRL (1971)

1971 283 Kelley (1972)

1972 57 LRL (1973)

1973 28 Thomas (1974)

1974 28.3 Stephens and Cantelow (1975)

1975 95.87 Cantelow (1976)

1976 5.35 Stephens (1977)

1977 5.3 Stephens (1978)

1978 7.29 Stephens (1979)

1979 10.1 Schleimer (1980)

1980 4 Schleimer (1981)

1981 15.1 Schleimer (1982)

Year 

Dose 

(mrem/yr) Reference

1982 24.5 Schleimer (1983)

1983 5.8 Schleimer (1984)

1984 5.4 Schleimer (1985)

1985 1.8 Schleimer (1986)

1986 3.5 Schleimer (1987)

1987 3.5 LBL (1988)

1988 1.9 LBL (1989)

1989 2.6 LBL (1990)

1990 7 LBL (1991)

1991 2 LBL (1992)

1992 2.3 LBL (1993)

1993 2.96 LBL (1994)

1994 1.53 LBNL (1995a)

1995 2.1 LBNL (1996)

1996 3.3 LBNL (1997)

1997 2 LBNL (1998)

1998 5 LBNL (1999)

1999 4 LBNL (2000)

2000 4 LBNL (2001)

2001 0.65 LBNL (2002)

2002 ND LBNL (2003)

2003 0.2 LBNL (2004)

2004 ND LBNL (2005b)

a. No values were reported from 1939 to 1958.

b. Highest of perimeter or onsite data was used. In general, due to the terrain of the facility, the perimeter readings are higher than the 

local onsite readings. This is due to the small size of the site, elevation differences, and skyshine with more shielding in the walls than 

roofs of the accelerator buildings. The dose values reflect a 365-d 24-hr measurement less background.

c. Energies are 30-250 keV for photons and 0.1-2 MeV for neutrons. Neutron component of dose is typically≥70% of total.

Table 4-2. Maximum site-wide annual median 

intakes (Bq/yr) via inhalation.

a,b,c,d

Year

Respiration rate: 2,400 m3/yr (2000 hrs/yr)

Gross

alpha

Gross

beta Tritium C-14

1939 0.43 8 3000 470

1940 0.43 9 3500 550

1941 0.43 11 4200 650

1942 0.43 12 4900 760

1943 0.43 15 5800 890

1944 0.43 17 6800 1100

1945 0.43 20 8000 1200

1946 0.43 24 9400 1500

1947 0.43 28 11000 1700

1948 0.43 33 13000 2000

1949 0.43 39 15000 2400

1950 0.43 46 18000 2800

1951 0.43 54 21000 3300

1952 0.43 63 25000 3900

1953 0.43 75 29000 4500

1954 0.43 88 34000 5300

1955 0.43 100 40000 6300

1956 0.43 120 48000 7400

1957 0.43 140 56000 8700

1958 0.43 170 66000 10000

1959 0.43 200 78000 12000

1960 0.43 230 91000 14000

1961 0.3432 273.6 110000 17000
Document No. ORAUT-TKBS-0049 Revision No. 00 Effective Date: 08/07/2006 Page 23 of 55

Table 4-2 (Continued). Maximum site-wide annual 

median intakes (Bq/yr) via inhalation.a,b,c,d

Year

Respiration rate: 2,400 m3/yr (2000 hrs/yr)

Gross

alpha

Gross

beta Tritium C-14

1962 0.0888 511.2 130000 20000

1963 0.0888 849.6 150000 23000

1964 0.0888 198.96 170000 27000

1965 0.0888 35.52 210000 32000

1966 0.0888 12.432 240000 38000

1967 0.0888 29.28 280000 44000

1968 0.0888 28.32 330000 52000

1969 0.0888 17.76 390000 61000

1970 0.444 44.4 460000 72000

1971 0.444 23.088 550000 85000

1972 0.0888 7.104 640000 100000

1973 0.07104 1.8648 750000 120000

1974 0.444 32.856 888,000 17,760

1975 0.6216 26.4 213,120 30,240

1976 0.5328 71.04 328,800 239,760

1977 0.3552 46.08 710,400 79,920

1978 0.444 24.96 2,222,400 40,080

1979 0.6216 20.424 1,687,200 32,856

1980 0.5328 21.312 62,160 31,080

1981 0.444 41.76 97,680 17,760

1982 0.3552 12.432 266,400 26,640

1983 0.1776 9.768 355,200 26,640

1984 0.2664 12.432 8,880,000 2,664,000

1985 0.3552 12.432 3,720,000 97,680

1986 0.07104 4.44 1,065,600 35,520

1987 0.444 17.76 444,000 35,520

1988 0.444 14.208 266,400 17,760

1989 0.7992 11.544 976,800 26,640

1990 0.5328 12.432 266,400 35,520

1991 0.444 1.5984 444,000 17,760

1992 0.5328 15.096 631,200 17,760

1993 0.444 14.208 427,200 31,200

1994 3.6408 6.216 213,120 142,080

1995 0.43 10 184,800 8,160

1996 0.43 10 13,200 2100

1997 0.43 10 26,640 4100

1998 0.43 10 21,384 3300

1999 0.552 3.12 2,592 2,592

2000 0.43 10 12,168 1900

2001 0.43 10 11,208 1700

2002 0.43 10 2,952 500

2003 0.43 10 528 100

2004 0.48 3.6 0 384

a. The site is so small that the environmental samples are 

representative of the site as a whole.

b. Highest of perimeter or onsite data was used. In general, 

due to the terrain of the facility, the perimeter readings are 

higher than the local onsite readings due to the small size 

of the site, elevation differences, and the height of the stack 

release points. Since 1964 the maximum reported value for 

the year was used except for 1986 because of the 

inordinate contribution from Chernobyl. Earlier years 

showed significant fluctuation due to fallout; because of its 

location on the west coast, LBNL routinely transmitted data 

on fallout to the U.S. Atomic Energy Commission (AEC). 

c. Estimated values in italics

d. Data from environmental reports listed in Table 4.1 for the 

appropriate year.
Document No. ORAUT-TKBS-0049 Revision No. 00 Effective Date: 08/07/2006 Page 24 of 55

5.0

The LBNL bioassay records show that the selection of personnel for bioassay and the radionuclides 

for analysis have been based on the work performed by the individual. Selection of employees to be 

included in the bioassay program was typically made by the laboratory’s Safety Services Department 

through their monitor staff. The monitors were directly aware of the radionuclides used throughout the 

laboratory and were therefore best qualified to select employees at risk for potential internal exposure.

OCCUPATIONAL INTERNAL DOSE

Bioassay measurement results were noted in the files as early as 1946. The earliest bioassay results 

are in vitro measurements. In vitro samples were primarily routine urine samples but even the earliest 

records showed measurement results for feces and sputum. Methods used to analyze the samples 

varied but relied primarily on standard methods (McClelland 1958) in use at other laboratories such as 

Los Alamos National Laboratory (LANL). Bioassay monitoring programs were in place from 1947.. 

However, in the early years monitoring was performed on an as needed basis and was not covered by 

a formal documented program (LRL undated). Routine monitoring of employees was initiated in about 

1961 (Howe 1961a). Beginning in 1996 the bioassay program changed such that personnel were 

selected for operational bioassay based on the radionuclide authorization program and reviews of 

work performed. The program currently uses these operational bioassays to evaluate worker 

exposure or, most often, to verify the absence of internal exposures. This program was started 

because so few worker groups were expected to exceed the 100 mrem/yr of internal exposure 

required to put them into a routine monitoring program. 

Table 5-1 lists the in vitro types of bioassay, the periods, and the frequencies of monitoring. Table 5-2 

lists the in vitro sample types and the analysis codes found in the records. 
Document No. ORAUT-TKBS-0049 Revision No. 00 Effective Date: 08/07/2006 Page 25 of 55

 

Table 5-1. Internal dose control program (in vitro). 

Monitoring type Routine/special Period Frequency

Urine, feces, and sputum from 1 employee assayed for 

alpha countsa

Special 1946 (b)

Urine, feces, and blood from a few employees were sent to 

Argonne National Laboratory-East (ANL-E) for analysisa Unknown, probably special

1947 (b)

All employees included in medical program that included 

chest X-ray, hematology, and urinalysisa 

Routine 1947 Periodic

Began developing a bioassay program through LANLa Unknown 1950 (b)

Samples were sent to Lawrence Livermore National 

Laboratory (LLNL) for analysisa

Unknown 1956–1959 (b)

Bioassay laboratory was started and presumably routine 

urine samples were analyzeda Routine 1960 (b)

Nasal smears appeared to be obtained as a matter of 

routine following spills or after hood filter changesc Special 1957–1960 (b)

Urine 24-hr, employees working with transuranic elements, 

Sr-90, and radiumd

Routine 1961 Quarterly

Urine 24-hr, employees working with activity but not 

defined by the quarterly frequencyd

Routine 1961 Annual

Urine 24-hr, employees with less potential for exposured Routine 1961 Every 5 yr

Urine 24-hr, radiochemists and Health Chemistry 

personnel more highly exposed to alpha emitterse

Routine 1962 Semi-annual

Urine 24-hr, radiochemists and Health Chemistry 

personnel, selected members of building trades frequently 

assigned work in active areas, and selected administrative 

personnel whose exposure is essentially zero and who 

should be considered controlse

Routine 1962 Annual

Urine 24-hr, Sr-90f Special 1962 Weekly

Semi-weekly

Feces Special 1962 Special

Blood Special 1962 Special

Urine 24-hrg Routine 1974 Annualc

Urine, feces, sputumg Special 1974 Specialc

Urineh Routine 1975 Annual

Fecesh Special 1975 Special

Breath, radioactive carbonh 1975 Special

Urine spot, H-3 1983 (b)

Urine spot, C-14 1993 (b)

Urine, 24-hr Routinei 1995–present (b)

Feces Speciali 1995–present (b)

Urine, spot 1995–present (b)

a. LRL(undated). 

b. Frequency not applicable or not available.

c. Nasal smear alpha and beta counts were documented following numerous spills in building 70 between 1957 and 1961. 

The radionuclide(s) involved in the spill were sometimes documented: Pu, Am, Pu-240, Pu-239, Am-241, Cm-244, Ru106, Ac-227, and Tb-161 (Kaufman 1957; Alloway 1957; LRL 1958a,b,c,d, 1959a,b, 1960, 1961). 

d. Howe (1961a) identifies that LBNL should establish a, “full-fledged bioassay program.” An attachment to the 

memorandum, “Bioassay Program Features,” identified routine scheduling. It is not clear if the quarterly frequency was 

implemented. Review of an electronic file of historical samples shows a number of employees provided routine urine 

(RU) samples more frequently than annually but it may have been at the discretion of the laboratory staff based on type 

of work rather than as scheduled frequency. 

e. Soule (1962).

f. Selected individuals performing Sr-90 work were followed at weekly or semi-weekly intervals from March 1962 through 

the end of 1962 (Low-Beer 1963). It is not clear that this was the practice throughout the history of the laboratory. 

g. Hartsough (1974) indicates that the frequency for bioassay may be increased for employees that show a consistent 

history of positive bioassay results. Special monitoring was performed at the request of the employee or Safety 

Services of Health Physics. Examples of cause for special bioassay included: Fire involving radioactive materials, 
Document No. ORAUT-TKBS-0049 Revision No. 00 Effective Date: 08/07/2006 Page 26 of 55

rupture of containment devices, air sample results at or above the maximum permissible concentration, high surface 

swipe activity, and skin cuts or punctures while working with radioactive material. 

h. Pickler (1975).

i. Routine measurements are only required when the relative hazard of an operation shows a likelihood of incurring an 

intake resulting in a dose greater than 100 mrem. LBNL uses routine monitoring but relies mainly on “supplementary” 

bioassay programs. Routine programs are implemented when the dose equivalent is expected to be above 100 mrem. 

