Page 1 of 133

DOE Review Release 04/04/2018

Monitoring Feasibility Evaluation for Exotic 

Radionuclides Produced by the Oak Ridge 

National Laboratory Isotopes Division 

ORAUT-RPRT-0090 Rev. 00 

Effective Date: 03/29/2018 

Supersedes: None 

Subject Expert(s): Joseph S. Guido

Document Owner 

Approval: Signature on File

Joseph S. Guido, Document Owner

Approval Date: 03/28/2018 

Concurrence: Signature on File

Matthew C. McFee, Objective 4 Manager

Concurrence Date: 03/29/2018

Concurrence: Vickie S. Short Signature on File for

Kate Kimpan, Project Director

Concurrence Date: 03/29/2018

Approval: Signature on File

James W. Neton, Associate Director for Science

Approval Date: 03/29/2018

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

REVISION AND DISCARD / DESTROY ALL COPIES OF THE PRIOR REVISION.

New Total Rewrite Revision Page Change
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PUBLICATION RECORD

EFFECTIVE 

DATE

REVISION 

NUMBER DESCRIPTION

03/29/2018 00 New report evaluating the Oak Ridge National Laboratory capability 

to monitor internal exposure to exotic radionuclides that were 

produced by the laboratory’s Isotopes Division. Incorporates formal 

internal and NIOSH review comments. Initiated by Joseph S. Guido. 
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TABLE OF CONTENTS

SECTION TITLE PAGE

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

1.0 Purpose ................................................................................................................................... 6

2.0 Scope....................................................................................................................................... 6

3.0 Isotope Production ................................................................................................................... 6

3.1 ORNL Facilities ............................................................................................................ 6

3.2 Y-12 Facilities............................................................................................................... 8

3.3 Material Transfers......................................................................................................... 8

4.0 Evaluation of Bioassay Program and Data ............................................................................... 9

4.1 Sampling Program........................................................................................................ 9

4.2 ORNL Bioassay Data ................................................................................................. 10

4.3 NOCTS Bioassay Data............................................................................................... 13

5.0 Evaluation of In Vivo Monitoring Counting Program ............................................................... 15

6.0 Inventory Development .......................................................................................................... 17

7.0 Feasibility Analysis................................................................................................................. 24

7.1 Initial Evaluation ......................................................................................................... 24

7.2 Additional Evaluation .................................................................................................. 25

8.0 Summary ............................................................................................................................... 43

References ........................................................................................................................................ 44

ATTACHMENT A SUMMARY OF IN VITRO BIOASSAY METHODS.......................................... 48

ATTACHMENT B SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER 

ANALYSIS ...................................................................................................... 56

ATTACHMENT C DOSE RECONSTRUCTION APPROACH FOR IODINE............................... 110
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LIST OF TABLES

TABLE TITLE PAGE

4-1 Urine bioassay codes used at ORNL, 1955 to 1988............................................................... 10

4-2 Fecal bioassay codes in use at ORNL, 1955 to 1988............................................................. 11

4-3 Bioassay code 000 with monitored nuclide, 1955 to 1988 ...................................................... 12

4-4 NOCTS versus ORNL database comparison of sample frequency by year............................ 13

4-5 NOCTS versus ORNL database comparison of sample frequency by analyte code............... 14

4-6 Gross beta samples in NOCTS and ORNL datasets (analyte codes 013 and GB0) ............... 15

5-1 Tabulation of in vivo counts from database versus annual reports ......................................... 16

6-1 Sources of radionuclide production information...................................................................... 18

6-2 Radionuclides added to inventory due to target rupture events .............................................. 19

6-3 Final radionuclide inventory for Isotopes Division................................................................... 20

7-1 Comparison of 35S production and number of reported bioassay samples ............................. 24

7-2 Results of feasibility analysis for 1955 to 1969....................................................................... 26

7-3 Results of feasibility analysis for 1970 to 1988....................................................................... 32

7-4 Thirty-four radionuclides identified as needing additional evaluation ...................................... 39

7-5 Derived air concentration values for 28 radionuclides requiring further evaluation ................. 39

7-6 Dosimetric analysis of radionuclides ...................................................................................... 41

7-7 Number of bioassay samples collected for code 000 analytes by year................................... 42

C-1 Commercial 131I production, 1946 to 1969............................................................................ 112

C-2 Weekly average number of gross beta/gamma air samples ................................................. 112

C-3 Available thyroid counting data, 1945 to 1957...................................................................... 113

C-4 Tolerance equivalents for various GM detectors .................................................................. 115

C-5 Calibration factors used to convert thyroid counting data ..................................................... 116

C-6 Summary of WBC data for 131I .............................................................................................. 116

C-7 Summary of available iodine urine samples ......................................................................... 117

C-8 Iodine urine bioassay samples by sample type .................................................................... 117

LIST OF FIGURES

FIGURE TITLE PAGE

3-1 General layout of isotope facilities............................................................................................ 7

3-2 Isotope production flow, 1955 to 1965...................................................................................... 9

C-1 Comparison of acute and chronic intake assessments......................................................... 118
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ACRONYMS AND ABBREVIATIONS 

CAM continuous air monitor

Ci curie

cm centimeter

cpm counts per minute

d day

DAC derived air concentration

DCF dose conversion factor

DOE U.S. Department of Energy

GM Geiger-Müller

HP health physics

hr hour

ICRP International Commission on Radiological Protection

in. inch

IMBA Integrated Modules for Bioassay Analysis

keV kiloelectron-volt (1,000 electron-volts)

m meter

mCi millicurie

min minute

mL milliliter

MPC maximum permissible concentration

mR milliroentgen

mrem millirem

nCi nanocurie

NIOSH National Institute for Occupational Safety and Health

NOCTS NIOSH-Division of Compensation Analysis and Support Claims Tracking System

ORAU Oak Ridge Associated Universities

ORNL Oak Ridge National Laboratory

pCi picocuries

RaLa radioactive lanthanum

s second

SEC Special Exposure Cohort

SRDB Ref ID Site Research Database Reference Identification (number)

WBC whole-body count

yr year

Y-12 Y-12 Plant (now Y-12 National Security Complex)

μCi microcurie
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1.0 PURPOSE

This report evaluates the internal monitoring capability of Oak Ridge National Laboratory (ORNL) for 

radionuclides that were produced by the Isotopes Division (termed “exotic radionuclides) and its 

predecessors from 1955 to 1988. The evaluation was initiated after publication of Special Exposure 

Cohort (SEC) evaluation report for ORNL (SEC-00189; NIOSH 2012), which left the issue on exotic 

radionuclides reserved. As a result of the evaluation of SEC-00189, a class was added to the SEC 

from the beginning of ORNL operations through July 31, 1955. The SEC evaluated isotopes of 

uranium, plutonium, thorium, and mixed fission products. Isotope production involved a wide array of 

radioactive materials (termed “exotic radionuclides”). Because of the potential challenges involved in 

monitoring intakes from such a wide variety of materials, the National Institute for Occupational Safety 

and Health (NIOSH) determined that an evaluation of the monitoring methods available at the time, 

and of the Isotopes Division materials, was necessary. The evaluation methodology consisted of the 

following steps:

• Identification of radionuclides that were produced by the Isotopes Division;

• Identification of available bioassay methodologies;

• Chronological benchmarking of the available bioassay methods against the radionuclide 

inventory to identify potential gaps in monitoring capability; and

• Evaluation of identified monitoring gaps to determine if dose reconstruction for these exotic 

radionuclides is feasible. 

2.0 SCOPE

The period under evaluation in this report is August 1, 1955, through December 31, 1988. The start 

date was selected to coincide with the end of the SEC period (NIOSH 2012). The end date coincides 

with the end of large-scale isotope production at ORNL. It should be noted that all operations under 

evaluation were managed by ORNL. Although most of the facilities were on the ORNL campus (many 

in an area termed “Isotope Circle”), the Isotope Division also used the cyclotron and calutron facilities 

at the Y-12 Plant. This report evaluates the monitoring capability of the ORNL HP program to have 

monitored all materials that were produced and handled by the Isotopes Division regardless of 

production location.

3.0 ISOTOPE PRODUCTION

Isotope production occurred at both ORNL and Y-12 under ORNL management. At times, Y-12 

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

transferred to ORNL.

3.1 ORNL FACILITIES

In the late 1940s, ORNL initiated a program to replace the wartime temporary structures with more 

permanent buildings. A major focus of this program was the provision for a radioisotope complex of 

10 buildings designed for processing, packaging, and shipping radioisotopes (Carver and 

Slater 1994).

Isotopes are produced in reactors, extracted by chemical processes, and then used for biological, 

medical, and industrial research. As early as 1946, radioisotopes were produced in the Oak Ridge 

Research Reactor. In 1947, the Isotopes Section (later Division) was formed at the Clinton 
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Laboratories. By 1950, ORNL was distributing (by order) over 50 radioisotopes to research centers 

around the world. 

Figure 3-1 shows the radioisotope buildings constructed under this expansion, which are grouped in 

an area termed “Isotope Circle.” The ten buildings, one stack, and their original designations were: 

• 3028 Radioisotope Processing Building F,

• 3029 Radioisotope Processing Building E,

• 3030 Radioisotope Processing Building D,

• 3031 Radioisotope Processing Building C,

• 3032 Radioisotope Processing Building B,

• 3033 Radioisotope Processing Building A,

• 3034 Radioisotope Service Building,

• 3036 Decontamination Building,

• 3037 Radioisotope Area Office Building,

• 3038 Radioisotope Analytical and Pack Building, and

• 3039 Exhaust Stack.

Figure 3-1. General layout of isotope facilities (Carver and Slater 1994).

One building (3038) was used for the analysis, storage, packaging, and shipment of materials. Six 

small buildings (3028 to 3033) were dedicated to radioisotope production and development, each 

having dedicated shielding and remote-handling capabilities. The use of dedicated small areas for 

material processing was purposeful to minimize interaction between different processing areas and to 

minimize the potential number of exposed individuals within each operational area (Thompson 1952). 
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The Fission Products Development Laboratory (Building 3517) was completed in 1958. It was 

originally designed and built to separate kilocurie quantities of 137Cs, 90Sr, 144Ce, and 147Pm from liquid 

reduction-oxidation and plutonium-uranium extraction waste streams. The facility was modified in 

1963 to allow production of megacurie amounts of 137Cs, 90S and 144Ce, primarily for use in the 

Systems for the Nuclear Auxiliary Power program. Large quantities of 244Cm were stored in the 

building (ORNL 1986).

In 1962, Building 3047 was built to house the Radioisotopes Development Laboratory for research 

and development and to produce radioisotopes. The radioactive materials the Isotopes Division 

handled included 90Sr, 137Cs, 152Eu, 154Eu, 238Pu, 111mSn, 166Dy/Ho, 186Re, and 188W/188Re. A single 

sealed source of 90Sr had activity as high as 350,000 Ci (MMES 1995). 

3.2 Y-12 FACILITIES

Concurrently with production of isotopes in reactors on the ORNL campus, the Isotopes Division 

involved the use of the cyclotron and calutron facilities on the Y-12 site to produce isotopes.

The calutron (electromagnetic separation) facilities were originally built to separate uranium isotopes 

and recover uranium enriched in 235U. With the successful operation of the gaseous diffusion 

process, the calutrons were phased out as a production operation for enriching uranium. 

By the end of 1950, plans were made to use the calutron facilities to separate the isotopes of 

plutonium to allow more accurate measurement of their nuclear properties. The first isotope to be 

separated was to be 240Pu, followed by 242Pu and 244Pu. Before 1962, radioisotope production in the 

Y-12 facility was limited to small quantities of plutonium and uranium that were produced in one or two 

calutrons in Track 5 of Building 9204-3, which was functionally separated from the other calutrons. In 

1962, a containment facility was built in Building 9204-3 that included separations areas, chemical 

processing areas, a change room, and a locker room. The actinide area operated continuously from 

1962 to 1972 and chiefly separated isotopes of plutonium and uranium but included many other 

isotopes:

• Americium-241, -242, -243; 

• Beryllium-9, -10; 

• Calcium-40, -41, -42, -43, -44, -46, -48; 

• Curium-243, -244, -245, -246, -247, -248, -250; 

• Lead-201, -204, -205, -206, -207, -208; 

• Plutonium-238, -239, -240, -241, -242, -244; 

• Promethium-146, -147; 

• Samarium-147, -148, -149, -150, -151, -152, -154; 

• Thorium-228, -230, -232; 

• Uranium-232, -233, -234, -235, -236, -238; and

• Yttrium-78. 

3.3 MATERIAL TRANSFERS

Figure 3-2 shows the production flow between ORNL, Y-12, and offsite locations. Certain 

radionuclides were produced at the ORNL Graphite Reactor, the cyclotron, and the calutrons. Some 

materials containing exotic radionuclides were shipped off site right after production, while others 

underwent further processing at ORNL first.
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Figure 3-2. Isotope production flow, 1955 to 1965 (NIOSH 2012). 

4.0 EVALUATION OF BIOASSAY PROGRAM AND DATA

4.1 SAMPLING PROGRAM

ORNL has collected urine and fecal samples from individuals suspected of potential intakes from 

1945 (and possibly as early as 1943) to the present. The processing of urine samples at the ORNL 

Urinalysis Building started in 1947 (Davis and Warden 1954) and was performed by the ORNL Body 

Fluids Analysis group (Burnett 1948). 

In the early years of the bioassay program, urine samples were collected based on the Area Health 

Physicist’s knowledge of field conditions (e.g., known spills or incidents, air and contamination sample 

results). A June 1950 document, Procedure for the Collection of Urine Samples, indicates that it was 

ORNL policy to “collect and analyze certain body fluids of all employees who work with large 

quantities of uranium, plutonium, and other types of radioactive materials” (Hart 1950). This 

procedure gave the responsibility for the selection of individuals for urine bioassay to the area HP 

staff. Urine samples were to be submitted along with a request form (Form X-386) indicating, among 

other things, the type and quantity of radioactivity with which the individual worked. A March 1954 

revision to this procedure (ORNL 1954a) included consideration of the need to make a second 

request for sample submission and made use of the same request format. By 1957, the sampling 

request was revised to include a list of routine analytes that could be requested (H-3, polonium, 

plutonium, radium, strontium, uranium, gross alpha, and gross beta) along with a space to write in a 

radionuclide name.

In earlier years, the element of concern was extracted chemically from the biological sample and the 

total radioactivity of the element in the extract was measured. At some point after the extraction and 

sample count, the total sample activity was attributed to a specific radionuclide. Many of the isotopic 

assignments were based on process knowledge because isotope-specific analyses were not possible 

or routinely performed.
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To evaluate the effectiveness of its bioassay program, and as a possible basis for improvement, 

ORNL conducted a study of all urinalysis samples from July 2, 1953, to August 23, 1954 (Davis and 

Warden 1954). The total number of samples was 1,265. ORNL concluded that the method for that 

period seemed adequate. They recommended that a major emphasis be placed on obtaining 

samples for employees regularly working with radioactive materials and that the sampling schedule be 

left at the discretion of the HP area surveyor. It was further recommended that the surveyor annually 

select at random a number of employees who do not work regularly with radioactive materials and 

suggest to them that they submit a sample.

Infrequently, a request was made for determination of a radionuclide not included in the routine 

procedure. Such determinations were usually made by the use of, or modification of, existing 

analytical methods from the literature (Henley 1968).

Attachment A summarizes the initial development of ORNL bioassay methods. The discussion in this 

attachment provides detail up through the initial deployment of each bioassay method.

4.2 ORNL BIOASSAY DATA

The Oak Ridge Associated Universities (ORAU) Team obtained a copy of the ORNL bioassay 

database dated April 28, 2013 (ORNL 2013). This database contains the results of 104,957 individual 

bioassay samples from September 7, 1949, through December 21, 1988. Of these, there are 94,988 

with collection dates during the period under evaluation in this report. These 94,988 samples (3,121 

fecal; 91,867 urine) were collected from 7,564 individual workers and subjected to analysis for 62 

different individually identified analytes and code 000, which indicates other. This code indicates a 

nonstandard analytical method. There were 1,532 code 000 urine samples from 502 individuals, 52

code “OO0” urine samples from 33 individuals, and 140 code “OF0” fecal samples for 64 individuals 

(note that the combination of capital “O” and numeral “0” in a code is not a transcription error.) 

Tables 4-1 and 4-2 provide a summary of the bioassay methods the ORNL bioassay database lists for 

urine and fecal samples, respectively. 

Table 4-1. Urine bioassay codes used at ORNL, 1955 to 1988. 

Bioassay 

code Description/analyte

Number of 

samples Period in use

000 Other 1,532 1955,1958,1961,1963–1974,1976–1977,1979–1983,1985

OO0a Other 52 1986–1988

001 S-35 3 1958–1959,1961

002 Co-60 14 1961–1963

003 Pb-210 3 1960

004 Na-24 2 1960

005 Zr-95/Nb-95 13 1960–1963

006 Tc-99 11 1960–1964

007 As-74 6 1960

008 Br-82/Br-83 6 1960–1961

009 Fe-59 11 1960,1964

010 Mn-54 3 1960,1978

011 I-131 13 1958,1961–1964

012 Cs-132 2 1961

013 Gross beta 153 1955,1960–1964

014 Ba-140 1 1961

015 Sb-125 18 1962–1963

016 Tl-204 7 1962

017 Np-237 12 1962–1964

018 Ag-110m 1 1963

AM0 Am-241 1 1987
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Table 4-1. Urine bioassay codes used at ORNL, 1955 to 1988 (continued). 

Bioassay 

code Description/analyte

Number of 

samples Period in use

C-14 C-14 67 1986–1988

CM0 Cm-244 11 1986,1988

CO0 Co-60 144 1963,1965,1967–1969,1972–1976,1982,1984,1987–1988

CS0 Cesium beta 1,589 1964–1970,1972–1977,1980–1988

CS7 Cs-137 284 1955–1957,1959–1964

FP0 Fission products 17 1956–1958

FU0 Total rare earth 1,333 1959–1967,1969–1978,1980,1985

GA0 Gross alpha 132 1965–1973,1975,1979–1980

GB0 Gross beta 26 1961,1965–1966,1968–1971,1973,1984

GD0 Gd-153 40 1987–1988

GG0 Gross gamma 9 1972,1984,1986–1988

GU0 Gross alpha 12,759 1955–1964

HY3 H-3 5,680 1955–1988

I25 I-125 8 1987–1988

I31 I-131 25 1987–1988

NP0 Np-237 64 1965–1970,1972,1978–1979

PA0 Pa-231 12 1968–1973,1975,1977

PA3 Pa-233 155 1955–1958,1960–1961,1964–1966,1969–1971,1975

PH2 P-32 232 1957–1965,1968–1969,1973–1976,1978–1984

PM7 Pm-147 5 1987

PO0a Po-210 48 1955–1957,1960–1961,1963,1966–1967,1975,1979

PU0 Pu-239 15,016 1964–1988

PU1 Pu-241 147 1968–1974,1976–1979,1981–1985

PU9 Pu-239 1,738 1957–1958,1960–1964

RA0 Ra-226 329 1955–1961,1963,1966,1968,1976–1977

RA6 Ra-226 1 1987

RU6 Ru-106 81 1958,1960,1962–1967,1972,1985

SR0 Sr-90 26,408 1955–1988

SR5 Sr-85 11 1960,1987

SR9 Sr-89 368 1960–1962,1966,1969

TA0 Ta-180 2 1986

TP0 Trans plutonium alpha 8,162 1958,1964,1966–1988

URO Uranium 15,100 1955–1988

All codes Total 91,867 1955–1988

a. The combination of capital “O” and numeral “0” in a code type is not a transcription error.

Table 4-2. Fecal bioassay codes in use at ORNL, 1955 to 1988. 

Bioassay 

code Description/analyte

Number of 

samples Period in use

OF0a Other 140 1964–1970,1976,1983,1988

GF0 Gross alpha 2,195 1955–1968,1972,1975

PF0 Pu-239 109 1968–1973,1975–1983

PF3 Pa-233 79 1957–1958,1961

RF0 Rare earth 70 1955,1960,1963–1965,1971–1972

SF0 Sr-90 243 1957–1958,1960–1974,1980

SF9 Sr-89 42 1960

TF0 Trans plutonium 178 1968–1983,1986

UF0 Uranium 65 1956,1963–1965,1968–1969,1973–1976,1979–1980

All codes Total 3,121 1955–1988

a. The combination of capital “O” and numeral “0” in a code type is not a transcription error.

To assess the target radionuclide associated with the 1532 code 000 bioassay samples, the ORAU 

Team examined both the data already on file for 114 workers in the NIOSH-Division of Compensation 
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Analysis and Support Claims Tracking System (NOCTS) as well as the bioassay cards for 

388 individuals that are not in that system. The Team reviewed the bioassay card data to identify the 

analyte and compile the bioassay information into a data file. A total of 1,584 individual urine 

bioassay samples were identified for 492 individuals.1

 These samples were analyzed for 53 different 

analytes. Table 4-3 provides a summary of the reported analytes for these code 000 samples. 

NOTE: The bioassay cards for the 140 code OF0 (fecal) and 52 code OO0 (urine) samples were not 

requested.

Table 4-3. Bioassay code 000 with monitored nuclide, 1955 to 1988. 

Bioassay code Description/analyte Number of samples Period in use

000 Am 60 1965–1967

000 Am-241 21 1965–1967

000 Am-243 2 1968

000 Bk-249 7 1965, 1969

000 C-14 14 1968, 1970–1973, 1979, 1982

000 Ca-45 19 1965–1966, 1968

000 Cd-109 1 1973

000 Ce 1 1969

000 Cl-36 3 1968

000 Cm 469 1965–1967

000 Cm-242 53 1965–1967

000 Cm-244 17 1965–1967

000 Co-57 2 1965

000 Co-60 4 1961, 1963, 1983

000 Cr 2 1964

000 Cr-51 4 1964, 1968, 1976

000 Cs-132 1 1961

000 Eu-152 2 1985

000 Eu-154a 1 1988

000 Eu-155a 1 1988

000 Fe-55 5 1983

000 Fe-59 2 1964–1965

000 Ga-66/67 5 1970

000 Ga-67 3 1968, 1971

000 Gd-153 1 1987

000 I 64 1963, 1965–1973, 1976

000 I-125 1 1976

000 I-131 51 1958, 1965–1967, 1969–1971, 1973–1974

000 Ir-192 2 1981

000 Nb-95 2 1968–1969

000 P-32 2 1968

000 Pa 1 1965

000 Pm 3 1965–1966

000 Pm-147 2 1967

000 Pu-241 74 1967

000 Ru 29 1968–1969, 1971

000 Ru-103 2 1965

000 Ru-103/106 4 1969

000 Ru-106 9 1968–1969, 1971–1972

000 S-35 5 1955, 1968

000 Tc 12 1965, 1979–1980

 

1 The ORNL bioassay database is known to be incomplete (some samples were not entered into the database). 

Therefore, it is expected that the number of database samples and the number of samples from the bioassay cards for 

individuals identified in the database might not be equal.
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Table 4-3. Bioassay code 000 with monitored nuclide, 1955 to 1988 (continued). 

Bioassay code Description/analyte Number of samples Period in use

000 Tc-99 9 1976–1979, 1981, 1983

000 Th 2 1965

000 Tl-201 1 1981

000 Tm-170 1 1968

000 TrPu 575 1961–1962, 1964–1969, 1974

000 W 1 1966

000 Y-88 2 1961

000 Y-90 1 1982

000 Zn-65 1 1968

000 Zr 20 1959, 1963, 1967–1969

000 Zr-95 2 1966, 1969

000 ZrNb 17 1964, 1968–1969

All codes Total 1,584 1955-1988

a. Analytical results associated with mixed nuclide release, not an individual nuclide.

4.3 NOCTS BIOASSAY DATA

Bioassay data for 1,003 workers in NOCTS were compiled into a spreadsheet. These 1,003 

individuals represent the total pool of ORNL workers in NOCTS with bioassay data when the ORAU 

Team data transcription project was initiated in mid-2014. Although the purpose of this transcription 

project was to compile a dataset for potential use as a source of ORNL coworker data, the data were 

used in this report evaluation to ascertain the degree to which the ORNL bioassay database 

represents the analysis types that were used for individual workers from August 1, 1955, through 

December 31, 1988. This was done by comparing the data in the NOCTS claim files (i.e., from 

individual bioassay cards) with the data in the ORNL database for the same individuals. This 

comparison was made for analytes containing more than 10 samples. 

With the exception of gross beta analysis (results of which seem to be missing from the ORNL 

database between 1955 and 1959), the sample frequency in the ORNL and NOCTS datasets are 

comparable, although the NOCTS data files tend to be more complete. Tables 4-4 and 4-5 show the 

results of this evaluation by sample year and by analytical method code, respectively. 

Table 4-4. NOCTS versus ORNL database comparison of sample frequency by year (for analytical 

methods with >10 samples). 

Year NOCTS sample count ORNL database sample count N/Oa

1955 485 467 1.04

1956 448 415 1.08

1957 562 517 1.09

1958 905 863 1.05

1959 674 615 1.10

1960 900 875 1.03

1961 1,010 864 1.17

1962 1,232 1,046 1.18

1963 1,330 1,157 1.15

1964 1,119 998 1.12

1965 1,170 982 1.19

1966 1,057 909 1.16

1967 878 760 1.16

1968 805 659 1.22

1969 870 733 1.19

1970 702 572 1.23

1971 687 533 1.29

1972 530 470 1.13
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Table 4-4. NOCTS versus ORNL database comparison of sample frequency by year (for analytical 

methods with >10 samples) (continued).

Year NOCTS sample count ORNL database sample count N/Oa

1973 701 578 1.21

1974 515 429 1.20

1975 360 342 1.05

1976 433 397 1.09

1977 311 297 1.05

1978 324 312 1.04

1979 271 267 1.01

1980 265 259 1.02

1981 194 194 1.00

1982 330 323 1.02

1983 254 245 1.04

1984 254 249 1.02

1985 213 209 1.02

1986 225 217 1.04

1987 172 168 1.02

1988 188 186 1.01

Overall 20,374 18,107 1.13

a. N/O = NOCTS Sample Count / ORNL Sample Count-Analytical Methods with >10 total samples (000, CS0, CS7, FU0, 

GA0, GF0, GU0, HY3, PA3, PF0, PH2, PU, PU0, PU1, PU9, RA0, RF0, SF0, SR9, TF0, TP0, UF0, UR0).

Table 4-5. NOCTS versus ORNL database comparison of sample frequency by analyte code (for 

analytical methods with >10 samples). 

Analyte code NOCTS sample count ORNL database sample count N/Oa

000 362 298 1.21

CS0 432 367 1.18

CS7 56 49 1.14

FU0 297 273 1.09

GA0, GU0, Pu, PU0, PU9 6,558 5,777 1.14

GF0 581 543 1.07

HY3 836 809 1.03

PA3 17 12 1.42

PF0 35 26 1.35

PH2 31 28 1.11

PU1 22 20 1.10

RA0 72 64 1.13

RF0 15 13 1.15

RU6 45 27 1.67

SF0 41 38 1.08

SR0 5,761 5,091 1.13

SR9 66 66 1.00

TF0 34 27 1.26

TP0 1,904 1,691 1.13

UF0 20 17 1.18

UR0 3,189 2,871 1.11

Overall 20,374 18,107 1.13

a. N/O = NOCTS Sample Count / ORNL Sample Count-Analytical Methods with >10 total samples (‘000’, CS0, CS7, FU0, 

GA0, GF0, GU0, HY3, PA3, PF0, PH2, PU, PU0, PU1, PU9, RA0, RF0, SF0, SR9, TF0, TP0, UF0, UR0).

To summarize, the ratio of the number of samples for the same group of individuals in NOCTS to that 

in the ORNL Database is 1:1.13. The ratio ranges from 1:1 to 1:1.29 when grouped by year 

(Table 4-4), and from 1:1 to 1:1.67 when grouped by method (Table 4-5). Note that the higher 

variance when grouped by analytical method is likely due to the smaller sample set for some of the 

groups (in comparison with the sets grouped by year). The results are consistent with the conclusion 
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of the ORNL Internal Dosimetry staff that the database is incomplete and might be missing up to 25% 

of the bioassay samples (ORAUT 2013), albeit comparison between NOCTS and the ORNL database 

indicate a slightly lower value. Note that this evaluation is only qualitative.

As indicated above, the ORNL database does not contain gross beta results (analyte codes 013 and 

GB0) between 1955 and 1959. Table 4-6 shows the number of gross beta samples for the same 

group of individuals when viewed in the NOCTS dataset versus the ORNL database. 

Table 4-6. Gross beta samples in NOCTS and ORNL datasets 

(analyte codes 013 and GB0). 

Dataset 1955 1956 1957 1958 1959

NOCTS 1 5 26 28 7

ORNL 0 0 0 0 0

This analysis indicates a discrepancy in the presence of gross beta samples (Analyte 013 and GB0) 

in the ORNL dataset. A review of the underlying data indicates that it was not uncommon for the 

gross beta analysis to be performed in conjunction with either fission product analysis (FP0), rare 

earth analysis (FU0), or strontium analysis (SR0). The results of these accompanying FP0, FU0, or 

SR0 analysis are in the ORNL database, but the gross beta results are not. It appears that gross beta 

sample results were not recorded in the ORNL database between 1955 and 1959. However, it is not 

clear from the data results if the FP0, FU0, or SR0 analysis was initiated as a result of the gross beta 

analysis result. 

5.0 EVALUATION OF IN VIVO MONITORING COUNTING PROGRAM

The main whole-body count (WBC) room (a shielded vault) was erected in Building 2008 on July 24,

1959, with a 14-in.-thick pre-World War II steel shield. The first recorded background count was

made on July 13, 1959, before the door and the roof were completed. The count room was initially

used primarily for counting biological samples, such as milk, grass, and cow thyroids (Watts et

al. 1995).

Use of the WBC facility for personnel monitoring began in June 1960. The system was configured

with a 200-channel tube-type analyzer connected to a single 4- by 4-in. NaI(Tl) crystal. This

configuration was initially used to measure 19 individuals involved in known contamination events.

From June 1960 to July 1961, the effort was expanded to include an additional 208 persons. The

system was then upgraded to a 512-channel analyzer connected to two 8-in.-diameter by 4-in. NaI(Tl)

detectors (Morgan 1961).

During the second year of operations (1961 to 1962), improvements in data analysis were instituted 

that used computer software and additional data handling (i.e., inclusion of paper tape recording).

Counter use was again focused on known or suspected internal exposures and resulted in 142 

measurements of 102 additional individuals (Morgan 1962). Starting in 1963, the scope of the 

counting program was expanded to include routine counting of potentially exposed persons as well as

baseline counts on individuals before entry into areas with potential for internal exposure. System

capacity was reported at 110 persons per month; and 492 individuals were counted between 1962 

and 1963.

