ORAU TEAM

Dose Reconstruction

Project for NIOSH

Oak Ridge Associated Universities I Dade Moeller I MJW Technical Services

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DOE Review Release 01/27/2014

Document Title:

Internal Dosimetry Coworker Data for X-10

Document Number: ORAUT-OTIB-0034

Revision: 02

Effective Date: 01/21/2014

Type of Document: OTIB

Supersedes: Revision 01

Subject Expert(s): Matthew G. Arno

Approval: Signature on File Approval Date: 12/23/2013

Matthew G. Arno, Document Owner

Concurrence: Richard E. Merrill Signature on File for Concurrence Date: 12/19/2013

John M. Byrne, Objective 1 Manager

Concurrence: Signature on File Concurrence Date: 12/20/2013

Edward F. Maher, Objective 3 Manager

Concurrence: Vickie S. Short Signature on File for Concurrence Date: 12/19/2013

Kate Kimpan, Project Director

Approval: Signature on File Approval Date: 01/21/2014

James W. Neton, Associate Director for Science

New Total Rewrite Revision Page Change

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

REVISION AND DISCARD / DESTROY ALL COPIES OF THE PRIOR REVISION.
Document No. ORAUT-OTIB-0034 Revision No. 02 Effective Date: 01/21/2014 Page 2 of 37

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 95th percentile 

intake rates was added. Incorporates formal internal and NIOSH 

review comments. Training required: As determined by the 

Objective Manager. Initiated by Matthew G. Arno.
Document No. ORAUT-OTIB-0034 Revision No. 02 Effective Date: 01/21/2014 Page 3 of 37

TABLE OF CONTENTS

SECTION TITLE PAGE

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

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

2.0 Overview.................................................................................................................................. 6

3.0 Data ......................................................................................................................................... 7

3.1 Selected Bioassay Data................................................................................................ 7

3.2 Analysis........................................................................................................................ 7

4.0 Intake Modeling........................................................................................................................ 7

4.1 Assumptions................................................................................................................. 7

4.2 Bioassay Fitting ............................................................................................................ 7

4.3 Radionuclides and Material Types................................................................................ 7

4.3.1 Strontium-90 ..................................................................................................... 8

4.3.2 Uranium-234 ..................................................................................................... 8

4.3.3 Plutonium-239................................................................................................... 8

4.3.4 Americium-241.................................................................................................. 9

4.3.5 Additional Radionuclides................................................................................... 9

5.0 Assignment of Intakes and Doses ............................................................................................ 9

5.1 Contribution from Additional Radionuclides ................................................................ 10

5.2 Dose Assignment ....................................................................................................... 10

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

ATTACHMENT A............................................................................................................................... 15

LIST OF TABLES

TABLE TITLE PAGE

5-1 Combined 90Sr Type F intake periods and rates..................................................................... 10

5-2 Combined 90Sr Type S intake periods and rates..................................................................... 10

5-3 Annual 234U Type F, M, and S intake periods and rates.......................................................... 12

5-4 Annual 239Pu Type M intakes and rates.................................................................................. 13

5-5 Annual 239Pu Type S intakes and rates................................................................................... 13

5-6 241Am Type M intake periods and rates ................................................................................. 13

A-1 Statistical summary of annual ORNL strontium 24-hour urinary 

excretion rates, 1951 to 1988................................................................................................. 15

A-2 Statistical summary of annual ORNL uranium 24-hour urinary excretion 

rates, 1951 to 1987 ................................................................................................................ 16

A-3 Statistical summary of annual ORNL plutonium 24-hour urinary 

excretion rates, 1951 to 1988................................................................................................. 17

A-4 Statistical summary of annual ORNL americium 24-hour urinary 

excretion rates, 1968 to 1987................................................................................................. 18

A-5 Type F 90Sr intake periods and rates...................................................................................... 18

A-6 Type S 90Sr intake periods and rates...................................................................................... 21
Document No. ORAUT-OTIB-0034 Revision No. 02 Effective Date: 01/21/2014 Page 4 of 37

A-7 Type F 234U intake periods and rates...................................................................................... 22

A-8 Type M 234U intake periods and rates..................................................................................... 24