LBNL uses the quantity thresholds requiring bioassay published in NUREG-1400 for relatively heavy elements (Hickey 

et al. 1993), and the quantity thresholds in the U.S. Nuclear Regulatory Commission Regulatory Guide Series for H-3 

and radioiodines, to establish the need for routine bioassays. Supplementary bioassays are implemented at thresholds 

below the 100-mrem guideline. Threshold values used at LBNL are provided in AlMahamid (2005).

Table 5-2. Sample type (in vitro).a

Routine 

monitoring type Sample type Period Frequency

Urine 24-hr RU = Routine urine 1960–1997 Annual

Urine SU = Special urine 1960–1997 (b)

Blood SB =Special blood 1965–1988 (b)

Fecal SF = Special fecal 1960–1980 (b)

Nasal SN = Special nasal 1957–1960 

1969–1989

(b)

Sputum SS = Special sputum 1967–1974 (b)

Urine TU = Tritium urine 1968–1995 (b)

a. SB, SN, SS, and TU sample types should be verified. These codes are 

seen throughout the history of the records. In some cases the code is a 

best guess based on discussions with LBNL employee James Floyd and 

review of sample analysis. Two other codes (SH and SL) were noted in 

the files only once each and are therefore not in the table. The periods 

are generally taken from the historical database of records. 

b. Frequency not applicable or not available.

From 1960 to 1996 both in vitro and in vivo monitoring records and associated interpretations exist

and are available in the Excel spreadsheet discussed below. In vivo monitoring consisted primarily of 

whole-body counts (WBCs) performed at LBNL from 1960 to 1996. The WB counter used throughout 

this period was located at the Donner laboratory. It was designed, built, and operated by Dr. Thornton 

Sargent, III, who modeled it after the counter at ANL-E. The WBC was located in an 8- by 9- by 6-ft 

room, shielded by walls of 6-in. “pre-atomic age” steel lined with 0.125-in. of lead. The main detector 

was a 9.375- by 4-in. NaI(Tl) crystal positionable in any geometry over a 1-m arc bed or an Argonne 

chair. The large crystal was used for counting energies above 50 keV. The WBC was equipped with 

a probe that could be mounted with 2-in. diameter crystals either 0.125 or 0.25 in. thick for counting 

low-energy gamma-emitting isotopes such as 125I. The 1960 calibration of the counter was performed 

by, “performing studies in which patients were injected with known amounts of various radioactive 

isotopes, and then immediately counted...” (Vargha 1996a).

After 1996 LBNL no longer performed WBCs but rather relied on Lawrence Livermore National 

Laboratory (LLNL) for occasional monitoring. Table 5-3 shows the in vivo monitoring and data 

storage from 1960 to the present.

Table 5-4 summarizes the detection limits found in available documents for in vitro bioassays. The 

minimum detectable activities (MDAs) in Table 5-4 were taken from the analysis results. In some 

cases, the analysis method was not available and the detection limit was not specified. Some of the 

records reviewed showed results for any positive net measurement, some simply noted "neg." A 

specific reporting level was not observed in the records and they appear to have reported only 

measurements above the detection limit. Table 5-6 shows the method codes used to identify analysis 

methods for bioassay samples. These codes were obtained from a computer listing of the analysis 

results.
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Table 5-3. Internal dose control program (in vivo). 

Monitoring type and storage Period Frequency

WBC–a

Records storage media:b

1. Alphabetically by individual, spectrum printouts are on 

paper tape

2. Electronic magnetic tape cassettes

Routine 1960–1983 Annual

Accident 1960–1983 (c)

Outside referral 1960–1983 (c)

Health chemistry 1960–1983 Annual

WBC–a

Records storage media:b

1. Alphabetically by individual

2. Electronic 8-in. diskettes

Routine 1983–1996 Annual

Accident 1983–1996 (c)

Outside referral 1983–1996 (c)

Special studies 1983–1996 (c)

WBC at LLNLd Special 1996–Present (c)

a. WBCs were performed at LBNL from 1960 to 1996. 

b. Vargha (1996b).

c. Frequency not applicable or not available. 

d. AlMahamid (2005, Appendix 2). LBNL employeeJim Floyd indicated that after 1996 WBC were no longer performed at 

LBNL and they relied on LLNL. The laboratory also moved away from routine annual monitoring around 1996 and relied 

on the authorization process for use of radionuclides and knowledge of the work to specify bioassay requirements and 

follow-up or periodic bioassays to verify the absence of internal exposures (Szalinski 2006). 

Table 5-5 summarizes the detection limits found for in vivo bioassays. Because the WB counter was 

the same system for most of the history for LBNL there isn’t much variation. Count times were 

typically 15 minutes but individual counts may have been increased to obtain lower detection limits. 

The count time is noted in the individual records.

Copies of results from all individual bioassays were distributed to the employee, the medical files 

(Medical Services) and to Safety Services. Vargha (1996b) contains information on the records for 

the WBCs between 1960 and 1996 and notes that the electronic files from 1960 to 1996 were 

available. The historical database showed approximately 10,000 samples were collected between 

1960 and 1997. It is noted that some of the original records calculate the activity concentration but 

where the result is below the detection level it is noted “neg.” The electronic database appears to 

include only those results that are above the detection level; sample results below the detection level 

are entered as 0. It may be useful for personnel performing dose reconstruction to review a copy of 

the electronic records which is contained in an Excel spreadsheet and can be accessed using SRDB 

Ref. ID 23481. This electronic record is noted to contain a table of samples with sequential assay 

numbers from 1 to 9999. Unfortunately the table of results does not have results for each assay 

number. The data gaps have been identified to LBNL personnel.

Table 5-7 lists radionuclides used in each facility. Information on the compounds was very limited and 

therefore not included in the table. A few WBC records contained some information about the 

compound, but most were noted with “unknown” under the compound heading. The solubility type 

(Type F, fast absorption, Type M, moderate absorption, or Type S, slow absorption) for some of the 

radionuclides can be found in International Commission on Radiological Protection (ICRP) Publication 

78, Individual Monitoring for Internal Exposure of Workers (ICRP 1998). Publication 78 also provides 

information on the class assigned for gases and vapors (Class SR-1 soluble or reactive, Class SR-2 

highly soluble or reactive, and Class SR-0 insoluble and nonreactive). The particle size for all 

particulate radionuclides should be assumed to be 5-μm AMAD in accordance with the ICRP 

recommendations for occupational exposure.
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Table 5-4. In vitro detection limits.

a

Radionuclide Period

Sample 

Typea Method/description MDA

Gross alpha 1957–1961 N Wet ashed (HNO3 + H2SO4) 60-min count time.e Method uses 3N HCl is also 

noted in 1957 records (Alloway 1957)

1 dpm

Gross alpha 

Isotopes of: 

thorium, 

plutonium, 

curium, 

actinium, and

neptunium

1960–1969 U Livermore method without modification.b,c Coprecipitation of the activity with 

BiPO4 

Sometime later the method was changed to lanthanum fluoride 

coprecipitation and the MDA improved to 0.2 dpm/24-hr urine g

Method descriptions note that uranium, radium, and polonium are not 

detected by this method [SRDB Ref ID 21251]

(Method Code 10)

0.3 dpm/24-hr 

urine 

(0.15 pCi/24-hr 

urine)

Gamma emitters

Gross Alpha ( assumed 

to include isotopes of 

thorium, plutonium, 

curium, actinium, and 

neptunium)

Gross Beta ( assumed to 

include Sr/Y-60, Sr-89, 

Ba/La-140, Ce/Pr-144, 

and fission products)

1969- present U or F Analysis of 24-hr urine sample.f Preparation of the sample by alkaline 

phosphate precipitation to eliminate monovalent cations. The ash from the 

alkaline phosphate precipitation is suspended in 10 ml of 2N HNO3. The whole 

sample is counted by gamma spectroscopy using a 4-in. NaI crystal and a 

400-channel pulse-height analyzer (gamma: method code 04). One fifth of 

the sample is then plated on aluminum for counting gross beta activity in a 

Nuclear-Chicago gas-flow proportional counter (gross beta: method code 

50). The remaining four fifths of the sample is processed by bismuth 

phosphate and lanthanum fluoride coprecipitation and counted for gross 

activity in the Nuclear-Chicago gas-flow proportional counter (gross alpha: 

method code 10).

Gamma 10 nCi

Alpha 0.1 pCi

Beta 1 pCi

Gross beta 1957–1961 N Wet ashed (HNO3 + H2SO4) 60-min count time.e Method uses 3N HCl is also 

noted in 1957 records (Alloway 1957)

30 dpm

Gross beta 

Sr/Y-90, 

Sr-89, 

Ba/La-140, 

Ce/Pr-144, 

and fission products

1960 – 1969 U Los Alamos method without modification. Phosphate precipitation. The 

method in McClelland (1958) describes that radionuclides include: Sr/Y-90, 

Sr-89, Ba/La-140, Ce/Pr-144, and fission products. Another reference 

LRL(1962) [SRDB Ref ID: 21251] notes that protactinium is not detected by 

this method.

(Method Code 50)b,c

5.1 dpm/24 hr 

urine (1968)

2 dpm/24 hr

urine (1969)

Am-241, 

Pu-239

1962 Column chromatography, electroprecipitation, and pulse height analysis 

(PHA)d 1962 was the only reference to this method.

Not specified

Am-241, Am-243 1995 – present U alpha spectrometry 0.02 pCi

1995 – present F alpha spectrometry 0.02 pCi

Bk-249 1995 – present U gross beta or alpha spectrometry 0.02 pCi

C-14 1968–1993 U Sample is decolorized using activated charcoal and counted on a liquid 

scintillation counter

(Method code 02)

5.0 nCi/L (1974)

1993 – present U (C-14 was listed in the 1995 TBD but the method was not specified) 2.0 nCi/L (1993)

Cm-243, Cm-244, 

Cm-246, Cm-248, 

2005 – present U or F Method not specified 0.02 pCi/sample

Cf-252 1965 – 1995 U or F Gross alpha using Livermore method: Coprecipitation of the activity with 

BiPO4. 