By 1964, continued improvements in instrumentation, scheduling, and operations made it possible to 

further increase system throughput. Between 1963 and 1964, a total of 1,568 counts were performed 

on 1,370 individuals. Emphasis was placed on routine counting of persons who were suspected of

having experienced an exposure or having a potential for exposure and on obtaining baseline counts.

The 1964 HP Division annual report indicated that “the increased rate of individual counting made it
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possible to expand the base-line counting and obtain counts on essentially all persons with even a 

remote chance for exposure” (Morgan, Snyder, and Struxness 1964).

The goal to obtain a baseline count on essentially every person with a potential for future exposure 

was completed in May 1965 (Morgan, Snyder, and Struxness 1965). Beginning in May, the method of 

selecting individuals was changed to allow selection by Applied HP personnel. A five-part priority 

system was implemented, as follows:

1. Persons suspected of having sustained an exposure,

2. Persons being recounted as follow-up to initial elevated in vivo counts,

3. Persons who worked directly with radioactive materials,

4. Persons who worked in the areas where radioactive materials are handled, but who did not 

work directly with the materials, and

5. Newly hired or other persons for baseline counts before beginning work with radioactive 

materials.

Based on these criteria, individuals who worked directly with radioactive materials were supposed to 

have been monitored quarterly, and those who worked where radioactive material was present were 

to have been monitored semiannually. Baseline counts were to be taken for new hires or other 

persons requiring a baseline count, and a limited number of workers were to be monitored before 

termination (Morgan, Snyder, and Struxness 1965).

By the beginning of the 1966 fiscal year (July 1965), the operation of the whole-body counter was 

reported as being used for “the routine monitoring and evaluation of the extent of exposure to gammaemitting radioisotopes of all Laboratory employees” (Morgan, Snyder, and Struxness 1966). The 

implementation of this routine monitoring effort was reported to be effective beginning in “the next 

fiscal year” (i.e., July 1967) due to logistical problems with implementation. As stated in the 1966 HP 

Division annual report, “...the effort required for selection of workers, the frequency of the counts of 

the workers, preparation of paperwork proved to be greater than anticipated. The new routine 

counting program is expected to get under way with the beginning of the new fiscal year.”

Although the 1967 HP Division annual report indicates that baseline and specified monitoring 

frequencies continued to be implemented, contemporary ORNL dosimetry staff indicated that a 

centrally controlled in vivo monitoring program did not exist at ORNL until approximately 1994 when 

site internal dosimetrists became responsible for identifying personnel for counting (ORAUT 2004). 

Before then, Area HP selected individuals for in vivo monitoring based on an understanding of the 

exposure potential. The Area HP staff was responsible for determining the radioisotopes to which a 

worker could be exposed as well as the counting frequencies. 

Table 5-1 shows the number of in vivo (whole-body and thyroid) counts taken each calendar year 

from the ORNL database (ORNL 2013) and the HP Division annual reports from before 1983. (The 

HP Division reports after 1982 have not been found). The annual report data were assessed to fill in 

the gaps in the ORNL dataset, which only lists counts starting in 1962.

Table 5-1. Tabulation of in vivo counts from database versus annual reports. 

Year Number of in vivo counts from ORNL databasea Number of in vivo counts from annual reportsb,c

1961 0 329

1962 71 395

1963 921 1,054
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Table 5-1. Tabulation of in vivo counts from database versus annual reports (continued).

Year Number of in vivo counts from ORNL databasea Number of in vivo counts from annual reportsb,c

1964 1,555 1,644

1965 1,169 1,222

1966 696 740

1967 966 983

1968 968 964

1969 1,057 1,108

1970 518 530

1971 324 332

1972 259 272

1973 325 350

1974 278 278

1975 330 331c

1976 255 255c

1977 291 291c

1978 306 305c

1979 402 460c

1980 700 750c

1981 557 590c

1982 556 650c

1983 411 Not available

1984 476 Not available

1985 525 Not available

1986 682 Not available

1987 681 Not available

1988 753 Not available

a. Source data from SRDB Ref ID: 126306.

b. Source data from SRDB Ref IDs: 11555, 11558, 12061, 12066, 12069, 12072, 12084, 12087, 12092, 12093, 13224, 

13226 to 13229, 13231, and 22548 to 22552.

c. Includes number of wound counts.

6.0 INVENTORY DEVELOPMENT 

A detailed inventory of the radionuclides the ORNL Isotopes Division produced and processed was 

developed using source documents in the ORAU Team Site Research Database (SRDB). In addition, 

the Team used documents it had collected for development of the ORNL and Y-12 site profiles, and 

during subsequent visits to capture data about radionuclide production activities. The predominant 

source data for this inventory included isotope shipping and sales reports as well as various 

operational and technical report series, as shown in Table 6-1. These data sources, as well as other 

ad hoc (nonseries) reports in the SRDB, were used to develop an initial inventory of radionuclides and 

quantities.

The initial radionuclide listing was reviewed to determine if the produced materials were handled in 

the ORNL processing facilities or (as in the case of many cyclotron materials) shipped directly off site 

for processing. Materials that were irradiated at ORNL but processed off site were identified as 

“service irradiations.” Because these materials were not handled in an unsealed form at ORNL or 

Y-12, they were not included in the isotope inventory. Thirty-six radionuclides were identified in this 

category and removed from the initial inventory. The exception to this was the case where a target 

otherwise identified as a service irradiation ruptured. Fifty (50) documents related to target rupture 

events were identified by a keyword search of the SRDB. Another 49 documents were identified 

through a review of the ORNL incident listing (ORNL 2012). In each event of a target rupture, the 

relevant radionuclide was retained in the radionuclide inventory if initially present. In a small number 

of cases, the radionuclide that was identified in the target rupture documentation was not contained 
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Table 6-1. Sources of radionuclide production information. 

Report series name

Publication 

frequency Start End SRDB Ref IDs

Chemical Technology 

Division Annual Progress 

Report

Annual 1957 1988 103941, 104046, 109875, 118695–118698, 

118701, 118706, 118708, 119232–119233, 

119235, 119250, 119255, 119264, 119274–

119275, 119278, 119279–119280, 119295, 

119345, 120407, 120410, 120412, 120419, 

120421, 120424

Electronuclear Research 

Division Annual Progress 

Report

Annual 1957 1961 11915, 11929, 11945, 121486

Isotope Separations 

Progress Report

Monthly 1976 1978 132481, 132490, 132493, 132495–132496, 

132498, 135508, 135510, 135512–135514, 

135516, 135518, 135520, 135522, 135524, 

135528, 135531, 135533, 135547

Isotopes Development 

Center Progress Report 

Curium Program

Variable 1962 1964 123031, 123039, 123044, 123052, 123075, 

123079, 123087, 123090, 123094

Isotopes Development 

Center Progress Report 

Fission Products

Variable 1962 1962 123030, 123060, 132911

Isotopes Development 

Center Progress Report 

Isotopes Separations

Variable 1962 1964 123036, 123053, 123059, 123078, 123083

Isotopes Development 

Center Progress Report 

Radioactive Source 

Development

Variable 1962 1963 123029

Isotopes Development 

Center Progress Report 

Reactor and Cyclotron 

Produced Isotopes

Variable 1963 1963 11934, 11941

Isotopes Development 

Center Progress Report 

Target Development

Variable 1962 1963 123035, 123047, 123058, 123077

Isotopes Division 

Quarterly Report

Quarterly 1960 1961 132855–132857, 132915

Isotopes Division 

Research and 

Development Report

Monthly 1962 1962 132858–132900, 132902, 132905, 132907

List of Radioisotope 

Customers with Summary 

of Radioisotope 

Shipments

Annual 1964 1988 40950, 56703, 76459, 77783–77784, 79142–

79143, 79470–79472, 79474–79475, 87578–

87579–87581, 100264, 100266, 100517–

100519, 100712, 101613, 115758, 126941, 

160563

ORNL Status and 

Progress Report

Monthly 1950 1967 102645, 120325, 120334, 120347, 120359, 

120362, 120366, 120371, 120374–120376, 

120378, 120380–120381, 120383–120384, 

120386, 120389, 120397–120399, 120401–

120403, 120405–120406, 121166–121193, 

121195–121289, 121483, 121485, 122579, 

122580–122583, 122585–122588, 122591–

122601, 122603, 122605, 122798–122800, 

122841, 122847–122848, 122851, 122853, 

122859, 122861, 122863, 122866–122867, 

122883, 122885, 122890–122891
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Table 6-1. Sources of radionuclide production information (continued). 

Report series name

Publication 

frequency Start End SRDB Ref IDs

Quantity Data on 

Radioisotopes

Quarterly 1959 1964 14019, 121493, 121497, 122815 - 122817, 

122819 - 122831

Radioisotope Cost-Price 

Study

Annual 1957 1974 101798, 122748–122751, 132204, 133608, 

137545, 137558, 137577, 137586

Radioisotope Distribution 

Program Progress Report

Monthly 1973 1980 98043, 119487–119495, 120818–120861, 

120863, 120869–120870, 120872–120873, 

121291–121296, 123183, 123229, 123237, 

123263, 123301, 123303, 123305, 123307

Radioisotope Inventory Monthly 1956 1966 121516, 121538, 121640, 121644, 121646–

121647, 121649, 121651, 121653, 137579

Radioisotope Production 

and Process 

Development Annual 

Report

Annual 1954 1956 103912, 103938, 120365

Radioisotope Program 

(8000) Progress Report

Monthly 1969 1973 119509, 119511–119517, 120529–120531, 

120533–120565, 121856

Review of Radioisotopes 

Program

Annual 1964 1967 79379, 119485–119486, 122852

Stable Isotope and Heavy 

Element Inventories

Monthly 1961 1969 121487–121490, 121494–121495, 121498, 

121500, 121502–121503, 121505, 121508, 

137542, 137615, 137682, 137689–137690, 

137692, 137697

Transuranium Processing 

Plant Semiannual Report 

of Production, Status, and 

Plan

Semi-annual 1969 1975 126245, 132271, 132286, 132288, 132300–

132306, 132386

on the previously identified inventory and was added (Table 6-2). Two radionuclides (123mTe and 

128Te) were identified in the inventory development but were removed because they are effectively 

stable with half-lives of 9.2 × 1016 years and 2.4 × 1024 years, respectively).

Table 6.2. Radionuclides added to 

inventory due to target rupture events. 

Radionuclide Year(s)

As-71 1960

As-72 1960

As-74 1958, 1960–1961

Mn-52 1960

Mn-54 1960

Sr-85 1961

Y-88 1961

Cs-132 1962

The ORAU Team reviewed a collection of logbooks in the ORNL records repository. These logbooks 

were selected from a master listing of over 17,000 logbooks. Logbook categories matching those in 

the table below were selected to narrow the review to 1,867 logbooks. Of these, 15,961 pages from 

823 logbooks were selected for data capture. During the course of the data capture, the ORNL 

radionuclide inventory listing was referenced so that radionuclides in logbook entries that were not 

listed on the existing inventory could be identified and subsequently added to the radionuclide 

inventory listing. As a result of this review, 25 additional radionuclides were identified, and one or 

more additional inventory years were identified for 23 radionuclides. Table 6-3 provides the final 

inventory list based on the above-listed data sources. 
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Table 6-3. Final radionuclide inventory for Isotopes Division. 

Nuclide Production years

Hydrogen-3 1955–1957, 1959–1988

Beryllium-7 1955, 1957–1959, 1962, 1964, 1969

Carbon-11 1975, 1977, 1979–1980

Carbon-14 1955–1975, 1980–1983, 1985

Sodium-22 1955–1956, 1961–1964

Sodium-24 1955–1967

Magnesium-28 1966, 1969–1970, 1977, 1983–1984, 1987–1988

Phosphorus-32 1955–1967

Phosphorus-33 1964–1965, 1967–1987

Sulfur-35 1955–1969

Chlorine-36 1955–1972

Chlorine-38 1956

Argon-37 1955–1957, 1959–1971, 1973–1982

Potassium-40 1979

Potassium-42 1955–1966

Potassium-43 1964–1965, 1967, 1971, 1973–1978, 1980–1981, 1983

Calcium-41 1977, 1986

Calcium-45 1955–1966

Calcium-47 1960–1984

Scandium-46 1955–1957, 1959–1973

Scandium-49 1955, 1965

Titanium-44 1956, 1958

Vanadium-48 1962

Chromium-51 1955–1967, 1975

Manganese-52 1960

Manganese-54 1955–1957, 1960, 1963–1965

Iron-55 1955–1956, 1959–1966, 1980–1986

Iron-59 1955–1956, 1958–1967

Cobalt-56 1967, 1972, 1977

Cobalt-57 1955–1957, 1964, 1972–1976

Cobalt-58 1955–1957, 1959–1965

Cobalt-60 1955–1988

Nickel-63 1955–1957, 1959–1972, 1978, 1980, 1985–1987

Nickel-66 1968

Copper-64 1955–1969, 1976

Copper-67 1963–1964, 1967–1968, 1970–1971, 1973–1976

Zinc-65 1955–1957, 1959–1966

Zinc-69m 1967, 1973–1974

Gallium-67 1958–1959, 1969–1978, 1983

Gallium-68 1971

Gallium-72 1955, 1957, 1960–1970

Arsenic-71 1960

Arsenic-72 1960

Arsenic-74 1957–1959, 1961, 1965

Arsenic-76 1956–1957, 1959–1967

Arsenic-77 1956–1957, 1959–1966

Selenium-75 1955–1957, 1959–1966, 1979–1986

Bromine-82 1956–1967

Bromine-85 1963

Krypton-85 1955–1988

Rubidium-83 1969

Rubidium-84 1964–1965, 1969, 1975

Rubidium-86 1955–1957, 1959–1972
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Table 6-3. Final radionuclide inventory for Isotopes Division (continued). 

Nuclide Production years

Rubidium-88 1964

Strontium-82 1970

Strontium-85 1955, 1957–1967, 1970, 1986

Strontium-87m 1960, 1964, 1970

Strontium-89 1955–1957, 1959–1963, 1965–1987

Strontium-90 1955–1988

Yttrium-86 1964, 1968

Yttrium-88 1957–1958, 1961–1963, 1965, 1974

Yttrium-90 1956–1968, 1973, 1987–1988

Yttrium-91 1955–1957, 1959–1978

Zirconium-95 1955–1986

Zirconium-97 1971

Niobium-90 1957

Niobium-92 1963

Niobium-92m 1967

Niobium-95 1955–1957, 1959–1981, 1983–1985

Molybdenum-93 1957, 1962

Molybdenum-99 1957, 1959–1971

Technetium-95m 1957–1958, 1967, 1970

Technetium-99 1955–1957, 1959–1970, 1972–1988

Technetium-99m 1966, 1968, 1970

Ruthenium-97 1959–1960, 1962, 1970

Ruthenium-103 1955–1957, 1959–1986

Ruthenium-105 1956

Ruthenium-106 1955–1957, 1959–1988

Rhodium-102 1958

Palladium-103 1962, 1964

Palladium-109 1957, 1959–1971

Silver-110m 1955–1957, 1959–1966

Silver-111 1956–1957, 1959–1970

Cadmium-109 1957–1958, 1960–1961, 1963–1966, 1972

Cadmium-115 1955–1956, 1960, 1962–1966

Cadmium-115m 1955–1956, 1960–1966

Indium-111 1969–1971, 1973

Indium-114 1955–1957, 1959–1977, 1981

Indium-114m 1975

Tin-113 1955–1957, 1959–1967, 1979

Tin-117m 1977

Tin-119m 1986

Antimony-122 1956, 1959–1968, 1971, 1987

Antimony-124 1955–1957, 1959–1967

Antimony-125 1955–1957, 1959–1966

Tellurium-121 1957

Tellurium-132 1963, 1968

Iodine-123 1965, 1967–1970

Iodine-125 1957, 1961–1964

Iodine-129 1955–1957, 1959–1988

Iodine-130 1960–1972, 1985

Iodine-131 1955–1976, 1978–1980, 1983, 1985–1986, 1988

Iodine-132 1967–1972

Iodine-133 1961, 1967–1968, 1977

Xenon-127 1983, 1987–1988

Xenon-133 1960–1976, 1978–1980
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Table 6-3. Final radionuclide inventory for Isotopes Division (continued). 

Nuclide Production years

Cesium-131 1965

Cesium-132 1962

Cesium-134 1955–1957, 1959–1966

Cesium-137 1955–1988

Barium-131 1955–1957, 1959–1971

Barium-133 1955–1957, 1959–1972

Barium-135m 1970, 1986

Barium-140 1955–1957, 1959–1968, 1970–1978, 1980–1981, 1983

Lanthanum-140 1955–1957, 1959–1966, 1987

Cerium-139 1955, 1957–1958

Cerium-141 1955–1957, 1959–1966, 1970

Cerium-144 1955–1979, 1981–1988

Praseodymium-142 1956–1957, 1959–1968, 1970

Praseodymium-143 1955–1957;1959–1968, 1970, 1972–1973

Praseodymium-144 1962

Neodymium-140 1969

Neodymium-147 1955–1957, 1959–1973, 1979

Neodymium-149 1979

Promethium-145 1968

Promethium-146 1974

Promethium-147 1955–1968, 1970–1987

Promethium-148 1970

Samarium-151 1968–1982, 1984–1987

Samarium-153 1956–1957, 1959–1961, 1963–1969

Europium-152 1962, 1968, 1974–1975, 1978–1981, 1984–1985, 1988

Europium-155 1955–1957, 1959–1968, 1975

Gadolinium-148 1970

Gadolinium-153 1971, 1973–1988

Terbium-156 1958, 1967–1968

Terbium-158 1970

Dysprosium-157 1975

Dysprosium-159 1957, 1961

Dysprosium-166 1965, 1984

Holmium-156 1965

Holmium-166 1958

Erbium-171 1973

Thulium-170 1962–1971, 1974–1975

Thulium-171 1967

Ytterbium-169 1980, 1986

Hafnium-181 1955, 1957, 1959–1977, 1979–1980

Tantalum-182 1955–1957, 1959–1972, 1974

Tungsten-181 1957–1958

Tungsten-185 1955–1957, 1959–1971

Tungsten-187 1955–1957, 1959–1970

Rhenium-186 1957, 1959–1972, 1979

Osmium-185 1957, 1966

Osmium-191 1957, 1959–1970, 1984

Iridium-192 1955–1968, 1970–1971, 1973–1988

Iridium-194 1959, 1961, 1963, 1968

Platinum-195m 1972–1974, 1978

Platinum-197 1965

Gold-195 1961

Gold-198 1955, 1957–1966
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Table 6-3. Final radionuclide inventory for Isotopes Division (continued). 

Nuclide Production years

Gold-199 1955, 1957, 1959–1967

Mercury-197 1957–1966

Mercury-203 1955–1957, 1959–1967

Thallium-201 1975

Thallium-204 1955–1971

Lead-203 1972–1973

Bismuth-206 1957–1958

Bismuth-207 1957

Bismuth-210 1955–1957, 1959–1970

Polonium-210 1962, 1966

Thorium-228 1962

Thorium-229 1968, 1970–1971, 1973–1974, 1977, 1979–1986, 1988

Thorium-230 1956, 1962–1963, 1965, 1967–1976, 1978–1988

Thorium-232 1963, 1968–1969, 1972–1976, 1978–1987

Thorium-234 1981

Protactinium-231 1961–1963, 1965–1966, 1968–1969, 1976–1981, 1984–1986

Protactinium-233 1963–1964, 1966, 1969

Uranium-232 1961–1965, 1968, 1970–1971, 1974–1979

Uranium-233 1961–1963, 1965–1988

Uranium-234 1956, 1961–1963, 1965–1988

Uranium-235 1955–1957, 1961–1963, 1965–1988

Uranium-236 1955–1956, 1961–1963, 1965–1988

Uranium-238 1955–1956, 1961–1988

Neptunium-236 1965

Neptunium-237 1955–1957, 1959, 1961–1962, 1964–1965, 1967–1968, 1970, 1972–1987

Neptunium-238 1966

Plutonium-236 1968, 1970, 1973, 1975, 1981, 1984, 1986

Plutonium-237 1984, 1986

Plutonium-238 1961–1963, 1965, 1968–1985, 1987–1988

Plutonium-239 1955–1956, 1961–1972, 1974–1985, 1987–1988

Plutonium-240 1961–1966, 1968–1986, 1988

Plutonium-241 1955–1956, 1959, 1962–1975, 1977–1986

Plutonium-242 1961–1988

Plutonium-244 1968, 1970–1982

Americium-241 1959–1988

Americium-243 1961–1978, 1980–1986, 1988

Curium-242 1961–1966, 1968, 1986

Curium-243 1965, 1972–1973, 1975–1976, 1981–1983

Curium-244 1962–1964, 1966–1988

Curium-245 1969, 1972–1973, 1986

Curium-246 1970–1971, 1973, 1977, 1988

Curium-247 1969, 1972

Curium-248 1968–1980, 1982–1984, 1986, 1988

Berkelium-249 1964, 1967, 1969–1984, 1986, 1988

Californium-248 1972

Californium-249 1968–1976, 1979–1982, 1984, 1986

Californium-250 1970, 1973–1976, 1980

Californium-252 1962, 1967–1988

Californium-253 1984

Einsteinium-252 1970

Einsteinium-253 1967–1981, 1984, 1986, 1988

Einsteinium-254 1972–1974, 1980, 1982, 1984, 1988
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Table 6-3. Final radionuclide inventory for Isotopes Division (continued). 

Nuclide Production years

Fermium-255 1984, 1988

Fermium-257 1968–1977, 1980, 1984, 1986, 1988

7.0 FEASIBILITY ANALYSIS

7.1 INITIAL EVALUATION

The annual production history for each of the 213 radionuclides in Table 6-3 was compared to the 

available in vitro bioassay methods for each year (Tables 4-1 to 4-3) and in vivo bioassay methods 

(Section 4.0) in each year. The information from the analysis of NOCTS bioassay data (Section 4.2) 

was incorporated to augment the listing of available methods (namely for gross beta) during periods 

for which the ORNL dataset does not include those methods. The ORAU Team determined if ORNL 

had monitoring capability for each radionuclide in each production year by taking into consideration 

the characteristic radionuclide emissions (type and energy) and analytical method sensitivity 

(including chemical specificity, radiation type, and energy). The ORAU Team performed this 

evaluation to identify potential gaps in monitoring capabilities specific to an individual radionuclide. 

No attempt was made to reconcile the quantity of a specific radionuclide against the frequency at 

which a particular monitoring method was used. 

In this evaluation, when an adequate monitoring method was indicated (i.e., by analytical results for a 

previous year), it was deemed adequate evidence for concluding there was no gap in monitoring 

capability. This was the case even when a particular radionuclide was produced in a later year in 

which no instances of that bioassay method were evident. That is, once a bioassay method was 

reported, it was assumed to be available each year thereafter. For example, 35S was produced each 

year between 1955 and 1969 but analytical results for methods capable of detecting 35S were only 

reported in 1955, 1958, 1959, and 1961 (Table 7-1). The lack of recorded monitoring results for the 

other years of interest was not considered indicative of a gap in monitoring capability. 

Table 7-1. Comparison of 35S production and 

number of reported bioassay samples. 

Year Inventory (Ci) S-35 samples reported

1955 57 1

1956 14 0

1957 67 0

1958 88 1

1959 60 1

1960 23 0

1961 150 1

1962 70 0

1963 29 0

1964 100 0

1965 14 0

1966 83 0

1967 0.1 0

1968 0.1 0

1969 0.01 0

Tables 7-2 and 7-3 provide a summary of the results of the monitoring capability evaluation. Color 

and letter codes in Tables 7-2 and 7-3 identify specific radionuclides in inventory, indicate if a 

bioassay method was available to detect the radionuclide, and if sample results for that particular 

bioassay method are available for that particular year. For instances where dose would be bounded 

by external radiation (i.e., noble gases), “EXT” is indicated as the bioassay method. As stated in 
Document No. ORAUT-RPRT-0090 Revision No. 00 Effective Date: 03/29/2018 Page 25 of 133

 

International Commission on Radiological Protection (ICRP) Publication 30, Section 8.2.3, “for 

submersion in radioisotopes of the noble gases, external irradiation will be of such overriding 

importance that it alone need be considered” (ICRP 1979).

In the tables colors and letters mean:

• Green or G

– A specific radionuclide was present in inventory in the specified year; and

– A bioassay method was available to detect the radionuclide in the specified year; and

– Sample results for that particular bioassay method are available for the specified year.

• Yellow or Y 

– A specific radionuclide was present in inventory in the specified year; and

– A bioassay method was available to detect the radionuclide, but no sample results for 

that particular bioassay method are available for the specified year.

• Red or R

– A specific radionuclide was present in inventory in the specified year, but an additional 

analysis was necessary to determine if the nuclide represented an infeasibility from a 

monitoring perspective.

• No color or N

– No radionuclide present in inventory in the specified year.

Of the 213 identified radionuclides, the ORAU Team determined that the ORNL HP program was able 

to monitor for 179 of them using an existing monitoring method (green or yellow shading, or coded as 

[G] or [Y]). For these 179 radionuclides, no further analysis was required. Attachment B summarizes 

the radiological properties and monitoring capability decisions for these nuclides.

In the case of 34 of the 213 radionuclides (Table 7-4), the ORAU Team concluded that additional 

evaluations were necessary to determine if the nuclides represented an infeasibility from a monitoring 

perspective. Table 7-5 provides a summary of the radiological properties of these 34 radionuclides. 

An analysis and evaluation of the monitoring capability of 28 of these 34 radionuclides is provided in 

Section 7.2. Separate analyses for five of the remaining six (radioiodines) are provided in Attachment 

C. The one remaining (Pu-241) was processed and handled on the Y-12 campus. Because 

associated exposure would have occurred at the Y-12 campus further analysis will be included in a Y12 specific evaluation.

7.2 ADDITIONAL EVALUATION 

As indicated in Table 7-4, below, 28 of the 34 radionuclides requiring additional evaluation all decay 

by either electron capture or isomeric transformation and generally have short half-lives (22 of the 28 

have half-lives of less than 1 year). NOTE: Separate analyses have been completed for the five of 

the remaining six (radioiodines are provided in Attachment C). The one remaining (Pu-241) was 

processed and handled on the Y-12 campus and as such, not addressed further in this document.

Table 7-5 lists the limiting derived air concentration (DAC) values based on solubility for each of the 

28 radionuclides under evaluation in this discussion. These values range from 1.6 × 10-5 μCi/cm3

(

87mSr) to 5.9 × 10-8 μCi/cm3

 (109Cd). For comparison purposes, before publication of NBS Handbook 

69 in 1961 the tolerance value for airborne beta/gamma activity in ORNL facilities was set at 1 × 10-7

μCi/cm3

. Respiratory protection was required for entry above 10% of this limit (1 × 10-8 μCi/cm3). By 

1961, the maximum permissible concentration (MPC) concept within National Bureau of 
 

Document No. ORAUT-RPRT-0090 Revision No. 00 Effective Date: 03/29/2018 Page 26 of 133

Table 7-2. Results of feasibility analysis for 1955 to 1969.

a

Nuclide Bioassay method code

b 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69

Hydrogen-3 HY3GGGNGGGGGGGGGGG

Beryllium-7 SC

b

RNRRRNNGNGNNNNG

Carbon-11 SCNNNNNNNNNNNNNNN

Carbon-14 000(C-14); 013/GB0;C14GGGGGGGGGGGGYGG

Sodium-22 013/GB0;SCGGNNNNGGGGNNNNN

Sodium-24 013/GB0;004;SCGGGGGGGGGGGGGNN

Magnesium-28 SCNNNNNNNNNNNGNNG

Phosphorus-32 000(P-32); PH2GGGGGGGGGGGYYNN

Phosphorus-33 013/GB0NNNNNNNNNGGNYGG

Sulfur-35 000(S-35);001GYYGGYGYYYYYYYY

Chlorine-36 000(Cl-36); 013/GB0GGGGGGGGGGGGYGG

Chlorine-38 013/GB0NGNNNNNNNNNNNNN

Argon-37 EXTGGGNGGGGGGGGGGG

Potassium-40 SCNNNNNNNNNNNNNNN

Potassium-42 013/GB0;SCGGGGGGGGGGGGNNN

Potassium-43 SCNNNNNNNNNGGNGNN

Calcium-41 (b)NNNNNNNNNNNNNNN

Calcium-45 000(Ca-45); 013/GB0GGGGGGGGGGGGNNN

Calcium-47 013/GB0;SCNNNNNGGGGGGGGGG

Scandium-46 013/GB0; FU0; SCGGGNGGGGGGGGYGG

Scandium-49 013/GB0; FU0GNNNNNNNNNGNNNN

Titanium-44 013/GB0NGNGNNNNNNNNNNN

Vanadium-48 SCNNNNNNNGNNNNNNN

Chromium-51 000(Cr-51); SC

c

RRRRRRRGGGGGGNN

Manganese-52 013/GB0NNNNNGNNNNNNNNN

Manganese-54 010;SC

c

RRRNNGNNGGGNNNN

Iron-55 000(Fe-55)

c

RRNNRRRRRRRRNNN

Iron-59 000(Fe-59); 

013/GB0;009;SC G G N G G G G G G G G G G N N 

Cobalt-56 SCNNNNNNNNNNNNGNN

Cobalt-57 000(Co-57); SC

c

RRRNNNNNNGNNNNN

Cobalt-58 013/GB0;SCGGGNGGGGGGGNNNN

Cobalt-60 000(Co-60); 

013/GB0;002;CO0;SC G G G G G G G G G G G G G G G 

Nickel-63 013/GB0GGGNGGGGGGGGYGG

Nickel-66 013/GB0NNNNNNNNNNNNNGN

Copper-64 013/GB0GGGGGGGGGGGGYGG

Copper-67 SCNNNNNNNNGGNNGGN

Zinc-65 000(Zn-65); 013/GB0;SCGGGNGGGGGGGGNNN
 

Document No. ORAUT-RPRT-0090 Revision No. 00 Effective Date: 03/29/2018 Page 27 of 133

Table 7-2. Results of feasibility analysis for 1955 to 1969 (continued).

a

Nuclide Bioassay method code

b 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69

Zinc-69m GB0NNNNNNNNNNNNYNN

Gallium-67 000(Ga-67); SC

c

NNNRRNNNNNNNNNG

Gallium-68 SCNNNNNNNNNNNNNNN

Gallium-72 013/GB0; SCGNGNNGGGGGGGYGG

Arsenic-71 013/GB0NNNNNGNNNNNNNNN

Arsenic-72 013/GB0NNNNNGNNNNNNNNN

Arsenic-74 007; 013/GB0;SCNNGGGNGNNNGNNNN

Arsenic-76 013/GB0;SCNGGNGGGGGGGGGNN

Arsenic-77 013/GB0NGGNGGGGGGGGNNN

Selenium-75 SC

c

RRRNRRRGGGGGNNN

Bromine-82 008, 0013/GB013;SCNGGGGGGGGGGGGNN

Bromine-85 013/GB0NNNNNNNNGNNNNNN

Krypton-85 EXTGGGGGGGGGGGGGGG

Rubidium-83 SCNNNNNNNNNNNNNNG

Rubidium-84 SCNNNNNNNNNGGNNNG

Rubidium-86 013/GB0;SCGGGNGGGGGGGGGGG

Rubidium-88 SCNNNNNNNNNGNNNNN

Strontium-82 SCNNNNNNNNNNNNNNN

Strontium-85 SR5; SC

c

RNRRRGYGGGGGYNN

Strontium-87m SC

c

NNNNNRNNNGNNNNN

Strontium-89 SR0;SR9; 013/GB0;GGGNGGGGGNGGGGG

Strontium-90 SR0GGGGGGGGGGGGGGG

Yttrium-86 SCNNNNNNNNNGNNNGN

Yttrium-88 000(Y-88); 013/GB0; 

