Page 1 of 35

DOE Review Release 08/26/2020

Internal Dosimetry Co-Exposure Data for Oak 

Ridge National Laboratory

ORAUT-OTIB-0034 Rev. 04

Effective Date: 09/01/2020

Supersedes: Revision 03

Subject Expert(s): Matthew G. Arno

Document Owner 

Approval: Signature on File

Matthew G. Arno, Document Owner

Approval Date: 03/30/2020

Concurrence: Signature on File

John M. Byrne, Objective 1 Manager

Concurrence Date: 04/01/2020

Concurrence: Signature on File

Scott R. Siebert, Objective 3 Manager

Concurrence Date: 03/30/2020

Concurrence: Vickie S. Short Signature on File for

Kate Kimpan, Project Director

Concurrence Date: 03/30/2020

Approval: Signature on File

Timothy D. Taulbee, Associate Director for Science

Approval Date: 08/05/2020

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
Document No. ORAUT-OTIB-0034 Revision No. 04 Effective Date: 09/01/2020 Page 2 of 35

 

PUBLICATION RECORD

EFFECTIVE 

DATE

REVISION 

NUMBER DESCRIPTION

12/13/2005 00 New technical information bulletin for assignment of X-10 internal 

doses based on coworker bioassay data. First approved issue.

Training required: As determined by the Task Manager. Initiated by 

William E. Kennedy, Jr.

04/23/2013 01 Plutonium modeling updated to include best estimate intakes for type

S material. 95th-percentile intakes added for all nuclides. Attachment 

A data tables expanded to include information on the number of 

samples and employees used in the statistical analysis. Incorporates 

formal internal review comments. No changes occurred as a result of 

formal NIOSH review. Training required: As determined by the 

Objective Manager. Initiated by Matthew G. Arno.

01/21/2014 02 Revision to modify Sections 4.3.5, 5.1, and 5.2 to reference OTIB0054 rather than provide fission products ratios based on 

environmental monitoring records. Clarification added that type S 

strontium should only be applied if exposure to strontium titanate is 

assumed. In addition, guidance on when to assign the 95thpercentile intake rates was added. Incorporates formal internal and 

NIOSH review comments. Training required: As determined by the 

Objective Manager. Initiated by Matthew G. Arno.

05/05/2014 03 Revision initiated to remove the inclusion of the Pilot Plant in Section 

4.3.5 and Section 5.2, first bullet. Updated references. Incorporates 

formal internal and NIOSH review comments. Training required: As 

determined by the Objective Manager. Initiated by Matthew G. Arno.

09/01/2020 04 Revision initiated to include adding the potential and intake rates for 

type SS plutonium. Incorporates formal internal and NIOSH review 

comments. Constitutes a total rewrite of the document. Training 

required: As determined by the Objective Manager. Initiated by 

Matthew G. Arno.
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TABLE OF CONTENTS

SECTION TITLE PAGE

Acronyms and Abbreviations ............................................................................................................... 6

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

2.0 Purpose ................................................................................................................................... 7

3.0 Overview.................................................................................................................................. 7

4.0 Data ......................................................................................................................................... 8

4.1 Selected Bioassay Data................................................................................................ 8

4.2 Analysis........................................................................................................................ 8

5.0 Intake Modeling........................................................................................................................ 8

5.1 Assumptions................................................................................................................. 8

5.2 Bioassay Fitting ............................................................................................................ 8

5.3 Radionuclides and Material Types................................................................................ 9

5.3.1 Strontium-90 .................................................................................................. 9

5.3.2 Uranium ......................................................................................................... 9

5.3.3 Plutonium..................................................................................................... 10

5.3.4 Americium-241............................................................................................. 10

5.3.5 Additional Radionuclides .............................................................................. 11

6.0 Assignment of Intakes and Doses .......................................................................................... 11

6.1 Contribution from Additional Radionuclides ................................................................ 13

6.2 Dose Assignment ....................................................................................................... 13

References ........................................................................................................................................ 14

ATTACHMENT A STATISTICAL ANALYSIS RESULTS FOR STRONTIUM, URANIUM, 

PLUTONIUM, AND AMERICIUM .................................................................... 15

LIST OF TABLES

TABLE TITLE PAGE

6-1 Combined 90Sr type F intake periods and rates ...................................................................... 11

6-2 Combined 90Sr type S intake periods and rates...................................................................... 11

6-3 Annual 234U type F intake periods and rates........................................................................... 12

6-4 Annual 234U type M intake periods and rates .......................................................................... 12

6-5 Annual 234U type S intake periods and rates........................................................................... 12

6-6 Annual 239Pu type M intake periods and rates ........................................................................ 12

6-7 Annual 239Pu type S intake periods and rates......................................................................... 12

6-8 Annual 239Pu type SS intake periods and rates....................................................................... 13

6-9 Americium-241 type M intake periods and rates..................................................................... 13

A-1 Statistical summary of annual strontium 24-hour urinary excretion rates, 1951 to 1988 ......... 17

A-2 Statistical summary of annual uranium 24-hour urinary excretion rates, 1951 to 1987 ........... 18

A-3 Statistical summary of annual plutonium 24-hour urinary excretion rates, 1951 to 1988......... 19
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A-4 Statistical summary of annual americium 24-hour urinary excretion rates, 1968 to 1987........ 20

A-5 Type F 90Sr intake periods and rates...................................................................................... 20

A-6 Type S 90Sr intake periods and rates...................................................................................... 21

A-7 Type F uranium intake periods and rates ............................................................................... 23

A-8 Type M uranium intake periods and rates .............................................................................. 24

A-9 Type S uranium intake periods and rates ............................................................................... 25

A-10 Type M plutonium intake periods and rates............................................................................ 28

A-11 Type S plutonium intake periods and rates ............................................................................ 30

A-12 Type SS plutonium intake periods and rates .......................................................................... 32

A-13 Type M 241Am intake periods and rates .................................................................................. 34

LIST OF FIGURES

FIGURE TITLE PAGE

A-1 Assumed 90Sr intake, 1951 to 1988, 50th-percentile results, type F ....................................... 21

A-2 Assumed 90Sr intake, 1951 to 1953, 50th-percentile results, type S ....................................... 21

A-3 Assumed 90Sr intake, 1954, 50th-percentile results, type S.................................................... 22

A-4 Assumed 90Sr intake, 1955 to 1964, 50th-percentile results, type S ....................................... 22

A-5 Assumed 90Sr intake, 1965 to 1983, 50th-percentile results, type S ....................................... 22

A-6 Assumed 90Sr intake, 1983 to 1988, 50th-percentile results, type S ....................................... 23

A-7 Predicted cumulative 90Sr excretion rate from independently fit intakes, 1951 to 1988, 

50th-percentile results, type S................................................................................................ 23

A-8 Assumed uranium intake, 1951 to 1987, 50th-percentile results, type F................................. 24

A-9 Assumed uranium intake, 1951 to 1987, 50th-percentile results, type M................................ 24

A-10 Assumed uranium intake, 1951 to 1955, 50th-percentile results, type S................................. 25

A-11 Assumed uranium intake, 1956, 50th-percentile results, type S ............................................. 25

A-12 Assumed uranium intake, 1957 to 1958, 50th-percentile results, type S................................. 26

A-13 Assumed uranium intake, 1959 to 1961, 50th-percentile results, type S................................. 26

A-14 Assumed uranium intake, 1962 to 1963, 50th-percentile results, type S................................. 27

A-15 Assumed uranium intake, 1964 to 1982, 50th-percentile results, type S................................. 27

A-16 Assumed uranium intake, 1983 to 1987, 50th-percentile results, type S................................. 28

A-17 Predicted cumulative uranium excretion rate from independently fit intakes, 1951 to 

1987, 50th-percentile, type S ................................................................................................. 28

A-18 Assumed plutonium intake, 1951 to 1952, 50th-percentile results, type M ............................. 29

A-19 Assumed plutonium intake, 1953 to 1968, 50th-percentile results, type M ............................. 29

A-20 Assumed plutonium intake, 1969 to 1984, 50th-percentile results, type M ............................. 29