0.3 dpm/24-hr 

urine 

Cf-252, Cm-244 1968 Alpha PHA was used to indicate the relative ratio of Cf-252:Cm-244 Not specified
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Cf-249, Cf-252 1995 – present U or F Method not specified 0.02 pCi

Fe-55, Fe-59 1995 - present Method not specified Not specified

H-3 1968 – 1982 U Liquid scintillation counting (Method code 03) 0.02 μCi/L

1982 – 1995 U 0.01 μCi/L

1995 – present U 4.5 pCi/sampleh

I-125 1980–1984 U Gamma spectroscopy (Method code 05) 0.02 nCi/L

Na-22, Na-24 1995 – present Method not specified Not specified

Np-237, NP-239 1995 – 2005 U Method not specified 0.05 pCi of Np237

2005 - present U or F Method not specified 0.02 pCi/sample

P-32, P-33 1963 – 1995 U Amonium phosphomolybdate precipitation (Method code 71) 20 pCi/L

1995 – present U or F Not specified 1.5 pCi

Protactinium 1960 Not specified (1960 only year noted for protactinium) Not specified

2005 – present 

(Pa-231)

U or F Method not specified 0.02 pCi/sample

Pu-238, Pu-239 1995 – present U or F Method not specified 0.02 pCi

Pu-241 2005 – present U or F Method not specified 0.02 pCi/sample

Rare earths (primarily 

Pm-147)

1961 U Not specified (1961 only year noted) 3 dpm/24-hr 

urine

Ra-226 1995 - present U Method not specified 0.1 pCi/L not 

listed in TBD but 

assumed (Note 

q)

Sulfur

S-35

1962– 1992 U or F Urine analysis and fecal analysis

(Method Code 52) 0.2 nCi/L (1982)

1992 – present U Barium sulfate precipitation 0.1 nCi/L (1992)

Strontium

Sr-90, Sr-89

1961 - 1995 Oak Ridge Method of ion exchange chromatography (Sunderman et al. 1960)

(Method Code 51)

Not specified

Thorium 1995 - 2005 U Method not specified Not listed in 

TBD assume 0.1 

pCi/L (note q)

2005 – present U or F Method not specified 0.02 pCi/sample

Uranium 1961–1988 U Los Alamos method of solvent extraction with dibutyl phosphate (McClelland 

1958)

(Method Code 11)

0.15 dpm/24-hr 

urine

1988 - 1995 U Anion exchange chromatography 0.15 dpm/24 hr 

urine

1995 - 2005 U Method not specified Not listed in 

TBD use 

previous MDA 

0.15 dpm/ 24 hr 

urine

1995 - 2005 F Method not specified Not listed use 1 

pCi/sample 

(note q)

2005 – present U or F Method not specified 0.02 pCi/sample
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a. Blanks in this table indicate not applicable or no data available. Sample types: N= nasal smears, U=urine, F=Fecal.

b. Low-Beer (1962) and McClelland (1958).

c. Howe (1961b).

d. Low-Beer (1963).

e. LRL (1958b).

f. Patterson, Low-Beer, and Sargent (1969). Although this 1969 reference specifies a 10 nCi detection limit for gamma emitters, numerous bioassay records on NOCTS showed a 

gamma detection limit of 30 dpm/specimen (13 pCi/specimen). Personnel performing dose reconstruction should use the MDA specified with the results.

g. LRL (1962) Bioassay Process – Circa 1962 [SRDB Ref ID 21251]

h. LBNL (1995b)

Additional Table notes:

1. The detection limits noted in results for “Bioassays beginning with A” (LRL 1965–1990). Periods identified are sometimes based on the record of available results (the historical 

database of records).

2. Also used in Table 5-4: Internal Dosimetry Evaluations (LBL 1980–1993).

3. Method Code refers to the code in the historical database of bioassays.

4. Where the period has a starting date of 1995 thee information was obtained from the Technical Basis Document for Internal Dosimetry, LBNL (1995b)

5. The majority of the bioassay records in NOCTS were observed to be gross alpha, gross beta, and gamma spec with the detection limits noted with the results.

6. Periods of time generally cover the period from when the first analysis was observed in the records to the year that a new method was noted; methods may have been used 

before or after the specified times. The time periods were obtained from bioassay records in the data capture files as well as bioassay records in the NOCTS claim files. 

7. The bioassay records within the files in NOCTS are noted to usually show the method used and the detection limit.

8. In some cases a radionuclide was noted in the LBNL internal dosimetry TBD but the method and MDA were not specified

9. The year beside the MDA indicates the year that this MDA was first noted in the analysis records.

10. When an MDA was not specified for the radionuclides listed in the LBNL TBD for internal dosimetry (LBNL 1995b), the value from ANSI HPS N13.30, Table C.4 was used and 

assumed to be conservative. 

11. Methods other than the ones listed may have been used. The assumption is made that other methods would have resulted in improved MDAs and those listed in this table are 

conservative resulting in claimant favorable dose reconstruction. 
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Table 5-5. In vivo detection limits.

a

Monitoring 

method Radionuclide Method/description Period MDA

In vivo Gamma-emitting 

radionuclides 

50 keV – 2 MeV

(including thyroid counts for 

I-131, I-123)

B-7, N-22,24, Mn-54, Ni57,63, Fe-55,59, 

Co-57,58,60, Zn-65

WBC.b The Donner WB counter was an ANL-E type, with a 6-in. steel shield. 

The individual sits in an inclined chair and is counted by a 9- by-4- in. by 

9.375-in. NaI(Tl) crystal. The gamma pulses were analyzed by a 400-channel 

pulse-height analyzer, calibrated at 5keV/PHU, for a 0–2.0 MeV spectrum 

range. Between 1960 and 1983, data were recorded on printed paper tape, 

which was then keypunched for computer analysis. Calibration of the area 

under the photopeaks to yield microcuries body burden was obtained from the 

spectra of medical patients injected with known quantities of short-lived 

radionuclides, with various gamma-ray energies. Count time was routinely 

15 min but later references showed longer count times when lower MDAs or 

better counting statistics were needed and tolerated by the subject.

1960–1996 1–10 nCi for the 

nuclides listed

Assume 1 nCi for 

I-123 and I-125,

Assume 10 nCi 

for other listed 

nuclides

In vivo Gamma-emitting 

radionuclides <50 keV (e.g., 

I-125)

WBC when count was performed using smaller (2 inch diameter by 1⁄4 inch 

thick)b detector

WBCs were also noted to identify the presence of high energy beta emitters 

such as P-32 and Y-90 presumably through increases in the Compton 

continuum due to bremsstrahlung.c 

1960 – 1996 10 nCi for I-125

(note d)

In vivo Am-241, Am-243 Lung count for Np-239 1995 – 1996 50 pCi

In vivo F-18 WBC 1995 - 1996 640 pCi

In vivo I-125, I-131 Thyroid count 1995 – 1996 

In vivo P-32 WBC (only one count for P-32 found in NOCTS) 1971 - 1996 1E5 pCi

a. Blanks in this table indicate not applicable or no data available.

b. Patterson, Low-Beer, and Sargent (1969). 

c. Vargha (1996a.)

d. A specific MDA for I-125 was not found. Vargha (1996b) specifies that the recommended count times produced MDAs for most isotopes in the range of 1 nCi. Based on the 

energy and photon yield for I-125, 10 nCi was assumed here.

Additional Table notes: 

1. Pickler (1975) refers to use of the Helgeson WB counter. This is the only reference found to this counter. 

2. The detection limits noted in results for “Bioassays beginning with A” (LRL 1965–1990). Periods identified are sometimes based on the record of available results (the 

historical database of records).

3. Also used in Table 5-5: Internal Dosimetry Evaluations (LBL 1980–1993) and WBC records in NOCTS claims.

4. Most WBC records reviewed showed only the note “normal activity.” In a few cases a detection limit for the radionuclide of concern was listed in the notes section of the 

WBC record. Quantified activity in WBC was frequently noted to be in the range of 1 – 10 nCi.

5. WBC after 1996 were performed at LLNL, and there have been very few performed since that time. If the detection limits are not noted on the LLNL results, the table above 

can be used as an estimate for dose reconstruction.

6. 10 nCi can be used as a conservative estimate for the MDA.
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Table 5-6. Unit codes and description of units. 

Computer code

(Method code) Description of units

Radionuclides reported with 

results

1 dpm/sample None listed

2 

nCi/L 

dpm/g C (only one sample result observed was 

reported in dpm/g C)

C-14

3 μCi/L

nCi/L (only a few samples were reported in nCi/L

H-3

4 nCi/L I-125 (gamma emitters)

5 nCi/L I-125, Sr-85, Cr-51

pCi/L Cs-137

6 nCi/L I-125

10

dpm/d Gross alpha

dpm/L (one sample) Gross alpha

μCi/L (one sample) H-3

11 dpm/d U-238

14 dpm None listed

15 dpm/d None listed

16 (a)

17 (a)

18 (a)

19 (a)

50 dpm/d, dpm/L Gross beta

51 dpm/d Sr-90

52 nCi/L S-35

54 (a)

55 nCi/L Ca-45

71 nCi/Lc P-32

a. Codes 16, 17, 18, 19, and 54 were observed in a computer listing of assays but there were no results or radionuclides 

reported with these codes. Note: only positive results are shown in the computer listing, copies of original records are 

marked “neg” when the result is below the detection level.

b. The available computer listing of results only shows measurement units for positive results and only shows 

radionuclides for some of the positive results.

c. These method codes are seen throughout the bioassay records from 1960-1996.
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Table 5-7. Radionuclidesa,b and fraction activitya by facility. Current 

building no. Building activity and compounds Radionuclide Fraction

1 Donner Laboratory (1961- present) C-14 4.28E-01

H-3 2.29E-01

I-125 2.31E-01

P-32 2.57E-02

S-35 8.55E-02

Alpha 1.41E-04

Beta 8.44E-04

3 Calvin Laboratory C-14 4.40E-03

H-3 5.37E-02

P-32 8.59E-02

P-33 1.77E-01

S-35 6.79E-01

4 (Nuclides obtained from 1977, 1979 worker bioassay lists) C-14

H-3

P-32

S-35

6, 16, 52 6: 184” Cyclotron (1957)

Advanced Light Source (present)

16: Sherwood Laboratory (1961)

Accelerator and Fusion Research (present)

52: General research (1961)

Accelerator and Fusion Research (present)

The radionuclides listed without a radionuclide fraction specified 

were obtained from a list of potential sources produced by 

accelerators (Bldg 6) identified in Patterson, Low-Beer, and Sargent 

(1969)d

U-238 2.90E-04

N-13 9.93E-01

O-15 5.19E-03

Ar-41 1.38E-03

Be-7

Co-57

Co-58

Co-60

Fe-55

Fe-59

Mn-54

Na-22

Na-24

Ni-57

Ni-63

Zn-65

10 Biomedical research (1986)

(nuclides obtained from 1977, 1979, 1982, 1983, 1986 worker 

bioassay lists)

C-14

Cr-51

H-3 

P-32

S-35

Beta-gamma

15 (Nuclides obtained from 1977 worker bioassay lists) H-3

25 Mechanical Technology

(nuclides obtained from 1977, 1979, 1982, 1983, 1986 worker 

bioassay lists)

Th

U-238

U

26, 76 Radioanalytical Laboratories (present) Ac-228 1.51E-08

Ag-108 2.65E-11

Am-241 4.15E-03

Am-243 2.56E-06

Ba-133 2.27E-04

Be-7 5.07E-10

Bk-249 9.91E-04

Br-76 6.94E-09

Br-77 3.78E-10

C-14 1.54E-02

Ce-144 5.72E-07

Cf-249 4.30E-04

Cf-250 7.57E-08

Cm-243 2.59E-07

Cm-244 2.12E-08

Cm-245 1.44E-10

Cm-246 1.13E-09
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Table 5-7 (Continued). Radionuclidesa,b and fraction activitya by facility.

Current 

building no. Building activity and compounds Radionuclide Fraction

26, 76 

(Cont’d.)