FU0;SC N N G G N N G G G N G N N N N 

Yttrium-90 000(Y-90); FU0NGGGGGGGGGGGYGN

Yttrium-91 013/GB0; FU0GGGNGGGGGGGGYGG

Zirconium-95 000(Zr-95)005; 

013/GB0;SC G G G G G G G G G G G G G G G 

Zirconium-97 SCNNNNNNNNNNNNNNN

Niobium-90 013/GB0NNGNNNNNNNNNNNN

Niobium-92 SCNNNNNNNNGNNNNNN

Niobium-92m SCNNNNNNNNNNNNGNN

Niobium-95 000(Nb-95); 005; 

013/GB0;SC G G G N G G G G G G G G G G G 

Molybdenum-93 (c)NNRNNNNRNNNNNNN

Molybdenum-99 013/GB0;SCNNGNGGGGGGGGGGG

Technetium-95m 013/GB0;SCNNGGNNNNNNNNGNN
 

Document No. ORAUT-RPRT-0090 Revision No. 00 Effective Date: 03/29/2018 Page 28 of 133

Table 7-2. Results of feasibility analysis for 1955 to 1969 (continued).

a

Nuclide Bioassay method code

b 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69

Technetium-99 000(Tc-99); 006; 

013/GB0;GB0; G G G N G G G G G G G G Y G G 

Technetium-99m SCNNNNNNNNNNNGNGN

Ruthenium-97 013/GB0NNNNGGNGNNNNNNN

Ruthenium-103 000(Ru-103); SC

c

RRRNRRRGGGGGGGG

Ruthenium-105 013/GB0NGNNNNNNNNNNNNN

Ruthenium-106 000(Ru-106); 013/GB0; 

RU6 G G G N G G G G G G G G G G G 

Rhodium-102 013/GB0NNNGNNNNNNNNNNN

Palladium-103 (c)NNNNNNNRNRNNNNN

Palladium-109 013/GB0NNGNGGGGGGGGYGG

Silver-110m 013/GB0;018;SCGGGNGGGGGGGGNNN

Silver-111 013/GB0NGGNGGGGGGGGYGG

Cadmium-109 000(Cd-109)

c

NNRRNRRNRRRRNNN

Cadmium-115 013/GB0GGNNNGNGGGGGNNN

Cadmium-115m 013/GB0GGNNNGGGGGGGNNN

Indium-111 SCNNNNNNNNNNNNNNG

Indium-114 013/GB0GGGNGGGGGGGGYGG

Indium-114m SCNNNNNNNNNNNNNNN

Tin-113 SC

c

RRRNRRRRRRRRRNN

Tin-117m SCNNNNNNNNNNNNNNN

Tin-119m (c)NNNNNNNNNNNNNNN

Antimony-122 013/GB0;SCNGNNGGGGGGGGGGN

Antimony-124 013/GB0;SCGGGNGGGGGGGGGNN

Antimony-125 013/GB0;015;SCGGGNGGGGGGGGNNN

Tellurium-121 (c)NNRNNNNNNNNNNNN

Tellurium-132 SCNNNNNNNNGNNNNGN

Iodine-123 THNNNNNNNNNNGNGGG

Iodine-125 000(I-125); I25; TH

c

NNRNNNRGGGNNNNN

Iodine-129 THRRRNRRRGGGGGGGG

Iodine-130 TH

c

NNNNNRRGGGGGGGG

Iodine-131 000(I-131); 011; I31; TH

c

RRRGYYGGGGGGGGG

Iodine-132 THNNNNNNNNNNNNGGG

Iodine-133 TH

c

NNNNNNRNNNNNGGN

Xenon-127EXTNNNNNNNNNNNNNNN

Xenon-133 EXTNNNNNGGGGGGGGGG

Cesium-131 (c)NNNNNNNNNNRNNNN

Cesium-132 000(Cs-132); 012; SCNNNNNNNGNNNNNNN

Cesium-134 013/GB0;SCGGGNGGGGGGGGNNN
 

Document No. ORAUT-RPRT-0090 Revision No. 00 Effective Date: 03/29/2018 Page 29 of 133

Table 7-2. Results of feasibility analysis for 1955 to 1969 (continued).

a

Nuclide Bioassay method code

b 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69

Cesium-137 CS7;CS0; SCGGGGGGGGGGGGGGG

Barium-131 SR0GGGNGGGGGGGGGGG

Barium-133 SC

c

RRRNRRRGGGGGGGG

Barium-135m SCNNNNNNNNNNNNNNN

Barium-140 014;SR0GGGNGGGGGGGGGGN

Lanthanum-140 013;FU0;SCGGGNGGGGGGGGNNN

Cerium-139 (c)RNRRNNNNNNNNNNN

Cerium-141 013/GB0;FU0GGGNGGGGGGGGNNN

Cerium-144 013/GB0;FU0;SCGGGGGGGGGGGGYGG

Praseodymium-

142

013/GB0;FU0 N G G N G G G G G G G G Y G N 

Praseodymium-

143

013/GB0;FU0 G G G N G G G G G G G G Y G N 

Praseodymium-

144

013/GB0;FU0 N N N N N N N G N N N N N N N 

Neodymium-140 013/GB0NNNNNNNNNNNNNNG

Neodymium-147 013/GB0;FU0; SCGGGNGGGGGGGGYGG

Neodymium-149 013/GB0;FU0; SCNNNNNNNNNNNNNNN

Promethium-145 (c)NNNNNNNNNNNNNRN

Promethium-146 013/GB0;FU0; SCNNNNNNNNNNNNNNN

Promethium-147 000(Pm-147); 013;PM7; 

FU0;Pm-147 G G G G G G G G G G G G Y G N 

Promethium-148 013/GB0;FU0; SCNNNNNNNNNNNNNNN

Samarium-151 013/GB0;FU0;NNNNNNNNNNNNNGG

Samarium-153 013/GB0;FU0NGGNGGGNGGGGYGG

Europium-152 000(Eu-152); SCNNNNNNNGNNNNNGN

Europium-155 000(Eu-155); 013;SCGGGNGGGGGGGGGGN

Gadolinium-148 GA0NNNNNNNNNNNNNNN

Gadolinium-153 000(Gd-153); GD0; SCNNNNNNNNNNNNNNN

Terbium-156 SC

c

NNNRNNNNNNNNGGN

Terbium-158 FU0NNNNNNNNNNNNNNN

Dysprosium-157 FU0NNNNNNNNNNNNNNN

Dysprosium-159 (c)NNRNNNRNNNNNNNN

Dysprosium-166 FU0NNNNNNNNNNGNNNN

Holmium-156 FU0; SCNNNNNNNNNNGNNNN

Holmium-166 013/GB0NNNGNNNNNNNNNNN

Erbium-171 013/GB0NNNNNNNNNNNNNNN

Thulium-170 000(Tm-170);FU0NNNNNNNGGGGGYGG

Thulium-171 FU0NNNNNNNNNNNNYNN
 

Document No. ORAUT-RPRT-0090 Revision No. 00 Effective Date: 03/29/2018 Page 30 of 133

Table 7-2. Results of feasibility analysis for 1955 to 1969 (continued).

a

Nuclide Bioassay method code

b 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69

Ytterbium-169 SCNNNNNNNNNNNNNNN

Hafnium-181 013/GB0GNGNGGGGGGGGYGG

Tantalum-182 013/GB0;SCGGGNGGGGGGGGGGG

Tungsten-181 (c)NNRRNNNNNNNNNNN

Tungsten-185 013/GB0GGGNGGGGGGGGYGG

Tungsten-187 013/GB0;SCGGGNGGGGGGGGGGG

Rhenium-186 013/GB0NNGNGGGGGGGGYGG

Osmium-185 SC

c

NNRNNNNNNNNGNNN

Osmium-191 013/GB0;SCNNGNGGGGGGGGGGG

Iridium-192 000(Ir-192); 

0013/GB0;SC G G G G G G G G G G G G G G N 

Iridium-194 013/GB0;SCNNNNGNGNGNNNNGN

Platinum-195m SCNNNNNNNNNNNNNNN

Platinum-197 SCNNNNNNNNNNGNNNN

Gold-195 (c)NNNNNNRNNNNNNNN

Gold-198 013/GB0; SCGNGGGGGGGGGGNNN

Gold-199 013/GB0;SCGNGNGGGGGGGGGNN

Mercury-197 SC

c

NNRRRRRGGGGGNNN

Mercury-203 013/GB0;SCGGGNGGGGGGGGGNN

Thallium-201 000(Tl-201); SCNNNNNNNNNNNNNNN

Thallium-204 013/GB0;016GGGGGGGGGGGGYGG

Lead-203 SCNNNNNNNNNNNNNNN

Bismuth-206 (c)NNRRNNNNNNNNNNN

Bismuth-207 013/GB0NNGNNNNNNNNNNNN

Bismuth-210 013/GB0GGGNGGGGGGGGYGG

Polonium-210 004;PO0; GU0NNNNNNNGNNNGNNN

Thorium-228 GU0NNNNNNNGNNNNNNN

Thorium-229 GF0;TF0NNNNNNNNNNNNNGN

Thorium-230 GF0;TF0;Th-230NGNNNNNYYNGNGGY

Thorium-232 GF0;TF0;NNNNNNNNYNNNNGY

Thorium-234 GB0NNNNNNNNNNNNNNN

Protactinium-231 PF3;PA0NNNNNNGYYNYYNGG

Protactinium-233 PA3, SCNNNNNNNNGGNGNNG

Uranium-232 UR0NNNNNNGGGGGNNGN

Uranium-233 UR0NNNNNNGGGNGGGGG

Uranium-234 UR0NGNNNNGGGNGGGGG

Uranium-235 UR0GGGNNNGGGNGGGGG

Uranium-236 UR0GGNNNNGGGNGGGGG

Uranium-238 UR0GGNNNNGGGGGGGGG
 

Document No. ORAUT-RPRT-0090 Revision No. 00 Effective Date: 03/2

9/2018 Page 31 of 133

Table 7-2. Results of feasibility analysis for 1955 to 1969 (continued).a

Nuclide Bioassay method codeb 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69

Neptunium-236 SC N N N N N N N N N N G N N N N

Neptunium-237 017;GU0;NP0; G G G N G N G G N G G N G G N

Neptunium-238 013/GB0; SC N N N N N N N N N N N G N N N

Plutonium-236 PU0 N N N N N N N N N N N N N G N

Plutonium-237 PU0 N N N N N N N N N N N N N N N

Plutonium-238 GU0;PU0 N N N N N N G G G N G N N G G

Plutonium-239 GU0;PU9;PU0 G G N N N N G G G G G G G G G

Plutonium-240 GU0;PU0 N N N N N N G G G G G G N G G

Plutonium-241 000(Pu-241); PU1c R R N N R N N R R R R R R G G

Plutonium-242 GU0;PU0 N N N N N N G G G G G G G G G

Plutonium-244 PU0 N N N N N N N N N N N N N G N

Americium-241 000(Am-241);AM0; 

GUO;TP0 N N N N G G G G G G G G G G G 

Americium-243 000(Am-243); TP0 N N N N N N G G G G G G G G G

Curium-242 000(Cm-242); TP0 N N N N N N G G G G G G N G N

Curium-243 TP0 N N N N N N N N N N G N N N N

Curium-244 000(Cm-244); TP0;CM0 N N N N N N N G G G N G G G G

Curium-245 TP0 N N N N N N N N N N N N N N G

Curium-246 TP0 N N N N N N N N N N N N N N N

Curium-247 TP0 N N N N N N N N N N N N N N G

Curium-248 TP0 N N N N N N N N N N N N N G G

Berkelium-249 000(Bk-249); TP0 N N N N N N N N N G N N G N G

Californium-248 TP0 N N N N N N N N N N N N N N N

Californium-249 TP0 N N N N N N N N N N N N N G G

Californium-250 TP0 N N N N N N N N N N N N N N N

Californium-252 TP0 N N N N N N N G N N N N G G G

Californium-253 TP0 N N N N N N N N N N N N N N N

Einsteinium-252 TP0 N N N N N N N N N N N N N N N

Einsteinium-253 TP0 N N N N N N N N N N N N G G G

Einsteinium-254 TP0 N N N N N N N N N N N N N N N

Fermium-255 TP0 N N N N N N N N N N N N N N N

Fermium-257 TP0 N N N N N N N N N N N N N G G

a. See Section 7.1 for color coding.

b. Bioassay codes defined in Tables 4-1 and 4-2. EXT indicates exposure monitored by external dosimetry, SC indicates monitored by in vitro analysis, TH indicates 

monitored by in vitro thyroid counting.

c. See discussion in Section 7.2.
 

Document No. ORAUT-RPRT-0090 Revision No. 00 Effective Date: 03/29/2018 Page 32 of 133

Table 7-3. Results of feasibility analysis for 1970 to 1988.

a 

Nuclide

Bioassay 

method code

a 70 71 72 73 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88

Hydrogen-3 HY3GGGGGGGGGGGGGGGGGGG

Beryllium-7 SC

c

NNNNNNNNNNNNNNNNNNN

Carbon-11 SCNNNNNGNGNGGNNNNNNNN

Carbon-14 000(C-14); 

013/GB0;C14 G G Y G Y Y N N N N Y Y Y Y N Y N N N 

Sodium-22 013/GB0;SCNNNNNNNNNNNNNNNNNNN

Sodium-24 013/GB0;004;SCNNNNNNNNNNNNNNNNNNN

Magnesium-28 SCGNNNNNNGNNNNNGGNNGG

Phosphorus-32 000(P-32); PH2NNNNNNNNNNNNNNNNNNN

Phosphorus-33 013/GB0GGYGYYYYYYYYYYGYYYN

Sulfur-35 000(S-35);001NNNNNNNNNNNNNNNNNNN

Chlorine-36 000(Cl-36); 

013/GB0 G G Y N N N N N N N N N N N N N N N N 

Chlorine-38 013/GB0NNNNNNNNNNNNNNNNNNN

Argon-37 EXTGGNGGGGGGGGGGNNNNNN

Potassium-40 SCNNNNNNNNNGNNNNNNNNN

Potassium-42 013/GB0;SCNNNNNNNNNNNNNNNNNNN

Potassium-43 SCNGNGGGGGGNGGNGNNNNN

Calcium-41 (c)NNNNNNNRNNNNNNNNRNN

Calcium-45 000(Ca-45); 

013/GB0 N N N N N N N N N N N N N N N N N N N 

Calcium-47 013/GB0;SCGGGGGGGGGGGGGGGNNNN

Scandium-46 013/GB0; FU0; 

SC G G G G N N N N N N N N N N N N N N N 

Scandium-49 013/GB0; FU0NNNNNNNNNNNNNNNNNNN

Titanium-44 013/GB0NNNNNNNNNNNNNNNNNNN

Vanadium-48 SCNNNNNNNNNNNNNNNNNNN

Chromium-51 000(Cr-51); SC

c

NNNNNGNNNNNNNNNNNNN

Manganese-52 013/GB0NNNNNNNNNNNNNNNNNNN

Manganese-54 010;SC

c

NNNNNNNNNNNNNNNNNNN

Iron-55 000(Fe-55)

c

NNNNNNNNNNRRRGYYYNN

Iron-59 000(Fe-59); 

013/GB0;009;SC N N N N N N N N N N N N N N N N N N N 

Cobalt-56 SCNNGNNNNGNNNNNNNNNNN

Cobalt-57 000(Co-57); SC

c

NNGGGGGNNNNNNNNNNNN

Cobalt-58 013/GB0;SCNNNNNNNNNNNNNNNNNNN
 

Document No. ORAUT-RPRT-0090 Revision No. 00 Effective Date: 03/29/2018 Page 33 of 133

Table 7-3. Results of feasibility analysis for 1970 to 1988 (continued).a 

Nuclide

Bioassay 

method code

a 70 71 72 73 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88

Cobalt-60 000(Co-60); 

013/GB0;002;CO

0;SC

G G G G G G G G G G G G G G G G G G G 

Nickel-63 013/GB0GGYNNNNNYNYNNNNYYYN

Nickel-66 013/GB0NNNNNNNNNNNNNNNNNNN

Copper-64 013/GB0NNNNNNYNNNNNNNNNNNN

Copper-67 SCGGNGGGGNNNNNNNNNNNN

Zinc-65 000(Zn-65); 

013/GB0;SC N N N N N N N N N N N N N N N N N N N 

Zinc-69m GB0NNNGYNNNNNNNNNNNNNN

Gallium-67 000(Ga-67); SC

c

GGGGGGGGGNNNNGNNNNN

Gallium-68 SCNGNNNNNNNNNNNNNNNNN

Gallium-72 013/GB0; SCGNNNNNNNNNNNNNNNNNN

Arsenic-71 013/GB0NNNNNNNNNNNNNNNNNNN

Arsenic-72 013/GB0NNNNNNNNNNNNNNNNNNN

Arsenic-74 007; 013/GB0;SCNNNNNNNNNNNNNNNNNNN

Arsenic-76 013/GB0;SCNNNNNNNNNNNNNNNNNNN

Arsenic-77 013/GB0NNNNNNNNNNNNNNNNNNN

Selenium-75 SC

c

NNNNNNNNNGGGGGGGGNN

Bromine-82 008, 

0013/GB013;SC N N N N N N N N N N N N N N N N N N N 

Bromine-85 013/GB0NNNNNNNNNNNNNNNNNNN

Krypton-85 EXTGGGGGGGGGGGGGGGGGGG

Rubidium-83 SCNNNNNNNNNNNNNNNNNNN

Rubidium-84 SCNNNNNGNNNNNNNNNNNNN

Rubidium-86 013/GB0;SCGGGNNNNNNNNNNNNNNNN

Rubidium-88 SCNNNNNNNNNNNNNNNNNNN

Strontium-82 SCGNNNNNNNNNNNNNNNNNN

Strontium-85 SR5; SC

c

YNNNNNNNNNNNNNNNYNN

Strontium-87m SC

c

GNNNNNNNNNNNNNNNNNN

Strontium-89 SR0;SR9; 

013/GB0; G G G G G G G G G G G G G G G G G G N 

Strontium-90 SR0GGGGGGGGGGGGGGGGGGG

Yttrium-86 SCNNNNNNNNNNNNNNNNNNN

Yttrium-88 000(Y-88); 

013/GB0; FU0;SC N N N N G N N N N N N N N N N N N N N 

Yttrium-90 000(Y-90); FU0NNNGNNNNNNNNNNNNNYY

Yttrium-91 013/GB0; FU0GGGGGGGGGNNNNNNNNNN
 

Document No. ORAUT-RPRT-0090 Revision No. 00 Effective Date: 03/29/2018 Page 34 of 133

Table 7-3. Results of feasibility analysis for 1970 to 1988 (continued).a 

Nuclide

Bioassay 

method code

a 70 71 72 73 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88

Zirconium-95 000(Zr-95)005; 

013/GB0;SC G G G G G G G G G G G G G G G G G N N 

Zirconium-97 SCNGNNNNNNNNNNNNNNNNN

Niobium-90 013/GB0NNNNNNNNNNNNNNNNNNN

Niobium-92 SCNNNNNNNNNNNNNNNNNNN

Niobium-92m SCNNNNNNNNNNNNNNNNNNN

Niobium-95 000(Nb-95); 005; 

013/GB0;SC G G G G G G G G G G G G N G G G N N N 

Molybdenum-93 (c)NNNNNNNNNNNNNNNNNNN

Molybdenum-99 013/GB0;SCGGNNNNNNNNNNNNNNNNN

Technetium-95m 013/GB0;SCGNNNNNNNNNNNNNNNNNN

Technetium-99 000(Tc-99); 006; 

013/GB0;GB0; G N Y G Y Y Y Y Y Y Y Y Y Y G G Y Y Y 

Technetium-99m SCGNNNNNNNNNNNNNNNNNN

Ruthenium-97 013/GB0GNNNNNNNNNNNNNNNNNN

Ruthenium-103 000(Ru-103); SC

c

GGGGGGGGGGGGGGGGGNN

Ruthenium-105 013/GB0NNNNNNNNNNNNNNNNNNN

Ruthenium-106 000(Ru-106); 

013/GB0; RU6 G G G G G G G G G G G G G G G G G G G 

Rhodium-102 013/GB0NNNNNNNNNNNNNNNNNNN

Palladium-103 (c)NNNNNNNNNNNNNNNNNNN

Palladium-109 013/GB0GGNNNNNNNNNNNNNNNNN

Silver-110m 013/GB0;018;SCNNNNNNNNNNNNNNNNNNN

Silver-111 013/GB0GNNNNNNNNNNNNNNNNNN

Cadmium-109 000(Cd-109)

c

NNRNNNNNNNNNNNNNNNN

Cadmium-115 013/GB0NNNNNNNNNNNNNNNNNNN

Cadmium-115m 013/GB0NNNNNNNNNNNNNNNNNNN

Indium-111 SCGGNGNNNNNNNNNNNNNNN

Indium-114 013/GB0GGYGYYYYNNNYNNNNNNN

Indium-114m SCNNNNNGNNNNNNNNNNNNN

Tin-113 SC

c

NNNNNNNNNGNNNNNNNNN

Tin-117m SCNNNNNNNGNNNNNNNNNNN

Tin-119m (c)NNNNNNNNNNNNNNNNRNN

Antimony-122 013/GB0;SCNGNNNNNNNNNNNNNNNGN

Antimony-124 013/GB0;SCNNNNNNNNNNNNNNNNNNN

Antimony-125 013/GB0;015;SCNNNNNNNNNNNNNNNNNNN

Tellurium-121 (c)NNNNNNNNNNNNNNNNNNN

Tellurium-132 SCNNNNNNNNNNNNNNNNNNN
 

Document No. ORAUT-RPRT-0090 Revision No. 00 Effective Date: 03/29/2018 Page 35 of 133

Table 7-3. Results of feasibility analysis for 1970 to 1988 (continued).a 

Nuclide

Bioassay 

method code

a 70 71 72 73 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88

Iodine-123 THGNNNNNNNNNNNNNNNNNN

Iodine-125 000(I-125); I25; 

THc N N N N N N N N N N N N N N N N N N N 

Iodine-129 THGGGGGGGGGYYYYYYYGGG

Iodine-130 TH

c

GGGNNNNNNNNNNNNYNNN

Iodine-131 000(I-131); 011; 

I31; THc G G G G G G G N G Y Y N N Y N Y G N G 

Iodine-132 THGGGNNNNNNNNNNNNNNNN

Iodine-133 TH

c

NNNNNNNGNNNNNNNNNNN

Xenon-127 EXTNNNNNNNNNNNNNGNNNGG

Xenon-133 EXTGGGGGGGNGGGNNNNNNNN

Cesium-131 (c)NNNNNNNNNNNNNNNNNNN

Cesium-132 000(Cs-132); 

012; SC N N N N N N N N N N N N N N N N N N N 

Cesium-134 013/GB0;SCNNNNNNNNNNNNNNNNNNN

Cesium-137 CS7;CS0; SCGGGGGGGGGGGGGGGGGGG

Barium-131 SR0GGNNNNNNNNNNNNNNNNN

Barium-133 SC

c

GGGNNNNNNNNNNNNNNNN

Barium-135m SCGNNNNNNNNNNNNNNNGNN

Barium-140 014;SR0GGGGGGGGGNGGNGNNNNN

Lanthanum-140 013;FU0;SCNNNNNNNNNNNNNNNNNGN

Cerium-139 (c)NNNNNNNNNNNNNNNNNNN

Cerium-141 013/GB0;FU0GNNNNNNNNNNNNNNNNNN

Cerium-144 013/GB0;FU0;SCGGGGGGGGGYNYYYYGGGG

Praseodymium-

142

013/GB0;FU0 G N N N N N N N N N N N N N N N N N N 

Praseodymium-

143

013/GB0;FU0 G N G G N N N N N N N N N N N N N N N 

Praseodymium-

144

013/GB0;FU0 N N N N N N N N N N N N N N N N N N N 

Neodymium-140 013/GB0NNNNNNNNNNNNNNNNNNN

Neodymium-147 013/GB0;FU0; SCGGGGNNNNNYNNNNNNNNN

Neodymium-149 013/GB0;FU0; SCNNNNNNNNNYNNNNNNNNN

Promethium-145 (c)NNNNNNNNNNNNNNNNNNN

Promethium-146 013/GB0;FU0; SCNNNNGNNNNNNNNNNNNNN

Promethium-147 000(Pm-147); 

013;PM7; 

FU0;Pm-147

G G G G G G G G G Y G Y Y Y Y G Y Y N 
 

Document No. ORAUT-RPRT-0090 Revision No. 00 Effective Date: 03/29/2018 Page 36 of 133

Table 7-3. Results of feasibility analysis for 1970 to 1988 (continued).a 

Nuclide

Bioassay 

method code

a 70 71 72 73 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88

Promethium-148 013/GB0;FU0; SCGNNNNNNNNNNNNNNNNNN

Samarium-151 013/GB0;FU0;GGGGGGGGGYGYYNYGYYN

Samarium-153 013/GB0;FU0NNNNNNNNNNNNNNNNNNN

Europium-152 000(Eu-152); SCNNNNGGNNGGGGNNGGNNG

Europium-155 000(Eu-155); 

013;SC N N N N N G N N N N N N N N N N N N N 

Gadolinium-148 GA0GNNNNNNNNNNNNNNNNNN

Gadolinium-153 000(Gd-153); 

GD0; SC N G N G G G G G G G G G G G G G G G G 

Terbium-156 SC

c

NNNNNNNNNNNNNNNNNNN

Terbium-158 FU0GNNNNNNNNNNNNNNNNNN

Dysprosium-157 FU0NNNNNGNNNNNNNNNNNNN

Dysprosium-159 (c)NNNNNNNNNNNNNNNNNNN

Dysprosium-166 FU0NNNNNNNNNNNNNNYNNNN

Holmium-156 FU0; SCNNNNNNNNNNNNNNNNNNN

Holmium-166 013/GB0NNNNNNNNNNNNNNNNNNN

Erbium-171 013/GB0NNNGNNNNNNNNNNNNNNN

Thulium-170 000(Tm-170);FU0GGNNGGNNNNNNNNNNNNN

Thulium-171 FU0NNNNNNNNNNNNNNNNNNN

Ytterbium-169 SCNNNNNNNNNNGNNNNNGNN

Hafnium-181 013/GB0GGYGYYYYNYYNNNNNNNN

Tantalum-182 013/GB0;SCGGGNGNNNNNNNNNNNNNN

Tungsten-181 (c)NNNNNNNNNNNNNNNNNNN

Tungsten-185 013/GB0GGNNNNNNNNNNNNNNNNN

Tungsten-187 013/GB0;SCGNNNNNNNNNNNNNNNNNN

Rhenium-186 013/GB0GGGNNNNNNGNNNNNNNNN

Osmium-185 SC

c

NNNNNNNNNNNNNNNNNNN

Osmium-191 013/GB0;SCGNNNNNNNNNNNNNGNNNN

Iridium-192 000(Ir-192); 

0013/GB0;SC G G N G G G G G G G G G G G G G G G G 

Iridium-194 013/GB0;SCNNNNNNNNNNNNNNNNNNN

Platinum-195m SCNNGGGNNNGNNNNNNNNNN

Platinum-197 SCNNNNNNNNNNNNNNNNNNN

Gold-195 (c)NNNNNNNNNNNNNNNNNNN

Gold-198 013/GB0; SCNNNNNNNNNNNNNNNNNNN

Gold-199 013/GB0;SCNNNNNNNNNNNNNNNNNNN

Mercury-197 SC

c

NNNNNNNNNNNNNNNNNNN

Mercury-203 013/GB0;SCNNNNNNNNNNNNNNNNNNN
 

Document No. ORAUT-RPRT-0090 Revision No. 00 Effective Date: 03/29/2018 Page 37 of 133

Table 7-3. Results of feasibility analysis for 1970 to 1988 (continued).a 

Nuclide

Bioassay 

method code

a 70 71 72 73 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88

Thallium-201 000(Tl-201); SCNNNNNGNNNNNNNNNNNNN

Thallium-204 013/GB0;016GGNNNNNNNNNNNNNNNNN

Lead-203 SCNNGGNNNNNNNNNNNNNNN

Bismuth-206 (c)NNNNNNNNNNNNNNNNNNN

Bismuth-207 013/GB0NNNNNNNNNNNNNNNNNNN

Bismuth-210 013/GB0GNNNNNNNNNNNNNNNNNN

Polonium-210 004;PO0; GU0NNNNNNNNNNNNNNNNNNN

Thorium-228 GU0NNNNNNNNNNNNNNNNNNN

Thorium-229 GF0;TF0YYNYYNNGNGGGGGYYGNY

Thorium-230 GF0;TF0;Th-230YYGYYGGNGGGGGGYYGYY

Thorium-232 GF0;TF0;NNGYYGGNGGGGGGYYGYN

Thorium-234 GB0NNNNNNNNNNNYNNNNNNN

Protactinium-231 PF3;PA0NNNNNNYGYYYYNNYYYNN

Protactinium-233 PA3, SCNNNNNNNNNNNNNNNNNNN

Uranium-232 UR0GGNNGGGGGGNNNNNNNNN

Uranium-233 UR0GGGGGGGGGGGGGGGGGGG

Uranium-234 UR0GGGGGGGGGGGGGGGGGGG

Uranium-235 UR0GGGGGGGGGGGGGGGGGGG

Uranium-236 UR0GGGGGGGGGGGGGGGGGGG

Uranium-238 UR0GGGGGGGGGGGGGGGGGGG

Neptunium-236 SCNNNNNNNNNNNNNNNNNNN

Neptunium-237 017;GU0;NP0;GNGYYYYYGGYYYYYYYYN

Neptunium-238 013/GB0; SCNNNNNNNNNNNNNNNNNNN

Plutonium-236 PU0GNNGNGNNNNNGNNGNGNN

Plutonium-237 PU0NNNNNNNNNNNNNNGNGNN

Plutonium-238 GU0;PU0GGGGGGGGGGGGGGGGNGG

Plutonium-239 GU0;PU9;PU0GGGNGGGGGGGGGGGGNGG

Plutonium-240 GU0;PU0GGGGGGGGGGGGGGGGGNG

Plutonium-241 000(Pu-241); 

PU1

c G G G G G Y N G G G Y G G G G G Y N N 

Plutonium-242 GU0;PU0GGGGGGGGGGGGGGGGGGG

Plutonium-244 PU0GGGGGGGGGGGGGNNNNNN

Americium-241 000(Am-241);

AM0; GUO; TP0 G G G G G G G G G G G G G G G G G G G 

Americium-243 000(Am-243); 

TP0 G G G G G G G G G N G G G G G G G N G 

Curium-242 000(Cm-242); 

TP0 N N N N N N N N N N N N N N N N G N N 
 

Document No. ORAUT-RPRT-0090 Revision No. 00 Effective Date: 03/2

9/2018 Page 38 of 133

Table 7-3. Results of feasibility analysis for 1970 to 1988 (continued).a 

Nuclide

Bioassay 

method codea 70 71 72 73 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88

Curium-243 TP0 N N G G N G G N N N N G G G N N N N N

Curium-244 000(Cm-244); 

TP0;CM0 G G G G G G G G G G G G G G G G G G G 

Curium-245 TP0 N N G G N N N N N N N N N N N N G N N

Curium-246 TP0 G G N G N N N G N N N N N N N N N N G

Curium-247 TP0 N N G N N N N N N N N N N N N N N N N

Curium-248 TP0 G G G G G G G G G G G N G G G N G N G

Berkelium-249 000(Bk-249); TP0 G G G G G G G G G G G G G G G N G N G

Californium-248 TP0 N N G N N N N N N N N N N N N N N N N

Californium-249 TP0 G G G G G G G N N G G G G N G N G N N

Californium-250 TP0 G N N G G G G N N N G N N N N N N N N

Californium-252 TP0 G G G G G G G G G G G G G G G G G G G

Californium-253 TP0 N N N N N N N N N N N N N N G N N N N

Einsteinium-252 TP0 G N N N N N N N N N N N N N N N N N N

Einsteinium-253 TP0 G G G G G G G G G G G G N N G N G N G

Einsteinium-254 TP0 N N G G G N N N N N G N G N G N N N G

Fermium-255 TP0 N N N N N N N N N N N N N N G N N N G

Fermium-257 TP0 G G G G G G G G N N G N N N G N G N G

a. See Section 7.1 for color coding.

b. Bioassay codes defined in Tables 4-1 and 4-2. EXT indicates exposure monitored by external dosimetry, SC indicates monitored by in vitro analysis, TH indicates 

monitored by in vitro thyroid counting.

c. See discussion in Section 7.2. 
Document No. ORAUT-RPRT-0090 Revision No. 00 Effective Date: 03/29/2018 Page 39 of 133

 

Table 7-4. Thirty-four radionuclides identified as needing additional evaluation. 