A-21 Assumed plutonium intake, 1985 to 1988, 50th-percentile results, type M ............................. 30

A-22 Predicted cumulative plutonium intake, 1951 to 1988, 50th-percentile composite results, 

type M....................................................................................................................................30

A-23 Assumed plutonium intake, 1951 to 1952, 50th-percentile results, type S.............................. 31

A-24 Assumed plutonium intake, 1953 to 1968, 50th-percentile results, type S .............................. 31

A-25 Assumed plutonium intake, 1969 to 1984, 50th-percentile results, type S.............................. 31

A-26 Assumed plutonium intake, 1985 to 1988, 50th-percentile results, type S.............................. 32

A-27 Predicted cumulative plutonium intake, 1951 to 1988, 50th-percentile composite results, 

type S.....................................................................................................................................32

A-28 Assumed plutonium intake, 1951 to 1952, 50th-percentile results, type SS............................ 33

A-29 Assumed plutonium intake, 1953 to 1968, 50th-percentile results, type SS............................ 33

A-30 Assumed plutonium intake, 1969 to 1984, 50th-percentile results, type SS............................ 33

A-31 Assumed plutonium intake, 1985 to 1988, 50th-percentile results, type SS............................ 34

A-32 Predicted cumulative plutonium intake, 1951 to 1988, 50th-percentile composite results, 

type SS ..................................................................................................................................34
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A-33 Assumed 241Am intake, 1968 to 1984, 50th-percentile results, type M.................................... 35

A-34 Assumed 241Am intake, 1985 to 1988, 50th-percentile results, type M.................................... 35

A-35 Predicted cumulative 241Am intake, 1968 to 1988, 50th-percentile composite results, type 

M ............................................................................................................................................35
Document No. ORAUT-OTIB-0034 Revision No. 04 Effective Date: 09/01/2020 Page 6 of 35

ACRONYMS AND ABBREVIATIONS

CER Center for Epidemiologic Research

d day

DOE U.S. Department of Energy

dpm disintegrations per minute

EDP Electronic Data Processing

F fast (absorption type)

GM geometric mean

GSD geometric standard deviation

hr hour 

ICRP International Commission on Radiological Protection

IDOT Internal Dosimetry Tool

IMBA Integrated Modules for Bioassay Analysis

IREP Interactive RadioEpidemiological Program

m meter

M moderate (absorption type)

NIOSH National Institute for Occupational Safety and Health

ORAU Oak Ridge Associated Universities

ORISE Oak Ridge Institute for Science and Education

ORNL Oak Ridge National Laboratory

S slow (absorption type)

SRDB Ref ID Site Research Database Reference Identification (number)

SS super slow (absorption type)

TIB technical information bulletin

USC United States Code

μm micrometer
Document No. ORAUT-OTIB-0034 Revision No. 04 Effective Date: 09/01/2020 Page 7 of 35

1.0 INTRODUCTION

Technical information bulletins (TIBs) are not official determinations made by the National Institute for 

Occupational Safety and Health (NIOSH) but are rather general working documents that provide 

historical background information and guidance to assist in the preparation of dose reconstructions at 

particular sites or categories of sites. They will be revised in the event additional relevant information 

is obtained about the affected site(s). TIBs may be used to assist NIOSH staff in the completion of 

individual dose reconstructions.

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

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

employer facility” or a “Department of Energy (DOE) facility” as defined in the Energy Employees 

Occupational Illness Compensation Program Act of 2000 [42 United States Code (USC) 7384l(5) 

and (12)].

2.0 PURPOSE

There are instances of energy employees who, for a variety of reasons, were not monitored for 

internal exposure during the course of their employment at a DOE facility, or for whom records of such 

monitoring are incomplete or unavailable. In these cases, monitoring data from other workers with 

similar exposure potential can be used to approximate another individual’s possible exposure using a 

co-exposure study. The purpose of this TIB is to provide the details of the calculation and assignment 

of co-exposure intakes based on data from workers with similar exposure potential from Oak Ridge 

National Laboratory (ORNL, formerly known as X-10) for estimation of unmonitored exposures or if 

records of monitoring are incomplete or unavailable, whether for discrete periods or for the entire 

period of employment.

3.0 OVERVIEW

ORAUT-OTIB-0019, Analysis of Coworker Bioassay Data for Internal Dose Assignment, describes the 

general process used for analyzing bioassay data for assigning doses to individuals based on results

from workers with similar exposure potential [ORAUT 2005].

Bioassay results for ORNL were obtained from the Oak Ridge Institute for Science and Education 

(ORISE) Center for Epidemiologic Research (CER) Dosimetry Database, which contains urinalysis 

records from the ORNL site for 1951 to 1988. ORISE obtained this database from ORNL to conduct

an epidemiology study of site workers. The database results are in units of disintegrations per minute 

per 24 hours. Because of the varied operations at the different ORNL facilities over time, the database 

contains urinalysis data for numerous radionuclides. These data are stored using Electronic Data 

Processing (EDP) codes, as documented in Section 5.2.4.2 of ORAUT-TKBS-0012-5, Oak Ridge 

National Laboratory – Occupational Internal Dose [ORAUT 2013].

In summary, data were stored under 64 EDP codes and included measurements for five radioisotopes 

of uranium, four radioisotopes of plutonium, seven other transuranic radionuclides, numerous fission 

and activation products, and gross alpha and gross beta measurements. The majority of the EDP 

codes contained fewer than 100 data entries. In reviewing these data, it was determined that only a 

few EDP codes contained enough entries to allow statistical evaluation for dose reconstruction. These 

were:

• SR and SR0 for 90Sr (12,893 entries from 1951 to 1988); 

• UR0 and UR for total uranium (11,434 entries from 1951 to 1988); 

• PU0, PU9, PU, GA0, and GU0 for plutonium alpha emitters (15,476 entries from 1951 to 

1988); and 
Document No. ORAUT-OTIB-0034 Revision No. 04 Effective Date: 09/01/2020 Page 8 of 35

• TP0 and TP for transplutonium radionuclides, primarily 241Am (5,670 entries from 1968 to 

1987).

GA0 and GU0 (gross alpha) results are treated as plutonium results as indicated in Table 5-6 of 

ORAUT [2013]. Transplutonium radionuclides were assumed to be and modeled as 241Am for this 

co-exposure study.

Further review of these data indicated that, except for followup for accidental exposures, they were 

collected on an annual sampling basis; therefore, the analysis that follows considers chronic 

exposures to estimate annual intakes. A statistical analysis of these data was performed in 

accordance with ORAUT-OTIB-0019 [ORAUT 2005]. The resultant values were input to the Integrated 

Modules for Bioassay Analysis (IMBA) computer program, and a fit to the data for each of the four 

radionuclides was performed to obtain intake rates for assigning dose distributions.

4.0 DATA

4.1 SELECTED BIOASSAY DATA

Data for each of the evaluated EDP codes were extracted from a series of database files that contain 

a version of the CER Dosimetry Database. These files were titled “tblORNL_Urinalysis_rawData,” for 

1951–1978, 1979–1985, and 1986–1988.

4.2 ANALYSIS

A lognormal distribution for the annual data for each of the four radionuclides was assumed and the 

50th and 84th percentiles were calculated using the method described in ORAUT-OTIB-0019 [ORAUT 

2005]. The strontium data for 1951 through 1953 were combined due to the small amount of data 

available in those years. Tables A-1 through A-4 in Attachment A show the statistical analysis results 

for strontium, uranium, plutonium, and americium, respectively.

5.0 INTAKE MODELING

5.1 ASSUMPTIONS

All results were assumed to be representative of a full day (24 hours) of urinary excretion. Each result 

used in the intake calculation was assumed to be normally distributed, and a uniform absolute error of 

1 was applied to all results to weight all results equally. A chronic exposure pattern was assumed; 

while this is unlikely for workers at ORNL, it approximates a series of acute intakes with unknown 

intake dates. Intakes were assumed to be via inhalation using a default breathing rate of 1.2 m3

/hr and 

a 5-μm activity median aerodynamic diameter particle size distribution.

5.2 BIOASSAY FITTING

IMBA and the Internal Dosimetry Tool (IDOT) software were used to fit the bioassay results to a series 

of inhalation intakes. Data for each radionuclide were fit as a series of chronic intakes.