Cm-248 4.54E-10

Co-56 9.83E-10

Co-57 7.00E-06

Co-58 5.29E-10

Co-60 1.64E-04

Cr-51 1.25E-10

Cs-134 9.63E-06

Cs-137 2.17E-03

Eu-152 3.93E-11

Fe-55 1.95E-05

H-3 1.77E-01

Hg-194 9.08E-09

I-125 3.80E-01

I-129 4.20E-05

I-131 3.81E-01

K-40 1.89E-09

Kr-76 1.51E-10

Mn-54 7.69E-06

Na-22 1.63E-08

Nb-95 1.63E-09

Ni-63 1.01E-05

Np-237 3.69E-06

Np-239 5.33E-08

Os-185 1.44E-09

P-32 3.78E-03

Pa-231 9.72E-08

Po-210 1.51E-08

Pu-238 5.46E-04

Pu-239 1.59E-03

Pu-241 3.40E-03

Pu-242 1.66E-08

Ra-226 2.27E-06

Ra-228 1.69E-04

Ru-106 2.27E-11

S-35 2.42E-02

Sb-125 8.81E-10

Sr-89 6.65E-07

Sr-90 1.38E-04

Tc-99 1.10E-06

Th-229 9.08E-08

Th-230 5.19E-06

Th-232 1.76E-05

U-232 3.79E-05

U-233 3.78E-03

U-235 4.17E-05

U-238 5.06E-04

Zn-65 1.20E-05

29 (Nuclides obtained from 1979 worker bioassay lists) Alpha

51 Bevatron

[U, and beta-gamma nuclides obtained from 1982, 1983, 1986 

worker bioassay lists; Am-241, Am-243, Bk-249, Cf-252, and Ra226 obtained from 1995 Internal Dose TBD (LBNL 1995b), the 

remainder of the radionuclides were obtained from a list of potential 

sources produced by accelerators that were identified in Patterson, 

Low-Beer, and Sargent (1969)d

] building is currently undergoing 

decontamination and decommissioning.

U

Beta gamma

Am-241

Am-243

Bk-249

Cf-252

Ra-226

Be-7

Co-57

Co-58

Co-60

Fe-55

Fe-59

Mn-54

Na-22
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Table 5-7 (Continued). Radionuclidesa,b and fraction activitya by facility.

Current 

building no. Building activity and compounds Radionuclide Fraction

51 (Cont’d.) Na-24

Ni-57

Ni-63

Zn-65

55, 56, 64 55: Animal house (1961)

Center for functional imaging and life sciences research (present)

56: Biomedical isotope facility (present)

64: Accelerator design (1961)

Life sciences research (present)

C-14 2.67E-08

Co-57 7.63E-08

Gd-153 2.29E-08

H-3 1.12E-05

I-123 4.40E-05

I-125 1.09E-04

I-131 6.02E-06

Nb-95 1.14E-07

P-32 4.58E-07

Ru-103 1.53E-07

Sn-113 7.63E-08

Tc-99m 3.16E-05

Tl-201 9.91E-07

F-18 1.00E+00

Alpha 3.71E-09

Beta 5.92E-08

57 (nuclides obtained from 1982 worker bioassay lists) I-125

I-131

In-111

P-32

Sr-82

Sr-85

Sr-90

62 Materials and Molecular Research

(nuclides obtained from 1982, 1983, 1986 worker bioassay lists)

Th-228

70, 70A 70/70A: Nuclear Chemistry (1961)

70: Environmental energy technology, nuclear science and earth 

sciences research (present)

70A: Nuclear, chemical, and life sciences research (present)

Ac-227c

Am-241 7.60E-06

Am-243 1.52E-04

Bi-207 7.60E-06

C-14 5.51E-01

Ca-45 1.20E-05

Ca-49 2.38E-08

Ce-141 2.59E-06

Cf-249 7.60E-07

Cf-252 7.60E-09

Cm-244 2.13E-08

Cm-248 1.08E-07

Co-60 3.61E-06

Cs-134 1.46E-06

Eu-152 1.07E-05

Fe-59 6.88E-03

H-3 2.76E-01

Hf-175 8.58E-06

Ho-166m 6.08E-06

I-125 2.25E-04

Mn-54 1.52E-07

Na-22 1.52E-06

Na-24 2.65E-05

Np-237 1.70E-03

P-32 4.13E-02

Pa-233 3.60E-06

Pu-238 4.35E-05

Pu-239 6.99E-06

Ra-226 1.52E-06

Rb-86 1.93E-04

Rh-101 7.60E-08

Ru-106c

S-35 1.06E-02

Sb-122 1.90E-07
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Table 5-7 (Continued). Radionuclidesa,b and fraction activitya by facility.

Current 

building no. Building activity and compounds Radionuclide Fraction

70, 70A 

(Cont’d.)

Sb-124 1.10E-06

Sc-46 1.34E-03

Sc-49 1.19E-08

Sr-90 6.08E-06

Ta-182 1.52E-06

Tb-161c

Tc-99 8.04E-02

Th-229 2.17E-05

Th-232 9.44E-04

Tl-204 1.52E-06

Tm-170 1.52E-05

U-233 2.61E-04

U-234 1.08E-04

U-235 1.08E-04

U-238 3.81E-04

Y-90 1.22E-05

Yb-175 1.96E-06

Zr-88 4.56E-07

Zr-95 7.60E-04

Alpha 4.04E-03

Beta 2.38E-02

71 HILAC (1961)

Accelerator and fusion research (present)

The radionuclides listed without a radionuclide fraction specified 

were obtained from a list of potential sources produced by 

accelerators that were identified in Patterson, Low-Beer, and 

Sargent (1969)d

F-18 1.20E-08

H-3 1.00E+00

Be-7

Co-57

Co-58

Co-60

Fe-55

Fe-59

Mn-54

Na-22

Na-24

Ni-57

Ni-63

Zn-65

72 Health Physics (1961)

Low-background facility (present)

Ac-227 8.33E-08

Au-198 2.83E-06

Ba-133 2.99E-09

Bi-207 3.01E-08

Br-82 2.48E-07

Cd-113 6.40E-09

Co-58 9.23E-01

Co-60 1.20E-03

Cr-51 1.51E-06

Cu-64 4.96E-04

Eu-152 4.96E-04

Fe-59 2.95E-02

Hg-194 4.68E-08

Mn-54 2.68E-06

Na-24 9.92E-04

Nb-95 1.34E-09

P-32 9.50E-06

Pa-231 4.94E-08

Sb-122 2.97E-11

Sb-124 9.92E-04

Ta-182 5.28E-08

Th-228 5.23E-12

Th-229 2.62E-05

Th-232 4.96E-08

Ti-44 1.35E-07

Xe-133 3.97E-10

Zn-65 3.47E-11
Document No. ORAUT-TKBS-0049 Revision No. 00 Effective Date: 08/07/2006 Page 37 of 55

Table 5-7 (Continued). Radionuclidesa,b and fraction activitya by facility.

Current 

building no. Building activity and compounds Radionuclide Fraction

72 (Cont’d.) Zr-95 4.10E-02

Zr-97 1.82E-03

74, 83, 84 74: Animal bio-radiological laboratory (1961)

74, 83, 84: Life sciences research (present)

C-14 4.92E-03

H-3 5.05E-01

P-32 3.46E-02

S-35 4.56E-01

75 Radioisotope services (1961)

Former waste handling facility, operations ceased in 1997

Former National Tritium Labeling Facility operations ceased in 2001

H-3 1.00E+00

Alpha (Th-232) 1.69E-09

beta (Sr-90) 5.72E-09

85 Hazardous waste handling facility (present) C-14 1.44E-01

H-3 8.56E-01

I-125 9.97E-06

Alpha (Th-232) 1.17E-06

Beta (Sr-90) 2.79E-06

88 88” cyclotron (1961 – present)

The radionuclides listed without a radionuclide fraction specified 

were obtained from a list of potential sources produced by 

accelerators that were identified in Patterson, Low-Beer, and 

Sargent (1969)d

U-238 1.40E-10

C-11 9.94E-01

Cr-51 1.95E-12

Fe-55 8.19E-13

Fe-59 2.03E-12

Ge-71 6.37E-03

Zr-95 1.56E-12

Zr-97 2.34E-12

Y-88 3.12E-12

Alpha 4.72E-07

Beta 1.63E-06

Be-7

Co-57

Co-58

Co-60

Mn-54

Na-22

Na-24

Ni-57

Ni-63

Zn-65

934 Previously Leased Building use of biomedical radionuclides for DNA 

Labeling (nuclides obtained from 1982, 1983, 1986 worker bioassay 

lists)

C-14

H-3

I-125

P-32

S-35

977e H-3

P-32

P-33

S-35

C-14

Cd-109

a. Blank values in this table indicate not appliicable or data not available. Unless otherwise noted, this table was derived from 

data reported for calendar years 2001 to 2004 as part of the National Emission Standards for Hazardous Air Pollutants 

(DOE 2002, 2003, 2004, 2005). Where stack emissions were not measured, LBNL derived a “receipts releasable” 

inventory of radionuclides available for release. While the emissions identified during this limited period of time is likely not 

fully representative of the source term in each building, they do provide an estimate of the types of radionuclides to which 

employees might have been exposed. Activity fractions were obtained by dividing the activity total by the total activity for all 

radionuclides in a specific building/buildings over the 4 yr.

b. Buildings and radionuclides were added based on historical lists (e.g. bioassay lists, LBNL 2005a,b), Patterson, Low-Beer 

and Sargent 1969). Radionuclide fractions were not determined for these.

c. Ac-227, Ru-106, and Tb-161 were added to the list of radionuclides listed for building 70 because there were documented 

spills in building 70 between 1957 and 1960 where these radionuclides were listed; no attempt to determine a radionuclide 

fraction has been made.

d. Although Patterson, Low-Beer, and Sargent (1969) identified these radionuclides as potential exposure sources, the article 

concluded that, “normal habits of cleanliness and occasionally the use of protective clothing ... are adequate to insure that 

the ordinary accelerator worker at LRL-Berkeley will not receive radiation exposure of any consequence from internal 

sources.”

e. Radionuclides obtained from (LBNL 2005a).
Document No. ORAUT-TKBS-0049 Revision No. 00 Effective Date: 08/07/2006 Page 38 of 55

6.0

This section describes the program for measuring skin and WB doses to workers from sources that 

were external to the body. Workers at LBNL were exposed to radiation from a variety of radioactive 

materials and radiation-producing machines. Personnel dosimeter records are generally available for 

all periods at LBNL for workers who had any potential for occupational radiation exposure. The 

operations and radiation safety staffs routinely reviewed dosimeter results for compliance with 

radiation control limits and investigated doses that approached annual or quarterly limits. LBNL used 

personnel dosimeters to measure and record doses from external radiation to designated workers 

throughout the history of its operations. These dosimeters included one or more of the following:

OCCUPATIONAL EXTERNAL DOSE

• Personnel WB beta/photon dosimeters 

• Pocket ionization chamber dosimeters (i.e. electrometers/electroscopes, etc.) 

• Personnel extremity dosimeters

• Personnel neutron dosimeters

LBNL began operations using dosimeter and processing technical support provided by the 

Metallurgical Laboratory at the University of Chicago. After 1952, LBNL operated its own fully 

functional personnel dosimetry program with in-house processing. Exposure data were recorded by 

film badges and thermoluminescent dosimeters (TLDs). Early exposure records also provided 

electroscope (or at times, electrometer or E was used) results, which supplemented the results 

measured by film. For purposes of dose reconstruction, the electroscope results should be used in a 

qualitative manner because no data was found on the calibration or energy response of these 

devices; the film or TLD results should be used to estimate the actual exposure. The electroscope 

results include daily readings in tables captioned "dosimeter," "slow neutron," and "electroscope." 