Nuclide Production years Half life

Decay 

modea

Photon 

energyb (keV)

Electron 

energyb (keV)

Beryllium-7 1955, 1957–1959, 1962, 1964, 1969 53.3 d EC 49.3 0

Calcium-41 1977, 1986 1.4E5 yr EC 0.4 2.3

Chromium-51 1955–1967, 1975 27.7 d EC 32.5 3.8

Manganese-54 1955–1957, 1960, 1963–1965 312.5 d EC 836 4.2

Iron-55 1955–1956, 1959–1966, 1980–1986 2.7 yr EC 1.6 4.2

Cobalt-57 1955–1957, 1964, 1972–1976 270.9 d EC 125.2 18.6

Gallium-67 1958–1959, 1969–1978, 1983 78.26 hr EC 158 35.5

Selenium-75 1955–1957, 1959–1966, 1979–1986 119.8 d EC 394.2 14.5

Strontium-85 1955, 1957–1967, 1970, 1986 64.84 d EC 511.8 8.9

Strontium-87m 1960, 1964, 1970 2.8 hr EC 320.3 66.9

Molybdenum-93 1957, 1962 3.5E3 yr EC 10.6 5.5

Ruthenium-103 1955–1957, 1959–1986 39.28 d EC 468.7 74.8

Palladium-103 1962, 1964 16.96 d EC 14.4 5.8

Cadmium-109 1957–1958, 1960–1961, 1963–

1966, 1972

464 d EC 26.3 82.6

Tin-113 1955–1957, 1959–1967, 1979 115.1 d EC 22.8 6.3

Tin-119m 1986 293 d IT 11.4 77.7

Tellurium-121 1957 17 d EC 577.3 9.9

Iodine-125 1957, 1961–1964 60.1 d EC 42 19.3

Iodine-129 1955–1957, 1959–1988 1.57E7 yr β– 24.6 63.8

Iodine-130 1960–1972, 1985 12.36 hr β– 2,138.5 297.2

Iodine-131 1955–1976, 1978–1980, 1983, 

1985–1986, 1988

8.04 d β– 381.5 191.7

Iodine-133 1961, 1967–1968, 1977 20.8 hr β– 607.1 410.6

Cesium-131 1965 9.69 d EC 22.8 6.5

Barium-133 1955–1957, 1959–1972 10.74 yr EC 401.9 54.2

Cerium-139 1955, 1957–1958 137.66 d EC 159.5 35.5

Promethium-145 1968 17.7 yr EC 31 14

Terbium-156 1958, 1967–1968 5.34 d EC 1,826 103.1

Dysprosium-159 1957, 1961 144.4 d EC 45 12.8

Tungsten-181 1957–1958 121.2 d EC 40.4 10.8

Osmium-185 1957, 1966 94 d EC 718.9 19.2

Gold-195 1961 183 d EC 84.6 50.7

Mercury-197 1957–1966 64.1 hr EC 70 66.4

Bismuth-206 1957–1958 6.24 d EC 3,278.1 135.8

Plutonium-241 1955–1956, 1959, 1962–1975, 

1977–1986

14.4 yr β– 0 5.2

a. EC = decay by electron capture, IT = decay by isomeric transition, β– = decay by beta emission.

b. Emitted photon and X-ray energy per transformation.

c. Emitted beta, conversion electron, and auger electron energy per transformation.

Table 7-5. Derived air concentration values for 28 

radionuclides requiring further evaluation. 

Nuclide DACa (μCi/cm3)

Beryllium-7 1.2E-05

Calcium-41 3.0E-06

Chromium-51 1.6E-05

Manganese-54 4.7E-07

Iron-55 6.1E-07

Cobalt-57 9.4E-07

Gallium-67 2.0E-06

Selenium-75 3.3E-07

Strontium-85 8.8E-07
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Table 7-5. Derived air concentration values for 28 

radionuclides requiring further evaluation (continued). 

Nuclide DACa (μCi/cm3)

Strontium-87m 1.6E-05

Molybdenum-93 4.0E-07

Ruthenium-103 2.6E-07

Palladium-103 1.9E-06

Cadmium-109 5.9E-08

Tin-113 3.0E-07

Tin-119m 3.8E-07

Tellurium-121 1.1E-06

Cesium-131 1.3E-05

Barium-133 3.1E-07

Cerium-139 4.0E-07

Promethium-145 2.3E-07

Terbium-156 4.0E-07

Dysprosium-159 2.3E-06

Tungsten-181 1.3E-05

Osmium-185 4.0E-07

Gold-195 4.7E-07

Mercury-197 1.3E-07

Bismuth-206 2.7E-07

a. Based on contemporary (ICRP 1994) DCFs and corresponds 

to the air concentration that, if breathed at the standard rate 

(1.2 m3/hr) for 2,000 hr/yr will result in a committed effective 

dose equivalent of 5 rem.

Standards Handbook 69 (NCRP 1959) was adopted. The MPC for occupational exposure to 

unidentified beta/gamma emitters was set at 1 x 10-9 μCi/cm3 (Hart 1960) with trigger levels remaining 

at 0.1 MPC (1 × 10-10 μCi/cm3

) for general entry without respiratory protection (ORNL 1961). 

Information on the DAC values associated with the radionuclides shown in Table 7-5 along with the 

general standards in place at the time is provided to illustrate the culture around radiation safety at the time 

of production of these exotics. For example, pre NBS, the respiratory protection requirements were set at values 

less than the DACs for the nuclides shown in Table 7-5. Post NBS, the standard was even more protective than 

the DACs shown in Table 7-5.

An evaluation of the dosimetric consequences of each of the 28 radionuclides requiring further 

analysis was conducted. The committed dose to the maximally exposed organ from inhalation of 

1 × 10-5 of the total annual inventory was computed for the year with the maximum recorded inventory 

(Table 7-6). The factor 1 × 10-5 was selected based on the guidance in NUREG-1400, which 

postulates that 1 × 10-6 times the material handled could serve as a reasonable estimate of the 

quantity that could be inhaled (Hickey et al. 1993). A factor of 10 was added to ensure a conservative 

evaluation. The organ dose conversion factor (DCF; mrem/mCi) for the organ with the highest unit 

dose per intake was selected from ICRP (1994), as shown in the table. Although inventory quantities 

were not available for six radionuclides (93Mo, 103Pd, 139Ce, 156Tb, 185Os, and 206Bi), dose 

consequences (50-year committed dose equivalent) from inhalation of a significant fraction of the 

annual inventory for the remainder range from 0.3 mrem to 1,464 mrem to the maximally exposed 

organ. It should be noted that the inventory quantity for 55Fe in this calculation did not consider the 

inventory during 1980 through 1982, during which values were as high as 1 × 106 mCi (a factor of 

1,600 higher than in previous years). The intake quantity calculated using the analysis method would 

predict an intake quantity of 0.1 Ci, which corresponds to an air activity of 4 × 10-5 μCi/ml. Exposure 

to this concentration of 55Fe without detection by workplace monitoring controls does not seem 

credible, considering the fact that the manufacturing process for 55Fe would also carry over a small 

percentage of 59Fe (an easily detected beta/gamma emitter). The ORNL radioisotope production 
Document No. ORAUT-RPRT-0090 Revision No. 00 Effective Date: 03/29/2018 Page 41 of 133

manual indicates that 59Fe is produced by the same production mechanism as 55Fe (irradiation of 

54Fe) and lists its presence at <5%.

Table 7-6. Dosimetric analysis of radionuclides. 

Nuclide

Maximum 

annual 

inventory (mCi)

Maximum 

organ DCFa

(mrem/mCi) Organa

Dose to organ from annual 

inhalation of 1 × 10-5 time 

inventoryb (mrem)

Beryllium-7 340 1,554 Extrathoracic airways 5

Calcium-41 501 9,250 Bone surface 46

Chromium-51 46,225 925 Extrathoracic airways 428

Manganese-54 115 27,010 Extrathoracic airways 31

Iron-55 620c 27,750 Spleen 172

Cobalt-57 175 13,690 Lungs 24

Gallium-67 120 6,290 Extrathoracic airways 8

Selenium-75 2,160 27,750 Kidneys 599

Strontium-85 142 20,720 Extrathoracic airways 29

Strontium-87m 84 2,220 Extrathoracic airways 2

Molybdenum-93 (d) 103,600 Bone surface (d)

Ruthenium-103 1,020 55,500 Lungs 566

Palladium-103 (d) 6,290 Extrathoracic airways (d)

Cadmium-109 64 851,000 Kidneys 545

Tin-113 610 48,100 Lungs 293

Tin-119m 3,598 40,700 Lungs 1464

Tellurium-121 13 19,980 Extrathoracic airways 3

Cesium-131 25 2,775 Extrathoracic airways 1

Barium-133 80 35,520 Bone surface 28

Cerium-139 (d) 37,000 Lungs (d)

Promethium-145 32 151,700 Bone surface 49

Terbium-156 (d) 51,800 Extrathoracic airways (d)

Dysprosium-159 60 9,620 Bone surface 6

Tungsten-181 18 1,628 Extrathoracic airways 0.3

Osmium-185 (d) 26,270 Extrathoracic airways (d)

Gold-195 5.6 30,710 Lungs 2

Mercury-197 542 133,200 Lungs 722

Bismuth-206 (d) 88,800 Extrathoracic airways (d)

a. DCFs are based on ICRP (1994), obtained from the Radiological Toolbox. While DCFs are provided for a multitude of

individual organs, the highest value (along with the associated organ) is listed and was used in subsequent calculations.

b. The calculated values represents the 50-year committed dose to the organ listed based on an intake of 1E-05 times the

listed inventory quantity.

c. Inventory quantities for 1980 to 1982 were not included in analysis.

d. No Inventory data are available for these radionuclides.

As indicated in Section 4.2, ORNL had an active bioassay program from the earliest period under 

evaluation (1955) and routinely performed analyses for tritium, polonium, plutonium, radium, 

strontium, uranium, gross alpha, and gross beta. When necessary, additional methods were 

developed to meet emergent sampling needs. Such supplemental sampling was coded specifically to 

the analyte (codes 001–018, as defined in Table 4-1) or was given a more general “000” code (or 0F0 

for fecal analysis). 

Table 4-3 lists all of the analytes associated with the 1584 code “000” sample results that are known 

to exist (based on the ORNL bioassay database; ORNL 2013). This listing is potentially incomplete 

because it is known that not all bioassay results were recorded into the bioassay database (see the 

discussion in Section 4.2). However, at one point or another bioassay analyses specific to eight of the 

28 radionuclides under evaluation (51Cr, 54Mn, 55Fe, 57Co, 67Ga, 85Sr, 103Ru, and 109Cd) were 

performed. Table 7-7 indicates the frequency of these samples.
Document No. ORAUT-RPRT-0090 Revision No. 00 Effective Date: 03/2

9/2018 Page 42 of 133

Table 7-7. Number of bioassay samples collected for code 000 analytes by year. 

Analytical 

method code 

(radionuclide) Production years 1960 1964 1965 1968 1969 1970 1971 1973 1976 1978 1983 1987

000 (Cr) 1955–1967, 1975 NS 2 NS NS NS NS NS NS NS NS NS NS

000 (Cr-51) 1955–1967, 1975 NS 1 NS 2 NS NS NS NS 1 NS NS NS

010 (Mn-54) 1955–1957, 1960, 1963–1965 2 NS NS NS NS NS NS NS NS 1 NS NS

000 (Fe-55) 1955–1956, 1959–1966, 1980–1986 NS NS NS NS NS NS NS NS NS NS 5 NS

000 (Co-57) 1955–1957, 1964, 1972–1976 NS NS 2 NS NS NS NS NS NS NS NS NS

000 (Ga-66/67) 1958–1959, 1969–1978, 1983 NS NS NS NS NS 5 NS NS NS NS NS NS

000 (Ga-67) 1958–1959, 1969–1978, 1983 NS NS NS 2 NS NS 1 NS NS NS NS NS

SR5 (Sr-85) 1955, 1957–1967, 1970, 1986 3 NS NS NS NS NS NS NS NS NS NS 8

000 (Ru-103) 1955–1957, 1959–1986 NS NS 2 NS NS NS NS NS NS NS NS NS

000 (Ru-103/106) 1955–1957, 1959–1986 NS NS NS NS 4 NS NS NS NS NS NS NS

000 (Cd-109) 1957–1958, 1960–1961, 1963–1966, 1972 NS NS NS NS NS NS NS 1 NS NS NS NS

a. NS = No samples collected.
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8.0 SUMMARY

Isotope production at ORNL involved a wide array of radioactive materials it termed exotic 

radionuclides. Radionuclides ORNL could not readily detect by gross alpha or beta/gamma methods 

presented a particular monitoring challenge. This report identifies 28 radionuclides that might present 

such a monitoring challenge. Evaluation of the ORNL bioassay program indicates the ability to 

develop specialized bioassay methods as needed to adapt to changing conditions and emergent 

events. While evidence has not been found for all of the 28 identified nuclides, it is clear that ORNL 

had the capability to develop methods as needed. In addition, the relatively low radiotoxicity of these 

same nuclides in comparison with a bounding potential intake (Table 7-6) lends credence to the 

position that a significant intake of one of these nuclides would not be credible.
Document No. ORAUT-RPRT-0090 Revision No. 00 Effective Date: 03/29/2018 Page 44 of 133

 

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ATTACHMENT A 

SUMMARY OF IN VITRO BIOASSAY METHODS

TABLE OF CONTENTS

SECTION TITLE PAGE

A.1 Gross Analysis Methods......................................................................................................... 49

A.1.1 Gross Alpha................................................................................................................ 49

A.1.2 Gross Beta ................................................................................................................. 49

A.1.3 Fission Products......................................................................................................... 49

A.1.4 Rare Earth.................................................................................................................. 49

A.1.5 Transplutonium........................................................................................................... 50

A.2 Element-Specific Analysis Methods ....................................................................................... 50

A.2.1 Barium........................................................................................................................ 50

A.2.2 Cesium ....................................................................................................................... 51

A.2.3 Cobalt......................................................................................................................... 51

A.2.4 Neptunium.................................................................................................................. 51

A.2.5 Plutonium ................................................................................................................... 52

A.2.6 Plutonium-241 ............................................................................................................ 52

A.2.7 Polonium .................................................................................................................... 52

A.2.8 Protactinium ............................................................................................................... 53

A.2.9 Radium....................................................................................................................... 53

A.2.10 Strontium.................................................................................................................... 54

A.2.11 Thorium ...................................................................................................................... 54

A.2.12 Tritium ........................................................................................................................ 54

A.2.13 Uranium...................................................................................................................... 55
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A.1 GROSS ANALYSIS METHODS

A.1.1 Gross Alpha

The ORAU Team observed gross alpha bioassays in the dataset as far back as 1951, and found a 

1957 procedure describing gross alpha urinalysis (Brown, Davis, and Henley 1957). The method 

includes a bismuth phosphate lanthanum fluoride precipitation of the raw urine with the sample dried 

for alpha counting. 

A 1978 gross alpha fecal method describes the following sequence: drying the fecal sample, 

treatment with an acid solution, separation using ion exchange resins, evaporation of the final product, 

and electrodepositing of the sample for alpha counting (Henley 1978).

A.1.2 Gross Beta

Gross beta bioassays were observed in the dataset from as far back as 1954, but reports indicate that 

gross beta urine measurements were performed as early as 1948. 

The first instance of a basic procedure for gross beta urinalysis was indicated in a 1948 memorandum 

(Farabee 1948a). During the procedure, a 50-mL urine sample was taken, the organic material was 

destroyed, the inorganic residue was deposited on a watch glass, and the total activity was 

determined. A note states that some of the activity may be due to potassium being present.

The first more-comprehensive procedure for gross beta urinalysis was issued in 1968 (Henley 1968). 

This method was used to estimate the beta activity in urine exclusive of the naturally occurring 40K. 

Two alternative methods were identified: (1) a precipitation using calcium phosphate, or (2) a nitric 

acid and hydrogen peroxide solution. Both methods involve transferring the precipitate to a betacounting planchet, drying, and beta-counting. 

Changes in the process occurred in 1978, based on either a precipitation using a nitric acid 

phosphoric acid solution or a nitric acid and ruthenium carrier solution. Both methods indicate 

transferring the precipitate to a beta-counting planchet, drying, and beta-counting (Henley 1978). 

A.1.3 Fission Products

Fission product bioassays were observed in the dataset from as far back as 1951, but reports indicate 

that a procedure for strontium urine measurements was in place as early as 1949 (Tompkins, 

Farabee, and Khym 1949). A total of 17 fission product urine samples were in the dataset through 

1958. The ORAU Team found no official fission product procedure for this period, but it appears that 

a rare-earth and alkaline-earth procedure might have been used for fission products based on 

process knowledge of the target radionuclide; this procedure is discussed in the next section.

A.1.4 Rare Earth

Rare-earth elements include the 15 lanthanides as well as scandium and yttrium. The lanthanides 

include cerium, dysprosium, erbium, europium, gadolinium, holmium, lanthanum, lutetium, 

neodymium, praseodymium, promethium, samarium, terbium, thulium, and ytterbium. Rare-earth 

bioassays were observed in the dataset as far back as 1951, but reports indicate that a procedure for 

rare-earth urine measurements was in place as early as 1949. 
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The first basic procedure for rare- and alkaline-earth element urinalysis was issued in 1949 

(Tompkins, Farabee, and Khym 1949). The method describes a coprecipitation of the rare- and 

alkaline-earth elements with calcium phosphate from an alkaline solution, separation of the 

phosphoric acid from the cations by ion exchange, and finally a separation of barium, strontium, and 

rare-earth elements from calcium and magnesium by a chromate precipitation. The final precipitate 

was filtered on a medium porosity glass filter, dried, and counted in a standard beta/gamma counting 

chamber.

The ORAU Team observed changes in the process based on a procedure issued in 1968 (Henley 

1968). This method was based on a precipitation from an acid solution of ashed urine salts as the 

oxalate. The oxalate was oxidized using perchloric acid and sodium bromate. The precipitate was 

then transferred to a beta-counting planchet, dried, and beta-counted.

Rare-earth fecal (RF0) sampling was performed beginning as early as 1955. Seventy rare-earth fecal 

samples were in the dataset through 1972. No method could be identified. 

A.1.5 Transplutonium

Transplutonium urine bioassays were observed from as far back as 1958. The first procedure for 

transplutonium urinalysis was issued in 1968 (Henley 1968). The method was improved by

performing transplutonium separation using ion-exchange methods with neptunium elution using 

hydrochloric acid. The sample was then eluted, evaporated, and alpha-counted. 

Two methods were identified from 1978 based on (1) extraction chromatography, or (2) bismuth 

phosphate ion exchange (Henley 1978). Both methods involve transferring the precipitate to a 

stainless-steel counting disk, drying, and alpha-counting. 

The extraction chromatography method used an extraction column to extract the actinide and 

lanthanide elements. The basic phosphate precipitate was eluted with a nitric acid and aluminum 

phosphate solution and passed through an extraction column. The solution was then transferred to a 

watch glass, dried, and alpha-counted.

The bismuth phosphate method uses a basic phosphate precipitate or a hydrochloric acid effluent 

from an ion exchange column. After the plutonium, uranium, neptunium, and protactinium were 

removed from the basic phosphate precipitate by ion exchange, the column effluent would contain any 

trivalent actinides. A rare-earth carrier and hydrofluoric acid were added. The precipitate was then 

transferred to a stainless-steel disk, dried, and alpha-counted.

The fecal sample method identified from 1978 involved drying the fecal sample, treatment with an acid 

solution, separation using ion exchange resins, evaporation of the final product, and deposit of the 

sample for alpha-counting (Henley 1978).

A.2 ELEMENT-SPECIFIC ANALYSIS METHODS

A.2.1 Barium

One barium-specific bioassay was observed in the dataset in 1961, but reports indicate that a 

procedure for barium and the rare-earth elements was in place as early as 1949 (Tompkins, Farabee, 

and Khym 1949). The method involved a coprecipitation of the rare- and alkaline-earth elements with 

calcium phosphate from an alkaline solution, separation of the phosphoric acid from the cations by ion 
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exchange, and finally a separation of barium, strontium, and rare-earth elements from calcium and 

magnesium by a chromate precipitation. The final precipitate was filtered on a medium-porosity glass 

filter, dried, and counted in a standard beta/gamma counting chamber.

The ORAU Team observed that changes in the process occurred in 1955 based on ion exchange and 

the eluting of strontium and barium with nitric acid. The final precipitate was deposited to a counting 

dish, dried, and counted in a standard beta/gamma counting chamber. This method was used for 

both barium and strontium analysis (Farabee 1955; Brown, Davis, and Henley 1957). 

Process improvements occurred in 1968 and again in 1978 based on ion exchange and the eluting of 

strontium and barium with nitric acid. The final precipitate was deposited to a counting dish, dried, 

and counted in a standard beta/gamma counting chamber. It was noted that this method was used 

for both 89Sr and 90Sr in urine. Residue was deposited, dried, and beta-counted in a low-background 

counter. If the presence of radiobarium and radium was suspected, identification could be made by 

spectral analysis (Henley 1968, 1978).

A.2.2 Cesium

Cesium bioassays were observed in the dataset from as far back as 1955, and reports indicate that a 

procedure for cesium urine measurements was in place as early as 1956 (Morgan 1956). A total of 

1,873 cesium urine samples are in the dataset through 1988. In this method, cesium (along with 

potassium) was precipitated from a dilute acid solution as a cobalt nitrite. This precipitate was 

dissolved in nitric acid and a cesium phosphotungstate precipitation separated the cesium from 

potassium. The cesium was finally precipitated for counting. The precipitate was then transferred to 

a counting planchet, dried, and beta-counted.

A 1968 report describes a method in which cesium (along with potassium) was precipitated from a 

dilute acid solution (Henley 1968). A 1978 report describes a method in which cesium (along with 

potassium) was precipitated from a dilute acid solution as a cobalt nitrite (Henley 1978). The 1978 

method remained mostly the same as the 1968 method. 

A.2.3 Cobalt

Cobalt bioassays were observed in the dataset from as far back as 1954. The first basic procedure 

for cobalt urinalysis was issued in 1968 (Henley 1968). In concentrations of 6-molar HCl, cobalt ions 

formed a complex of sufficient strength to be absorbed by ion exchange resins. Then the cobalt was 

eluted with HCl, dried, and beta-counted. A 1978 report describes a cobalt urine method that was 

mostly the same as the 1968 method (Henley 1978).

A.2.4 Neptunium

Neptunium bioassays were observed from as far back as 1962. A total of 64 neptunium-specific urine 

samples were in the dataset through 1979, although neptunium might also have been measured using 

the gross alpha procedure. 

The first procedure for neptunium urinalysis was issued in 1968 (Henley 1968). The method was

improved by performing neptunium separation using ion exchange methods with neptunium elution 

using HCl. The sample was then eluted, evaporated, electrodeposited, and alpha-counted.
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The 1978 neptunium fecal method involved drying of the fecal sample, treatment with an acid solution, 

separation using ion exchange resins, evaporation of the final product, and electrodeposit of the 

sample for alpha-counting (Henley 1978).

Gross alpha fecal sampling was performed, possibly for neptunium, beginning as early as 1955. 

A.2.5 Plutonium 

The first procedure for plutonium urinalysis at ORNL was implemented in 1946. The method involved 

precipitating bismuth phosphate from urine, dissolving the precipitate, reprecipitating bismuth 

phosphate, oxidizing the organic matter, and finally precipitating LaF3. The sample was then 

deposited on a platinum disk, dried, and alpha-counted (Farabee 1946).

In 1947, the method improved but remained mostly the same as the 1946 method (Farabee 1947). 

In January 1957, a method was described that involved using a precipitation of calcium oxalate from 

urine, oxidation of the organic matter, and a final LaF3 precipitation (Brown, Davis, and Henley 1957). 

The sample was deposited on a platinum disk, dried, and alpha-counted.

In 1968, the method was improved by performing plutonium separation using ion exchange methods 

with plutonium elution using HCl (Henley 1968). The sample was then eluted, evaporated, and 

electrodeposited for counting. 

Plutonium-specific fecal sampling was performed beginning in 1968. The fecal sample method 

identified in 1978 involved drying the fecal sample, treatment with an acid solution, separation using 

ion exchange resins, evaporation of the final product, and electrodeposit of the sample for alphacounting (Henley 1978).

A.2.6 Plutonium-241

The first basic procedure for 241Pu urinalysis was issued in 1957 (Henley 1968). This method was 

based on urine samples that were treated with HCl. The plutonium, neptunium, uranium, 

protactinium, and transplutonium elements were adsorbed on an anion exchange resin column. The 

plutonium was eluted from the column with HCl and transferred to a glass cylinder. Toluene was 

added to the sample and then counted for low-energy beta using a liquid scintillation counter. 

Another report (Henley 1978) describes another method from 1978. This method was based on urine 

samples that were treated with HCl. The plutonium elements were adsorbed on an anion exchange 

resin column. The plutonium was eluted from the column with HCl and transferred to a glass cylinder. 

Toluene was added to the sample and the counted for low-energy beta using a liquid scintillation 

counter. The method remained mostly the same as the 1968 method.

A.2.7 Polonium

The first basic procedure for polonium urinalysis was issued in 1957 (Brown, Davis, and Henley 

1957). This method was based on urine samples treated with HCl and the polonium plated onto clean 

copper disks suspended in the solution for 2 hours. Deposition of the polonium was done by 

electrolysis. The alpha activity was determined by counting both sides of the disks. 
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Another report describes a method in which polonium was quantitatively deposited on a nickel disk 

from HCl (Henley 1968). The salt of the ashed urine sample was dissolved in a dichloric acid and a 

clean nickel disk was suspended in the solution for 2 hours. Deposition of the polonium was by 

electrolysis. The alpha activity was determined by counting both sides of the disks. 

Another report (Henley 1978) describes a method in which the polonium was quantitatively deposited 

on a nickel disk from HCl. The salt of the ashed urine sample was dissolved in a dichloric acid and a 

clean nickel disk was suspended in the solution for 2 hours. Deposition of the polonium was by 

electrolysis. The alpha activity was determined by counting both sides of the disks. The method 

remained mostly the same as the 1968 method. 

A.2.8 Protactinium

Protactinium bioassays were observed from as far back as 1962. From 1952 to 1975, 189 

protactinium urine samples were in the dataset. Note that protactinium might also have been 

measured using the gross alpha procedure. 

The initial method involved an extraction of niobium and protactinium from the raw urine using nitric 

and HCl solutions. A protactinium separation was performed using oxalic acid with the sample 

transferred to a stainless-steel planchet, dried, and beta-counted (Henley undated). 

Changes in the process occurred in 1968 (Henley 1968). The method was improved by performing 

protactinium separation using ion exchange methods with protactinium elution using HCl. The sample 

was then eluted, evaporated, and alpha-counted. 

Further changes in the process occurred in 1978 (Henley 1978). The method included an extraction 

of niobium and protactinium from the raw urine using nitric and hydrochloric acid solutions. A 

protactinium separation was performed using oxalic acid with the sample then transferred to a 

stainless-steel planchet, dried, and beta-counted. 

A.2.9 Radium 

Radium bioassays were observed in the dataset from as far back as 1954, but reports indicate that a 

procedure for radium urine measurements was in place as early as 1948 (Farabee 1948b). A total of 

330 radium-in-urine samples were in the dataset from 1954 to 1987. 

The first basic procedure for radium urinalysis was issued in 1948 (Farabee 1948b). The referenced 

method, CH-3534, could not be found, but a beta/gamma counting of the decay products in the urine 

was performed at approximately 12 days of ingrowth, at which time the percent of progeny in 

equilibrium with radium and radon was 88.5%. 

The first basic procedure for radium urinalysis found was issued in 1957. This method involved an 

extraction based on HCl and sulfuric acid solutions. The precipitate was then transferred to a 

lacquered platinum disk, dried, and counted. If the activity was found to be greater than 1 cpm, a 

count was performed at a 1- or 2-day interval to determine which isotope was present (Brown, Davis, 

and Henley 1957).
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SUMMARY OF IN VITRO BIOASSAY METHODS (continued)

A.2.10 Strontium

Strontium bioassays were observed in the dataset from as far back as 1951, but reports indicate that 

a procedure for strontium urine measurements was in place as early as 1949 (Tompkins, Farabee, 

and Khym 1949). 