Because type S strontium; type S uranium; types M, S, and SS plutonium isotopes; and type M 

americium isotopes at ORNL have very long half-lives and because the material is retained in the 

body for long periods, excretion results are not independent. For example, an intake in the early 

1950s could contribute to urinary excretion in the 1980s and later. To avoid potential underestimation 

of intakes for people who worked at ORNL for relatively short periods, each intake was fit 

independently using only the bioassay results from the single intake period. This results in an 
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overestimate of intakes, particularly for assumed type SS or S exposures extending through multiple 

assumed intake periods.

5.3 RADIONUCLIDES AND MATERIAL TYPES

For each radionuclide, the bioassay results were entered into IMBA and/or IDOT with assumed 

material types as discussed in more detail in the following sections. The assumed 50th-percentile 

intakes that resulted are shown in the figures in Attachment A. In these figures, annual bioassay data 

used in the fits are shown as dark dots (●), and data that are not used in the fits are shown as lighter 

dots (●). For certain radionuclides and material types, it is necessary to show figures for both the 

composite intake over the entire data period and the individual plots of subsets of selected groups of 

years during the data period that were used to develop the composite figure. The composite plot 

shows the merged fit for all intake periods to the bioassay data. The IMBA output figures in 

Attachment A show the fit to the bioassay data for each annual intake period in terms of days after the 

date of initial data reporting. For example, for 90Sr, day 1 equals June 1, 1951, and day 13,515 equals 

June 1, 1988.

5.3.1 Strontium-90

Strontium results were assumed to be 90Sr. Because of the presence of 90Sr both as an effluent from 

reactor operations and in a highly insoluble titanate form, bioassay results for 90Sr were fit using 

type F and S material. Figure A-1 in Attachment A shows the fit to the 50th-percentile intake values for 

type F 90Sr. Table A-5 summarizes the intake periods and rates for the 50th- and 84th-percentile 

values along with the geometric standard deviations (GSDs) for type F 90Sr. The GSDs were 

determined by dividing the 84th-percentile intake rates by the 50th-percentile intake rates. 

Figures A-2 through A-6 show the fits corresponding to each of the subsets of years across the intake 

period used to develop the composite figure for type S 90Sr. Figure A-7 shows the composite of the 

subsets of selected groups of years used to fit the 50th-percentile intake values for type S 90Sr. Table 

A-6 summarizes the intake periods and rates for the 50th- and 84th-percentile values along with the 

calculated GSDs for type S 90Sr. The same intake periods were applied to the 84th-percentile values 

for both 90Sr type F and S material because the values followed a similar pattern; results of the 

individual fits are not shown here because they were largely in agreement. The urinalysis data for 

1964 were insufficient to support a complete analysis and were therefore omitted from the sample set. 

The intake rate for 1964 was assumed to be the same as for 1963, the higher of the contiguous years.

5.3.2 Uranium

Because a variety of uranium enrichments and exposure conditions have been possible at the ORNL 

site, 234U was assumed for the IMBA intake modeling even though the source data are for gross 

uranium in varying amounts, depending on the enrichment. This assumption does not affect the fitting 

of the data for intake determination (e.g., the same total intakes would be obtained for any enrichment 

that was assumed) because all uranium isotopes behave the same biokinetically and the isotopes 

considered in this analysis have long half-lives in relation to the assumed intake period. International 

Commission on Radiological Protection (ICRP) Publication 68 [ICRP 1995] dose coefficients (also 

referred to as dose conversion factors) for 234U are 7% to 31% larger than those for 235U, 236U, and 

238U. Because of the varied isotopic compositions of the source terms, the 234U dose conversion factor 

will overestimate doses for any combination of the uranium radioisotopes, but the assumption of 

intake of 100% 234U is made to ensure the doses are favorable to the claimant.

Because uranium has been present in many chemical forms at ORNL, the bioassay data were fit 

using type F, M, and S material. Figures A-8 and A-9 in Attachment A show the fits for the 50thpercentile values for type F and M uranium, respectively. Table A-7 summarizes the intake periods for 
Document No. ORAUT-OTIB-0034 Revision No. 04 Effective Date: 09/01/2020 Page 10 of 35

the 50th- and 84th-percentile values along with the calculated GSDs for type F uranium, while Table 

A-8 lists similar information for type M uranium. Again, the GSDs were determined by dividing the

84th-percentile intake rates by the 50th-percentile intake rates.

For type S uranium, Figures A-10 through A-16 show the fits corresponding to each of the subsets of 

years across the intake period used to develop the composite figure. Figure A-17 provides the 

composite of the subsets of selected groups of years used to fit the 50th-percentile intake values.

Table A-9 summarizes the intake periods and rates for the 50th- and 84th-percentile values along with 

the calculated GSDs for type S uranium. Plots of the results of the fits to the 84th-percentile values for 

all three material types are not shown here because they were largely in agreement. 

5.3.3 Plutonium

ICRP Publication 68 [ICRP 1995] assigns all forms of plutonium to types M and S. In addition, type SS 

is evaluated in accordance with ORAUT-OTIB-0049, Estimating Doses for Plutonium Strongly 

Retained in the Lung [ORAUT 2020]. Although the bioassay results are for all alpha-emitting isotopes 

of plutonium, the results were assumed to represent the concentration of 239Pu alone. Figures A-18 

through A-21 in Attachment A show the fits for type M material corresponding to each of the subsets 

of years across the intake period used to develop the composite figure. Figure A-22 shows the 

composite of the subsets of selected years used to fit the 50th-percentile intake values for type M 

plutonium. Table A-10 summarizes the intake periods and rates for the 50th- and 84th-percentile 

values along with the GSDs for type M plutonium. The GSDs were determined by dividing the 84thpercentile intake rates by the 50th-percentile intake rates. Plots of the results of the individual fits to 

the 84th-percentile values for type M plutonium are not shown here because they were largely in 

agreement.

Figures A-23 through A-26 in Attachment A show the fits for type S material corresponding to each of

the subsets of years across the intake period used to develop the composite figure. Figure A-27 

shows the composite of the subsets of selected years used to fit the 50th-percentile intake values for 

type S plutonium. Table A-11 summarizes the intake period and rate for the 50th- and 84th-percentile 

values along with the GSDs for type S plutonium. Again, the GSDs were determined by dividing the 

84th-percentile intake rates by the 50th-percentile intake rates. Plots of the results of the individual fits 

to the 84th-percentile values for type S plutonium are not shown here because they were largely in 

agreement.

Figures A-28 through A-31 in Attachment A show the fits for type SS material corresponding to each 

of the subsets of years across the intake period used to develop the composite figure. Figure A-32 

shows the composite of the subsets of selected years used to fit the 50th-percentile intake values for 

type SS plutonium. Table A-12 summarizes the intake period and rate for the 50th- and 84thpercentile values along with the GSDs for type SS plutonium. Again, the GSDs were determined by 

dividing the 84th-percentile intake rates by the 50th-percentile intake rates. Plots of the results of the 

individual fits to the 84th-percentile values for type SS plutonium are not shown here because they 

were largely in agreement.

5.3.4 Americium-241

ICRP Publication 68 [ICRP 1995] assigns all forms of americium to type M. Figures A-33 and A-34 in 

Attachment A show the fits corresponding to each of the subsets of years across the intake period 

used to develop the composite figure. Figure A-35 shows the composite of the subsets of selected 

years used to fit the 50th-percentile intake values for type M 241Am. Table A-13 summarizes the intake 

periods and rates for the 50th- and 84th-percentile values along with the GSDs for type M 241Am.

Again, the GSDs were determined by dividing the 84th-percentile intake rates by the 50th-percentile 

intake rates. The same intake periods were applied to the 84th-percentile values for type M 241Am 
Document No. ORAUT-OTIB-0034 Revision No. 04 Effective Date: 09/01/2020 Page 11 of 35

because the values followed a similar pattern; results of the individual fits are not shown here because 

they were largely in agreement.

5.3.5 Additional Radionuclides

Hundreds of different radionuclides have been present at ORNL at some point during its operations.