The three readings occurred on the same dates and were evidently used to measure exposure at the 

end of work shifts. There are data in claimant records which shows a comparison of the film dosimeter 

to electroscope records for the same interval; the data are similar and correlate, but are not identical. 

This is likely due to a combination of energy dependence, calibration, where worn in relation to each 

other, geometry, etc.

Where the records bear the heading "All readings are recorded in daily doses" the "daily dose" is 100 

millirem. The units are in fractions of 100 millirem, e.g. 0.08 = 8 millirem (Heinzelman 2003). 

There are no records of monitoring for beta exposure using film.

Table 6-1 lists dosimeter types, periods of use, exchange frequency, minimum detection limits 

(MDLs), and potential annual missed doses for LBNL. Tables 6-2 and 6-3 list the energies and 

percentages for neutron and beta/photon radiation, respectively. Where more than one energy range 

and percentage combination is provided use the combination which is favorable to claimants. Table 

6-4 summarizes recorded dose practices, and Table 6-5 summarizes the interpretation of the reported 

data. Table 6-6 lists adjustments to recorded dose, and Table 6-7 lists the bias and uncertainty of 

each specific dosimeter system. The adjustment to neutron dose of X2 provided in Table 6-6 should 

be used unless claimant records provide sufficient information to use the more specific ICRP 60 

correction factor provided in Table 6-3. There is limited information about the use of extremity 

dosimeters prior to 1982. It appears that xray film were used as finger rings; there is no reference to 

wrist dosimeters as used at LANL or ORNL. Estimates of missed dose can use dose results for 

coworkers or the recorded dose before and after the period of missed dose.
Document No. ORAUT-TKBS-0049 Revision No. 00 Effective Date: 08/07/2006 Page 39 of 55

Table 6-1. LBNL dosimeter type, period of use, exchange frequency, MDL, and potential annual 

missed dose. 

Period of use Dosimeter

MDLa 

(rem)

Exchange

frequencyb

Annual 

missed 

dosec (rem)

1941 - 1969d Photon/electron - DuPont 558 and 519 filme 0.015 Weekly (n=50) 0.375

0.020 Biweekly (n=25) 0.25

0.030 Monthly (n=12) 0.18

Neutron - Kodak NTA filmf 0.050 Weekly (n=50) 1.25

0.050 Biweekly (n=25) 0.625

0.050 Monthly (n=12) 0.30

1969 - 1985 Photon/electron/neutron - Harshaw TLD 

(TLD-100, TLD-200, TLD-600, and TLD-700)

0.010 Monthly (n=12) 0.06

0.020 Quarterly (n=4) 0.04

1985 - present Photon/electron - Panasonic 810AS and 802AS 

TLD

0.010 Monthly (n=12) 0.06

0.015 Quarterly (n=4) 0.03

0.025 Semi-annual (n=2) 0.025

Neutron – CR-39 0.010 Monthly (n=12) 0.06

0.010 Quarterly (n=4) 0.02

a. Estimated MDLs for each dosimeter technology. Dose values were recorded at levels less than the MDL. 

b. Exchange frequencies were dependent on work assignment. If the exchange frequency is not evident based on trends 

in an individual’s personnel records, assume a monthly exchange frequency, If there is a possibility of more frequent 

monitoring than monthly that is not evident from review of worker data, the dose reconstructor should contact LBNL to 

request additional information.

c. Annual missed dose calculated using the MDL/2 method from NIOSH (2002).

d. From 1941 to 1952, Argonne East processed film dosimeters for LBNL. The procedure to process the dosimeter was 

described by Pardue in a 1944 report (Pardue, et al, 1944). From 1952 to 1955, LBNL processed film dosimeters using 

an equivalent method. 

e. No record of the type of beta-gamma film used initially is available, but DuPont films were in use by ANL-E by the late 

1950s (ORAUT 2006). 

f. The beginning of neutron monitoring is uncertain, but it appears to have been in use as early as 1951. Records indicate 

that films were developed but not routinely read before 1960. Films were apparently not evaluated unless there had 

been a gamma dose measured for the same period (ORAU, 2006) (Dolecek, 1981). 

Table 6-2. Selection of beta and photon radiation energies and percentages. 

Buildings Description

Radiation 

type

Energy 

selection (MeV) Percentage

1, 2, 3, 4, 5, 5A, 7, 8, 

9, 10, 11, 14, 16, 18, 

19, 20, 22, 24, 25, 

29, 38, 39, 55, 71

Chemistry: radioactive materials 

including Co-60, S-90, fission products, 

enriched uranium, depleted uranium, 

natural uranium, and others

Beta >15 100

Photon 30–250 

> 250

25

75

6, 26, 70, 70A, 88 Chemistry Heavy Elements Facility: 

Cf-252 Cm-244, Am-241, U-233, Pu239, and others

Beta >15 100

Photon <30

30–250 

> 250

25

50

25

75 Waste Storage Yard fission products, 

enriched uranium, natural uranium and 

others

Beta >15 100

Photon 30–250 

> 250

25

75

72, 74, 75 Irradiators Co-60, Cs137 Beta >15 100

Photon 30–250 

> 250

25

75

51, 71 Cyclotrons and Accelerators Beta >15 100

Photon <30 0

30-250 10

>250 90
Document No. ORAUT-TKBS-0049 Revision No. 00 Effective Date: 08/07/2006 Page 40 of 55

Table 6-3. Selection of neutron radiation energies and percentages. 

Buildings Description

Radiation 

type

Energy

selection 

(MeV) Percentage

ICRP 60 

Correction 

Factor

1, 2, 3, 4, 5, 5A, 7, 

8, 9, 10, 11, 14, 

16, 18, 19, 20, 22, 

24, 25, 29, 38, 39, 

55, 71

Chemistry: radioactive 

materials including Co-60, S-90, 

fission products, enriched 

uranium, depleted uranium, 

natural uranium, and others

Neutron 0.1–2.0 100 1.91

6, 26, 70, 70A, 88 Chemistry Heavy Elements 

Facility: Cf-252 Cm-244, Am241, U-233, Pu-239, and others

Neutron 0.1–2.0

2.0-20

90

10

1.71

0.13

75 Waste Storage Yard fission 

products, enriched uranium, 

natural uranium and others

Neutron 0.1–2.0

2.0-20

90

10

1.71

0.13

72, 74, 75 Irradiators Co-60, Cs137 Neutron 0.1–2.0 100 1.91

51, 71 Cyclotrons and Accelerators Neutron 0.1–2.0

2.0-20

50

50

0.95

0.65

Table 6-4. Recorded dose practices. 

Year

Dosimeter measured 

quantities Compliance dose quantities

Photon/electron film dosimeter + NTA neutron dosimeter

1941–1981 Gamma (G)

Neutron (N)

WB = gamma + neutron

Photon/electron/neutron–Harshaw TLD

1982–1985 Gamma (G)

Neutron (N)

Total = photon + neutron (γ+η)

Skin = shallow = photon + neutron

Hand = finger extremity dose 

Photon/electron/neutron–Panasonic TLD + CR-39 neutron dosimeter

1986–present Skin

Photon 

Neutron 

Skin = photon + neutron (P/N)

WB = Photon + neutron

Table 6-5. Interpretation of reported data.

Period

Reported 

quantity Description

Interpretation 

of zeroes

Interpretation 

of blanks 

(no data)

Rollup of 

individual and 

annual data

Monitored/ 

unmonitored

1941–

1981

rem Reported WB doses 

include gamma. 

Neutron doses were 

designated with “N.” 

Claimant records 

indicate that some 

recorded results are 

expressed as a 

fraction of the daily 

dose limit of 100 

mrem.

Zeroes were generally 

not reported. Reported 

zero should be 

interpreted as meaning 

less than MDL.

No data or blanks 

should be interpreted 

as individual was 

monitored with zero 

result.

Photon WB dose

Neutron WB dose

Shallow skin dose

Total deep WB 

dose

All employees with 

significant exposure 

potential were 

monitored (more than 

95% of employees 

were monitored before 

1958). After 1958, all 

employees were 

monitored 

continuously.

1982–

1985

rem Reported WB doses 

qualified as either 

photon or neutron

Zeroes were generally 

not reported before 

1980. Reported zero 

should be interpreted 

as meaning less than 

MDL.

No data or blanks 

should be interpreted 

as individual was 

monitored with zero 

result.

Photon WB dose

Neutron WB dose

Shallow skin dose

Total deep WB 

dose

All employees were 

monitored 

continuously.

1985–

present

rem Photon deep, neutron 

deep, and skin dose 

reported.

Zeroes were typically 

reported. Reported 

zero should be 

interpreted as meaning 

less than MDL.

No data or blanks 

should be interpreted 

as individual was 

monitored with zero 

result.

Photon WB dose

Neutron WB dose

Shallow skin dose

Total deep WB 

dose

All employees were 

monitored 

continuously.
Document No. ORAUT-TKBS-0049 Revision No. 00 Effective Date: 08/07/2006 Page 41 of 55

Table 6-6. Adjustments to recorded dose. 

Period Dosimeter Facility Adjustment to reported dose

1941–1985a Photon dosimetersb All facilities Use roentgen-to-organ dose conversion factors.

1986–present Photon dosimeters All facilities Use Hp(10)-to-organ dose conversion factors.

All years Neutron dosimetersc All facilities Multiply reported doses by factor of 2 to account for 

ICRP Publication 60 weighting factors (ICRP 1991).

a. Beta and non penetrating dose was not reported prior to 1982. In general, non-penetrating radiation doses should be 

assigned as <30 keV photons if the employee worked with or around Plutonium, otherwise, > 15 keV electrons should 

be assigned (ORAU, 2005d). The guidance from ORAU is as follows, 

If the nature of the non-penetrating dose is unknown, consider the following guidance: 

1. For a likely non-compensable case, it is acceptable to assume the non-penetrating dose is associated with <30 

keV photons, as this maximizes POC. 

2. For a likely compensable case, it is acceptable to assume the non-penetrating dose is associated with >15 keV 

electrons, as this minimizes POC.

3. If the compensability decision may hinge on this issue, and if the partitioning of the nonpenetrating dose cannot 

be decided based on the available information, additional research may be required.

b. The dose from low energy photons (<30 kev) were underestimated from 1941 through 1985 as a result of the design of 

the dosimeter holder (ORAU, 2005). The dose from <30 kev photons should be calculated by the following formula: 

Photon kev =< (30 shallow WB ×− 2)

c. The NTA dosimeter (1941-1969) exhibited a lower energy threshold of approximately 700 kev (ORAU, 2004). The 

photon dose was measured adequately and all LBNL neutron dose was accompanied by a significant photon dose. For 

neutron dose received prior to 1969, the dose should be adjusted by using a neutron to photon ratio. The ratio varied by 

operation and task. For Buildings 6, 26, 70, 70A, 75 and 88, the neutron exposure was determined with a neutron to 

photon ratio of 0.73±2.10. The geometric mean was 0.73 and the geometric standard deviation was 2.10. The upper 

95th percentile was assumed to be 2.47.

Table 6-7. Bias and uncertainty. 