A report from April 15, 1950, indicates that an analysis procedure for strontium was in use (Morgan 

1950). The report notes that the 1949 procedure was in use but recommended a change that would 

separate strontium from calcium and magnesium by a strontium nitrate precipitation using a nitric acid 

solution. The report noted that 18 samples had been assayed for strontium by using this procedure. 

Another report, from July 20, 1951, indicates that an analysis procedure for strontium was in use 

(Morgan 1951a). The report notes that the procedure was lengthy and included the elements of 

barium, strontium, yttrium, lanthanum, and other rare earths. 

Changes in the process occurred in 1955 based on ion exchange and the eluting of strontium and 

barium with nitric acid. The final precipitate was deposited to a counting dish, dried and counted in a 

standard beta/gamma counting chamber. This method was for both barium and strontium analysis 

(Farabee 1955; Brown, Davis, and Henley 1957). 

Improvements in the process occurred in 1968 based on ion exchange and the eluting of strontium 

and barium with nitric acid. The final precipitate was deposited to a counting dish, dried, and counted 

in a standard beta/gamma counting chamber. It was noted that this method was for both 89Sr and 90Sr 

in urine. Residue was deposited, dried, and beta-counted in a low-background counter. If the 

presence of radiobarium and radium was suspected, identification could be made by spectral analysis 

(Henley 1968).

Fecal bioassays specific to 90Sr were observed in the dataset from 1960. The fecal sample method 

identified in 1978 involved drying of the fecal sample, treatment with an acid solution, separation using 

ion exchange resins, evaporation of the final product, and deposition of the sample for beta-counting 

(Henley 1978).

A.2.11 Thorium 

No thorium-specific fecal sampling was identified. However, gross alpha fecal sampling could have 

been performed for thorium beginning as early as 1955. 

One thorium fecal sample method was identified in 1978 (Henley 1978). It involved drying of the fecal 

sample, treatment with an acid solution, separation using ion exchange resins, evaporation of the final 

product, and electrodeposition of the sample for alpha-counting.

A.2.12 Tritium

Tritium urine bioassays were observed as far back as 1953. No early tritium method was identified, 

but it is thought that a procedure was used that was based on an Argonne National Laboratory 

method extant around 1950 (Western 1950). 

The first procedure for tritium urinalysis was issued in 1968 (Henley 1968). In this method, tritium 

samples were counted by liquid scintillation. Urine samples were analyzed by either distilling the 
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SUMMARY OF IN VITRO BIOASSAY METHODS (continued)

sample and counting a portion of the distillate for tritium beta, or by adding the raw urine directly to the 

scintillation mix.

Another method for tritium urinalysis was issued in 1978 (Henley 1978). The method remained mostly 

the same as the 1968 method. 

A.2.13 Uranium

Uranium bioassays were observed from as far back as 1949. A total of 15,100 uranium urine samples 

were in the dataset from 1949 through 1988. Only basic information is available for the methods used 

from 1947 to 1949. In 1949, a procedure was developed that describes the separation and elution for 

uranium (Morgan 1949). The sample was transferred to a platinum plate, evaporated, and counted on 

a standard alpha counter. The overall recovery of 80% to 85% was typical for 233U. In 1951, 

improvements were be developed to minimize the time necessary to complete the procedure (Morgan 

1951b). 

In January 1957, a method using tributyl phosphate in hexane was in use (Brown, Davis, and Henley 

1957). In this method, the uranium was separated, transferred to a stainless-steel disk, dried, and 

alpha-counted. 

In 1968, the method was improved by performing uranium separation using ion exchange methods 

with uranium elution using HCl (Henley 1968). The sample was then eluted, evaporated, and 

electrodeposited for counting. 

Gross alpha fecal sampling was performed for uranium beginning as early as 1955. The fecal sample 

method (from 1978) involved drying the fecal sample, treatment with an acid solution, separation 

using ion exchange resins, evaporation of the final product, and electrodeposition of the sample for 

alpha-counting (Henley 1978).
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ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS

The following 179 radionuclides required no further analysis to determine there is no infeasibility in 

respect to ORNL’s monitoring capabilities. Nuclear decay information was generally obtained from 

the Radiological Toolbox. When data were not available in the radiological toolbox, data were

obtained from the NuDat 2.7 dataset at the National Nuclear Data Center (NNDC 2018). 

Americium-241

• Production years: 1959–1988

• Half-life: 432 yr

• Decay mode: α

• Progeny: Np-237

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 5,440 13.0%

alpha 5,490 84.7%

gamma 59.5 35.9%

• Bioassay method: transplutonium (TP0) in urine, GF0 (gross alpha fecal)

Americium-243

• Production years: 1961–1978, 1980–1986,1988 

• Half-life: 7,370 yr

• Decay mode: α

• Progeny: Np-239

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 5,230 11.0%

alpha 5,280 87.6%

gamma 74.7 68.2%

• Bioassay method: transplutonium (TP0) in urine and GF0 (gross alpha fecal)

Antimony-122

• Production years: 1956, 1959–1968, 1971, 1987

• Half-life: 2.7 d

• Decay mode: EC, β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 521 67.2%

beta 771 25.7%

gamma 564 70.7%

• Bioassay method: gross beta (013) then whole-body counting

Antimony-124

• Production years: 1955–1957, 1959–1967

• Half-life: 60.2 d
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ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 194 52.2%

beta 918 22.4%

gamma 603 98.3%

gamma 723 10.8%

gamma 1,690 47.8%

• Bioassay method: gross beta (013) then whole-body counting

Antimony-125

• Production years: 1955–1957, 1959–1966

• Half-life: 2.7 yr

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 24.9 13.4%

beta 34.7 17.9%

beta 86.9 40.4%

beta 215 13.6%

X-ray 27.5 26.6%

gamma 428 29.8%

gamma 463 10.6%

gamma 601 17.8%

gamma 636 11.3%

• Bioassay method: gross beta (013) then whole-body counting; Sb-125 specific method (015) 

used in 1962 and 1963. Radiation from daughter Te-125m.

Argon-37

• Production years: 1955–1957, 1959–1971, 1973–1982

• Half-life: 35.04 d

• Decay mode: EC 

• Progeny: stable

• Important energy emissions: NA

• Bioassay method: NA-noble gas: external monitoring is controlling for these materials

Arsenic-71

• Production years: 1960 

• Half-life: 65.3 hr

• Decay mode: EC, β+ 

• Progeny: stable

• Important energy emissions:
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ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

Emission type Energy (keV) Abundance

positron 352 28.0%

gamma 175 82.0%

gamma 511 56.7%

• Bioassay method: gross beta (013) 

Arsenic-72

• Production years: 1960 

• Half-life: 26 hr

• Decay mode: EC, β+ 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

positron 1,120 64.2%

positron 1,530 16.3%

gamma 511 176.0%

gamma 834 79.5%

• Bioassay method: gross beta (013)

Arsenic-74

• Production years: 1957–1959, 1961, 1965

• Half-life: 17.77 d

• Decay mode: EC, β+, β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 243 15.4%

positron 408 26.0%

beta 531 18.6%

gamma 511 58.1%

gamma 596 59.4%

gamma 635 15.4%

• Bioassay method: gross beta (013) then whole-body counting

Arsenic-76

• Production years: 1956–1957, 1959–1967

• Half-life: 25.9 hr

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 993 35.3%

beta 1,260 51.1%

gamma 559 45.0%
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ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Bioassay method: Gross beta (013) then whole-body counting

Arsenic-77

• Production years: 1956–1957, 1959–1966

• Half-life: 38.8 hr

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 229 97%

• Bioassay method: gross beta (013 and GB0)

Barium-131

• Production years: 1955–1957, 1959–1971

• Half-life: 11.5 d

• Decay mode: EC

• Progeny: Cs-131

• Important energy emissions:

Emission type Energy (keV) Abundance

A.E. 3.45 79.1%

A.E. 4.17 24.4%

I.C. 87.8 17.9%

gamma 216 19.7%

gamma 373 14.0%

gamma 496 46.8%

• Bioassay method: strontium (SR0)

Barium-135m

• Production years: 1970, 1986 

• Half-life: 28.7 hr

• Decay mode: IT

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

I.C. 231 59.9%

I.C. 262 11.3%

X-ray 31.8 15.5%

X-ray 32.2 28.9%

gamma 268 15.6%

• Bioassay method: in vivo counting

Barium-140

• Production years: 1955–1957, 1959–1968, 1970–1978, 1980–1981, 1983

• Half-life: 12.75 d
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ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Decay mode: β- 

• Progeny: La-140

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 141 23.9%

beta 344 38.2%

beta 362 24.1%

I.C. 23.7 56.0%

I.C. 28.8 12.9%

gamma 30 14.1%

gamma 537 24.4%

• Bioassay method: strontium (SR0); Ba-140 specific method (014) used one time in 1961

Berkelium-249

• Production years: 1964, 1967, 1969–1984, 1986, 1988 

• Half-life: 330 d

• Decay mode: SF, β-, α

• Progeny: Am-245

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 32.4 100%

• Bioassay method: transplutonium (TPO)

Bismuth-207

• Production years: 1957

• Half-life: 32.9 yr

• Decay mode: EC, β+

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

A.E. 10.4 16.1%

X-ray 73 21.8%

X-ray 75.3 36.6%

gamma 570 97.8%

gamma 1,060 74.6%

• Bioassay method: gross beta (013)

Bismuth-210

• Production years: 1955–1957, 1959–1970 

• Half-life: 5.01 d

• Decay mode: β- 

• Progeny: Po-210

• Important energy emissions:
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ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

Emission type Energy (keV) Abundance

beta 389 100%

• Bioassay method: gross beta (013 and GB0) 

Bromine-82

• Production years: 1956–1967

• Half-life: 35.3 hr

• Decay mode: β- 

• Progeny: stable

• Important energy emissions: 

Emission type Energy (keV) Abundance

beta 138 97.0%

gamma 554 70.8%

gamma 619 43.4%

gamma 698 28.5%

gamma 777 83.5%

gamma 828 24.0%

gamma 1,040 27.2%

gamma 1,320 26.5%

gamma 1,470 16.3%

• Bioassay method: gross beta (013), Br-82/Br-83 (008) then whole-body counting; Br-82 

specific method used in 1960 and 1961 

Bromine-85

• Production year: 1963

• Half-life: 2.9 min

• Decay mode: β- 

• Progeny: Kr-85m

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 1,070 95.7%

• Bioassay method: gross beta

Cadmium-115

• Production years: 1955–1956, 1960, 1962–1966 

• Half-life: 53.46 hr

• Decay mode: β- 

• Progeny: In-115m

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 184 33.0%

beta 394 62.5%

gamma 528 27.5%
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ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Bioassay method: gross beta (013 and GB0). Radiation from daughter In-115m.

Cadmium-115m

• Production years: 1955–1956, 1960–1966 

• Half-life: 44.6 d

• Decay mode: β- 

• Progeny: In-115

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 618 97%

gamma 934 2%

• Bioassay method: gross beta (013 and GB0). Radiation from daughter In-115m.

Calcium-45

• Production years: 1955–1966 

• Half-life: 162.7 d

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 77.2 100%

• Bioassay method: gross beta (013 and GB0).

Calcium-47

• Production years: 1960–1984 

• Half-life: 4.54 d

• Decay mode: β- 

• Progeny: Sc-47

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 243 80.9%

beta 819 19.0%

gamma 1,300 74.6%

• Bioassay method: gross beta (013) then whole-body counting. .Radiation from daughter 

Sc-47. 

Californium-248

• Production years: 1972 

• Half-life: 334 d 

• Decay mode: SF, α

• Progeny: Cm-244

• Important energy emissions:
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ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

Emission type Energy (keV) Abundance

alpha 6,220 19.6%

alpha 6,260 80.0%

• Bioassay method: transplutonium (TP0)

Californium-249

• Production years: 1968–1976, 1979–1982, 1984, 1986 

• Half-life: 351 yr

• Decay mode: SF, α

• Progeny: Cm-245

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 5,810 82.4%

I.C. 31.0 13.6%

I.C. 35.8 10.5%

gamma 333 14.6%

gamma 388 66.0%

• Bioassay method: transplutonium (TP0)

Californium-250

• Production years: 1970, 1973–1976, 1980 

• Half-life: 13.08 yr

• Decay mode: SF, α

• Progeny: Cm-246

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 5,990 15.0%

alpha 6,030 84.6%

• Bioassay method: transplutonium (TP0)

Californium-252

• Production years: 1962, 1967–1991 

• Half-life: 2.638 yr 

• Decay mode: SF, α

• Progeny: Cm-248

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 6,080 15.2%

alpha 6,120 81.5%

beta 1,280 19.2%

• Bioassay method: transplutonium (TP0), Cf-252 specific method 1989–1992
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ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

Californium-253

• Production years: 1984 

• Half-life: 17.81 d

• Decay mode: β-, α

• Progeny: Cm-249, Es-253

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 65.5 49.8%

beta 79.1 49.8%

A.E. 12.3 10.2%

I.C. 19.6 32.9%

• Bioassay method: transplutonium (TP0)

Carbon-11

• Production years: 1975, 1977, 1979–1980 

• Half-life: 20.39 min

• Decay mode: EC, β+

• Progeny: stable

• Important energy emissions: 

Emission type Energy (keV) Abundance

positron 386 99.8%

gamma 511 200%

• Bioassay method: whole-body counting 

Carbon-14

• Production years: 1945–1975, 1980–1983, 1985 

• Half-life: 5,700 yr

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 49.5 100%

• Bioassay method: gross beta (013 and GB0); C-14 specific methods 1986–1992

Cerium-141

• Production years: 1955–1957, 1959–1966, 1970

• Half-life: 32.5 d

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:
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ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

Emission type Energy (keV) Abundance

beta 130 69.7%

beta 181 30.3%

I.C. 103 18.9%

gamma 145 48.3%

• Bioassay method: rare earths (FU0)

Cerium-144

• Production years: 1955–1979, 1981–1988

• Half-life: 284.9 d

• Decay mode: β- 

• Progeny: Pr-144m, Pr-144

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 50.3 19.6%

beta 91.3 76.6%

gamma 134 11.1%

• Bioassay method: rare earths (FU0), whole-body counting, Ce-144 specific method; 

Cesium-132

• Production years: 1962

• Half-life: 6.5 d

• Decay mode: EC 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

Gamma 668 97.5

• Bioassay method: nuclide specific method (012), whole-body counting

Cesium-134

• Production years: 1955–1957, 1959–1966

• Half-life: 2.06 yr

• Decay mode: EC, β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 23.1 27.3%

beta 210 70.2%

gamma 569 15.4%

gamma 605 97.6%

gamma 796 85.5%

• Bioassay method: gross beta (013) then whole-body counting
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ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

Cesium-137

• Production years: 1955–1988

• Half-life: 30.16 yr

• Decay mode: β- 

• Progeny: Ba-137m

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 174 94.4%

gammaa 662 100.0%

a. See Comments below.

• Bioassay method: Cs-137 specific method (CS7) then whole-body counting

• Comments: 662 keV gamma is from daughter Ba-137m; 

Chlorine-36

• Production years: 1955–1972 

• Half-life: 3.01E5 yr

• Decay mode: EC, β+, β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 278 98.1%

• Bioassay method: gross beta (013 and GB0)

Chlorine-38

• Production years: 1947

• Half-life: 37.2 min

• Decay mode: β- 

• Progeny: stable

• Important energy emissions: 

Emission type Energy (keV) Abundance

beta 420 31.9%

beta 1,180 10.5%

beta 2,240 57.6%

gamma 1,640 31.9%

gamma 2,170 42.4%

• Bioassay method: gross beta (013); only production year in pre-existing SEC

Cobalt-56

• Production years: 1967, 1972 and 1976

• Half-life: 77.2 d

• Decay mode: EC, β+

• Progeny: stable

• Important energy emissions:
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ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

Emission type Energy (keV) Abundance

positron 631 18.1%

gamma 511 38.0%

gamma 847 99.9%

gamma 1,240 66.9%

gamma 1,770 15.5%

gamma 2,600 17.3%

• Bioassay method: whole-body counting

Cobalt-58

• Production years: 1955–1957, 1959–1965

• Half-life: 70.86 d

• Decay mode: EC, β+

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

positron 201 14.9%

gamma 511 29.8%

gamma 811 99.5%

• Bioassay method: gross beta (013) then whole-body counting

Cobalt-60

• Production years: 1955–1988

• Half-life: 5.27 yr

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 95.9 99.9%

gamma 1,170 99.9%

gamma 1,330 100.0%

• Bioassay method: gross beta (013) then whole-body counting; Co-60-specific method used in 

1962–1964

Copper-64

• Production years: 1955–1969, 1976

• Half-life: 12.7 hr

• Decay mode: EC, β+, β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 190 39.0%

positron 278 17.4%

gamma 511 34.8%
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ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Bioassay method: gross beta (013 and GB0)

Copper-67 

• Production years: 1963–1964, 1967–1968, 1970–1971, 1973–1976

• Half-life: 61.83 hr

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 116 56.9%

beta 149 22.0%

beta 184 20.0%

I.C. 83.7 12.1%

gamma 93.3 16.1%

gamma 185 48.7%

• Bioassay method: whole-body counting

Curium-242

• Production years: 1961–1966, 1968, 1986 

• Half-life: 162.8 d

• Decay mode: SF, α

• Progeny: Pu-238

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 6,070 25.9%

alpha 6,110 74.1%

• Bioassay method: transplutonium (TP0)

Curium-243

• Production years: 1965, 1972–1973, 1975–1976, 1981–1983 

• Half-life: 29.1 yr

• Decay mode: α, EC

• Progeny: Pu-239, Am-243

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 5,740 11.5%

alpha 5,790 72.6%

A.E. 10.7 28.2%

A.E. 14.2 14.6%

I.C. 106 23.3%

I.C. 155 17.5%

X-ray 18.4 13.8%

X-ray 100 14.7%

X-ray 104 23.3%
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ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

Emission type Energy (keV) Abundance

gamma 228 10.6%

gamma 278 14.0%

• Bioassay method: transplutonium (TP0)

Curium-244

• Production years: 1962–1964, 1966–1988 

• Half-life: 18.1 yr

• Decay mode: SF, α

• Progeny: Pu-240

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 5,760 23.6%

alpha 5,800 76.4%

• Bioassay method: transplutonium (TP0); Cm-242/244 specific method (CM0) used in 1986–

1988

Curium-245

• Production years: 1969, 1972–1973, 1986 

• Half-life: 8,500 yr

• Decay mode: α

• Progeny: Pu-241

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 5,362 92.9%

I.C. 52.6 44.6%

X-ray 18.4 11.1%

X-ray 100 21.6%

X-ray 104 34.2%

• Bioassay method: transplutonium (TP0)

Curium-246

• Production years: 1970–1971, 1973, 1977, 1988 

• Half-life: 4,760 yr

• Decay mode: SF, α

• Progeny: Pu-242

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 5,340 17.8%

alpha 5,390 82.2%

• Bioassay method: transplutonium (TP0)
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ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

Curium-247

• Production years: 1969, 1972 

• Half-life: 1.56E+07 yr

• Decay mode: α

• Progeny: Pu-243

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 4,870 71.0%

alpha 5,270 13.8%

gamma 402 72.0%

• Bioassay method: transplutonium (TP0)

Curium-248

• Production years: 1968–1980, 1982–1984, 1986, 1988 

• Half-life: 3.48E+05 yr

• Decay mode: SF, α

• Progeny: Pu-244

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 5,030 16.5%

alpha 5,080 75.0%

beta 1,370 55.9%

gamma 1,100 12.2%

• Bioassay method: transplutonium (TP0)

Dysprosium-157

• Production years: 1975 

• Half-life: 8.1 hr

• Decay mode: EC

• Progeny: Tb-157

• Important energy emissions:

Emission type Energy (keV) Abundance

X-ray 43.8 24.2%

X-ray 44.6 43.3%

gamma 326 92.0%

• Bioassay method: rare earth (FU0)

Dysprosium-166 

• Production years: 1965, 1984 

• Half-life: 81.6 hr

• Decay mode: β- 

• Progeny: Ho-166

• Important energy emissions:
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ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

Emission type Energy (keV) Abundance

beta 118 89.1%

I.C. 18.9 14.1%

I.C. 26.8 54.6%

I.C. 46.2 10.6%

X-ray 46.8 14.8%

X-ray 47.6 26.3%

gamma 82.5 13.8%

• Bioassay method: rare earth (FU0)

Einsteinium-252

• Production years: 1970 

• Half-life: 471.7 d

• Decay mode: α, EC

• Progeny: Bk-248

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 6,562 10.6%

alpha 6,632 62.6%

A.E. 11.2 15.2%

X-ray 15.7 18.8%

gamma 139 11.7%

gamma 785 15.4%

• Bioassay method: gross alpha

Einsteinium-253

• Production years: 1967–1981, 1984, 1986, 1988 

• Half-life: 20.47 d

• Decay mode: SF, α

• Progeny: Bk-249

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 6,630 89.8%

• Bioassay method: transplutonium (TP0)

Einsteinium-254

• Production years: 1972–1974, 1980, 1982, 1984, 1988 

• Half-life: 275.7 d

• Decay mode: α

• Progeny: Bk-250

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 6,430 93.4%

A.E. 11.5 43.9%
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ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

Emission type Energy (keV) Abundance

A.E. 15.4 23.4%

I.C. 10.2 31.7%

I.C. 16.0 16.2%

I.C. 17.3 66.3%

I.C. 30.5 14.9%

I.C. 37.6 18.2%

X-ray 15.3 32.1%

• Bioassay method: transplutonium (TP0)

Erbium-171

• Production years: 1973

• Half-life: 7.52 hr

• Decay mode: β- 

• Progeny: Tm-171

• Important energy emissions: 

Emission type Energy (keV) Abundance

beta 362 94.3%

I.C. 52.1 39.5%

gamma 112 20.5%

gamma 296 28.9%

gamma 308 64.4%

• Bioassay method: gross beta (Sr-90) (GB0) as production in years of pre-existing SEC

Europium-152

• Production years: 1962, 1968, 1974–1975, 1978–1981, 1984–1985, 1988

• Half-life: 13.53 yr

• Decay mode: β-, EC, β+

• Progeny: Au-152

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 222 13.8%

I.C. 74.9 19.4%

X-ray 40.2 38.3%

gamma 122 28.7%

gamma 344 26.6%

gamma 779 13.0%

gamma 964 14.6%

gamma 1,090 10.2%

gamma 1,110 13.7%

gamma 1,410 21.1%

• Bioassay method: whole-body counting

Europium-155

• Production years: 1955–1957, 1959–1968, 1975
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ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Half-life: 4.76 yr

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 39.2 46.7%

beta 44.6 24.8%

beta 70.2 17.5%

I.C. 36.2 11.1%

X-ray 43.1 11.8%

gamma 86.5 30.7%

gamma 105 21.2%

• Bioassay method: whole-body counting

Fermium-255

• Production years: 1984, 1988 

• Half-life: 20.07 hr

• Decay mode: α

• Progeny: Cf-251

• Important energy emissions: 

Emission type Energy (keV) Abundance

alpha 7,020 92.5%

A.E. 11.4 36.2%

A.E. 15.4 19.4%

I.C. 17.9 16.0%

I.C. 19.7 31.2%

I.C. 24.8 11.6%

I.C. 32.4 20.4%

I.C. 56.2 20.1%

I.C. 61.5 13.5%

X-ray 15.7 30.1%

X-ray 20.7 15.2%

• Bioassay method: transplutonium (TP0) 

Fermium-257

• Production years: 1968–1977, 1980, 1984, 1986, 1988 

• Half-life: 100.5 d

• Decay mode: α

• Progeny: Cf-253

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 6,520 92.4%

A.E. 11.8 34.5%

A.E. 15.8 18.5%

I.C. 35.6 34.9%
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ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

Emission type Energy (keV) Abundance

I.C. 36.4 12.8%

I.C. 43.8 40.8%

I.C. 56.5 14.0%

I.C. 105 14.7%

X-ray 15.7 25.6%

X-ray 20.7 14.9%

X-ray 110 16.4%

X-ray 116 25.3%

gamma 241 11.0%

• Bioassay method: transplutonium (TP0)

Gadolinium-148

• Production years: 1970 

• Half-life: 74.6 yr

• Decay mode: α

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 3,180 100%

• Bioassay method: gross alpha (GA0)

Gadolinium-153

• Production years: 1971, 1973–1988

• Half-life: 240.4 d

• Decay mode: EC

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

I.C. 21.1 11.0%

I.C. 54.6 30.8%

X-ray 40.9 35.0%

X-ray 41.6 63.1%

X-ray 47.1 12.3%

gamma 97.4 29.0%

gamma 103 21.1%

• Bioassay method: rare earth (FU0) then whole-body counting

Gallium-68

• Production years: 1971

• Half-life: 67.71 min

• Decay mode: EC, β+

• Progeny: stable

• Important energy emissions:
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ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

Emission type Energy (keV) Abundance

positron 836 87.7%

gamma 511 178.0%

• Bioassay method: whole-body counting 

Gallium-72

• Production years: 1955, 1957, 1960–1970

• Half-life: 14.1 hr

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 22.1 15.0%

beta 22.7 21.7%

beta 346 27.6%

beta 1,360 10.3%

gamma 630 24.8%

gamma 834 95.6%

gamma 2,200 25.9%

gamma 2,510 12.8%

• Bioassay method: gross beta (013 and GB0)

Gold-198

• Production years: 1955, 1957–1966

• Half-life: 2.7 d

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 314 99.0%

gamma 412 95.6%

• Bioassay method: gross beta (013 and GB0)

Gold-199

• Production years: 1955, 1957, 1959–1967

• Half-life: 3.14 d

• Decay mode: β−

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 67.2 21.5%

beta 82.3 72.0%

I.C. 144 10.1%

gamma 158 40.0%
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ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Bioassay method: gross beta (013) then whole-body counting

Hafnium-181

• Production years: most years between 1955, 1957, 1959–1977, 1979–1980

• Half-life: 42.4 d

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 121 92.5%

I.C. 65.5 21.2%

I.C. 122 12.7%

I.C. 123 10.5%

X-ray 57.7 16.0%

gamma 133 43.3%

gamma 346 15.1%

gamma 482 80.5%

• Bioassay method: gross beta (013 and GB0) then whole-body counting 

Holmium-156

• Production years: 1965 

• Half-life: 56 min

• Decay mode: EC, β+

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

I.C. 83.9 24.1%

gamma 138 51.1%

gamma 266 64.9%

gamma 366 14.3%

gamma 511 86.3%

• Bioassay method: rare earth (FU0)

Holmium-166

• Production years: 1958 

• Half-life: 26.83 hr

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 651 48.7%

beta 694 50.0%

I.C. 23.0 11.0%

I.C. 71.3 12.7%

I.C. 72.2 13.1%
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ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Bioassay method: 013 gross beta

Hydrogen-3 

• Production years: 1955–1957, 1959–1988 

• Half-life: 12.35 yr

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 5.7 100%

• Bioassay method: HY3

Indium-111

• Production years: 1969–1971, 1973

• Half-life: 2.83 d

• Decay mode: EC

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

A.E. 19.3 10.6%

X-ray 23.0 24.0%

X-ray 23.2 45.0%

gamma 171 90.7%

gamma 24.5 94.1%

• Bioassay method: whole-body counting

Indium-114

• Production years: 1955–1957, 1959–1977, 1981

• Half Life: 71.9 s

• Decay mode: β-, EC, β+

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 779 99.4%

• Bioassay method: gross beta (013)

Indium-114m

• Production years: 1975 

• Half-life: 49.51 d

• Decay mode: EC, IT

• Progeny: In-114

• Important energy emissions: 
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ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

Emission type Energy (keV) Abundance

I.C. 162 39.8%

I.C. 186 16.0%

I.C. 187 12.8%

X-ray 24.2 18.3%

gamma 190 15.56%

• Bioassay method: whole-body counter

Iodine-123

• Production years: 1965; 1967–1970 

• Half-life: 13.3 hr

• Decay mode: EC

• Progeny: Te-123m, Te-123

• Important energy emissions: 

Emission type Energy (keV) Abundance

I.C. 12.7 13.7%

X-ray 27.2 25.0%

X-ray 27.5 46.5%

gamma 159 83.3%

• Bioassay method: thyroid count

Iodine-132

• Production years: 1967–1972

• Half-life: 2.3 hr

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 242 12.9%

beta 422 18.7%

beta 608 12.5%

beta 841 18.9%

gamma 523 16.0%

gamma 630 13.3%

gamma 668 98.7%

gamma 773 75.6%

gamma 955 17.6%

• Bioassay method: thyroid count

Iridium-192

• Production years: 1955–1968,1970–1971,1973–1988

• Half-life: 73.8 d

• Decay mode: β-, EC

• Progeny: stable

• Important energy emissions:
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ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

Emission type Energy (keV) Abundance

beta 162 41.4%

beta 210 48.0%

gamma 296 28.7%

gamma 308 29.7%

gamma 317 82.7%

gamma 468 47.8%

• Bioassay method: gross beta (013) then whole-body counting

Iridium-194

• Production years: 1959, 1961, 1963, 1968

• Half-life: 19.3 hr

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 846 85.4%

gamma 328 13.1%

• Bioassay method: gross beta (013) then whole-body counting

Iron-59

• Production years: 1955–1956, 1958–1967

• Half-life: 44.5 d

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 81 45.3%

beta 149 53.1%

gamma 1,100 56.5%

gamma 1,290 43.2%

• Bioassay method: gross beta (013 and GB0) then whole-body counting; Fe-59 specific method 

(009) used between 1960 and 1964

Krypton-85 

• Production years: 1955–1988

• Half-life: 10.76 yr

• Decay mode: β- 

• Progeny: stable

• Important energy emissions: NA

Emission type Energy (keV) Abundance

beta 252 99.6%

gamma 514 0.4%
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ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Bioassay method: NA-noble gas: external monitoring is controlling for these materials

Lanthanum-140

• Production years: 1955–1957, 1959–1966, 1987

• Half-life: 1.68 d

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 442 11.2%

beta 488 45.2%

beta 630 19.7%

gamma 329 20.3%

gamma 487 45.5%

gamma 816 23.3%

gamma 1,600 95.4%

• Bioassay method: rare earth (FU0) and whole-body counting

Lead-203

• Production years: 1972–1973

• Half-life: 51.9 hr

• Decay mode: EC

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

A.E. 10.1 17.6%

I.C. 193 13.6%

X-ray 71.1 25.8%

X-ray 73.1 43.5%

gamma 279 80.8%

• Bioassay method: whole-body counting

Magnesium-28

• Production years: 1966, 1969–1970, 1977, 1983–1984, 1987–1988 

• Half-life: 20.91 hr

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 156 94.7%

I.C. 29.1 27.7%

gamma 401 36.6%

gamma 941 38.3%

gamma 1,340 52.6%
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ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Bioassay method: whole-body counting

Manganese-52

• Production years: 1960

• Half-life: 5.59 d

• Decay mode: EC, β+

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 242 29.7%

gamma 511 59.3%

gamma 744 90.0%

gamma 936 94.5%

gamma 1,430 100.0%

• Bioassay method: gross beta (013)

Mercury-203

• Production years: 1955–1957, 1959–1967

• Half-life: 46.6 d

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 57.8 100.0%

I.C. 193 13.8%

gamma 279 81.5%

• Bioassay method: gross beta (013) then whole-body counting

Molybdenum-99

• Production years: 1957, 1959–1971

• Half-life: 65.9 hr

• Decay mode: β- 

• Progeny: Tc-99m, Tc-99

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 133 16.4%

beta 443 82.2%

gamma 740 12.13%

• Bioassay method: gross beta (013) then whole-body counting

Neodymium-140

• Production years: 1969 

• Half-life: 3.37 d

• Decay mode: EC
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ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Progeny: Pr-140

• Important energy emissions: emissions listed include Pr-140 progeny.