For fission and activation product mixtures, dose reconstructors should use the intake mixture ratios in 

the latest revision of ORAUT-OTIB-0054, Fission and Activation Product Assignment for Internal 

Dose-Related Gross Beta and Gross Gamma Analyses [ORAUT 2014]. ORAUT-OTIB-0054 is 

applicable for workers in the Reactor Division and the Tank Farms areas. It should not be used for 

workers from the Isotopes Separations Division or Isotope Development Center (Buildings 3030 to 

3047).

6.0 ASSIGNMENT OF INTAKES AND DOSES

This section describes the derived intake rates and provides guidance for assigning doses. For each 

radionuclide, the 50th- and 95th-percentile intake rates along with the GSDs are provided in specific 

tables. In most cases, doses for individuals who were potentially exposed routinely should be 

calculated from the 50th-percentile intake rates by assuming the material type that results in the 

largest probability of causation. The GSD values have been adjusted from the values in the tables in 

Attachment A to allow for the addition of doses from different intake periods into a single input line for 

a given year in the Interactive RadioEpidemiological Program (IREP) input file and to ensure that 

none are less than 3, the value used when assigning intakes to individuals from person-specific 

bioassay results. For cases in which there is justification that the individual might have had intakes 

larger than the 50th-percentile intake rates, dose reconstructors should use the 95th-percentile intake 

rates input into IREP as a constant.

• Strontium-90. For 90Sr, several intake periods were defined as listed in Table 6-1 for type F

material and Table 6-2 for type S material. There were five intake periods defined for 90Sr

type F intakes and six for 90Sr type S intakes.

Table 6-1. Combined 90Sr type F intake periods and rates (dpm/d). 

From To 50th percentile GSD 95th percentile

01/01/1951 12/31/1953 475.2 10.0 20,983

01/01/1954 12/31/1954 80.99 10.0 3,576

01/01/1955 12/31/1960 47.34 4.17 496

01/01/1961 12/31/1964 47.34 3.00 288

01/01/1965 12/31/1988 15.52 3.00 94.57

Table 6-2. Combined 90Sr type S intake periods and rates (dpm/d). 

From To 50th percentile GSD 95th percentile

01/01/1951 12/31/1953 24,646 9.53 1,005,436

01/01/1954 12/31/1954 7,232 9.53 295,030

01/01/1955 12/31/1960 2,379 5.73 42,030

01/01/1961 12/31/1964 2,379 3.00 14,496

01/01/1965 12/31/1983 795.0 3.00 4,844

01/01/1984 12/31/1988 425.5 4.51 5,070

• Uranium. Tables 6-3 through 6-5 list the calculated annual intake rates for uranium for 1951

through 1987 for types F, M, and S material, respectively. The intakes should be assumed to

be 100% 234U.
Document No. ORAUT-OTIB-0034 Revision No. 04 Effective Date: 09/01/2020 Page 12 of 35

Table 6-3. Annual 234U type F intake periods and rates (dpm/d). 

From Years 50th percentile GSD 95th percentile

01/01/1951 12/31/1955 11.19 3.08 71.20

01/01/1956 12/31/1956 4.213 6.71 96.51

01/01/1957 12/31/1958 1.942 9.25 75.43

01/01/1959 12/31/1961 5.171 3.48 40.22

01/01/1962 12/31/1963 1.881 6.71 43.09

01/01/1964 12/31/1984 0.413 3.08 2.63

01/01/1985 12/31/1987 0.0957 3.08 0.609

Table 6-4. Annual 234U type M intake periods and rates (dpm/d). 

From Years 50th percentile GSD 95th percentile

01/01/1951 12/31/1955 47.03 3.33 340.2

01/01/1956 12/31/1956 11.45 9.70 480.9

01/01/1957 12/31/1958 7.49 9.70 314.6

01/01/1959 12/31/1961 21.81 3.33 157.8

01/01/1962 12/31/1963 6.56 7.24 170.3

01/01/1964 12/31/1984 1.641 3.33 11.87

01/01/1985 12/31/1987 0.294 3.33 2.127

Table 6-5. Annual 234U type S intake periods and rates (dpm/d). 

From Years 50th percentile GSD 95th percentile

01/01/1951 12/31/1955 850.7 3.00 5,184

01/01/1956 12/31/1956 675.7 3.00 4,117

01/01/1957 12/31/1958 247.7 7.74 7,176

01/01/1959 12/31/1961 509 4.17 5,331

01/01/1962 12/31/1963 235.3 6.04 4,533

01/01/1964 12/31/1982 23.7 3.00 144.4

01/01/1983 12/31/1983 15.25 4.67 192.4

01/01/1984 12/31/1987 15.25 3.00 92.93

• Plutonium. Tables 6-6 through 6-8 list the calculated annual intake rates for plutonium for

types M, S, and SS material, respectively, for 1951 through 1988. The intakes should be

assumed to be 100% 239

Pu.

Table 6-6. Annual 239Pu type M intake periods and rates (dpm/d). 

From Years 50th percentile GSD 95th percentile

01/01/1951 12/31/1952 40.75 3.0 248

01/01/1953 12/31/1959 10.98 7.9 329

01/01/1960 12/31/1968 10.98 3.0 66.9

01/01/1969 12/31/1984 7.35 3.0 44.8

01/01/1985 12/31/1988 1.614 4.2 17.1

Table 6-7. Annual 239Pu type S intake periods and rates (dpm/d). 

From Years 50th percentile GSD 95th percentile

01/01/1951 12/31/1952 1,489 3.00 9,073

01/01/1953 12/31/1959 159.8 11.06 8,325

01/01/1960 12/31/1968 159.8 3.00 973

01/01/1969 12/31/1972 118.5 3.40 886

01/01/1973 12/31/1984 118.5 3.00 722

01/01/1985 12/31/1988 36.26 5.46 592
Document No. ORAUT-OTIB-0034 Revision No. 04 Effective Date: 09/01/2020 Page 13 of 35

Table 6-8. Annual 239Pu type SS intake periods and rates (dpm/d). 

From Years 50th percentile GSD 95th percentile

01/01/1951 12/31/1952 5,730 3.00 34,916

01/01/1953 12/31/1959 1,440 8.26 46,466

01/01/1960 12/31/1968 1,440 3.00 8,775

01/01/1969 12/31/1972 1,060 3.31 7,598

01/01/1973 12/31/1984 1,060 3.00 6,459

01/01/1985 12/31/1988 229 5.20 3,445

• Americium-241. Table 6-9 lists the combined 241Am type M material intake periods and rates

for 1968 through 1988. There were two defined intake periods.

Table 6-9. Americium-241 type M intake periods and rates (dpm/d). 

From Years 50th percentile GSD 95th percentile 

01/01/1968 12/31/1984 6.673 3.00 40.66

01/01/1985 12/31/1988 2.207 3.00 13.45

6.1 CONTRIBUTION FROM ADDITIONAL RADIONUCLIDES

For 90Sr, the calculated intake rates for type F material should be applied for all exposures unless 

claimant interview information or related bioassay results indicate there was a potential for exposure 

to strontium titanate (SrTiO3) or unless the individual worked in a location where it was found 

(Building 3517), in which case type S intakes should be assigned. If an individual was exposed only to 

type S material (titanate), intakes of associated radionuclides as discussed in ORAUT-OTIB-0054 

[ORAUT 2014] should not be included. ORAUT-OTIB-0054 is applicable for workers in the Reactor 

Division and the Tank Farms areas and in all other areas except for workers in Building 3517 or from 

the Isotopes Separations Division or Isotope Development Center (Buildings 3030 to 3047). When a 

type F 90Sr intake is assigned, the worker should also be assigned intakes of associated radionuclides 

as discussed in the latest revision of ORAUT-OTIB-0054.