Site-specific dosimetry system

Bias magnitude and range Uncertainty factors

Overall biasa Range in biasb Systematicc Randomd

Photon/electron film (1941–1969) non Pu 

facility

1.27 1.23-1.60 1.2 1.8

Neutron NTA film (1941–1969) non Pu facility 1.0 0.5–2.0 1.05 2.0

Photon/electron film (1941–1969) Pu facility 1.0 0.25–2.0 1.05 1.3

Neutron NTA film (1941–1969) Pu facility 1.0 0.5–2.0 1.05 2.0

Harshaw photon/electron/neutron TLD (1969–

1985)

1.12 1.04–1.2 1.05 1.2

Panasonic photon/electron TLD (1986–present) 1.0 0.8–1.2 1.05 1.2

CR-39 neutron (1986–present) 1.0 0.6–1.5 1.05 1.5

a. Based on the distribution of energy levels and geometry judged most likely. Divide recorded dose by the table's bias 

value to calculate deep dose.

b. Range of overall bias factors based on alternative distributions of energy levels and geometry.

c. Systematic uncertainty resulting from lack of knowledge regarding actual distributions of energy levels and geometry.

d. Random uncertainty resulting from variation among workers in energy levels and geometry.
Document No. ORAUT-TKBS-0049 Revision No. 00 Effective Date: 08/07/2006 Page 42 of 55

REFERENCES

Alloway, D., 1957, "Nose Swipes - [Privacy Act information]," DIA-1027-57, memorandum to J. S. 

Lichliter, University of California, Lawrence Radiation Laboratory, Berkeley, California, 

September 11. [SRDB Ref ID: 21162]

AlMahamid, I., 2005, Technical Basis Document for Internal Dosimetry, EH&S Procedure 301, Rev. 4, 

University of California, Lawrence Berkeley National Laboratory, Berkeley, California, May 12. 

[SRDB Ref ID: 22749]

Bradfield, N. E., 1987, ”Operational Safety Procedures for Picker X-Ray Machine 26-126,” Lawrence 

Berkeley National Laboratory. See especially the handwritten note, bottom page 4, 

September 28, 1987.

Bradfield-Montoya, N., 1994, “Activity Hazard Document 163, Picker X-Ray Clinix,” Lawrence 

Berkeley National Laboratory, June 22, 1994.

Cantelow, H. P., 1976, "Environmental Sampling Data - 1975," HPC:047:76, memorandum to R. H. 

Thomas, University of California, Lawrence Berkeley Laboratory, Berkeley, California, 

February 26. [SRDB Ref ID: 23076]

CER (Center for Epidemiological Research), 1981, Dosimetry Hazards and Radiation Questionnaire, 

received as part of the DOE Health and Mortality Study, completed by E. H. Dolecek, 

(Argonne National Laboratory-East), Oak Ridge Associated Universities, Oak Ridge, 

Tennessee, December. [SRDB Ref ID: 18883]

de Castro, T. M., 1977a, “X-Ray Machine Survey – Building 26, March 1977,” memo to Dr. H. Stauffer 

(Medical Services, Lawrence Berkeley National Laboratory), October 13, 1977.

de Castro, T. M., 1977b, “X-Ray Machine Survey – Building 26, October 14, 1977,” memo to Dr. H. 

Stauffer (Medical Services, Lawrence Berkeley National Laboratory), October 14, 1977.

de Castro, T. M., and S. B. Thomas, 1975, “X-Ray Machine Survey – Building 26, March 19, 1975,” 

memo to Dr. T. Budinger (Medical Services, Lawrence Berkeley National Laboratory) April 1, 

1975.

de Castro, T., 1983, “Radiographic Safety and Performance Survey,” Lawrence Berkeley National 

Laboratory, February 18, 1983.

de Castro, T., 1986, “Radiographic Safety and Performance Survey,” Lawrence Berkeley National 

Laboratory, September 15, 1986.

de Castro, Ted, and Phil Hill, 1984, “Radiographic Safety and Performance Survey,” Lawrence 

Berkeley National Laboratory, April 20, 1984.

DOE (U.S. Department of Energy), 2002, Radionuclide Air Emission Report (in compliance with 40 

CFR 61, Subpart H), Calendar Year 2001, University of California, Lawrence Berkeley 

National Laboratory, Berkeley, California.
Document No. ORAUT-TKBS-0049 Revision No. 00 Effective Date: 08/07/2006 Page 43 of 55

DOE (U.S. Department of Energy), 2003, Radionuclide Air Emission Report for 2002 (in compliance 

with 40 CFR 61, Subpart H), Lawrence University of California, Berkeley National Laboratory, 

Berkeley, California, May.

DOE (U.S. Department of Energy), 2004, Radionuclide Air Emission Report for 2003 in compliance 

with 40 CFR 61, Subpart H), Lawrence University of California, Berkeley National Laboratory, 

Berkeley, California, May.

DOE (U.S. Department of Energy), 2005, Radionuclide Air Emission Report for 2004 (in compliance 

with 40 CFR 61, Subpart H), Lawrence University of California, Berkeley National Laboratory, 

Berkeley, California, May.

Dolecek E.H., 1981. Response to Dosimetry Records and Radiation Hazards Questionnaire, for the 

Department of Energy’s Health and Mortality Study, Oak Ridge Associated Universities, 

Argonne, Illinois.

Goldstein, H. A., 1989, Food and Drug Administration letter to H. H. Stauffer, M. D. (Medical Services 

Department, Lawrence Berkeley National Laboratory), March 2, 1989.

Hartsough, W. D., 1974, “Bioassay Programs,” letter to R. L. Westby (U. S. Atomic Energy 

Commission), University of California, Lawrence Berkeley Laboratory, Berkeley, California, 

August 26. [SRDB Ref ID: 21012]

Heinzelman, K, 2003, "(Name Withheld) EEOICPA Request," memorandum to C. Grandona, 

December 4, 2003

Hickey, E. E., G. A. Stoetzel, D. G. Strom, G. R. Cicotte, C. M. Wiblin, and S. A. McGuire, 1993, Air 

Sampling in the Workplace, Final Report, NUREG-1400, U.S. Nuclear Regulatory 

Commission, Office of Nuclear Regulatory Research, Washington, D.C., September. [SRDB 

Ref ID: 20129]

Howe, P. W., 1961a, “Bioassay Program,” memorandum to W. B. Reynolds, PWH-248-61, University 

of California, Lawrence Radiation Laboratory, Berkeley, California, March 17. [SRDB Ref ID: 

20569]

Howe, P. W., 1961b, untitled letter to Dr. L. B. Werner, PWH-472-61, University of California, 

Lawrence Radiation Laboratory, Berkeley, California, May 23. [SRDB Ref ID: 20664]

ICRP (International Commission on Radiological Protection), 1991, 1990 Recommendations of the 

International Commission on Radiological Protection, Publication 60, Pergamon Press, Oxford, 

England.

ICRP (International Commission on Radiological Protection), 1998, Individual Monitoring for Internal 

Exposure of Workers, Publication 78, Pergamon Press, Oxford, England.

Kaufman, J. A., 1957, "Results of Assay of Nose Swipes of [Privacy Act information] Taken after Spill 

in Room 143, Bldg. 70 on Sept. 12, 1957," JAK-1050-57, memorandum to J. S. Lichliter, 

University of California, Lawrence Radiation Laboratory, Berkeley, California, September 27. 

[SRDB Ref ID: 21161]
Document No. ORAUT-TKBS-0049 Revision No. 00 Effective Date: 08/07/2006 Page 44 of 55

Kelly, E. L., 1970, "Environmental Radiation Report for Second Half of 1969 and Annual Summary for 

1969," DC-70-159, letter with attachments to E. C. Snute (U.S. Atomic Energy Commission), 

University of California, Lawrence Radiation Laboratory, Berkeley, California, February 20. 

[SRDB Ref ID: 20989]

Kelly, E. L., 1970, "Environmental Radiation Report for Second Half of 1970 and the Annual Summary 

for 1971," DC-72-176, letter with attachments to E. C. Snute (U.S. Atomic Energy 

Commission), University of California, Lawrence Radiation Laboratory, Berkeley, California, 

February 23. [SRDB Ref ID: 23072]

LBL (Lawrence Berkeley Laboratory), 1965–1990, collection of employee bioassay records, University 

of California, Berkeley, California. [SRDB Ref ID: 21985, 21986]

LBL (Lawrence Berkeley Laboratory), 1980–1993, collection of internal dosimetry evaluations, 

University of California, Berkeley, California. [SRDB Ref ID: 21876]

LBL (Lawrence Berkeley Laboratory), 1988, annual summary of environmental monitoring for 1987, 

University of California, Berkeley, California. 

LBL (Lawrence Berkeley Laboratory), 1989, annual summary of environmental monitoring for 1988, 

University of California, Berkeley, California. 

LBL (Lawrence Berkeley Laboratory), 1990, annual summary of environmental monitoring for 1989, 

University of California, Berkeley, California. 

LBL (Lawrence Berkeley Laboratory), 1991, annual summary of environmental monitoring for 1990, 

University of California, Berkeley, California. 

LBL (Lawrence Berkeley Laboratory), 1992, annual summary of environmental monitoring for 1991, 

University of California, Berkeley, California. 

LBL (Lawrence Berkeley Laboratory), 1993, annual summary of environmental monitoring for 1992, 

University of California, Berkeley, California. 

LBL (Lawrence Berkeley Laboratory), 1994, annual summary of environmental monitoring for 1993, 

University of California, Berkeley, California. 

LBNL (Ernest Orlando Lawrence Berkeley National Laboratory), 1996, Lawrence Berkeley National 

Laboratory 1995 Site Environmental Report, LBL-27170 (1996), University of California, 

Berkeley, California, July.

LBNL (Ernest Orlando Lawrence Berkeley National Laboratory), 1997, Lawrence Berkeley National 

Laboratory 1996 Site Environmental Report, LBL-27170 (1997), University of California, 

Berkeley, California, July.

LBNL (Ernest Orlando Lawrence Berkeley National Laboratory), 1998, Site Environmental Report for 

1997, LBL-27170 (1998), University of California, Berkeley, California, September.

LBNL (Ernest Orlando Lawrence Berkeley National Laboratory), 1999, Site Environmental Report for 

1998, LBL-27170 (1999), University of California, Berkeley, California, September.
Document No. ORAUT-TKBS-0049 Revision No. 00 Effective Date: 08/07/2006 Page 45 of 55

LBNL (Ernest Orlando Lawrence Berkeley National Laboratory), 2000, Site Environmental Report for 

1999, LBL-27170 (2000), University of California, Berkeley, California, August.

LBNL (Ernest Orlando Lawrence Berkeley National Laboratory), 2001, Site Environmental Report for 

2000, LBL-27170 (2001), University of California, Berkeley, California, September. [SRDB Ref 

ID: 23058]

LBNL (Ernest Orlando Lawrence Berkeley National Laboratory), 2002, Site Environmental Report for 

2001, LBL-27170 (2002), University of California, Berkeley, California, August. [SRDB Ref ID: 

23063]

LBNL (Ernest Orlando Lawrence Berkeley National Laboratory), 2003, Site Environmental Report for 

2002, LBL-27170 (2003), University of California, Berkeley, California, July.

LBNL (Ernest Orlando Lawrence Berkeley National Laboratory), 2004, Site Environmental Report for 

2003, LBL-27170 (2004), University of California, Berkeley, California, July. [SRDB Ref ID: 

23059, 23060]

LBNL (Ernest Orlando Lawrence Berkeley National Laboratory), 2005b, Current RWA Locations 

Report, November 10, Berkeley, California.