Emission type Energy (keV) Abundance

X-ray 35.6 21.7%

X-ray 36.1 39.7%

Positron 1,070 51.0%

• Bioassay method: gross beta 

Neodymium-147

• Production years: 1955–1957,1959–1973, 1979 

• Half-life: 10.98 d

• Decay mode: β- 

• Progeny: Pm-147

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 106 15.3%

beta 264 80.9%

I.C. 45.9 49.2%

X-ray 38.2 13.3%

X-ray 38.8 24.1%

gamma 91.1 27.9%

gamma 531 13.1%

• Bioassay method: rare earth (FU0)

Neodymium-149

• Production years: 1979

• Half-life: 1.73 hr

• Decay mode: β- 

• Progeny: Pm-149

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 355 18.6%

beta 403 21.0%

beta 515 17.1%

beta 541 24.1%

I.C. 69.1 17.6%

X-ray 38.8 16.9%

gamma 114 19.2%

gamma 211 25.9%

gamma 270 10.7%

• Bioassay method: rare earth (FU0)

Neptunium-236

• Production years: 1965
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ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Half-life: 154,000 yr

• Decay mode: EC, β- 

• Progeny: Pu-236, U-236

• Important energy emissions: annihilation photons

Emission type Energy (keV) Abundance

beta 46.4 12.0%

A.E. 103 71.7%

A.E. 13.6 36.5%

I.C. 83.2 34.4%

I.C. 139 22.0%

X-ray 13.6 42.7%

X-ray 17.3 40.8%

X-ray 95.1 20.2%

X-ray 98.9 32.3%

gamma 160 31.5%

• Bioassay method: whole-body counting

Neptunium-237 

• Production years: 1955–1957,1959,1961–1962,1964–1965,1967–1968,1970,1972–1987 

• Half-life: 2.144 E6 yr

• Decay mode: α

• Progeny: Pa-233

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 4,770 25.7%

alpha 4,790 48.3%

I.C. 36.7 27.3%

I.C. 40.4 22.9%

I.C. 52.9 14.1%

gamma 29.4 15.0%

gamma 86.5 12.4%

• Bioassay method: gross alpha (GU0) and neptunium (NP0), Np-237 (017)

Neptunium-238

• Production years: 1966

• Half-life: 2.117 d

• Decay mode: β- 

• Progeny: Pu-238

• Important energy emissions: annihilation photons

Emission type Energy (keV) Abundance

beta 72.2 44.8%

beta 412 41.0%

I.C. 21.7 30.9%

I.C. 26.0 26.5%

I.C. 39.5 16.3%
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ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

Emission type Energy (keV) Abundance

gamma 984 25.2%

gamma 1,030 18.3%

• Bioassay method: gross beta (013 and GB0)

Nickel-63 

• Production years: most years 1955–1957, 1959–1972, 1978, 1980, 1985–1987 

• Half-life: 100.1 yr

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 17.4 100%

• Bioassay method: gross beta (013 and GB0) 

Nickel-66

• Production years: 1968

• Half-life: 54.6 hr

• Decay mode: β- 

• Progeny: Cu-66

• Progeny: stable

• Important energy emissions: 

Emission type Energy (keV) Abundance

beta 73.4 100%

• Bioassay method: gross beta (GB0)

Niobium-90

• Production years: 1957 

• Half-life: 14.6 hr

• Decay mode: EC, β+

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 662 53.7%

I.C. 123 18.0%

gamma 511 107.0%

gamma 1,130 92.7%

gamma 2,320 82.0%

• Bioassay method: gross beta (013) 

Niobium-92

• Production years: 1963 

• Half-life: 3.47 E+7 yr
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ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Decay mode: EC

• Progeny: stable

• Important energy emissions: annihilation photons

Emission type Energy (keV) Abundance

A.G. 13.3 16.4%

gamma 561 100.0%

gamma 935 100.0%

• Bioassay method: whole-body counting

Niobium-92m

• Production years: 1967

• Half-life: 10.15 d

• Decay mode: EC, β+

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

A.E 13.3 17.1%

gamma 934 99.1%

• Bioassay method: whole-body counting

Niobium-95

• Production years: 1955–1957,1959–1981,1983–1985

• Half-life: 35 d

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 43.4 100.0%

gamma 766 99.8%

• Bioassay method: gross beta (013), Nb-95 specific method (005 – Zn/Nb95), whole-body 

counting

Osmium-191

• Production years: 1957, 1959–1970, 1984

• Half-life: 15.4 d

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 37.8 100.0%

I.C. 53.1 65.3%

X-ray 63.5 18.2%
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ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

Emission type Energy (keV) Abundance

X-ray 65.1 31.3%

gamma 129.42 29.0%

• Bioassay method: gross beta (013) and whole-body counting

Palladium-109

• Production years: 1957, 1959–1971

• Half-life: 13.7 hr

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 361 99.9%

I.C. 62.6 41.1%

I.C. 84.5 19.3%

I.C. 84.7 22.4%

X-ray 22.1 18.6%

• Bioassay method: gross beta (013 and GB0)

Phosphorus-32

• Production years: 1955–1967 

• Half-life: 14.26 d

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 695 100%

• Bioassay method: P-32 specific method (PH2)

Phosphorus-33 

• Production years: 1964–1965, 1967–1987

• Half-life: 25.3 d 

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 76.4 100

• Bioassay method: gross beta (013 and GB0);

Platinum-195m 

• Production years: 1972–1974, 1978 

• Half-life: 4.02 d

• Decay mode: IT
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ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

I.C. 116 17.5%

I.C. 118 40.1%

I.C. 127 19.6%

X-ray 65.3 22.7%

X-ray 67.0 38.8%

gamma 98.85 11.4%

• Bioassay method: whole-body counting

Platinum-197

• Production years: 1965 

• Half-life: 19.89 hr

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 198 81.2%

beta 225 10.6%

I.C. 63.0 30.7%

I.C. 63.6 14.1%

I.C. 65.4 10.5%

I.C. 74.6 13.5%

gamma 77.4 17.0%

• Bioassay method: whole-body scan

Plutonium-236

• Production years: 1968, 1970, 1973, 1975, 1984, 1986 

• Half-life: 2.86 yr

• Decay mode: SF, α

• Progeny: U-232

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 5,720 30.6%

alpha 5,770 69.3%

I.C. 26.5 11.9%

I.C. 30.4 10.4%

• Bioassay method: plutonium (PU0)

Plutonium-237

• Production years: 1984, 1986 

• Half-life: 45.2 d

• Decay mode: α, EC
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ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Progeny: U-233, Np-237

• Important energy emissions:

Emission type Energy (keV) Abundance

A.E. 10.4 28.3%

A.E. 13.9 14.6%

X-ray 97.5 12.4%

X-ray 102 19.8%

• Bioassay method: plutonium (PU0)

Plutonium-238

• Production years: 1961–1963, 1965, 1968–1985, and 1987–1988 

• Half-life: 87.7 yr

• Decay mode: SF, α 

• Progeny: U-234, Np-237

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 5,460 29.0%

alpha 5,500 70.9%

I.C. 22.5 10.9%

• Bioassay method: gross alpha (GU0), plutonium (PU0)

Plutonium-239

• Production years: 1955–1956,1961–1972,1974–1985,1987–1988 

• Half-life: 2.4E4 yr

• Decay mode: α

• Progeny: U-235

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 5,110 11.9%

alpha 5,140 17.1%

alpha 5,160 70.7%

• Bioassay method: gross alpha (GU0), Pu-239 specific method (PU9), and plutonium 

(PU0). 

Plutonium-240

• Production years: 1961–1966, 1968–1986, 1988

• Half-life: 6,564 yr

• Decay mode: SF, α

• Progeny: U-236

• Important energy emissions:
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ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

Emission type Energy (keV) Abundance

alpha 5,120 27.1%

alpha 5,170 72.8%

I.C. 24.2 10.3%

• Bioassay method: gross alpha (GU0) and plutonium (PU0)

Plutonium-242

• Production years: 1961–1988 

• Half-life: 3.75E+05 yr

• Decay mode: SF, α 

• Progeny: U-238

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 4,860 23.5%

alpha 4,900 76.5%

• Bioassay method: gross alpha (GU0) and plutonium (PU0)

Plutonium-244

• Production years: 1968, 1970–1982 

• Half-life: 8.00 E7 yr

• Decay mode: SF, α

• Progeny: U-240

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 4,550 19.4%

alpha 4,590 80.5%

• Bioassay method: plutonium (PU0)

Polonium-210

• Production years: 1962, 1966

• Production method: β: Bi-210, EC: At-210, α: Rn-214

• Half-life: 138.4 d

• Decay mode: α

• Progeny: stable

• Important energy emissions: 

Emission type Energy (keV) Abundance

alpha 5,300 100%

• Bioassay method: gross alpha (GU0)

Potassium-40

• Production years: 1979

• Half-life: 1.25E9 yr
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ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Decay mode: β-, EC

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 585 89.1%

gamma 1,460 10.7%

• Bioassay method: whole-body counting

Potassium-42

• Production years: 1955–1966

• Half-life: 12.36 hr

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 824 17.6%

beta 1,570 81.9%

gamma 1,520 18.1%

• Bioassay method: gross beta (013) then whole-body counting

Potassium-43

• Production years: 1964–1965,1967,1971,1973–1978,1980–1981,1983 

• Half-life: 22.3 hr

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 297 90.9%

gamma 373 86.8%

gamma 617 79.2%

• Bioassay method: whole-body counting

Praseodymium-142

• Production years: 1956–1957, 1959–1968, 1970

• Half-life: 19.12 hr

• Decay mode: β-, EC

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 834 96.3%

gamma 1,580 3.68%

• Bioassay method: rare earth (FU0)
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ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

Praseodymium-143

• Production years: 1955–1957, 1959–1968, 1970, 1972–1973 

• Half-life: 13.57 d

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 315 100%

• Bioassay method: rare earth (FU0)

Praseodymium-144

• Production years: 1962

• Half-life: 17.28 min

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 1,220 97.9%

• Bioassay method: rare earth (FU0)

Promethium-146

• Production years: 1974 

• Half-life: 5.53 yr

• Decay mode: β-, EC

• Progeny: Sm-146

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 260 31.9%

gamma 454 65.0%

gamma 736 22.5%

gamma 747 34.0%

• Bioassay method: rare earth (FU0), whole-body counting

Promethium-147 

• Production years: 1955–1968, 1970–1987, 1990 

• Half-life: 2.46 yr

• Decay mode: β- 

• Progeny: Sm-147

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 61.9 100%
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ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Bioassay method: rare earth (FU0); Pm-147 specific method (PM7) used in 1987

Promethium-148

• Production years: 1970

• Half-life: 5.37 d

• Decay mode: β- 

• Progeny: stable

• Important energy emissions: 

Emission type Energy (keV) Abundance

beta 341 33.3%

beta 976 55.5%

gamma 550 22.0%

gamma 915 11.5%

gamma 1,470 22.2%

• Bioassay method: rare earth (FU0) , whole-body counting

Protactinium-231

• Production years: 1961–1963, 1965–1966, 1968–1969, 1976–1981, 1984–1986 

• Half-life: 3.28E4 yr

• Decay mode: α

• Progeny: Ac-227

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 4,950 23.0%

alpha 5,020 25.6%

alpha 5,030 20.2%

alpha 5,060 11.1%

• Bioassay method: protactinium (PA0) and Pa231/233 fecal (PF3)

Protactinium-233

• Production years: 1950, 1963–1964, 1966, 1969

• Half-life: 26.97 d

• Decay mode: β- 

• Progeny: U-233

• Important energy emissions: 

Emission type Energy (keV) Abundance

beta 41.4 25.4%

beta 46.3 15.0%

beta 62.9 36.7%

beta 71.3 15.6%

I.C. 196 29.7%

gamma 312 38.6%

• Bioassay method: Pa-233 beta (PA3), whole-body counting
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ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

Rhenium-186

• Production years: 1957, 1959–1972, 1979 

• Half-life: 90.46 hr

• Decay mode: β-, EC

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 306 21.5%

beta 359 70.9%

• Bioassay method: gross beta (013)

Rhodium-102 

• Production years: 1958

• Half-life: 207 d

• Decay mode: EC, β+

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 413 20.0%

positron 576 11.3%

gamma 475 45.9%

gamma 511 30.8%

• Bioassay method: gross beta (013), whole-body counting

Rubidium-83

• Production years: 1969

• Half-life: 86.2 d

• Decay mode: EC

• Progeny: Kr-83m

• Important energy emissions:

Emission type Energy (keV) Abundance

A.E. 10.8 23.4%

gamma 520 44.7%

gamma 530 29.3%

gamma 553 16.0%

• Bioassay method: whole-body counting

Rubidium-84

• Production years: 1964–1965, 1969, 1975

• Half-life: 32.77 d

• Decay mode: EC, β+, β- 

• Progeny: stable

• Important energy emissions:
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ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

Emission type Energy (keV) Abundance

positron 339 14.0%

positron 75.7 13.1%

A.E. 10.8 16.3%

gamma 511 54.2%

gamma 882 69.0%

• Bioassay method: whole-body counting

Rubidium-86

• Production years: 1946, 1955–1957, 1959–1972

• Half-life: 18.64 d

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 70.9 91.4%

gamma 1,080 9.0%

• Bioassay method: gross beta (013) then whole-body counting 

Rubidium-88

• Production years: 1964

• Half-life: 17.78 min

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 2,370 78.0%

gamma 898 14.0%

gamma 1,840 21.4%

• Bioassay method: whole-body counting

Ruthenium-97 

• Production years: 1959–1960, 1962, 1970 

• Half-life: 2.9 d

• Decay mode: EC

• Progeny: Tc-97m

• Important energy emissions:

Emission type Energy (keV) Abundance

A.E. 15.4 14.0%

• Bioassay method: gross beta (013) 

Ruthenium-105

• Production years: 1956
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ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Half-life: 4.44 hr

• Decay mode: β- 

• Progeny: Rh-105

• Important energy emissions: 

Emission type Energy (keV) Abundance

beta 397 18.8%

beta 405 16.9%

beta 431 47.8%

I.C. 107 14.4%

gamma 469 17.5%

gamma 676 15.7%

gamma 724 47.3%

• Bioassay method: gross beta (013)

Ruthenium-106 

• Production years: 1955–1957, 1959–1988

• Half-life: 373.6 d

• Decay mode: β- 

• Progeny: Rh-106

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 10.0 100%

• Bioassay method: Ru-106 specific method (RU6) 

Samarium-151 

• Production years: 1968–1982, 1984–1987

• Half-life: 90 yr

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 19.8 99.1%

• Bioassay method: rare earth (FU0)

Samarium-153

• Production years: 1956–1957, 1959–1961, 1963–1969

• Half-life: 46.7 hr

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 200 32.2%

beta 225 49.6%
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ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

Emission type Energy (keV) Abundance

beta 264 17.5%

I.C. 21.1 22.1%

I.C. 54.6 43.4%

X-ray 40.9 17.9%

X-ray 41.6 32.2%

gamma 103 29.8%

• Bioassay method: rare earth (FU0)

Scandium-46

• Production years: 1955–1957;1959–1973

• Half-life: 83.8 d

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 112 100%

gamma 889 100%

gamma 1,120 100%

• Bioassay method: rare earth (FU0) 

Scandium-49

• Production years: 1955, 1965 

• Half-life: 57.2 min

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 818 99.9%

• Bioassay method: rare earth (FU0) 

Silver-110m 

• Production years: 1955–1957, 1959–1966 

• Half-life: 249.76 d

• Decay mode: IT, β- 

• Progeny: Ag-110

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 21.6 66.9%

beta 165 30.1%

gamma 658 94.3%

gamma 885 72.7%

gamma 937 34.2%

gamma 1,380 24.9%
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ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Bioassay method: gross beta (013 and GB0)

Silver-111

• Production years: 1956–1957, 1959–1970

• Half-life: 7.45 d

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 364 91.7%

• Bioassay method: gross beta (013).

Sodium-22 

• Production years: 1955–1956, 1961–1964

• Half-life: 2.6 yr

• Decay mode: EC, β+

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

positron 215 89.8%

gamma 511 180.0%

gamma 1,270 99.9%

• Bioassay method: gross beta (013), whole-body counting

Sodium-24

• Production years: 1955–1967

• Half-life: 14.96 hr

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 554 99.9%

gamma 1,370 100.0%

gamma 2,750 99.9%

• Bioassay method: gross beta (013), Na-24 specific method used in 1960; whole-body counting

Strontium-82

• Production years: 1970 

• Half-life: 25.36 d

• Decay mode: EC

• Progeny: Rb-82

• Important energy emissions: emissions listed from Rb-82 progeny
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ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

Emission type Energy (keV) Abundance (%)

Gamma 776 13

Positron 1,520 83

• Bioassay method: whole-body counting 

Strontium-89 

• Production years: 1955–1957;1959–1963;1965–1987 

• Half-life: 50.5 d

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 585 100%

• Bioassay method: strontium (SR0); Sr-89 specific urine method (SR9) beginning in 1960

Strontium-90

• Production years: 1955–1988 

• Half-life: 28.79 yr

• Decay mode: β- 

• Progeny: Y-90

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 196 100%

betaa 933 100%

a. See Comments below.

• Bioassay method: strontium (SR0)

Sulfur-35 

• Production years: 1955–1969 

• Half-life: 87.5 d

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 48.7 100%

• Bioassay method: S-35 specific method (001)

Tantalum-182

• Production years: 1955–1957, 1959–1972, 1974

• Half-life: 114.43 d

• Decay mode: β- 

• Progeny: stable
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ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 73.2 29.5%

beta 129 20.7%

beta 158 40.0%

I.C. 88.5 16.6%

I.C. 89.9 14.9%

gamma 1,120 34.9%

gamma 1,190 16.2%

gamma 1,220 27.0%

gamma 1,230 11.4%

• Bioassay method: gross beta (013) then whole-body counting

Technetium-95m

• Production years: 1957–1958, 1967, 1970 

• Half-life: 61 d

• Decay mode: EC, β+, IT

• Progeny: Tc-95

• Important energy emissions:

Emission type Energy (keV) Abundance

A.E. 14.7 14.5%

gamma 204 63.2%

gamma 582 30.0%

gamma 835 26.6%

• Bioassay method: gross beta (013) then whole-body counting

Technetium-99 

• Production years: 1955–1957, 1959–1970, 1972–1988 

• Half-life:2.11E5 yr

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 101 100%

• Bioassay method: gross beta (013, GB0), Tc-99 specific method (006) beginning in 1960

Technetium-99m

• Production years: 1966, 1968, 1970 

• Half-life: 6.02 hr

• Decay mode: IT

• Progeny: Tc-99

• Important energy emissions:
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ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

Emission type Energy (keV) Abundance

gamma 141 89.1%

• Bioassay method: whole-body counting

Tellurium-132

• Production years: 1963, 1968

• Half-life: 3.204 d

• Decay mode: β- 

• Progeny: I-132

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 67.0 100.0%

I.C. 16.6 74.0%

gamma 228 88.0%

• Bioassay method: whole-body counting

Terbium-158

• Production years: 1970

• Half-life: 180 yr

• Decay mode: β-, EC

• Progeny: stable

• Important energy emissions: 

Emission type Energy (keV) Abundance

beta 275 15.5%

I.C. 29.2 23.2%

I.C. 71.6 16.2%

I.C. 72.3 17.6%

gamma 944 43.9%

gamma 962 20.3%

• Bioassay method: rare earth (FU0)

Thallium-201

• Production years: unknown quantity in 1975 

• Half-life: 72.9 hr

• Decay mode: EC

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

I.C. 84.1 15.6%

X-ray 69.1 27.4%

X-ray 71.1 46.4%

gamma 167 10.0%

• Bioassay method: whole-body counting
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ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

Thallium-204

• Production years: 1955–1971 

• Half-life: 3.78 yr

• Decay mode: EC, β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 244 97.1%

• Bioassay method: gross beta (013 and GB0)

Thorium-228

• Production years: 1962

• Half-life: 1.91 yr

• Decay mode: α

• Progeny: Ra-224

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 5,340 27.2%

alpha 5,420 72.1%

I.C. 65.8 10.7%

• Bioassay method: gross alpha (GU0)

Thorium-229 

• Production years: 1968, 1970–1971, 1973–1974, 1977, 1979–1986, 1988 

• Half-life: 7340 yr

• Decay mode: α

• Progeny: Ra-225

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 4,850 55.6%

alpha 4,900 10.1%

X-ray 85.8 15.3%

X-ray 88.9 25.1%

• Bioassay method: gross alpha and fecal monitoring (GF0, TF0) 

Thorium-230 

• Production years: 1956, 1962–1963, 1965, 1967–1976, 1978–1988, 1990 

• Half-life: 75,380 yr

• Decay mode: α

• Progeny: Ra-226

• Important energy emissions:
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ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

Emission type Energy (keV) Abundance

alpha 4,620 23.4%

alpha 4,690 76.4%

• Bioassay method: gross alpha and fecal monitoring (GF0), (TF0), Th-230 

Thorium-232 

• Production years: 1963, 1968–1969, 1972–1976, 1978–1987 

• Half-life: 1.4E10 yr

• Decay mode: α

• Progeny: Ra-228

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 3,950 21.7%

alpha 4,010 78.2%

• Bioassay method: gross alpha and fecal monitoring, (GF0), (TF0) 

Thorium-234

• Production years: 1981 

• Half-life: 24.1 d

• Decay mode: β- 

• Progeny: Pa-234m

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 26.7 19.2%

beta 52.4 70.3%

I.C. 71.3 10.8%

• Bioassay method: gross beta (GB0)

Thulium-170

• Production years: 1962–1971, 1974–1975

• Half-life: 128.6 d

• Decay mode: EC, β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 290 18.3%

beta 323 81.6%

• Bioassay method: rare earth (FU0)

Thulium-171

• Production years: 1967 

• Half-life: 1.92 yr

• Decay mode: β- 
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ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 25.1 98%

• Bioassay method: rare earth (FU0)

Tin-117m

• Production years: 1977 

• Half-life: 13.76 d

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

I.C. 127 66.3%

I.C. 152 13.7%

I.C. 152 10.6%

gamma 159 86.4%

• Bioassay method: whole-body counting

Titanium-44

• Production years: 1956, 1958

• Half-life: 60 yr

• Decay mode: EC

• Progeny: Sc-44

• Important energy emissions:

Emission type Energy (keV) Abundance

gamma 67.9 93.0%

gamma 78.4 96.4%

• Bioassay method: gross beta (013). Radiation from daughter Sc-44.

Tungsten-185

• Production years: 1955–1957, 1959–1971

• Half-life: 75.1 d

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 127 99.9%

• Bioassay method: gross beta (013 and GB0) 

Tungsten-187

• Production years: 1955–1957, 1959–1970
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ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Half-life: 23.7 hr

• Decay mode: β- 

• Progeny: Re-187 

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 193 55.4%

beta 457 30.1%

I.C. 62.4 16.7%

gamma 480 21.8%

gamma 686 27.3%

• Bioassay method: gross beta (013), whole-body counting

Uranium-232

• Production years: 1961–1965, 1968, 1970–1971, 1974–1979

• Half-life: 68.9 yr

• Decay mode: α

• Progeny: Th-228

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 5,260 31.5%

alpha 5,320 68.1%

I.C. 38.0 12.1%

I.C. 41.5 10.3%

• Bioassay method: uranium (UR0)

Uranium-233

• Production years: 1961–1963, 1965–1988

• Half-life: 1.59E5 yr

• Decay mode: α

• Progeny: U-233

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 4,780 13.2%

alpha 4,820 84.5%

• Bioassay method: uranium (UR0)

Uranium-234

• Production years: 1956, 1961–1963, 1965–1988

• Half-life: 2.45E5 yr

• Decay mode: α

• Progeny: Th-230

• Important energy emissions:
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ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

Emission type Energy (keV) Abundance

alpha 4,720 28.4%

alpha 4,780 71.4%

I.C. 33.4 11.0%

• Bioassay method: uranium (UR0)

Uranium-235

• Production years: 1955–1957, 1961–1963, 1965–1988

• Half-life: 7E8 yr

• Decay mode: α

• Progeny: Th-231

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 4,370 17.2%

alpha 4,400 55.6%

I.C. 15.6 44.2%

gamma 186 57.2%

• Bioassay method: uranium (UR0)

Uranium-236

• Production years: 1955–1956, 1961–1963, 1965–1988

• Half-life: 2.34E7 yr

• Decay mode: α

• Progeny: Th-232

• Important energy emissions:

Emission type Energy (keV) Abundance

Alpha 4,450 25.9%

Alpha 4,490 73.8%

• Bioassay method: uranium (UR0)

Uranium-238

• Production years: 1955–1956, 1961–1988

• Half-life: 4.47E9 yr

• Decay mode: SF, α

• Progeny: Th-234

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 4,150 22.3%

alpha 4,200 77.5%

• Bioassay method: uranium (UR0)

Vanadium-48

• Production years: 1962
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ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Half-life: 15.97 d

• Decay mode: EC, β+

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

positron 290 49.4%

gamma 511 100.0%

gamma 984 100.0%

gamma 1,310 97.5%

• Bioassay method: whole-body counting

Xenon-127

• Production years: 1983, 1987–1988

• Half-life: 36.34 d

• Decay mode: EC

• Progeny: stable

• Important energy emissions: 

Emission type Energy (keV) Abundance

gamma 172 25.5%

gamma 203 68.3%

gamma 375 17.2%

• Bioassay method: NA-noble gas: external monitoring is controlling for these materials

Xenon-133 

• Production years: 1960–1976, 1978–1980

• Half-life: 5.24 d

• Decay mode: β- 

• Progeny: stable

• Important energy emissions: 

Emission type Energy (keV) Abundance

beta 101 99.2%

I.C. 45.0 55.4%

X-ray 31.0 26.6%

gamma 81.0 36.0%

• Bioassay method: NA-noble gas: external monitoring is controlling for these materials

Ytterbium-169

• Production years: 1980, 1986

• Half-life: 32 d

• Decay mode: EC

• Progeny: stable

• Important energy emissions:
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ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

Emission type Energy (keV) Abundance

I.C. 50.3 35.3%

I.C. 138 13.1%

gamma 177 22.2%

gamma 198 35.8%

• Bioassay method: whole-body counting

Yttrium-86

• Production years: 1964, 1968

• Half-life: 14.74 hr

• Decay mode: EC, β+

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

positron 535 11.9%

A.E 12.0 13.8%

gamma 443 16.9%

gamma 511 63.8%

gamma 628 32.6%

gamma 703 15.4%

gamma 777 22.4%

gamma 1,080 82.5%

gamma 1,150 30.5%

gamma 1,850 17.2%

gamma 1,920 20.8%

• Bioassay method: whole-body counting

Yttrium-88

• Production years: 1957–1958, 1961–1963, 1965, 1974

• Half-life: 106.65 d

• Decay mode: EC, β+

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

A.E. 12.0 20.0%

gamma 898 93.7%

gamma 1,840 99.2%

• Bioassay method: rare earth (FU0) and whole-body counting

Yttrium-90 

• Production years: 1956–1968, 1973, 1987–1988

• Half-life: 64 hr

• Decay mode: β-

• Progeny: stable

• Important energy emissions:
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SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

Emission type Energy (keV) Abundance

beta 933 100%

• Bioassay method: rare earth (FU0). Daughter of Sr-90.

Yttrium-91

• Production years: 1955–1957, 1959–1978

• Half-life: 58.5 d

• Decay mode: β-

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 604 99.7%

• Bioassay method: rare earth (FU0)

Zinc-65

• Production years: 1955–1957, 1959–1966

• Half-life: 243.9 d

• Decay mode: EC, β+

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

positron 143 1.4%

gamma 511 2.8%

gamma 1,120 50.6%

• Bioassay method: gross beta (013), whole-body counting

Zinc-69m

• Production years: 1967, 1973–1974

• Half-life: 13.76 hr

• Decay mode: EC, β-

• Progeny: Zn-69

• Important energy emissions:

Emission type Energy (keV) Abundance

I.C. 429 4.55%

beta 321 100.0% 

gamma 439 94.8%

• Bioassay method: gross beta (GB0) , beta emission from Zn-69 progeny

Zirconium-95

• Production years: 1955–1986

• Half-life: 64.0 d

• Decay modes: β-

• Progeny: Nb-95m
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SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 110 54.5%

beta 121 44.3%

gamma 724 44.3%

gamma 757 54.4%

• Bioassay method: gross beta (013), Zr-95/Nd-95 (005), whole-body counting

Zirconium-97

• Production years: 1971

• Half-life: 16.74 hr

• Decay mode: β- 

• Progeny: Nb-97m

• Important energy emissions: 

Emission type Energy (keV) Abundance

beta 757 88.2%

gamma 743 93.1%

• Bioassay method: whole-body counting
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ATTACHMENT C 

DOSE RECONSTRUCTION APPROACH FOR IODINE

TABLE OF CONTENTS

SECTION TITLE PAGE

C.1 Overview.............................................................................................................................. 111

C.2 Radioiodine Inventory .......................................................................................................... 111

C.3 Workplace Monitoring .......................................................................................................... 111

C.4 Thyroid Monitoring ............................................................................................................... 112

C.5 Evaluation of Thyroid Monitoring Data.................................................................................. 116

C.6 Whole-Body Counting .......................................................................................................... 116

C.7 Iodine Urinary Sampling....................................................................................................... 117

C.8 Comparison of Proposed Chronic Iodine Intake with Later Data........................................... 117

C.9 Proposal for Unmonitored Workers ...................................................................................... 118

C.10 Acute Intake Analysis Summary, 1946 to 1957 .................................................................... 119

C.11 Chronic Intake Assessment Summary, 1946 to 1957 ........................................................... 126

C.12 Acute Intake Assessment Summary, 1962 to 1969 .............................................................. 129

LIST OF TABLES

TABLE TITLE PAGE

C-1 Commercial 131I production, 1946 to 1969............................................................................ 112

C-2 Weekly average number of gross beta/gamma air samples ................................................. 112

C-3 Available thyroid counting data, 1945 to 1957...................................................................... 113

C-4 Tolerance equivalents for various GM detectors .................................................................. 115

C-5 Calibration factors used to convert thyroid counting data ..................................................... 116

C-6 Summary of WBC data for 131I .............................................................................................. 116

C-7 Summary of available iodine urine samples ......................................................................... 117

C-8 Iodine urine bioassay samples by sample type .................................................................... 117

LIST OF FIGURES 

FIGURE TITLE PAGE

C-1 Comparison of acute and chronic intake assessments......................................................... 118
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C.1 OVERVIEW

Between 1946 and 1980, the Isotopes Division at ORNL produced iodine for commercial applications. 