6.2 DOSE ASSIGNMENT

In most cases, doses to be assigned to individuals potentially exposed on a routine basis are 

calculated from the 50th-percentile intake rates; the material type resulting in the largest probability of 

causation is selected. The lognormal distribution should be selected in IREP with the calculated dose 

entered as Parameter 1 and the associated GSD as Parameter 2. The GSD is associated with the 

intake, so it is applied to all annual doses determined from the intake period, with the exception of 

ORAUT-OTIB-0054 [ORAUT 2014] intakes of associated radionuclides. 
Document No. ORAUT-OTIB-0034 Revision No. 04 Effective Date: 09/01/2020 Page 14 of 35

REFERENCES

ICRP [1995]. Dose coefficients for intakes of radionuclides by workers. ICRP Publication 68. Ann 

ICRP 24(4). [SRDB Ref ID: 22731]

ORAUT [2005]. Analysis of coworker bioassay data for internal dose assignment. ORAUT-OTIB-0019 

Rev. 01. Oak Ridge, TN: Oak Ridge Associated Universities Team. October 7. [SRDB Ref ID: 19438]

ORAUT [2013]. Oak Ridge National Laboratory – occupational internal dose. ORAUT-TKBS-0012-5 

Rev. 02. Oak Ridge, TN: Oak Ridge Associated Universities Team. February 8. [SRDB Ref ID:

122541]

ORAUT [2014]. Fission and activation product assignment for internal dose-related gross beta and

gross gamma analyses. ORAUT-OTIB-0054 Rev. 02. Oak Ridge, TN: Oak Ridge Associated

Universities Team. March 6. [SRDB Ref ID: 130852]

ORAUT [2020]. Estimating doses for plutonium strongly retained in the lung. ORAUT-OTIB-0049 Rev. 

02. Oak Ridge, TN: Oak Ridge Associated Universities Team. September 1. [SRDB Ref ID: 178329]
Document No. ORAUT-OTIB-0034 Revision No. 04 Effective Date: 09/01/2020 Page 15 of 35

ATTACHMENT A 

STATISTICAL ANALYSIS RESULTS FOR

STRONTIUM, URANIUM, PLUTONIUM, AND AMERICIUM

LIST OF TABLES

TABLE TITLE PAGE

A-1 Statistical summary of annual strontium 24-hour urinary excretion rates, 1951 to 1988 ......... 17

A-2 Statistical summary of annual uranium 24-hour urinary excretion rates, 1951 to 1987 ........... 18

A-3 Statistical summary of annual plutonium 24-hour urinary excretion rates, 1951 to 1988......... 19

A-4 Statistical summary of annual americium 24-hour urinary excretion rates, 1968 to 1987........ 20

A-5 Type F 90Sr intake periods and rates...................................................................................... 20

A-6 Type S 90Sr intake periods and rates...................................................................................... 21

A-7 Type F uranium intake periods and rates ............................................................................... 23

A-8 Type M uranium intake periods and rates .............................................................................. 24

A-9 Type S uranium intake periods and rates ............................................................................... 25

A-10 Type M plutonium intake periods and rates............................................................................ 28

A-11 Type S plutonium intake periods and rates ............................................................................ 30

A-12 Type SS plutonium intake periods and rates .......................................................................... 32

A-13 Type M 241Am intake periods and rates .................................................................................. 34

LIST OF FIGURES

FIGURE TITLE PAGE

A-1 Assumed 90Sr intake, 1951 to 1988, 50th-percentile results, type F ....................................... 21

A-2 Assumed 90Sr intake, 1951 to 1953, 50th-percentile results, type S ....................................... 21

A-3 Assumed 90Sr intake, 1954, 50th-percentile results, type S.................................................... 22

A-4 Assumed 90Sr intake, 1955 to 1964, 50th-percentile results, type S ....................................... 22

A-5 Assumed 90Sr intake, 1965 to 1983, 50th-percentile results, type S ....................................... 22

A-6 Assumed 90Sr intake, 1983 to 1988, 50th-percentile results, type S ....................................... 23

A-7 Predicted cumulative 90Sr excretion rate from independently fit intakes, 1951 to 1988,

50th-percentile results, type S................................................................................................ 23

A-8 Assumed uranium intake, 1951 to 1987, 50th-percentile results, type F................................. 24

A-9 Assumed uranium intake, 1951 to 1987, 50th-percentile results, type M................................ 24

A-10 Assumed uranium intake, 1951 to 1955, 50th-percentile results, type S................................. 25

A-11 Assumed uranium intake, 1956, 50th-percentile results, type S ............................................. 25

A-12 Assumed uranium intake, 1957 to 1958, 50th-percentile results, type S................................. 26

A-13 Assumed uranium intake, 1959 to 1961, 50th-percentile results, type S................................. 26

A-14 Assumed uranium intake, 1962 to 1963, 50th-percentile results, type S................................. 27

A-15 Assumed uranium intake, 1964 to 1982, 50th-percentile results, type S................................. 27

A-16 Assumed uranium intake, 1983 to 1987, 50th-percentile results, type S................................. 28

A-17 Predicted cumulative uranium excretion rate from independently fit intakes, 1951 to

1987, 50th-percentile, type S ................................................................................................. 28

A-18 Assumed plutonium intake, 1951 to 1952, 50th-percentile results, type M ............................. 29

A-19 Assumed plutonium intake, 1953 to 1968, 50th-percentile results, type M ............................. 29

A-20 Assumed plutonium intake, 1969 to 1984, 50th-percentile results, type M ............................. 29

A-21 Assumed plutonium intake, 1985 to 1988, 50th-percentile results, type M ............................. 30

A-22 Predicted cumulative plutonium intake, 1951 to 1988, 50th-percentile composite results,

type M....................................................................................................................................30

A-23 Assumed plutonium intake, 1951 to 1952, 50th-percentile results, type S.............................. 31
Document No. ORAUT-OTIB-0034 Revision No. 04 Effective Date: 09/01/2020 Page 16 of 35

ATTACHMENT A

STATISTICAL ANALYSIS RESULTS FOR

STRONTIUM, URANIUM, PLUTONIUM, AND AMERICIUM (continued)

A-24 Assumed plutonium intake, 1953 to 1968, 50th-percentile results, type S.............................. 31

A-25 Assumed plutonium intake, 1969 to 1984, 50th-percentile results, type S.............................. 31

A-26 Assumed plutonium intake, 1985 to 1988, 50th-percentile results, type S.............................. 32

A-27 Predicted cumulative plutonium intake, 1951 to 1988, 50th-percentile composite results,

type S.....................................................................................................................................32

A-28 Assumed plutonium intake, 1951 to 1952, 50th-percentile results, type SS............................ 33

A-29 Assumed plutonium intake, 1953 to 1968, 50th-percentile results, type SS............................ 33

A-30 Assumed plutonium intake, 1969 to 1984, 50th-percentile results, type SS............................ 33

A-31 Assumed plutonium intake, 1985 to 1988, 50th-percentile results, type SS............................ 34

A-32 Predicted cumulative plutonium intake, 1951 to 1988, 50th-percentile composite results,

type SS ..................................................................................................................................34

A-33 Assumed 241Am intake, 1968 to 1984, 50th-percentile results, type M.................................... 35

A-34 Assumed 241Am intake, 1985 to 1988, 50th-percentile results, type M.................................... 35

A-35 Predicted cumulative 241Am intake, 1968 to 1988, 50th-percentile composite results, type

M............................................................................................................................................35
Document No. ORAUT-OTIB-0034 Revision No. 04 Effective Date: 09/01/2020 Page 17 of 35

ATTACHMENT A

STATISTICAL ANALYSIS RESULTS FOR

STRONTIUM, URANIUM, PLUTONIUM, AND AMERICIUM (continued)

Table A-1. Statistical summary of annual strontium 24-hour 

urinary excretion rates (dpm/d), 1951 to 1988.

a

Effective 

bioassay 

date

GM 

(50th) 