LBNL (Ernest Orlando Lawrence Berkeley National Laboratory), 2005a, Site Environmental Report for 

2004, LBL-27170 (2005), University of California, Berkeley, California, September. [SRDB Ref 

ID: 23061, 23062]

LBNL (Lawrence Berkeley National Laboratory), 1995a, 1994 Site Environmental Report, LBL-27170 

(1995 rev.), University of California, Berkeley, California, May. [SRDB Ref ID: 6448]

LBNL (Lawrence Berkeley National Laboratory), 1995b, Technical Basis Document for Internal 

Dosimetry, University of California, Berkeley, California, May 12. [SRDB Ref ID: 20926]

Lichliter, J. S., 1964, "Revised Radiation Summary," memorandum to Distribution with 1963 radiation 

measurement attachments, University of California, Lawrence Radiation Laboratory, Berkeley, 

California. [SRDB Ref ID: 21060]

Low-Beer, A. deG., 1962, “Report of Bioassay Program for 1961,” memorandum to Dr. H. G. Parker, 

University of California, Lawrence Radiation Laboratory, Berkeley, California, January 10. 

[SRDB Ref ID: 21253]

Low-Beer, A. deG., 1963, Low-Beer, A.G., “Report of Bioassay Program for 1962,” memorandum to 

Dr. H. G. Parker, University of California, Lawrence Radiation Laboratory, Berkeley, California, 

January 31. [SRDB Ref ID: 21252]

LRL (Lawrence Radiation Laboratories), 1963, Lawrence Radiation Laboratory, Environmental 

Radiation Levels, Berkeley and Livermore, with attachments, University of California, Berkeley, 

California. [SRDB Ref ID: 21536]

LRL (Lawrence Radiation Laboratory), 1958a, collection of nose swipes reports for April 1958, 

University of California, Berkeley, California. [SRDB Ref ID: 21761]
Document No. ORAUT-TKBS-0049 Revision No. 00 Effective Date: 08/07/2006 Page 46 of 55

LRL (Lawrence Radiation Laboratory), 1958b, collection of nose swipes reports for March and April 

1958, University of California, Berkeley, California. [SRDB Ref ID: 21762]

LRL (Lawrence Radiation Laboratory), 1958c, collection of nose swipes reports for March 1958, 

University of California, Berkeley, California. [SRDB Ref ID: 21763]

LRL (Lawrence Radiation Laboratory), 1958d, collection of nose swipes reports for January and 

February 1958, University of California, Berkeley, California. [SRDB Ref ID: 21764]

LRL (Lawrence Radiation Laboratory), 1959a, "Health Chemistry Department Report of Special 

Analysis," University of California, Berkeley, California, July 20. [SRDB Ref ID: 21767]

LRL (Lawrence Radiation Laboratory), 1959b, collection of 1959 "Health Chemistry Department 

Reports of Special Analysis," University of California, Berkeley, California. [SRDB Ref ID: 

21768]

LRL (Lawrence Radiation Laboratory), 1960, collection of 1960 "Health Chemistry Department 

Reports of Special Analysis," University of California, Berkeley, California. [SRDB Ref ID: 

21769]

LRL (Lawrence Radiation Laboratory), 1961, collection of 1961 "Health Chemistry Department 

Reports of Special Analysis," University of California, Berkeley, California. [SRDB Ref ID: 

21770]

LRL (Lawrence Radiation Laboratory), 1967, collection of 1966 radiation measurement attachments, 

University of California, Berkeley, California. [SRDB Ref ID: 21052]

LRL (Lawrence Radiation Laboratory), 1968, Annual Summary of Environmental Monitoring -1967- 

Lawrence Radiation Laboratory, Berkeley, California, with attachment, University of California, 

Berkeley, California. [SRDB Ref ID: 20996]

LRL (Lawrence Radiation Laboratory), 1969, Annual Summary of Environmental Monitoring, 1968, 

Lawrence Radiation Laboratory, Berkeley, California, with attachment, University of California, 

Berkeley, California. [SRDB Ref ID: 20994]

LRL (Lawrence Radiation Laboratory), 1971, Annual Summary of Environmental Monitoring, 1970, 

Lawrence Radiation Laboratory, Berkeley, California, with attachment, University of California, 

Berkeley, California. [SRDB Ref ID: 20941]

LRL (Lawrence Radiation Laboratory), 1973, annual summary of environmental monitoring for 1972, 

University of California, Lawrence Radiation Laboratory, Berkeley, California.

LRL (LawrenceRadiationl Laboratory), undated circa 1971, Early Years of Bioassay at LRL, University 

of California, Berkeley, California,. [SRDB Ref ID: 21721] 

Maroncelli, J. M., and T. L. Karpin, 2002, The Traveler's Guide to Nuclear Weapons: A Journey 

Through America's Cold War Battlefields, Silverdale, Washington. 

McClelland, J., 1958, Analytical Procedures of the Industrial Hygiene Group, LA-1858 (2nd Edition), 

University of California, Los Alamos Scientific Laboratory, Los Alamos, New Mexico, 

September 1. [SRDB Ref ID: 12948]
Document No. ORAUT-TKBS-0049 Revision No. 00 Effective Date: 08/07/2006 Page 47 of 55

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

Implementation Guideline, OCAS-IG-001, Rev. 1, Office of Compensation Analysis and 

Support, Cincinnati, Ohio, August.

ORAU, 2004. Technical Basis Document for the Hanford Site- Occupational External Dosimetry, 

ORAUT-TKBS-0006-6, January 19, 2004.

ORAU, 2005a, Dose Reconstruction from Occupationally Related Diagnostic X-Ray Procedures, 

ORAUT-OTIB-0006, Revision. 03 PC-1, Oak Ridge, Tennessee, December 21.

ORAU, 2005b. Supplemental Dose Information for the Rocky Flats Plant, ORAUT-OTIB-0027, May 

19, 2005.

ORAU, 2005d. Interpretation Of Dosimetry Data For Assignment Of Shallow Dose, ORAUT-OTIB0017, October 11, 2005.

ORAU, 2006. Argonne National Laboratory – East, External Dosimetry, ORAUT-TKBS-0036-6, 

ORAUT-TKBS-0036-6, February 9, 2006.

ORAUT (Oak Ridge Associated Universities Team), 2006, Argonne National Laboratory-East – 

External Dosimetry, ORAUT-TKBS-0036-6, Rev. 00, Oak Ridge, Tennessee, February 9.

Pardue, L. A., N. Goldstein, and E. O. Wollan, 1944, Photographic Film As a Pocket Radiation 

Dosimeter, CH-1553-A-2223, University of Chicago, Metallurgical Laboratory, Chicago, Illinois, 

April. [SRDB Ref ID: 8599] 

Patterson, H. W., 1962, untitled memorandum to J. S. Lickliter, University of California, Lawrence 

Radiation Laboratory, Berkeley, California, January 15. [SRDB Ref ID: 21085]

Patterson, H. W., 1965, untitled memorandum to J. S. Lichliter with 1964 radiation measurement 

attachments, University of California, Lawrence Radiation Laboratory, Berkeley, California, 

February 11. [SRDB Ref ID: 21059]

Patterson, H. W., 1966, untitled memorandum to J. S. Lichliter with 1965 radiation measurement 

attachments, University of California, Lawrence Radiation Laboratory, Berkeley, California, 

May 8. [SRDB Ref ID: 21055]

Patterson, H. W., A. deG. Low-Beer, and T. W. Sargent, 1969, Whole-Body Counting and Bioassay 

Determinations Made on Accelerator Workers, UCRL-18683 (Preprint), University of 

California, Lawrence Radiation Laboratory, Berkeley, California, January 3. [SRDB Ref ID: 

21694]

Pickler, D. A., 1975, “Answers to Questions on Bioassays,” letter to S. P. Fivozinsky (U.S. Department 

of Commerce), State of California, Radioactive Materials Licensing, February 21. [SRDB Ref 

ID: 21276]

Schleimer, G. E., editor, 1979, Annual Environmental Monitoring Report of the Lawrence Berkeley 

Laboratory, 1978, LBL-9080, University of California, Lawrence Berkeley Laboratory, Berkeley, 

California, April. [SRDB Ref ID: 23080]
Document No. ORAUT-TKBS-0049 Revision No. 00 Effective Date: 08/07/2006 Page 48 of 55

Schleimer, G. E., editor, 1980, Annual Environmental Monitoring Report of the Lawrence Berkeley 

Laboratory, 1979, LBL-11192, University of California, Lawrence Berkeley Laboratory, 

Berkeley, California, June. [SRDB Ref ID: 23082]

Schleimer, G. E., editor, 1981, Annual Environmental Monitoring Report of the Lawrence Berkeley 

Laboratory, 1980, LBL-12604, University of California, Lawrence Berkeley Laboratory, 

Berkeley, California, June. [SRDB Ref ID: 23083]

Schleimer, G. E., editor, 1982, Annual Environmental Monitoring Report of the Lawrence Berkeley 

Laboratory, 1981, LBL-14553, University of California, Lawrence Berkeley Laboratory, 

Berkeley, California, June. [SRDB Ref ID: 23084]

Schleimer, G. E., editor, 1983, Annual Environmental Monitoring Report of the Lawrence Berkeley 

Laboratory, 1982, LBL-15978, University of California, Lawrence Berkeley Laboratory, 

Berkeley, California, April. [SRDB Ref ID: 23085]

Schleimer, G. E., editor, 1984, Annual Environmental Monitoring Report of the Lawrence Berkeley 

Laboratory, 1983, LBL-17622, University of California, Lawrence Berkeley Laboratory, 

Berkeley, California, April. [SRDB Ref ID: 23086]

Schleimer, G. E., editor, 1985, Annual Environmental Monitoring Report of the Lawrence Berkeley 

Laboratory, 1984, LBL-19345, University of California, Lawrence Berkeley Laboratory, 

Berkeley, California, April. [SRDB Ref ID: 23087]

Schleimer, G. E., editor, 1986, Annual Environmental Monitoring Report of the Lawrence Berkeley 

Laboratory, 1985, LBL-21447, University of California, Lawrence Berkeley Laboratory, 

Berkeley, California, April. [SRDB Ref ID: 23088]

Schleimer, G. E., editor, 1987, Annual Environmental Monitoring Report of the Lawrence Berkeley 

Laboratory, 1986, LBL-23235, University of California, Lawrence Berkeley Laboratory, 

Berkeley, California, April. [SRDB Ref ID: 23089]

Soule, H. F., 1962, “Revision to Bioassay Schedule,” memorandum to Dr. H. G. Parker, HFS-258-62, 

University of California, Lawrence Radiation Laboratory, Berkeley, California, March 22. 