The largest quantities, ranging between 740 and 3,600 Ci/yr, were produced between 1953 and 1964. 

An assessment of internal exposure from these activities is complicated by limited personnel 

monitoring data. A coworker analysis based on thyroid monitoring between 1944 and 1954 could be 

used to assign internal exposure to potentially exposed individuals during the period from 1955 to 

1962, when routine monitoring data for iodine are not available. The early data demonstrate the 

capability of workplace controls for episodic iodine releases and it is reasonable to assume that such 

releases would be identified during the subsequent period from 1955 to 1962. Individuals with no 

individual monitoring data during the period would not be expected to be routinely exposed beyond 

the reported levels in the earlier monitoring data, which were largely collected after the occurrence of 

a release or incident.

C.2 RADIOIODINE INVENTORY 

Production of radioiodine at ORNL began in 1946, initially through irradiation of tellurium. By 1958, 

production had shifted to separation of the iodine fission product from reactor fuel (Rupp, Beauchamp, 

and Farmakes 1958). The production activities were initially performed in Building 3026C/D (706C/D 

at that time); by 1951, they had shifted to a new facility in Building 3028 (910 at that time) (Ramsey 

1950). In addition, between 1944 and 1956, significant quantities of iodine were present in facilities 

as a byproduct of radioactive lanthanum (RaLa) production – not to be confused with the commercial 

iodine-production process. During this period, between 8,800 and 42,000 Ci of radioactive iodine 

were released annually as a RaLa byproduct (ATSDR 2008). This quantity is an order of magnitude 

higher than the amounts produced by the isotopes group (Table C-1). 

Separations activities were primarily conducted in Buildings 706C and 706D (later 3026C/D), 3028 

(Radioisotope Production Laboratory), and 3047 (Isotope Technology Building). However, radioiodine 

exposure was possible in any area where reactor fuel processing was performed, such as 3019 (Pilot 

Plant, Radiochemical Development Laboratory, High Level Radiation Analytical Laboratory), 3505 

(Metal Recovery Facility), 3515 (Fission Product Semi-Works), 3517 (Fission Product Development 

Laboratory), and 4507 (High Level Chemical Development Laboratory) (Brooksbank, Patton, and 

Krichinsky 1994; ORAUT 2007).

Table C-1 shows annual production through 1969.

C.3 WORKPLACE MONITORING

Air monitoring was an integral part of the ORNL radiological monitoring program from the onset of 

operations. Applied HP annual reports list the total and/or average number of gross beta/gamma air 

samples (see Table C-2). These data were in the form of annual summaries only. Detailed 

information and breakdown by work area is not available in the SRDB. 

Tolerance values were established by 1944 based on gross beta air concentrations and areas were 

evacuated at the tolerance level (1 × 10-07 μCi/cm3

). Respiratory protection was required at 10% of 

the tolerance air concentration (1 × 10-08 μCi/cm3

) (AEC 1947). Entry into areas with respiratory

protection was allowed up 100 times tolerance (1 × 10-05 μCi/cm3

) (Sadowski 1953). The “operating 

maximum permissible level” was defined as 10% of the MPC and was 1 × 10-8 μCi/cm3 during this 

period. By 1961, the guidance in NCRP (1959) about the concept of MPC was adopted. Therefore, 

the MPC for occupational exposure to unidentified beta/gamma-emitters was set at 10-9 μCi/cm3 (Hart 
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Table C-1. Commercial 131I production, 

1946 to 1969.

a

Year Amount (Ci)

1946 1.3

1947 10

1948 46

1949 190

1950 310

1951 450

1952 490

1953 1,700

1954 820

1955 1,000

1956 740

1957 1,200

1958 3,600

1959 2,300

1960 1,500

1961 3,300

1962 2,200

1963 2,400

1964 2,000

1965 80

1966 55

1967 28

1968 8

1969 160

a. Annual values do not include iodine as a 

byproduct from RaLa processing. 

Table C-2. Weekly average number of gross beta/gamma air 

samples. 

Year Samples per week SRDB Ref ID

1955 222 22545

1956 186 13248

1957 496 22546

1958 429 21780

1959 327 22547

1960 695 12083

1961 681 12084

1962 573 12093

1963 452 12092

1964 409 12090

1960), with trigger levels remaining at 0.1 MPC for general entry without respiratory protection, and 

100 MPC as a ceiling value for entry with respiratory protection (ORNL 1961).

C.4 THYROID MONITORING

Thyroid monitoring before the implementation of WBCs in 1962 was performed using a Geiger-Müller 

(GM) detector, typically pressed against the left side of the neck, then on the right side of the neck. 

(There also are reports showing only one result, without indicating if it was the average of left and 
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DOSE RECONSTRUCTION APPROACH FOR IODINE (continued)

right measurements or measured with the detector at the middle of neck.) A dedicated counting 

system was available as of April 1954 (ORNL 1954b), but no additional detail on counter configuration 

or procedures is available. 

A total of 230 measurements are available; these measurements were performed on 147 individuals 

and span the period from 1945 through 1957 (see Table C-3). All of the available data were gathered 

from incident reports and/or internal memoranda summarizing each monitoring event. The ORAU 

Team reviewed periodic Applied HP group reports to determine if the frequency of thyroid counting 

was included. These reports included statistics on various radiological services and were semiannual 

from 1955 to 1956 and annual thereafter. The average weekly number of thyroid counts is only 

reported in the 1957 and 1958 reports (ORNL 1957; Hart 1960). No data are noted from before 1957 

or after 1958. The number of thyroid measurements was reported as 100 in 1957 (weekly average of 

two) and 50 in 1958. Table C-3 shows that these numbers do not correspond with the actually 

available data for these years, which show 18 in 1957 and none in 1958. It appears that additional 

data might have existed, but they are not available. 

Table C-3. Available thyroid counting data, 1945 to 1957. 

Date Counts Individuals

SRDB Ref 

ID Summary

09/21/1945a 9 9 103999 Nine individual “special probing” thyroid and chest counts 

taken. These workers were all located in 706-D (3026-D: 

RaLa chemical separation) and worked 9/20/45 on night 

shift.

03/5/1946 1 1 22957 A precipitron run at 7:45 p.m. on 3/5/46 indicated 

increased airborne activity in 706-D. The source of 

activity was determined to be failure of a steam jet to 

automatically shut off at the W5 tank in the tank farm 

outside Building 706-D. The complicating factor was the 

metal being dissolved was very fresh, giving rise to 

release of short-lived material. Guards and other 

personnel around the tank farm area at the time of high 

airborne activity were checked for iodine accumulation in 

thyroid (only one result was listed in the report; other 

readings are unavailable).

07/2/1946 1 1 22957 A uranium slug that had cooled for 72 hours was loaded 

into the dissolver in Cell #1. Dissolving started at 12:00 

p.m., 7/1/46. A single precipitron high count was 

observed about two hours after the dissolving started. No 

alpha contamination was observed. During 

decontamination, high hand and shoe counts on workers 

were observed.

08/16/1946 

to 

08/19/1946

28 15 116562 A report titled 706-D H.P. Report Period Ending 8/17/46

describes an incident involving high air activity on the 

third level when wind direction was from north. Twentythree air samples (taken from 8/13/46 through 8/18/46) 

exceeding 10% of tolerance were recorded. It was 

concluded that the activity was coming from 706-D offgas and the vent-duct stack.
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Table C-3. Available thyroid counting data, 1945 to 1957 (continued). 

Date Counts Individuals

SRDB Ref 

ID Summary

8/29/1947 1 1 22957 One thyroid count was taken on August 29, 1947, after a 

violent oxalic acid chemical reaction in the iodine setup at 

Building 706-D [SRDB 22959, p. 114; 118330, p. 3]. A 

30-minute precipitron run at the work site resulted in

measured air activity of 7.72E-11 μCi/cm3 beta/gamma. 

The two continuous air monitors (CAMs) in the area 

showed no increase in activity.

12/09/1947 

to 

12/10/1947a 

54 54 22959 A report titled 706-D H.P. Report for Week Ending 12-6-

47 describes decontamination work in Cell A that 

continued from the prior week. Contamination surveys of 

Building 105 took place during this time. The personnel 

who took part in work were subjected to thyroid counting, 

chest counts, and nasal swipes on December 9–10 and 

worked 9/20/1945.

09/27/1948 

to 

10/22/1948a 

31 6 110152 Six workers were selected for repeat counts in 

September and October 1948. Work locations and 

reasons for the counts were not given. Each worker was 

scheduled for six separate counts for a total of 36 counts, 

but some workers did not report for later repeat counts, 

resulting in 31 thyroid counts.

04/18/1949 

to 

04/22/1949a 

22 7 119713 Six workers at Building 706-D were repeatedly thyroidcounted from April 15 through 22, 1949. These workers 

were involved in Product Run #88. The thyroid counts 

taken from April 15 to 17 are not included in the coworker study because the product run was not fully 

underway until April 18.

11/22/1949 4 4 104084 Four thyroid counts were taken in November 1949 after 

intermittent high air activity throughout the day on 

11/22/1949 in Building 706-C. Air activity was suspected 

to have originated from the I-131 run in progress. A rise 

in air activity was noted on the CAMs immediately after 

the sparging operation in the cell. Several precipitron 

samples taken during the day did not reveal activity 

approaching tolerance level, and the activity collected in 

the precipitron foils decayed rapidly. The filter papers on 

the CAMs had to be replaced constantly to keep the 

instruments in scale. Several CAM filters were autoradiographed and the result indicated that the activity was 

diffused rather than particulate in nature.

03/14/1950 

to 

03/15/1950

18 9 104119 Thyroid counts were taken on workers in the vicinity of 

the I-131 process cell during the period of high air activity 

in 706-C. The air activity became high enough that the 

building was evacuated. The source of the activity was 

traced to material escaping through opening in the top of 

the I-131 process well. The decay and absorption curves 

indicated that the isotopes were I-131, and possibly some 

Te-132. Thyroid counts were taken on maintenance 

workers and operators working in the vicinity of the cell.
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Table C-3. Available thyroid counting data, 1945 to 1957 (continued).

Date Counts Individuals

SRDB Ref 

ID Summary

01/11/1951 

to 

01/13/1951

8 3 104244 Eight counts were taken on three individuals in January 

after a contamination incident. On January 11, the three 

employees were performing nitrate analysis on iodide 

products in a laboratory in Building 706-D. When they 

dissolved sodium iodide in sulfuric acid, free iodide and 

radioactive fumes scattered over the room and one of 

them became externally contaminated.

10/24/1951 1 1 104405 A thyroid count was performed on an employee who was 

working in the vicinity of a suspected high airborne fission 

product release in Building 3026.

1/28/1952 7 3 104471 Loss of off-gas vacuum at 5:00 p.m. on January 28, 1952 

on the I-131 setup resulted in release of airborne activity. 

The building was evacuated upon CAM alarm.

4/29/1954 27 27 147059, 

147108, 

147114, 

147210

Fumes boiled over upon the addition of a nitric acid 

solution to very hot (thermally) slugs within the dissolver 

tank. Highly radioactive fumes set off the monitron and 

CAMs.

10/25/1957 18 6 033238 Pressurization of feed adjustment tank resulted in the 

release of air activity.

Total 230 147 Not 

applicable

Not applicable

a. Indicates data assessed collectively in chronic intake assessment; all other data assessed individually as acute intakes.

Medical records for individuals likely to have been exposed to radioiodine (based on incident reports 

and work history) were reviewed to determine if records of thyroid counting were included in the 

medical charts. While the reviewed charts did include records of thyroid counting associated with 

some radiological incidents, there were no records of routine thyroid counts.

Calibration data for thyroid measurements were sometimes included with the documentation of the 

measurements themselves and were expressed as the number of cpm being equivalent to 

“tolerance.” The tolerance value is equivalent to the organ MPC based on the exposure limits at the 

time. The thyroid tolerance value was 2.0 μCi before July 1947 (Morgan 1947) but was changed to 

0.2 μCi by May 1948 (Morgan 1948). This change is evident on inspection of thyroid tolerance values 

expressed in cpm, which vary by a factor of 10 when comparing pre-1948 values with post-1948 

values. Table C-4 presents a summary of the available data on factors that were used to convert 

thyroid measurements to thyroid burden. 

Table C-4. Tolerance equivalents for various GM detectors (cpm).

a

Date Glass Brass

Bi-GM

(Bismuth-C coated) SRDB Ref ID

08/16/46 Not applicable 750 Not applicable 22957, p. 264

08/26/46 296 194b Not applicable 22957

09/17/46 445c 834 Not applicable 22946

04/18/49 Not applicable 75 Not applicable 109284

05/01/51 Not applicable Not applicable 400 109500, p. 31

a. The tolerance value was defined as the instrument response in cpm equivalent to the maximum allowable thyroid 

burden. This value was initially 2 μCi and was changed to 0.2 μCi in May 1948.

b. Glass-walled tube with brass covering.

c. Protective wire covering closer to the tube than used on 08/26/1946.
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DOSE RECONSTRUCTION APPROACH FOR IODINE (continued)

C.5 EVALUATION OF THYROID MONITORING DATA

The ORAU Team reviewed the available thyroid monitoring data for the period from 1945 to 1957 (see 

Table C-3) to determine the nature of the exposure (chronic versus acute). Once this was done, a 

single dataset representing chronic iodine exposure conditions, and a series of datasets representing 

individual acute (episodic/incident) exposure conditions, were compiled. The thyroid detector 

calibration information (Table C-4) was used to develop a mechanism to convert each thyroid 

measurement to an individual iodine thyroid burden in microcuries (Table C-5).

Table C-5. Calibration factors used to convert thyroid counting data.

Period Value Basis

1945–1946 750 cpm = 2.0 μCi Documentation published in 1947 indicated the 2.0 μCi maximum 

thyroid burden value [SRDB 13233].

1947–1952 75 cpm = 0.2 μCi Change of thyroid burden value from 2.0 μCi to 0.2μCi between 1947 

and 1948 [SRDB 13233; 101475] and measurement data sheets 

[SRDB 109284].

1954–1957 400 cpm = 0.2 μCi SRDB 103344

Data in Table C-3 that were indicative of episodic releases (incidents) were converted to thyroid 

burden in microcuries and evaluated as individual acute intakes using the actual measurement and 

exposure date/time parameters. 

Data in Table C-3 that were indicative of routine measurements (as indicated by an ‘a’ adjacent to the 

date range) were converted to thyroid burden in microcuries and assessed as a single chronic intake 

using standard one person–one sample methodology. 

A lognormal distribution with geometric mean of 0.04167 μCi and geometric standard deviation of 

6.036 was fit to the thyroid burden data. This resulted in a 95th-percentile thyroid burden of 0.8 μCi. 

The Integrated Modules for Bioassay Analysis (IMBA) program was used to calculate the intake 

quantity associated with the calculated 95th-percentile thyroid burden as well as the projected urinary 

excretion rate and whole-body burden. The equilibrium intake (i.e., > 90-day exposure period for 131I) 

associated with this burden is 5.4 × 105 pCi/d. Note that the equilibrium intake associated with the 

geometric mean burden (50th percentile) is 2.8 × 104 pCi/d.

C.6 WHOLE-BODY COUNTING

In 1961, the ORNL whole-body counter was brought into operation. Individuals were counted in either 

a chair or scanning-bed configuration. 

Table C-6 below summarizes the maximum detected quantity of 131I for each specified year. 

Currently, only summary data are available for the WBC results; however, these data would be 

expected to be reported in individual claimant files as well.

Table C-6. Summary of WBC data for 131I.

Year

Highest measured activity

in μCi (whole body)

Number with 

measurable activity

Number of measurements 

performed

SRDB Ref 

ID

1961 0.20 4 102 12084

1962 0.28 17 395 12093

1963 0.15 32 1,054 12092

1964 0.022 11 1,483 12090
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C.7 IODINE URINARY SAMPLING

Urine bioassays for iodine appear to have been begun as early as 1958, with only a small number of 

samples analyzed before 1962. Tables C-7 and C-8 present the number and relative magnitude of 

the available data. No urine bioassay data are available for 1977 to 1986. 

Table C-7. Summary of available iodine 

urine samples.

Year Number of samples

1958 2

1961 1

1962 5

1963 3

1964 4

1965 18

1966 11

1967 11

1968 1

1969 15

1970 13

1971 5

1972 1

1973 41

1974 2

1976 2

1987 5

1988 28

Total 168

Table C-8. Iodine urine bioassay samples by sample type. 

Sample type Count Min (pCi/24 hr) Max (pCi/24 hr)

Incident/follow-up/resample 40 0 2.2E+07

Unknown 6 0 9.5E+02

Work area/routine 54 0 4.5E+03

Results <5% exposure index 18 Not applicable Not applicable

Total 118 Not applicable Not applicable

Results unavailable 50a Not applicable Not applicable

a. Results listed in totals, but actual result not available.

C.8 COMPARISON OF PROPOSED CHRONIC IODINE INTAKE WITH LATER DATA

The ORAU Team evaluated iodine intake events between 1962 and 1969 to compare them to the 

potential intake quantities that were derived from data for 1945 to 1957 in Section C.5. 

Section C.12 provides a summary of bioassay data (urine, thyroid, and WBCs) and the results of an 

intake assessment associated with acute iodine intakes between 1962 and 1969. One very high 

exposure event occurred on June 21, 1967, during which two individuals were administered 

potassium iodide (KI). Intakes for this event were 9.7 × 106 pCi and 1.8 × 107 pCi for the two workers. 

Excluding this one event, intake quantities between 1962 and 1969 ranged from 6.9 × 102 pCi to 

6.9 × 105 pCi. This is a few orders of magnitude lower than intakes computed for the period from 

1944 to 1957 (8.5 × 103 pCi to 2.5 × 107 pCi).
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A graphical comparison of the acute intakes that were calculated for the events during both 1946 to 

1957 and 1962 to 1969, along with the chronic intake calculated using the routine monitoring data 

between 1945 and 1954, are shown in Figure C-1. This figure clearly shows the difference in 

magnitude of acute intake quantities when comparing events before 1955 to those after 1955. The 

intake quantity based on the 95th percentile of the routine monitoring data (5.4 × 105 pCi/d) is 

superimposed on this chart (solid horizontal line). This chronic intake bounds acute intakes during the 

post-1955 period. This conclusion is based on the observation that events equivalent to the highest 

acute intake after 1955 (1.8 × 107 pCi) would have to occur on a monthly basis to yield an intake 

higher than that of the chronic scenario (5.4 × 105 pCi/d × 365 d = 2.0 × 108 pCi).

Figure C-1. Comparison of acute and chronic intake assessments.

C.9 PROPOSAL FOR UNMONITORED WORKERS

As indicated earlier, the ORAU Team has proposed that the chronic intake that has been developed 

using the chronic intakes that were derived from the 1947 to 1949 monitoring data could be used to 

assign iodine intakes to individuals for whom no monitoring data are available during the period 

between the end of the current SEC period and the onset of routine WBCs (i.e., from 1955 to 1961). 

During this period, a chronic intake of 5.4 × 105 pCi/d would be assigned. Such an intake would 

equate to a urinary excretion of 1.7 × 105 pCi/d, result in a whole-body accumulation of 1.2 μCi, and 

be equivalent to exposure to an air concentration of 1.8 × 10-8 μCi/cm3

. Comparing these values to 
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available data yields the following conclusions, which support application of this intake for 

unmonitored individuals: 

1. The projected urinary excretion (1.7 × 105 pCi/d) is more than an order of magnitude greater 

than the highest measured urinary excretion for routine sampling of 4.5 × 103 pCi/d (see 

Table C-8).

2. The projected whole-body accumulation (1.2 μCi) is a factor of 4 larger than the highest 

measured whole-body accumulation of 0.28 μCi (see Table C-6).

3. The projected air concentration (1.8 μCi/cm3

) is nearly a factor of 2 greater than the maximum 

operating level used to control facility air concentrations. 

The quantity of iodine in process from 1955 to 1961 (1,000 to 3,600 Ci/yr) is bounded by the amount 

in process from 1947 to 1949 (8,800 to 42,000 Ci/yr). In summation, it is postulated that an individual 

with no thyroid monitoring from 1955 to 1962 would not have been exposed to a higher level than that 

determined by a chronic intake using the 95th percentile of routine monitoring data for 1947 to 1949. 

The workplace monitoring data that were in place from 1944 forward were able to detect intakes of 

this magnitude and, in such cases, personnel monitoring for iodine (thyroid-counting) was performed.

C.10 ACUTE INTAKE ANALYSIS SUMMARY, 1946 TO 1957

Start Date(s) of Incident: 03/05/1946 

Description/Reference: A precipitron run at 7:45 p.m. on 3/5/1946 indicated increased airborne 

activity in 706-D. The source of activity was determined to be failure of steam jet to automatically shut 

off at the W5 tank in the tank farm outside of Building 706-D. A complicating factor was that the metal 

being dissolved was very fresh, giving rise to a release of short-lived material. Guards and other 

personnel around the tank farm area at the time of high airborne activity were checked for iodine 

accumulation in their thyroids. [SRDB Ref ID: 22957]

Thyroid count data table

Name

Measurement 

date

Measurement 

time

Time of measurement 

(after intake days)

Measurement result 

(pCi)

Worker 1 03/05/1946 Unknown 0.17 6.8E+05

Worker 1 03/08/1946 Unknown 3.0 8.0E+04

Intake assessment table

Name Intake (pCi)

Worker 1 7.6E+05

Start Date(s) of Incident: 07/02/1946

Description/Reference: A uranium slug that had cooled for 72 hours was loaded into the dissolver in 

Cell #1. Dissolving started at 12:00 p.m., 7/1/1946. A single precipitron high count was observed 

about 2 hours after the dissolving started. No alpha contamination was observed. During 

decontamination, high hand and shoe counts on workers were observed. [SRDB Ref ID: 22957]

Thyroid count data table

Name

Measurement 

date

Measurement 

time

Time of measurement 

(after intake days)

Measurement result 

(pCi)

Worker 2 07/02/1946 Unknown 0.17 4.9E+05
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Intake assessment table

Name Intake (pCi)

Worker 2 1.4E+07

Start Date(s) of Incident: 08/16/1946

Description/Reference: A report titled 706-D H.P. Report Period Ending 8/17/46 describes an incident 

involving high air activity on the third level when wind direction was from north. Twenty-three air 

samples (taken from 8/13/1946 through 8/18/1946) exceeding 10% of tolerance were recorded. It 

was concluded that the activity was coming from 706-D off-gas and the vent-duct stack. [SRDB Ref 

ID: 116562]

Thyroid count data table

Name

Measurement 

date

Measurement 

time

Time of measurement 

(after intake days)

Measurement result 

(pCi)

Worker 3 08/19/1946 7:36:00 5.40 1.0E+03

Worker 4 08/16/1946 22:55:00 3.04 8.1E+05

Worker 4 08/17/1946 22:35:00 4.03 2.3E+05

Worker 4 08/18/1946 23:45:00 5.07 1.0E+05

Worker 5 08/16/1946 22:46:00 3.03 6.2E+05

Worker 5 08/17/1946 22:26:00 4.02 2.7E+05

Worker 5 08/18/1946 23:33:00 5.07 3.8E+05

Worker 6 08/16/1946 22:49:00 3.03 1.0E+03

Worker 6 08/17/1946 22:29:00 4.02 1.0E+03

Worker 7 08/17/1946 22:38:00 4.03 1.8E+06

Worker 7 08/18/1946 23:36:00 5.07 7.3E+05

Worker 8 08/18/1946 15:21:00 4.72 5.7E+05

Worker 9 08/16/1946 22:40:00 3.03 3.1E+06

Worker 9 08/17/1946 22:20:00 4.01 2.2E+06

Worker 9 08/18/1946 16:35:00 4.78 8.5E+05

Worker 9 08/18/1946 23:39:00 5.07 6.3E+05

Worker 10 08/16/1946 22:52:00 3.04 1.8E+06

Worker 10 08/17/1946 22:32:00 4.02 5.3E+04

Worker 10 08/18/1946 23:42:00 5.07 1.9E+05

Worker 11 08/19/1946 7:33:00 5.40 1.5E+05

Worker 12 08/18/1946 15:18:00 4.72 3.1E+05

Worker 13 08/18/1946 16:30:00 4.77 3.2E+05

Worker 14 08/16/1946 22:43:00 3.03 7.1E+05

Worker 14 08/17/1946 22:23:00 4.02 1.0E+03

Worker 14 08/18/1946 23:30:00 5.06 2.6E+05

Worker 15 08/18/1946 15:15:00 4.72 2.2E+05

Worker 16 08/18/1946 17:00:00 4.79 9.8E+05

Worker 17 08/19/1946 7:30:00 5.40 9.1E+04

Worker 3 08/19/1946 7:36:00 5.40 1.0E+03

Intake assessment table

Name Intake (pCi)

Worker 3 1.2E+04

Worker 4 1.5E+06

Worker 5 3.5E+06

Worker 6 9.4E+03

Worker 7 9.8E+06

Worker 8 6.2E+06
Document No. ORAUT-RPRT-0090 Revision No. 00 Effective Date: 03/29/2018 Page 121 of 133

ATTACHMENT C

DOSE RECONSTRUCTION APPROACH FOR IODINE (continued)

Name Intake (pCi)

Worker 9 9.4E+06

Worker 10 6.5E+05

Worker 11 1.7E+06

Worker 12 3.3E+06

Worker 13 3.5E+06

Worker 14 1.0E+04

Worker 15 2.4E+06

Worker 16 1.1E+07

Worker 17 1.0E+06

Start Date(s) of Incident: 08/29/1947

Description/Reference: One thyroid count was taken on August 29, 1947 after a violent oxalic acid 

chemical reaction in the iodine setup at Building 706-D (SRDB 22959, p. 114; 118330, p. 3). A 30-

minute precipitron run at the work site resulted in measured air activity of 7.72 × 10-11 μCi/cm3

beta/gamma. The two CAMs in the area showed no increase in activity. [SRDB Ref ID: 22959,

118330]

Thyroid count data table

Name

Measurement 

date

Measurement 

time

Time of measurement 

(after intake days)

Measurement result 

(pCi)

Worker 18 08/29/1947 Unknown 0.17 7.2E+05

Intake assessment table 

Name Intake (pCi)

Worker 18 2.0E+07

Start Date(s) of Incident: 11/22/1949

Description/Reference: Four thyroid counts were taken in November 1949 after intermittent high air 

activity throughout the day on 11/22/1949 in Building 706-C. Air activity was suspected to have 

originated from the 131I run in progress. A rise in air activity was noted on the CAMs immediately after

the sparging operation in the cell. Several precipitron samples taken during the day did not reveal 

activity approaching tolerance level, and the activity collected in the precipitron foils decayed rapidly. 

The filter papers on the CAMs had to be replaced constantly to keep the instruments in scale. 

Several CAM filters were auto-radiographed and the result indicated that the activity was diffused 

rather than particulate in nature. [SRDB Ref ID: 104084]

Thyroid count data table

Name

Measurement 

date

Measurement 

time

Time of measurement 

(after intake days)

Measurement result 

(pCi)

Worker 19 11/22/1949 Unknown 0.17 8.1E+05

Worker 20 11/22/1949 Unknown 0.17 4.7E+05

Worker 21 11/22/1949 Unknown 0.17 9.1E+05

Worker 22 11/22/1949 Unknown 0.17 8.9E+05

Intake assessment table

Name Intake (pCi)

Worker 19 2.3E+07

Worker 20 1.3E+07

Worker 21 2.5E+07

Worker 22 2.5E+07
Document No. ORAUT-RPRT-0090 Revision No. 00 Effective Date: 03/29/2018 Page 122 of 133

ATTACHMENT C

DOSE RECONSTRUCTION APPROACH FOR IODINE (continued)

Start Date(s) of Incident: 03/14/1950

Description/Reference: Thyroid counts were taken on workers in the vicinity of the 131I process cell 

during the period of high air activity in 706-C. The air activity became high enough that the building 

was evacuated. The source of the activity was traced to material escaping through opening in the top 

of the 131I process well. The decay and absorption curves indicated that the isotopes were 131I, and 

possibly some 132Te. Thyroid counts were taken on maintenance workers and operators working in 

the vicinity of the cell. [SRDB Ref ID: 104119]

Thyroid count data table

Name

Measurement 

date

Measurement 

time

Time of measurement 

(after intake days)

Measurement result 

(pCi)

Worker 23 03/14/1950 15:30:00 0.21 4.0E+05

Worker 23 03/15/1950 8:30:00 0.92 2.5E+05

Worker 24 03/14/1950 15:30:00 0.21 2.1E+05

Worker 24 03/15/1950 8:30:00 0.92 1.7E+05

Worker 25 03/14/1950 15:30:00 0.21 6.0E+05

Worker 25 03/15/1950 8:30:00 0.92 1.5E+05

Worker 26 03/14/1950 15:30:00 0.21 3.9E+05

Worker 26 03/15/1950 8:30:00 0.92 1.3E+04

Worker 27 03/14/1950 15:30:00 0.21 7.4E+05

Worker 27 03/15/1950 8:30:00 0.92 1.0E+03

Worker 28 03/14/1950 15:30:00 0.21 2.6E+05

Worker 28 03/15/1950 8:30:00 0.92 2.2E+05

Worker 29 03/14/1950 15:30:00 0.21 4.2E+05

Worker 29 03/15/1950 8:30:00 0.92 1.0E+03

Worker 30 03/14/1950 15:30:00 0.21 4.2E+05

Worker 30 03/15/1950 8:30:00 0.92 2.9E+05

Worker 31 03/14/1950 15:30:00 0.21 5.7E+05

Intake assessment table

Name Intake (pCi)

Worker 23 2.4E+06

Worker 24 1.7E+06

Worker 25 1.4E+06

Worker 26 1.2E+05

Worker 27 8.5E+03

Worker 28 2.3E+06

Worker 29 8.5E+03

Worker 30 2.9E+06

Worker 31 2.1E+06

Start Date(s) of Incident: 01/11/1951

Description/Reference: Eight counts were taken on three individuals in January after a contamination 

incident. On January 11, the three employees were performing nitrate analysis on iodide products in 

a laboratory in Building 706-D. When they dissolved sodium iodide in sulfuric acid, free iodide and 

radioactive fumes scattered over the room and one of them became externally contaminated. [SRDB 

Ref ID: 104244]
Document No. ORAUT-RPRT-0090 Revision No. 00 Effective Date: 03/29/2018 Page 123 of 133

ATTACHMENT C

DOSE RECONSTRUCTION APPROACH FOR IODINE (continued)

Thyroid count data table

Name

Measurement 

date

Measurement 

time

Time of measurement 

(after intake days)

Measurement result 

(pCi)

Worker 32 01/11/1951 Unknown 0.17 2.3E+05

Worker 32 01/12/1951 8:00:00 1.00 4.3E+04

Worker 33 01/11/1951 Unknown 0.17 5.3E+05

Worker 33 01/12/1951 9:00:00 1.00 3.5E+05

Worker 34 01/11/1951 Unknown 0.17 6.7E+05

Worker 34 01/11/1951 Unknown 0.17 7.7E+05

Worker 34 01/12/1951 12:00:00 1.00 5.5E+05

Worker 34 01/12/1951 16:00:00 1.00 3.5E+05

Worker 34 01/13/1951 Unknown 2.00 2.7E+04

Intake assessment table

Name Intake (pCi)

Worker 32 3.8E+05

Worker 33 3.3E+06

Worker 34 2.6E+05

Start Date(s) of Incident: 10/24/1951

Description/Reference: A thyroid count was performed on an employee who was working in the 

vicinity of a suspected high airborne fission product release in Building 3026. [SRDB Ref ID: 104405]

Thyroid count data table

Name

Measurement 

date

Measurement 

time

Time of measurement 

(after intake days)

Measurement result 

(pCi)

Worker 35 10/24/1951 Unknown 0.17 2.1E+05

Intake assessment table

Name Intake (pCi)

Worker 35 1.9E+07

Start Date(s) of Incident: 01/28/1952

Description/Reference: Loss of off-gas vacuum at 5:00 p.m. on January 28, 1952 on the 131I setup

resulted in release of airborne activity. The building was evacuated upon CAM alarm. [SRDB Ref ID: 

104471]

Thyroid count data table

Name

Measurement 

date

Measurement 

time

Time of measurement 

(after intake days)

Measurement result 

(pCi)

Worker 36 01/28/1952 21:30:00 0.19 3.6E+06

Worker 36 01/29/1952 21:30:00 1.19 2.0E+06

Worker 36 01/30/1952 16:00:00 1.96 8.7E+05

Worker 37 01/28/1952 21:30:00 0.19 9.0E+05

Worker 37 01/29/1952 21:30:00 1.19 1.6E+05

Worker 38 01/28/1952 21:30:00 0.19 8.3E+05

Worker 38 01/29/1952 21:30:00 1.19 3.7E+05

Intake assessment table

Name Intake (pCi)

Worker 36 9.3E+06

Worker 37 1.4E+06
Document No. ORAUT-RPRT-0090 Revision No. 00 Effective Date: 03/29/2018 Page 124 of 133

ATTACHMENT C

DOSE RECONSTRUCTION APPROACH FOR IODINE (continued)

Name Intake (pCi)

Worker 38 3.4E+06

Start Date(s) of Incident: 04/29/1954

Description/Reference: Fumes boiled over upon the addition of a nitric acid solution to very hot 

(thermally) slugs within the dissolver tank. Highly radioactive fumes set off the monitron and CAMs. 