GM × GSD

(84th)b

No. of 

samples

No. of 

employees

07/01/1952c 109.15 1,008.55 134 16

07/01/1954 24.68 241.98 246 162

07/01/1955 13.10 63.17 722 534

07/01/1956 13.54 82.88 705 538

07/01/1957 15.71 68.85 879 566

07/01/1958 17.01 75.45 1,394 620

07/01/1959 12.20 59.03 1,035 623

07/01/1960 15.67 65.07 624 364

07/01/1961 9.48 28.06 1,328 952

07/01/1962 12.04 29.49 2,440 1,579

07/01/1963 10.08 26.23 2,328 1,524

1964d No data No data No data No data

07/01/1965 4.86 15.75 2,203 1,649

07/01/1966 3.62 17.78 1,619 1,274

07/01/1967 3.35 12.86 1,609 1,332

07/01/1968 1.02 7.77 1,147 915

07/01/1969 3.89 8.96 1,295 1,028

07/01/1970 6.07 13.96 636 456

07/01/1971 6.91 15.08 607 437

07/01/1972 7.54 22.75 358 211

07/01/1973 5.18 13.45 397 316

07/01/1974 7.66 24.76 282 217

07/01/1975 5.27 10.68 290 239

07/01/1976 5.14 11.59 270 201

07/01/1977 5.19 11.58 168 120

07/01/1978 5.04 9.61 149 109

07/01/1979 2.44 6.68 215 169

07/01/1980 5.69 23.05 242 162

07/01/1981 3.04 7.22 159 127

07/01/1982 5.23 12.06 146 98

07/01/1983 5.71 14.48 145 96

07/01/1984 4.38 14.14 136 88

07/01/1985 2.11 5.93 161 134

07/01/1986 0.67 2.88 221 168

07/01/1987 3.37 15.98 228 151

07/01/1988 0.56 1.96 275 225

a. GM = geometric mean; No data = insufficient data for analysis.

b. The actual GSDs from the statistical analyses are used as input into

the intake modeling. The GSDs of the results of the intake modeling

are adjusted to a minimum of 3.00 for assignment of intakes.

c. This period includes data for 01/01/1951 through 12/31/1953.

d. See Section 5.3.1 for discussion of evaluation of 1964.
Document No. ORAUT-OTIB-0034 Revision No. 04 Effective Date: 09/01/2020 Page 18 of 35

ATTACHMENT A

STATISTICAL ANALYSIS RESULTS FOR

STRONTIUM, URANIUM, PLUTONIUM, AND AMERICIUM (continued)

Table A-2. Statistical summary of annual uranium 24-hour 

urinary excretion rates (dpm/d), 1951 to 1987. 

Effective

bioassay

date

GM

(50th)

GM × GSD

(84th)a 

No. of

samples

No. of

employees

07/01/1951 3.41 7.81 351 262

07/01/1952 2.88 8.01 722 419

07/01/1953 3.64 7.54 615 494

07/01/1954 2.27 5.46 851 665

07/01/1955 3.07 9.34 823 591

07/01/1956 1.20 8.16 783 531

07/01/1957 0.50 3.65 942 664

07/01/1958 0.64 4.74 992 553

07/01/1959 1.43 6.93 745 461

07/01/1960 1.36 3.97 506 324

07/01/1961 1.52 5.73 686 456

07/01/1962 0.52 3.57 439 290

07/01/1963 0.58 3.24 698 389

07/01/1964 0.25 1.29 875 541

07/01/1965 0.17 0.62 1,462 1,178

07/01/1966 0.18 0.52 782 597

07/01/1967 0.09 0.21 687 530

07/01/1968 0.13 0.34 512 324

07/01/1969 0.10 0.33 457 268

07/01/1970 0.16 0.65 281 176

07/01/1971 0.09 0.26 288 201

07/01/1972 0.13 0.39 256 145

07/01/1973 0.07 0.30 278 206

07/01/1974 0.06 0.22 188 138

07/01/1975 0.08 0.32 219 149

07/01/1976 0.10 0.46 229 135

07/01/1977 0.20 0.48 191 131

07/01/1978 0.14 0.31 240 165

07/01/1979 0.14 0.52 318 213

07/01/1980 0.11 0.39 261 189

07/01/1981 0.13 0.22 179 145

07/01/1982 0.17 0.31 141 99

07/01/1983 0.12 0.28 167 106

07/01/1984 0.10 0.19 203 141

07/01/1985 0.07 0.17 217 158

07/01/1986 0.04 0.08 163 128

07/01/1987 0.00 0.03 212 164

a. The actual GSDs from the statistical analyses are used as input into

the intake modeling. The GSDs of the results of the intake modeling

are adjusted to a minimum of 3.00 for assignment of intakes.
Document No. ORAUT-OTIB-0034 Revision No. 04 Effective Date: 09/01/2020 Page 19 of 35

ATTACHMENT A

STATISTICAL ANALYSIS RESULTS FOR

STRONTIUM, URANIUM, PLUTONIUM, AND AMERICIUM (continued)

Table A-3. Statistical summary of annual plutonium 24-hour 

urinary excretion rates (dpm/d), 1951 to 1988. 

Effective 

bioassay 

date

GM 

(50th)

GM × GSD 

(84th)a

No. of 

samples

No. of 

employees

07/01/1951 0.13 0.30 507 260

07/01/1952 0.11 0.31 668 394

07/01/1953 0.04 0.14 446 394

07/01/1954 0.07 0.36 972 583

07/01/1955 0.07 0.26 740 525

07/01/1956 0.04 0.36 627 473

07/01/1957 0.14 0.73 674 423

07/01/1958 0.15 0.52 785 400

07/01/1959 0.12 0.62 889 460

07/01/1960 0.13 0.28 1,927 595

07/01/1961 0.07 0.21 1,758 983

07/01/1962 0.01 0.08 2,680 1,658

07/01/1963 0.01 0.09 2,825 1,624

07/01/1964 0.08 0.23 2,147 1,446

07/01/1965 0.13 0.26 1,237 746

07/01/1966 0.12 0.21 1,179 803

07/01/1967 0.10 0.19 1,247 927

07/01/1968 0.12 0.24 1,262 775

07/01/1969 0.04 0.17 1,356 927

07/01/1970 0.08 0.19 828 481

07/01/1971 0.06 0.23 792 484

07/01/1972 0.06 0.18 686 350

07/01/1973 0.03 0.11 675 420

07/01/1974 0.06 0.12 529 350

07/01/1975 0.04 0.12 487 335

07/01/1976 0.05 0.13 532 341

07/01/1977 0.07 0.15 418 272

07/01/1978 0.06 0.15 431 262

07/01/1979 0.08 0.14 380 219

07/01/1980 0.05 0.11 320 215

07/01/1981 0.09 0.16 323 224

07/01/1982 0.10 0.17 345 226

07/01/1983 0.07 0.13 329 211

07/01/1984 0.07 0.11 370 237

07/01/1985 0.01 0.05 368 253

07/01/1986 0.01 0.04 297 212

07/01/1987 0.01 0.04 234 185

07/01/1988 0.00 0.03 169 128

a. The actual GSDs from the statistical analyses are used as input into

the intake modeling. The GSDs of the results of the intake modeling

are adjusted to a minimum of 3.00 for assignment of intakes.
Document No. ORAUT-OTIB-0034 Revision No. 04 Effective Date: 09/01/2020 Page 20 of 35

ATTACHMENT A

STATISTICAL ANALYSIS RESULTS FOR

STRONTIUM, URANIUM, PLUTONIUM, AND AMERICIUM (continued)

Table A-4. Statistical summary of annual americium 24-hour 

urinary excretion rates (dpm/d), 1968 to 1987. 

Effective 

bioassay 

date

GM 

(50th) 

GM × GSD 

(84th)a

No. of 

samples

No. of 

employees

07/01/1968 0.12 0.31 405 216

07/01/1969 0.10 0.42 455 253

07/01/1970 0.10 0.33 514 267

07/01/1971 0.09 0.24 444 262

07/01/1972 0.12 0.27 503 271

07/01/1973 0.09 0.16 547 336

07/01/1974 0.08 0.15 351 206

07/01/1975 0.12 0.30 367 246

07/01/1976 0.15 0.52 475 274

07/01/1977 0.11 0.18 358 223

07/01/1978 0.10 0.18 403 241

07/01/1979 0.10 0.17 279 196

07/01/1980 0.10 0.14 267 189

07/01/1981 0.07 0.17 289 213

01/01/1983 0.10 0.17 561 272

07/01/1984 0.10 0.15 345 225

07/01/1985 0.05 0.09 342 258

07/01/1986 0.01 0.05 280 217

07/01/1987 0.01 0.04 199 181

a. The actual GSDs from the statistical analyses are used as input into

the intake modeling. The GSDs of the results of the intake modeling

are adjusted to a minimum of 3.00 for assignment of intakes.