[SRDB Ref ID: 20908]

Stephens, L. D., and H. Cantelow, 1975, Annual Environmental Monitoring Report -- 1974, LBL-3821, 

University of California, Lawrence Berkeley Laboratory, Berkeley, California, March 4. [SRDB 

Ref ID: 23075]

Stephens, L. D., editor, 1977, Annual Environmental Monitoring Report of the Lawrence Berkeley 

Laboratory, LBL-6405, University of California, Lawrence Berkeley Laboratory, Berkeley, 

California, March. [SRDB Ref ID: 23077]

Stephens, L. D., editor, 1978, Annual Environmental Monitoring Report of the Lawrence Berkeley 

Laboratory, 1977, LBL-7530 with addendum, University of California, Lawrence Berkeley 

Laboratory, Berkeley, California, March. [SRDB Ref ID: 23078]

Sunderman, D. N., and C. W. Townley, 1960, The Radiochemistry of Barium, Calcium, and Strontium, 

NAS-NS 3010, National Academies Press, Washington, D.C.
Document No. ORAUT-TKBS-0049 Revision No. 00 Effective Date: 08/07/2006 Page 49 of 55

Szalinski, P. A., 2006, “E. A. Langille and J. G. Floyd, Discussion on Internal Exposure Monitoring 

Changes around 1996,” documented communication, Oak Ridge Associated Universities, Oak 

Ridge, Tennessee, May 4.

Thomas, M., 1991, Food and Drug Administration letter to H. Stauffer, M. D. (Medical Services 

Department, Lawrence Berkeley National Laboratory), September 13, 1991.

Thomas, R. H., 1974, untitled letter with attachments to H. Carwell (U.S. Atomic Energy Commission), 

University of California, Lawrence Berkeley Laboratory, Berkeley, California, March 4. [SRDB 

Ref ID: 23073]

Vargha, P., 1996a, "Cover Letter for QA Manual," memorandum with attachment to K. Dinnel, FS-96-

352, University of California, Lawrence Berkeley National Laboratory, Berkeley, California, 

April 5. [SRDB Ref ID: 20898]

Vargha, P., 1996b, “WBC Records,” memorandum to K. Dinnel, FS-96-334, University of California, 

Lawrence Berkeley National Laboratory, Berkeley, California, March 27. [SRDB Ref ID: 

20902]

Vaughan, P. N., 1982, “Completion of Routine Safety Maintenance, the X-Ray Machine Designated 

Picker 26-126,” report sent to T. de Castro, Lawrence Berkeley Laboratory, March 18, 1982.
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GLOSSARY

absorbed dose

Energy absorbed per unit mass; units are rad and gray.

activity median aerodynamic diameter (AMAD)

The diameter of a unit density sphere with the same terminal settling velocity in air as that of 

the aerosol particle whose activity is the median for the entire aerosol.

acute

Pertaining to intakes received “acutely,” i.e., within a short period. 

alpha radiation

Radiation consisting of charged particles identical with the isotope helium-4.

background radiation

Radiation received that is not associated with a worker’s occupation. This includes cosmic 

and terrestrial sources.

backscatter

Radiation that is scattered backwards, enhancing skin dose in areas where X-ray beam enters 

the body.

becquerel (Bq)

The derived International System unit of radioactivity equal to one disintegration per second.

beta radiation

Radiation consisting of electrons emitted spontaneously from the nuclei of certain radioactive 

elements.

bioassay

Measurement of amount or concentration of radioactive material either in the body or in 

biological material excreted or removed from the body. Another word for radiobioassay. 

bioassay procedure

A procedure used to determine the kind, quantity, location, and retention of radionuclides in 

the body by direct (in vivo) measurements or by in vitro analysis of material excreted or 

removed from the body.

body burden

The quantity of radioactive material contained in the individual's body at a particular point in 

time.

chronic

Pertaining to low-level intakes received on a prolonged basis.

curie

A special unit of activity. One curie exactly equals 3.7 × 1010 nuclear transitions per second.
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dose 

A general term for absorbed dose, dose equivalent, effective dose equivalent, committed dose 

equivalent, committed effective dose equivalent, or total effective dose equivalent.

deep dose equivalent

Dose equivalent at a depth of 1.0 cm in soft tissue.

depleted uranium

The uranium remaining after removing 235U from natural uranium. The remaining isotopic 

content is typically on the order of 99.8% 238U, 0.2% 235U, and a trace amount (0.001%) of 

234U. 

dose equivalent (H)

The product of absorbed dose (D) in rad (or gray) in tissue, a quality factor (Q), and other 

modifying factors (N). Dose equivalent is expressed in units of rem (or sievert) (1 rem = 0.01 

sievert).

dosimeter

A device used to measure the quantity of radiation received. A holder with radiation-absorbing 

elements (filters) and an insert with radiation-sensitive elements packaged to provide a record 

of absorbed dose or dose equivalent received by an individual. (See film dosimeter, neutron 

film dosimeter, thermoluminescent dosimeter.)

dose equivalent

Product of absorbed dose and a quality factor or radiation weighting factor. With absorbed 

dose in rad, unit is rem.

dosimetry

The science of assessing absorbed dose, dose equivalent, effective dose equivalent, etc., 

from external and internal sources of radiation.

dosimetry system

A system used to assess dose equivalent from external radiation to the whole body, skin, or 

extremities. This includes the fabrication, assignment, and processing of dosimeters as well 

as interpretation and documentation of the results.

exposure

The general condition of being subjected to ionizing radiation, such as by exposure to ionizing 

radiation from external sources or to ionizing radiation sources inside the body. In this 

document, exposure does not refer to the radiological physics concept of charge liberated per 

unit mass of air. 

film

In the context of this document, a packet that contains one or more pieces of film in a lighttight wrapping. The film when developed has an image caused by radiation that can be 

measured using an optical densitometer. (See nuclear emulsion.)

film dosimeter

A small packet of film within a holder that attaches to a wearer.
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fission products

Isotopes formed during fission of uranium or plutonium.

gamma rays

Electromagnetic radiation (photons) originating in atomic nuclei and accompanying many 

nuclear reactions (e.g., fission, radioactive decay, and neutron capture). Physically, gamma 

rays are identical to X-rays of high energy, the only essential difference being that X-rays do 

not originate in the nucleus.

gray

Unit of absorbed dose, defined as 1 joule per kilogram. It is equal to 100 rad. 

intake

The amount of radionuclide taken into the body by inhalation, absorption through intact skin, 

injection, ingestion, or through wounds. Depending on the radionuclide involved, intakes can 

be reported in units of mass, activity, or potential alpha energy.

internal dose or exposure

The dose equivalent received from radioactive material taken into the body (i.e., internal 

sources).

internal dose assessment

An assessment of the intake and associated internal radiation dose to workers based on 

measurements taken in the work environment or from individual bioassay measurements.

in vitro measurement

Measurements to determine the presence of or to estimate the amount of radioactive material 

in the excreta or in other biological materials removed from the body.

in vivo measurement

The measurement of radioactive material in the human body utilizing instrumentation that 

detects radiation emitted from the radioactive material in the body.

lung solubility type (F, M, or S)

A classification scheme for inhaled material according to its rate of clearance from the 

pulmonary region of the lung.

minimum detectable amount (MDA)

The smallest amount (activity or mass) of an analyte in a sample that will be detected with a 

probability of nondetection (Type II error) while accepting a probability of erroneously deciding 

that a positive (non-zero) quantity of analyte is present in an appropriate blank sample (Type I 

error).

minimum detection level (MDL)

The minimum quantifiable dose equivalent that a given dosimetry system can reliably 

measure.

missed dose

The potential dose equivalent that might not have been measured due to the limitation of the 

dosimeter, even though a worker was monitored.
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monitoring (personnel)

The measurement of radioactivity in the whole body, in a region of the body, in material 

eliminated from the body or in the air for reasons related to the estimation of intake of 

radioactive material. The term monitoring includes interpretation of the measurements.

natural uranium

Uranium is a naturally occurring radioactive element consisting of three isotopes: 238U 

(99.276%), 235U (0.719%), and a trace amount of 234U (0.0057%). 

neutron

A basic particle that is electrically neutral and has nearly the same mass as the hydrogen

atom.

neutron film dosimeter

A film dosimeter that contains a nuclear track emulsion, type A, film packet.

nuclear track emulsion, Type A (NTA)

A film that is sensitive to fast neutrons. The developed image has tracks caused by neutrons 

that can be seen by using an appropriate imaging capability such as oil immersion and 

1,000-power microscope or a projection capability.

occupational dose

An individual's ionizing radiation dose (external and internal) resulting from that individual's 

work assignment. Occupational dose does not include doses received as a medical patient or 

doses resulting from background radiation or participation as a subject in medical research 

programs.

occupational exposure

Individuals’ exposure to radiation and/or to radioactive material from sources of radiation, 

whether in the possession of the DOE site contractor or other person, in a restricted area or in 

the course of employment in which the individual's assigned duties. Occupational exposure 

does not include exposure to background radiation, as a patient from medical practices, from 

voluntary participation in medical research programs, or as a member of the general public.

occupational medical exposure

Individuals’ exposure to radiation or radioactive materials from medical diagnostic procedures 

during physical examinations which are required as a condition of employment. For the 

purpose of dose reconstruction, occupational medical exposure is considered a component of 

occupational exposure.

personal dose equivalent, Hp(d)

Represents the dose equivalent in soft tissue below a specified point on the body at an 

appropriate depth d. The depths selected for personnel dosimetry are 0.07 millimeter and 

10 millimeters for the skin and body, respectively. These are noted as Hp(0.07) and Hp(10), 

respectively.

photon

A unit or particle of electromagnetic radiation consisting of X- and/or gamma rays.

primary X-rays 

X-rays that constitute the useful beam that emerges from an X-ray machine tube.
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rad

Unit of absorbed dose, defined as 100 ergs per gram. It is equal to is 0.01 gray. 

radiation

Ionizing radiation: alpha particles, beta particles, gamma rays, X-rays, neutrons, high-speed 

electrons, high-speed protons, and other particles capable of producing ions. Radiation, as 

used in this document, does not include nonionizing radiation, such as radio- or microwaves, 

or visible, infrared, or ultraviolet light.

radioactivity

The spontaneous emission of radiation, generally alpha or beta particles, gamma rays, and 

neutrons from unstable nuclei.

rem

Unit of dose equivalent. 

roentgen (R)

Unit of exposure.

routine monitoring

Monitoring carried out at regular intervals during normal operations.

secondary X-rays 

As distinct from primary X-rays, secondary X-rays are those that are scattered from objects or 

leak from the source assembly.

shallow absorbed dose (Ds) 

The absorbed dose at a depth of 0.07 millimeter in a material of specified geometry and 

composition.

shallow dose equivalent (Hs)

Dose equivalent at a depth of 0.07 millimeter in tissue.

sievert

The special name for the International System unit of dose equivalent. One sievert equals 1 

joule per kilogram, which equals 100 rem.

special monitoring

Monitoring carried out in actual or suspected abnormal conditions (i.e., measurements 

performed to estimate the amount of radionuclide deposited in a person when an intake is 

known or is suspected to have occurred). 

spot sample

A single void of urine.

thermoluminescence

Property of a material that causes it to emit light as a result of being excited by heat.
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thermoluminescent dosimeter (TLD)

A device used to measure radiation dose. It consists of a holder containing solid chips of 

material that when heated will release the stored energy as light. The measurement of this 

light provides a measurement of absorbed dose.

transuranic elements

Elements with an atomic number greater than uranium (92).

unmonitored dose

The potential unrecorded dose equivalent that could have resulted because an exposed 

worker was not monitored.

whole-body dose

Commonly defined as the absorbed dose at a tissue depth of 1.0 centimeter (1,000 milligrams 

per square centimeter); however, this term is also used to refer to the recorded dose.

X-ray

(1) Electromagnetic radiation emitted by fast electrons slowing down in matter or in certain 

electronic transitions in atoms. (2) A radiograph produced by X-rays.