[SRDB Ref ID: 147059, 147108, 147114, 147210]

Thyroid count data table

Name

Measurement 

date

Measurement 

time

Time of measurement 

(after intake days)

Measurement result 

(pCi)

Worker 39 04/29/1954 Unknown 0.17 3.8E+05

Worker 40 04/29/1954 Unknown 0.17 1.4E+05

Worker 41 04/29/1954 Unknown 0.17 1.0E+03

Worker 42 04/29/1954 Unknown 0.17 1.0E+03

Worker 43 04/29/1954 Unknown 0.17 3.5E+03

Worker 44 04/29/1954 Unknown 0.17 9.8E+04

Worker 45 04/29/1954 Unknown 0.17 1.0E+03

Worker 46 04/29/1954 Unknown 0.17 1.0E+03

Worker 47 04/29/1954 Unknown 0.17 1.7E+05

Worker 48 04/29/1954 Unknown 0.17 8.1E+04

Worker 49 04/29/1954 Unknown 0.17 1.2E+04

Worker 50 04/29/1954 Unknown 0.17 1.0E+03

Worker 51 04/29/1954 Unknown 0.17 3.0E+05

Worker 52 04/29/1954 Unknown 0.17 3.8E+05

Worker 53 04/29/1954 Unknown 0.17 7.2E+04

Worker 54 04/29/1954 Unknown 0.17 1.0E+05

Worker 55 04/29/1954 Unknown 0.17 3.7E+05

Worker 56 04/29/1954 Unknown 0.17 4.2E+05

Worker 57 04/29/1954 Unknown 0.17 4.3E+04

Worker 58 04/29/1954 Unknown 0.17 3.0E+04

Worker 59 04/29/1954 Unknown 0.17 1.0E+03

Worker 60 04/29/1954 Unknown 0.17 7.0E+03

Worker 61 04/29/1954 Unknown 0.17 9.4E+04

Worker 62 04/29/1954 Unknown 0.17 1.0E+05

Worker 63 04/29/1954 Unknown 0.17 6.1E+04

Worker 64 04/29/1954 Unknown 0.17 1.7E+05

Worker 65 04/29/1954 Unknown 0.17 5.7E+04

Intake assessment table

Name Intake (pCi)

Worker 39 1.1E+07

Worker 40 4.0E+06

Worker 41 2.8E+04

Worker 42 2.8E+04

Worker 43 9.8E+04

Worker 44 2.7E+06

Worker 45 2.8E+04

Worker 46 2.8E+04

Worker 47 4.6E+06

Worker 48 2.3E+06

Worker 49 3.2E+05
Document No. ORAUT-RPRT-0090 Revision No. 00 Effective Date: 03/29/2018 Page 125 of 133

ATTACHMENT C

DOSE RECONSTRUCTION APPROACH FOR IODINE (continued)

Name Intake (pCi)

Worker 50 2.8E+04

Worker 51 8.3E+06

Worker 52 1.1E+07

Worker 53 2.0E+06

Worker 54 2.9E+06

Worker 55 1.0E+07

Worker 56 1.2E+07

Worker 57 1.2E+06

Worker 58 8.2E+05

Worker 59 2.8E+04

Worker 60 2.0E+05

Worker 61 2.6E+06

Worker 62 2.9E+06

Worker 63 1.7E+06

Worker 64 4.9E+06

Worker 65 1.6E+06

Start Date(s) of Incident: 10/25/1957

Description/Reference: Pressurization of feed adjustment tank resulted in the release of air activity. 

[SRDB Ref ID: 33238]

Thyroid count data table

Name

Measurement 

date

Measurement 

time

Time of measurement 

(after intake days)

Measurement result 

(pCi)

Worker 66 10/25/1957 Unknown 0.17 1.9E+02

Worker 67 10/25/1957 Unknown 0.17 4.1E+06

Worker 67 10/28/1957 Unknown 3.00 5.4E+05

Worker 67 11/04/1957 Unknown 10.00 2.0E+04

Worker 68 10/28/1957 Unknown 3.00 6.0E+05

Worker 68 11/04/1957 Unknown 10.00 2.7E+04

Worker 69 10/25/1957 Unknown 0.17 8.4E+06

Worker 69 10/28/1957 Unknown 3.00 3.8E+05

Worker 69 11/04/1957 Unknown 10.00 1.6E+04

Worker 70 10/25/1957 Unknown 0.17 6.1E+05

Worker 70 10/28/1957 Unknown 3.00 5.9E+04

Worker 70 11/04/1957 Unknown 10.00 2.0E+04

Worker 71 10/25/1957 Unknown 0.17 3.3E+06

Worker 71 10/28/1957 Unknown 3.00 1.6E+05

Worker 71 11/04/1957 Unknown 10.00 2.9E+04

Worker 72 10/25/1957 Unknown 0.17 7.0E+06

Worker 72 10/28/1957 Unknown 3.00 4.7E+05

Worker 72 11/04/1957 Unknown 10.00 2.7E+04

Intake assessment table

Name Intake (pCi)

Worker 66 5.2E+03

Worker 67 3.8E+05

Worker 68 5.1E+05

Worker 69 3.0E+05

Worker 70 4.1E+05
Document No. ORAUT-RPRT-0090 Revision No. 00 Effective Date: 03/29/2018 Page 126 of 133

ATTACHMENT C

DOSE RECONSTRUCTION APPROACH FOR IODINE (continued)

Name Intake (pCi)

Worker 71 6.1E+05

Worker 72 5.2E+05

C.11 CHRONIC INTAKE ASSESSMENT SUMMARY, 1946 TO 1957

Start Date(s) of Incident: 09/21/1945 

Description/Reference: Nine individual “special probing” thyroid and chest counts taken. These 

workers were all located in 706-D (3026-D: RaLa chemical separation) and worked 9/20/45 on night 

shift. [SRDB Ref ID: 103999]

Bioassay data table

Name Measurement date

Right measurement 

(cpm)

Left measurement 

(cpm)

Derived thyroid 

burden (μCi)

Worker 39 09/21/1945 120 122 0.33

Worker 73 09/21/1945 468 210 1.26

Worker 74 09/21/1945 272 136 0.73

Worker 75 09/21/1945 112 132 0.36

Worker 76 09/21/1945 20 176 0.48

Worker 77 09/21/1945 618 618 1.67

Worker 78 09/21/1945 No data 246 0.66

Worker 79 09/21/1945 0 0 0.0027a

Worker 80 09/21/1945 84 136 0.37

a. De minimus/censored data point.

Start Date(s) of Incident: 12/09/1947 to 12/10/1947

Description/Reference: A report titled 706-D H.P. Report for Week Ending 12-6-47 describes 

decontamination work in Cell A that continued from the prior week. Contamination surveys of Building 

105 took place during this time. The personnel who took part in work were subjected to thyroid 

counting, chest counts, and nasal swipes on December 9 and 10 and worked 9/20/1945. [SRDB Ref 

ID: 22959]

Bioassay data table

Name Measurement date

Right measurement 

(cpm)

Left measurement 

(cpm)

Derived thyroid 

burden (μCi)

309 12/10/1947 0 0 0.0027a

1071 12/10/1947 15 1 0.04

1214 12/09/1947 11 12 0.03

1521 12/09/1947 0 11 0.03

1858 12/09/1947 63 90 0.24

1877 12/10/1947 0 3 0.01

2004 12/09/1947 14 5 0.04

2030 12/09/1947 49 42 0.13

2070 12/10/1947 0 3 0.01

2088 12/10/1947 0 0 0.0027a

2108 12/10/1947 11 16 0.04

2119 12/09/1947 7 22 0.06

2147 12/10/1947 5 25 0.07

2238 12/09/1947 0 0 0.0027a

2286 12/09/1947 27 45 0.12

2411 12/10/1947 15 38 0.10

2417 12/10/1947 3 10 0.03
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ATTACHMENT C

DOSE RECONSTRUCTION APPROACH FOR IODINE (continued)

Name Measurement date

Right measurement 

(cpm)

Left measurement 

(cpm)

Derived thyroid 

burden (μCi)

2420 12/09/1947 0 10 0.03

2436 12/09/1947 15 21 0.06

2520 12/10/1947 12 0 0.03

2745 12/09/1947 12 0 0.03

3772 12/09/1947 66 128 0.35

3783 12/10/1947 19 26 0.07

3941 12/10/1947 0 0 0.0027a

4088 12/10/1947 0 0 0.0027a

4317 12/09/1947 0 7 0.02

4322 12/09/1947 8 2 0.02

4418 12/10/1947 1 1 0.003

4471 12/10/1947 0 5 0.01

4546 12/10/1947 4 3 0.01

4550 12/10/1947 10 0 0.03

4575 12/10/1947 6 4 0.02

4729 12/10/1947 20 16 0.05

4731 12/10/1947 0 0 0.0027a

4922 12/10/1947 13 0 0.04

5886 12/10/1947 30 74 0.20

6199 12/09/1947 0 0 0.0027a

6218 12/10/1947 0 0 0.0027a

6318 12/10/1947 0 4 0.01

6410 12/09/1947 0 0 0.0027a

6441 12/09/1947 11 0 0.03

6454 12/09/1947 4 5 0.01

6456 12/09/1947 0 0 0.0027a

6522 12/10/1947 0 0 0.0027a

6635 12/09/1947 490 300 1.32

6720 12/10/1947 9 5 0.02

6846 12/09/1947 2 15 0.04

6866 12/09/1947 0 3 0.01

6974 12/09/1947 97 61 0.26

8060 12/09/1947 102 35 0.28

8080 12/09/1947 14 8 0.04

8103 12/09/1947 3 9 0.02

8111 12/10/1947 24 30 0.08

8254 12/10/1947 8 32 0.09

a. De minimus/censored data point.

Start Date(s) of Incident: 09/27/1948 to 10/22/1948

Description/Reference: Six workers were selected for repeat counts in September and October 1948. 

Work locations and reasons for the counts were not given. Each worker was scheduled for six 

separate counts for a total of 36 counts, but some workers did not report for later repeat counts, 

resulting in 31 thyroid counts. [SRDB Ref ID: 110152]

Bioassay data table

Name Measurement date

Right measurement 

(cpm)

Left measurement 

(cpm)

Derived thyroid 

burden (μCi)

Worker 81 09/28/1948 25 BKG 0.068

Worker 81 09/30/1948 BKG BKG 0.068
Document No. ORAUT-RPRT-0090 Revision No. 00 Effective Date: 03/29/2018 Page 128 of 133

ATTACHMENT C

DOSE RECONSTRUCTION APPROACH FOR IODINE (continued)

Name Measurement date

Right measurement 

(cpm)

Left measurement 

(cpm)

Derived thyroid 

burden (μCi)

Worker 81 10/04/1948 5 BKG 0.068

Worker 81 10/08/1948 22 12 0.068

Worker 81 10/18/1948 3 BKG 0.068

Worker 82 09/27/1948 BKG BKG 0.089

Worker 82 10/01/1948 10 18 0.089

Worker 82 10/04/1948 6 12 0.089

Worker 82 10/06/1948 15 15 0.089

Worker 82 10/18/1948 BKG 33 0.089

Worker 82 10/21/1948 BKG 16 0.089

Worker 83 09/27/1948 15 9 0.078

Worker 83 09/30/1948 13 20 0.078

Worker 83 10/04/1948 11 29 0.078

Worker 83 10/18/1948 13 9 0.078

Worker 83 10/22/1948 10 23 0.078

Worker 84 09/29/1948 BKG 20 0.105

Worker 84 09/30/1948 18 BKG 0.105

Worker 84 10/05/1948 20 21 0.105

Worker 84 10/08/1948 23 39 0.105

Worker 84 10/18/1948 7 BKG 0.105

Worker 85 09/27/1948 BKG BKG 0.059

Worker 85 09/30/1948 5 2 0.059

Worker 85 10/04/1948 15 BKG 0.059

Worker 85 10/08/1948 18 22 0.059

Worker 85 10/18/1948 BKG 14 0.059

Worker 86 09/27/1948 BKG BKG 0.100

Worker 86 09/30/1948 25 11 0.100

Worker 86 10/04/1948 37 16 0.100

Worker 86 10/08/1948 12 6 0.100

Worker 86 10/18/1948 11 17 0.100

Start Date(s) of Incident: 04/18/1949 to 04/22/1949

Description/Reference: Six workers at Building 706-D were repeatedly thyroid-counted from April 15 

through 22, 1949. These workers were involved in Product Run #88. The thyroid counts taken from 

April 15 to 17 are not included in the co-worker study because the product run was not fully underway 

until April 18. [SRDB Ref ID: 119713]

Bioassay data table

Name Measurement date

Right measurement 

(cpm)

Left measurement 

(cpm)

Derived thyroid 

burden (μCi)

Worker 87 04/21/1949 0 9 0.024

Worker 88 04/18/1949 9 14 0.038

Worker 89 04/19/1949 16 81 0.219

Worker 89 04/20/1949 9 0 0.219

Worker 89 04/21/1949 0 0 0.219

Worker 90 04/18/1949 3 7 0.149

Worker 90 04/19/1949 55 5 0.149

Worker 90 04/20/1949 29 27 0.149

Worker 90 04/22/1949 48 17 0.149

Worker 38 04/18/1949 37 30 0.497

Worker 38 04/19/1949 184 142 0.497
Document No. ORAUT-RPRT-0090 Revision No. 00 Effective Date: 03/29/2018 Page 129 of 133

ATTACHMENT C

DOSE RECONSTRUCTION APPROACH FOR IODINE (continued)

Name Measurement date

Right measurement 

(cpm)

Left measurement 

(cpm)

Derived thyroid 

burden (μCi)

Worker 38 04/20/1949 120 140 0.497

Worker 38 04/21/1949 14 8 0.497

Worker 38 04/22/1949 111 87 0.497

Worker 91 04/18/1949 23 10 0.251

Worker 91 04/19/1949 77 73 0.251

Worker 91 04/20/1949 36 28 0.251

Worker 91 04/21/1949 54 93 0.251

Worker 91 04/22/1949 0 16 0.251

Worker 92 04/18/1949 2 12 0.032

Worker 92 04/19/1949 0 0 0.032

Worker 92 04/22/1949 0 0 0.032

C.12 ACUTE INTAKE ASSESSMENT SUMMARY, 1962 TO 1969

Start Date(s) of Incident: 9/21/1962

Description/Reference: An event report for a 3/16/1965 exposure described this as a similar event 

involving Worker 93. [NOCTS ID: DOE_Response_ personal ID redacted _D203, p. 549]

Bioassay data table

Name Type

Measurement 

date

Measurement 

time

Time of measurement 

(after intake days)

Measurement result 

(pCi/24 hr)a

Worker 93 Urine 09/21/1962 02:30 p.m. 0.16 1.9E+05

Worker 93 Urine 09/21/1962 08:00 p.m. 0.39 1.1E+05

Worker 93 Urine 09/22/1962 08:00 a.m. 0.89 1.6E+04

Worker 93 Urine 09/22/1962 08:00 p.m. 1.39 6.1E+03

Worker 93 Urine 09/23/1962 08:00 a.m. 1.89 2.6E+03

Worker 93 Urine 09/23/1962 08:00 p.m. 2.39 1.4E+03

Worker 93 Urine 09/24/1962 06:00 a.m. 2.80 8.9E+02

Worker 93 Urine 09/24/1962 06:00 p.m. 3.80 2.4E+02

a. Urine results are normalized to pCi/24 hr.

Intake assessment table

Name Intake (pCi)

Worker 93 5.7E4

Start Date(s) of Incident: 12/11/1963

Description/Reference: Personnel contamination in Cell II. On 12/11/1963 at about 2:45 p.m., 

Worker 94 [NOCTS ID: redacted] and Worker 95 [NOCTS ID: redacted] were cleaning a spill. There 

was no indication of release from the continuous air monitor in the cell. Investigation was based on 

personnel contamination detected on exit. [NOCTS ID: DOE_Response_personal ID 

redacted_D203, p. 243]

Bioassay data table

Name Type

Measurement 

date

Measurement 

time

Time of measurement 

(after intake days)

Measurement result 

(pCi/24 hr)a

Worker 94 WBC 12/12/1963 10:00 a.m. 0.8 2.0E+03

Worker 95 WBC 12/12/1963 10:00 a.m. 0.8 No data

a. WBC results were recorded as pCi.
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ATTACHMENT C

DOSE RECONSTRUCTION APPROACH FOR IODINE (continued)

Intake assessment table

Name Intake (pCi)

Worker 94 7.33E3

Start Date(s) of Incident: 03/16/1965

Description/Reference: CAM alarm during decontamination of shipping insert that was contaminated 

with 131I. Worker 79 (iodine worker files), Worker 96 (iodine worker files), Worker 84 [NOCTS ID: 

redacted], Worker 98, and Worker 97 [NOCTS ID: redacted] in area during activity when CAM 

alarmed on high scale at 12:30 p.m. [NOCTS ID: DOE_Response_personal ID redacted_D203, p. 

549]

Bioassay data table

Name Type

Measurement 

date

Measurement 

time

Time of measurement 

(after intake days)

Measurement result 

(pCi/24 hr)a

Worker 96 Urine 03/16/1965 Unknown 0.12 3.5E+05

Worker 96 Urine 03/17/1965 10:00 a.m. 0.90 2.4E+05

Worker 96 Urine 03/28/1965 06:00 p.m. 12.23 1.7E+02

Worker 96 WBC 03/16/1965 03:31 p.m. 0.13 1.1E+06

Worker 96 WBC 03/19/1965 09:41 a.m. 2.88 5.4E+04

Worker 84 Urine 03/16/1965 Unknown 0.10 1.1E+05

Worker 84 Urine 03/17/1965 10:00 a.m. 0.90 8.6E+04

Worker 84 Urine 03/29/1965 10:00 a.m. 12.90 5.9E+01

Worker 84 WBC 03/16/1965 02:44 p.m. 0.09 5.8E+05

Worker 84 WBC 03/19/1965 10:40 a.m. 2.92 2.8E+04

Worker 79 Urine 03/16/1965 Unknown 0.08 2.9E+05

Worker 79 Urine 03/17/1965 11:00 a.m. 0.94 1.4E+05

Worker 79 Urine 03/27/1965 08:30 a.m. 10.83 5.0E+02

Worker 79 WBC 03/16/1965 02:20 p.m. 0.08 4.8E+05

Worker 79 WBC 03/19/1965 10:13 a.m. 2.90 5.0E+04

Worker 97 Urine 03/16/1965 Unknown 0.06 7.1E+04

Worker 97 Urine 03/17/1965 10:00 a.m. 0.90 2.2E+04

Worker 97 Urine 03/28/1965 06:30 p.m. 12.25 2.3E+02

Worker 97 WBC 03/16/1965 02:09 p.m. 0.11 1.3E+05

Worker 98 Urine 03/16/1965 Unknown 0.13 3.0E+05

Worker 98 Urine 03/17/1965 Unknown 0.9 1.3E+05

Worker 98 Urine 03/28/1965 Unknown 11.9 2.0E+02

Worker 98 WBC 03/16/1965 Unknown 0.06 9.1E+05

a. Urine results are normalized to pCi/24 hr; WBC results were recorded as pCi.

Intake assessment table

Name Intake (pCi)

Worker 96 6.3E5

Worker 84 3.1E5

Worker 79 4.9E5

Worker 97 1.0E5

Worker 98 6.9E5

Start Date(s) of Incident: 12/17/1965

Description/Reference: A bottle containing 1 Ci of 131I was dropped by Worker 100 [NOCTS ID: 

redacted] while performing measurements. Worker 99 (ORNL iodine worker file), Worker 103, Worker 

102, and [worker name redacted] were working in the adjacent room. Initial thyroid scan for Worker 
Document No. ORAUT-RPRT-0090 Revision No. 00 Effective Date: 03/29/2018 Page 131 of 133

ATTACHMENT C

DOSE RECONSTRUCTION APPROACH FOR IODINE (continued)

100 indicated 0.2 mR/hr. Whole-body scans indicated intakes of 170 nCi and 100 nCi for Worker 103 

and Worker 99, respectively.

Bioassay data table

Name Type

Measurement 

date

Measurement 

time

Time of measurement 

(after intake days)

Measurement result 

(pCi/24 hr)a

Worker 99 Urine 12/18/1965 12:45 p.m. 0.69 6.3E+04

Worker 99 Urine 12/23/1965 6:15 a.m. 1.71 9.5E+02

Worker 99 WBC 12/22/1965 9:05 a.m. 0.17 5.3E+04

Worker 100 Urine 12/19/1965 9:00 a.m. 0.78 2.8E+03

Worker 101 Urine 12/18/1965 9:00 a.m. 1.82 3.2E+03

Worker 102 Urine 12/20/1965 7:15 a.m. 7.73 9.5E+02

Worker 103 Urine 12/18/1965 4:00 p.m. 1.22 3.6E+04

Worker 103 Urine 12/23/1965 6:00 a.m. 5.80 7.2E+02

Worker 103 Fecal 12/18/1965 Unknown Unknown 9.9E+01

a. Urine results are normalized to pCi/24 hr; WBC results were recorded as pCi.

Intake assessment table

Name Intake (pCi)

Worker 99 2.9E+05

Worker 100 7.4E+04

Worker 101 1.2E+04

Worker 102 3.3E+05

Worker 103 1.7E+05

Start Date(s) of Incident: 06/21/1967

Description/Reference: While disassembling 131I-contaminated equipment on 6/21/1967, two 

individuals became contaminated at 4:15 p.m. Individuals involved were Worker 104 [NOCTS ID: 

redacted] and Worker 105 [NOCTS ID: redacted]. Both individuals were administered KI at 7:00 p.m.

Bioassay data table 

Name Type

Measurement 

date

Measurement 

time

Time of measurement 

(after intake days)

Measurement result 

(pCi/24 hr)a

Worker 104 Urine 06/22/1967 8:45 a.m. 0.69 7.7E+06

Worker 104 Urine 06/23/1967 9:15 a.m. 1.71 1.2E+06

Worker 104 Urine 06/23/1967 4:00 p.m. 1.99 1.3E+05

Worker 104 Urine 07/12/1967 2:00 p.m. 20.91 3.2E+02

Worker 104 Urine 07/20/1967 1:00 p.m. 28.86 4.2E+02

Worker 104 WBC 06/21/1967 8:15 p.m. 0.17 6.9E+06

Worker 104 WBC 06/22/1967 10:54 a.m. 0.78 2.7E+06

Worker 104 WBC 06/23/1967 12:00 p.m. 1.82 1.6E+06

Worker 104 WBC 06/29/1967 9:46 a.m. 7.73 6.0E+05

Worker 104 WBC 07/07/1967 10:35 a.m. 15.76 1.4E+05

Worker 104 WBC 07/27/1967 1:03 p.m. 35.87 2.3E+04

Worker 104 Thy 06/21/1967 8:55 p.m. 0.19 4.3E+05

Worker 104 Thy 06/22/1967 11:25 a.m. 0.80 2.4E+05

Worker 104 Thy 06/23/1967 11:17 a.m. 1.79 2.2E+05

Worker 104 Thy 06/29/1967 9:36 a.m. 7.72 1.2E+05

Worker 104 Thy 07/07/1967 10:15 a.m. 15.75 4.6E+04

Worker 104 Thy 07/27/1967 1:30 p.m. 35.89 8.9E+03

Worker 105 Urine 06/22/1967 7:00 a.m. 0.61 2.2E+07

Worker 105 Urine 06/23/1967 7:00 a.m. 1.61 2.2E+06
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ATTACHMENT C

DOSE RECONSTRUCTION APPROACH FOR IODINE (continued)

Name Type

Measurement 

date

Measurement 

time

Time of measurement 

(after intake days)

Measurement result 

(pCi/24 hr)a

Worker 105 Urine 06/23/1967 4:00 p.m. 1.99 1.4E+06

Worker 105 Urine 07/12/1967 1:30 p.m. 20.89 7.2E+02

Worker 105 Urine 07/20/1967 4:30 p.m. 29.01 5.9E+02

Worker 105 WBC 06/21/1967 8:23 p.m. 0.17 1.3E+07

Worker 105 WBC 06/22/1967 12:20 p.m. 0.84 5.8E+06

Worker 105 WBC 06/23/1967 10:20 a.m. 1.75 3.2E+06

Worker 105 WBC 06/29/1967 10:50 a.m. 7.77 1.1E+06

Worker 105 WBC 07/07/1967 11:32 a.m. 15.80 4.7E+05

Worker 105 WBC 07/27/1967 2:25 p.m. 35.92 Unknown

Worker 105 Thy 06/21/1967 8:15 p.m. 0.17 1.5E+06

Worker 105 Thy 06/22/1967 12:00 p.m. 0.82 9.0E+05

Worker 105 Thy 06/23/1967 10:59 a.m. 1.78 8.6E+05

Worker 105 Thy 06/29/1967 10:40 a.m. 7.77 5.0E+05

Worker 105 Thy 07/07/1967 11:52 a.m. 15.82 2.2E+05

Worker 105 Thy 07/27/1967 2:09 p.m. 35.91 Unknown

a. Urine results are normalized to pCi/24 hr; WBC and thyroid results are pCi.

Intake assessment table

Name Intake (pCi)

Worker 104 9.7E6

Worker 105 1.8E7

Start Date(s) of Incident: 01/17/1969

Description/Reference: Airborne release while unloading a thermally heated sample carrier on 

01/17/1969 at 9:45 a.m. Individuals present were Worker 106 (iodine worker files), Worker 107 

(iodine worker files), Worker 108 [NOCTS ID: redacted], [name redacted], [name redacted], and 

[name redacted].

Bioassay data table

Name Type

Measurement 

date

Measurement 

time

Time of measurement 

(after intake days)

Measurement result 

(pCi/24 hr)a

Worker 106 Urine 01/20/1969 6:30 a.m. 2.86 3.1E+03

Worker 106 Urine 01/31/1969 Unknown Unknown 0

Worker 106 WBC 01/17/1969 12:49 p.m. 0.13 1.3E+05

Worker 106 WBC 01/20/1969 12:10 p.m. 3.10 3.6E+04

Worker 107 Urine 01/19/1969 6:00 p.m. 2.34 2.0E+03

Worker 107 Urine 01/30/1969 8:00 p.m. 13.43 4.3E+01

Worker 107 WBC 01/17/1969 2:41 p.m. 0.21 2.7E+04

Worker 108 Urine 01/20/1969 8:00 a.m. 2.93 9.0E+02

Worker 108 Urine 01/30/1969 4:00 p.m. 13.26 5.9E+01

Worker 108 WBC 01/17/1969 2:15 p.m. 0.19 1.8E+04

a. Urine results are normalized to pCi/24 hr; WBC results were recorded as pCi.

Intake assessment table

Name Intake (pCi)

Worker 106 2.2E5

Worker 107 5.2E4

Worker 108 2.9E4
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ATTACHMENT C

DOSE RECONSTRUCTION APPROACH FOR IODINE (continued)

Start Date(s) of Incident: 05/06/1969

Description/Reference: Airborne release occurred at 11:15 a.m. on 5/6/1969 while performing a filter

performance test using 131I. Individual involved was Worker 109 [NOCTS ID: redacted].

Bioassay data table

Name Type

Measurement 

date

Measurement 

time

Time of measurement 

(after intake days)

Measurement result 

(pCi/24 hr)a

Worker 109 Urine 05/07/1969 6:00 a.m. 0.78 1.7E+02

a. Urine results are normalized to pCi/24 hr.

Intake assessment table

Name Intake (pCi)

Worker 109 6.9E2

Start Date(s) of Incident: 09/26/1969

Description/Reference: Worker 110 [NOCTS ID: redacted] became contaminated while 

decontaminating manipulator tongs at 3:30 p.m. on 9/26/1969.

Bioassay data table

Name Type

Measuremen

t date

Measurement 

time

Time of measurement 

(after intake days)

Measurement result 

(pCi/24 hr)a

Worker 110 WBC 09/26/1969 05:37 p.m. .09 3.6E+04

Worker 110 Lung 10/01/1969 08:55 a.m. 4.73 5.0E+3b

a. WBC results were recorded as pCi.

b. Lung count data not used in assessment.

Intake assessment table

Name Intake (pCi)

Worker 110 4.7E4