Table A-5. Type F 90Sr intake periods and rates (dpm/d). 

Start End 50th percentile 84th percentile GSDa

01/01/1951 12/31/1953 475.2 4,389 9.24

01/01/1954 12/31/1954 80.99 810.4 10.04

01/01/1955 12/31/1960 47.34 197.3 4.17

01/01/1961 12/31/1964 47.34 62.43 1.32

01/01/1965 12/31/1988 15.52 36.88 2.38

a. The actual GSDs from the results of the intake modeling are presented here.

These GSDs are adjusted to a minimum of 3.00 for assignment of intakes as

discussed in Section 6.
Figure A-1. Assumed 90Sr intake, 1951 to 1988, 50th-percentile results, type F. 

The first bioassay datum with an effective bioassay date of 07/01/1952 is based 

on data for 01/01/1951 through 12/31/1953. 

Table A-6. Type S 90Sr intake periods and rates (dpm/d). 

Document No. ORAUT-OTIB-0034 Revision No. 04 Effective Date: 09/01/2020 Page 21 of 35

ATTACHMENT A

STATISTICAL ANALYSIS RESULTS FOR

STRONTIUM, URANIUM, PLUTONIUM, AND AMERICIUM (continued)

• annual bioassay

value (50th percentile)

● not used in fit

____ fit

• annual bioassay

value (50th percentile)

____ fit

Start End 50th percentile 84th percentile GSDa

01/01/1951 12/31/1953 24,646 227,730 9.24

01/01/1954 12/31/1954 7,232 68,924 9.53

01/01/1955 12/31/1960 2,379 13,628 5.73

01/01/1961 12/31/1964 2,389 6,431 2.69

01/01/1965 12/31/1983 795.0 1,917 2.41

01/01/1984 12/31/1988 425.5 1,917 4.51

a. The actual GSDs from the results of the intake modeling are presented here.

These GSDs are adjusted to a minimum of 3.00 for assignment of intakes as

discussed in Section 6.0.

Figure A-2. Assumed 90Sr intake, 1951 to 1953, 50th-percentile results, type S. 

The first bioassay datum with an effective bioassay date of 07/01/1952 is based 

on data for 01/01/1951 through 12/31/1953. 
Figure A-3. Assumed 90Sr intake, 1954, 50th-percentile results, type S. 

Figure A-4. Assumed 90Sr intake, 1955 to 1964, 50th-percentile results, type S. 

Figure A-5. Assumed 90Sr intake, 1965 to 1983, 50th-percentile results, type S. 

Document No. ORAUT-OTIB-0034 Revision No. 04 Effective Date: 09/01/2020 Page 22 of 35

ATTACHMENT A

STATISTICAL ANALYSIS RESULTS FOR

STRONTIUM, URANIUM, PLUTONIUM, AND AMERICIUM (continued)

• annual bioassay

value (50th percentile)

● not used in fit

____ fit

• annual bioassay

value (50th percentile)

● not used in fit

____ fit

• annual bioassay

value (50th percentile)

● not used in fit

____ fit
Figure A-6. Assumed 90Sr intake, 1983 to 1988, 50th-percentile results, type S. 

Figure A-7. Predicted cumulative 90Sr excretion rate from independently fit intakes, 1951 to 1988, 

50th-percentile results, type S. 

Table A-7. Type F uranium intake periods and rates (dpm/d). 

Document No. ORAUT-OTIB-0034 Revision No. 04 Effective Date: 09/01/2020 Page 23 of 35

ATTACHMENT A

STATISTICAL ANALYSIS RESULTS FOR

STRONTIUM, URANIUM, PLUTONIUM, AND AMERICIUM (continued)

• annual bioassay

value (50th percentile)

● not used in fit

____ fit

● bioassay data

____ cumulative fit

Start End 50th percentile 84th percentile GSDa

01/01/1951 12/31/1955 11.19 28.28 2.53

01/01/1956 12/31/1956 4.213 28.28 6.71

01/01/1957 12/31/1958 1.942 17.97 9.25

01/01/1959 12/31/1961 5.171 17.97 3.48

01/01/1962 12/31/1963 1.881 12.05 6.41

01/01/1964 12/31/1984 0.413 1.272 3.08

01/01/1985 12/31/1987 0.0957 0.227 2.37

a. The actual GSDs from the results of the intake modeling are presented here.

These GSDs are adjusted to a minimum of 3.00 for assignment of intakes as

discussed in Section 6.
Document No. ORAUT-OTIB-0034 Revision No. 04 Effective Date: 09/01/2020 Page 24 of 35

ATTACHMENT A

STATISTICAL ANALYSIS RESULTS FOR

STRONTIUM, URANIUM, PLUTONIUM, AND AMERICIUM (continued)

Figure A-8. Assumed uranium intake, 1951 to 1987, 50th-percentile results, type 

F. 

Table A-8. Type M uranium intake periods and rates (dpm/d). 

Start End 50th percentile 84th percentile GSDa

01/01/1951 12/31/1955 47.03 117.8 2.50

01/01/1956 12/31/1956 11.45 117.8 10.29

01/01/1957 12/31/1958 7.49 72.66 9.70

01/01/1959 12/31/1961 21.81 72.66 3.33

01/01/1962 12/31/1963 6.56 47.49 7.24

01/01/1964 12/31/1984 1.641 4.809 2.93

01/01/1985 12/31/1987 0.294 0.659 2.24

a. The actual GSDs from the results of the intake modeling are presented here.

These GSDs are adjusted to a minimum of 3.00 for assignment of intakes as

discussed in Section 6.

Figure A-9. Assumed uranium intake, 1951 to 1987, 50th-percentile results, type

M.

• annual bioassay

value (50th percentile)

● not used in fit

____ fit

• annual bioassay

value (50th percentile)

● not used in fit

____ fit
Table A-9. Type S uranium intake periods and rates (dpm/d). 

Start End 50th percentile 84th percentile GSDa

01/01/1951 12/31/1955 850.7 2,048 2.41

01/01/1956 12/31/1956 675.7 2,048 3.03

01/01/1957 12/31/1958 247.7 1,917 7.74

01/01/1959 12/31/1961 509 1,917 3.77

01/01/1962 12/31/1963 235.3 1,422 6.04

01/01/1964 12/31/1982 23.7 71.203 3.00

01/01/1983 12/31/1983 15.25 71.203 4.67

01/01/1984 12/31/1987 15.25 31.58 2.07

a. The actual GSDs from the results of the intake modeling are presented here.

These GSDs are adjusted to a minimum of 3.00 for assignment of intakes as

discussed in Section 6.

Figure A-10. Assumed uranium intake, 1951 to 1955, 50th-percentile results,

type S. 

Figure A-11. Assumed uranium intake, 1956, 50th-percentile results, type S. 

Document No. ORAUT-OTIB-0034 Revision No. 04 Effective Date: 09/01/2020 Page 25 of 35

ATTACHMENT A

STATISTICAL ANALYSIS RESULTS FOR

STRONTIUM, URANIUM, PLUTONIUM, AND AMERICIUM (continued)

• annual bioassay

value (50th percentile)

● not used in fit

____ fit

• annual bioassay

value (50th percentile)

● not used in fit

____ fit
Figure A-12. Assumed uranium intake, 1957 to 1958, 50th-percentile results, 

type S. 

Figure A-13. Assumed uranium intake, 1959 to 1961, 50th-percentile results, 

type S. 

Document No. ORAUT-OTIB-0034 Revision No. 04 Effective Date: 09/01/2020 Page 26 of 35

ATTACHMENT A

STATISTICAL ANALYSIS RESULTS FOR

STRONTIUM, URANIUM, PLUTONIUM, AND AMERICIUM (continued)

• annual bioassay

value (50th percentile)

● not used in fit

____ fit

• annual bioassay

value (50th percentile)

● not used in fit

____ fit
Figure A-14. Assumed uranium intake, 1962 to 1963, 50th-percentile results, 

type S. 

Figure A-15. Assumed uranium intake, 1964 to 1982, 50th-percentile results, 

type S. 

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ATTACHMENT A

STATISTICAL ANALYSIS RESULTS FOR

STRONTIUM, URANIUM, PLUTONIUM, AND AMERICIUM (continued)

• annual bioassay

value (50th percentile)

● not used in fit

____ fit

• annual bioassay

value (50th percentile)

● not used in fit

____ fit
Figure A-16. Assumed uranium intake, 1983 to 1987, 50th-percentile results, type

S. 

Figure A-17. Predicted cumulative uranium excretion rate from independently fit 

intakes, 1951 to 1987, 50th-percentile, type S. 

Document No. ORAUT-OTIB-0034 Revision No. 04 Effective Date: 09/01/2020 Page 28 of 35

ATTACHMENT A

STATISTICAL ANALYSIS RESULTS FOR

STRONTIUM, URANIUM, PLUTONIUM, AND AMERICIUM (continued)

Table A-10. Type M plutonium intake periods and rates (dpm/d). 

• annual bioassay

value (50th percentile)

● not used in fit

____ fit

● bioassay data

____cumulative fit

Start End 50th percentile 84th percentile GSDa

01/01/1951 12/31/1952 40.75 109.8 2.69

01/01/1953 12/31/1959 10.98 86.42 7.87

01/01/1960 12/31/1968 10.98 22.45 2.04

01/01/1969 12/31/1984 7.35 22.45 3.05

01/01/1985 12/31/1988 1.614 6.811 4.22

a. The actual GSDs from the results of the intake modeling are presented here.

These GSDs are adjusted to a minimum of 3.00 for assignment of intakes as

discussed in Section 6.
Figure A-18. Assumed plutonium intake, 1951 to 1952, 50th-percentile results, 

type M. 

Figure A-19. Assumed plutonium intake, 1953 to 1968, 50th-percentile results, 

type M. 

Figure A-20. Assumed plutonium intake, 1969 to 1984, 50th-percentile results, 

type M. 

Document No. ORAUT-OTIB-0034 Revision No. 04 Effective Date: 09/01/2020 Page 29 of 35

ATTACHMENT A

STATISTICAL ANALYSIS RESULTS FOR

STRONTIUM, URANIUM, PLUTONIUM, AND AMERICIUM (continued)

• annual bioassay

value (50th percentile)

● not used in fit

____ fit

• annual bioassay

value (50th percentile)

● not used in fit

____ fit

• annual bioassay

value (50th percentile)

● not used in fit

____ fit
Figure A-21. Assumed plutonium intake, 1985 to 1988, 50th-percentile results, 

type M. 

Figure A-22. Predicted cumulative plutonium intake, 1951 to 1988, 50thpercentile composite results, type M. 

Document No. ORAUT-OTIB-0034 Revision No. 04 Effective Date: 09/01/2020 Page 30 of 35

ATTACHMENT A

STATISTICAL ANALYSIS RESULTS FOR

STRONTIUM, URANIUM, PLUTONIUM, AND AMERICIUM (continued)

• annual bioassay

value (50th percentile)

● not used in fit

____ fit

● bioassay data

____cumulative fit

Table A-11. Type S plutonium intake periods and rates (dpm/d). 

Start End 50th percentile 84th percentile GSDa

01/01/1951 12/31/1952 1,489 3,874 2.60

01/01/1953 12/31/1959 159.8 1,767 11.06

01/01/1960 12/31/1968 159.8 402.5 2.52

01/01/1969 12/31/1984 118.5 402.5 3.40

01/01/1985 12/31/1988 36.26 198 5.46

a. The actual GSDs from the results of the intake modeling are presented here.

These GSDs are adjusted to a minimum of 3.00 for assignment of intakes as

discussed in Section 6.
Figure A-23. Assumed plutonium intake, 1951 to 1952, 50th-percentile results, type S. 

Figure A-24. Assumed plutonium intake, 1953 to 1968, 50th-percentile results, type S. 

Figure A-25. Assumed plutonium intake, 1969 to 1984, 50th-percentile results, type S. 

Document No. ORAUT-OTIB-0034 Revision No. 04 Effective Date: 09/01/2020 Page 31 of 35

ATTACHMENT A

STATISTICAL ANALYSIS RESULTS FOR

STRONTIUM, URANIUM, PLUTONIUM, AND AMERICIUM (continued)

• annual bioassay

value (50th percentile)

● not used in fit

____ fit

• annual bioassay

value (50th percentile)

● not used in fit

____ fit

• annual bioassay

value (50th percentile)

● not used in fit

____ fit
Figure A-26. Assumed plutonium intake, 1985 to 1988, 50th-percentile results, type S. 

Figure A-27. Predicted cumulative plutonium intake, 1951 to 1988, 50th-percentile composite 

results, type S. 

Document No. ORAUT-OTIB-0034 Revision No. 04 Effective Date: 09/01/2020 Page 32 of 35

ATTACHMENT A

STATISTICAL ANALYSIS RESULTS FOR

STRONTIUM, URANIUM, PLUTONIUM, AND AMERICIUM (continued)

• annual bioassay

value (50th percentile)

● not used in fit

____ fit

● bioassay data

____cumulative fit

Table A-12. Type SS plutonium intake periods and rates (dpm/d). 

Start End 50th percentile 84th percentile GSDa

01/01/1951 12/31/1952 5,730 14,500 2.53

01/01/1953 12/31/1959 1,440 11,900 8.26

01/01/1960 12/31/1968 1,440 3,510 2.44

01/01/1969 12/31/1984 1,060 3,510 3.31

01/01/1985 12/31/1988 229 1,190 5.20

a. The actual GSDs from the results of the intake modeling are presented here.

These GSDs are adjusted to a minimum of 3.00 for assignment of intakes as

discussed in Section 6.
Document No. ORAUT-OTIB-0034 Revision No. 04 Effective Date: 09/01/2020 Page 33 of 35

ATTACHMENT A

STATISTICAL ANALYSIS RESULTS FOR

STRONTIUM, URANIUM, PLUTONIUM, AND AMERICIUM (continued)

Figure A-28. Assumed plutonium intake, 1951 to 1952, 50th-percentile results, type SS. 

Figure A-29. Assumed plutonium intake, 1953 to 1968, 50th-percentile results, type SS. 

Figure A-30. Assumed plutonium intake, 1969 to 1984, 50th-percentile results, type SS. 
Document No. ORAUT-OTIB-0034 Revision No. 04 Effective Date: 09/01/2020 Page 34 of 35

ATTACHMENT A

STATISTICAL ANALYSIS RESULTS FOR

STRONTIUM, URANIUM, PLUTONIUM, AND AMERICIUM (continued)

Figure A-31. Assumed plutonium intake, 1985 to 1988, 50th-percentile results, type SS. 

Figure A-32. Predicted cumulative plutonium intake, 1951 to 1988, 50th-percentile composite results, 

type SS. 

Table A-13. Type M 241Am intake periods and rates (dpm/d). 

Start End 50th percentile 84th percentile GSDa

01/01/1968 12/31/1984 6.673 14.61 2.19

01/01/1985 12/31/1988 2.207 6.659 2.99

a. The actual GSDs from the results of the intake modeling are presented here.

These GSDs are adjusted to a minimum of 3.00 for assignment of intakes as

discussed in Section 6.
Figure A-33. Assumed 241Am intake, 1968 to 1984, 50th-percentile results, 

type M. 

Figure A-34. Assumed 241Am intake, 1985 to 1988, 50th-percentile results, 

type M. 

Figure A-35. Predicted cumulative 241Am intake, 1968 to 1988, 50th-percentile 

composite results, type M. 

Document No. ORAUT-OTIB-0034 Revision No. 04 Effective Date: 09/01/2020 Page 35 of 35

ATTACHMENT A

STATISTICAL ANALYSIS RESULTS FOR

STRONTIUM, URANIUM, PLUTONIUM, AND AMERICIUM (continued)

• annual bioassay

value (50th percentile)

● not used in fit

____ fit

• annual bioassay

value (50th percentile)

● not used in fit

____ fit

● bioassay data

____cumulative fit