A-9 Type S 234U intake periods and rates ..................................................................................... 29

A-10 Type M 239Pu intake periods and rates ................................................................................... 32

A-11 Type S 239Pu intake periods and rates.................................................................................... 35

A-12 Type M 241Am intake periods and rates .................................................................................. 37

LIST OF FIGURES

FIGURE TITLE PAGE

A-1 Assumed 90Sr intake, 1951 to 1988, 50th-percentile results, Type F ...................................... 18

A-2 Assumed 90Sr intake, 1951 to 1953, 50th-percentile results, Type S...................................... 19

A-3 Assumed 90Sr intake, 1954, 50th-percentile results, Type S................................................... 19

A-4 Assumed 90Sr intake, 1955 to 1964, 50th-percentile results, Type S...................................... 19

A-5 Assumed 90Sr intake, 1965 to 1983, 50th-percentile results, Type S...................................... 20

A-6 Assumed 90Sr intake, 1983 to 1988, 50th-percentile results, Type S...................................... 20

A-7 Predicted strontium excretion rate from independently fit intakes, 1951 

to 1988, 50th-percentile results, Type S................................................................................. 20

A-8 Assumed 234U intake, 1951 to 1987, 50th-percentile results, Type F...................................... 21

A-9 Assumed 234U intake, 1951 to 1987, 50th-percentile results, Type M ..................................... 23

A-10 Assumed 234U intake, 1951 to 1955, 50th-percentile results, Type S...................................... 25

A-11 Assumed 234U intake, 1956, 50th-percentile results, Type S................................................... 25

A-12 Assumed 234U intake, 1957 to 1958, 50th-percentile results, Type S...................................... 26

A-13 Assumed 234U intake, 1959 to 1961, 50th-percentile results, Type S...................................... 26

A-14 Assumed 234U intake, 1962 to 1963, 50th-percentile results, Type S...................................... 27

A-15 Assumed 234U intake, 1964 to 1982, 50th-percentile results, Type S...................................... 27

A-16 Assumed 234U intake, 1983 to 1987, 50th-percentile results, Type S...................................... 28

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

to 1987, 50th-percentile, Type S ............................................................................................ 28

A-18 Assumed 239Pu intake, 1951 to 1952, 50th-percentile results, Type M.................................... 30

A-19 Assumed 239Pu intake, 1953 to 1968, 50th-percentile results, Type M.................................... 30

A-20 Assumed 239Pu intake, 1969 to 1984, 50th-percentile results, Type M.................................... 30

A-21 Assumed 239Pu intake, 1985 to 1988, 50th-percentile results, Type M.................................... 31

A-22 Predicted 239Pu intake, 1951 to 1988, 50th-percentile composite 

results, Type M ......................................................................................................................31

A-23 Assumed 239Pu intake, 1951 to 1952, 50th-percentile results, Type S................................... 33

A-24 Assumed 239Pu intake, 1953 to 1968, 50th-percentile results, Type S.................................... 33

A-25 Assumed 239Pu intake, 1969 to 1984, 50th-percentile results, Type S.................................... 33

A-26 Assumed 239Pu intake, 1985 to 1988, 50th-percentile results, Type S.................................... 34

A-27 Predicted 239Pu intake, 1951 to 1988, 50th-percentile composite 

results, Type S.......................................................................................................................34

A-28 Assumed 241Am intake, 1968 to 1984, 50th-percentile results, Type M................................... 36

A-29 Assumed 241Am intake, 1985 to 1988, 50th-percentile results, Type M................................... 36

A-30 Predicted 241Am intake, 1968 to 1988, 50th-percentile composite 

results, Type M ......................................................................................................................36
Document No. ORAUT-OTIB-0034 Revision No. 02 Effective Date: 01/21/2014 Page 5 of 37

ACRONYMS AND ABBREVIATIONS 

CER Center for Epidemiologic Research

d day

DOE U.S. Department of Energy

DOL U.S. Department of Labor

dpm disintegrations per minute

EDP Electronic Data Processing

EEOICPA Energy Employees Occupational Illness Compensation Program Act of 2000

GM geometric mean

GSD geometric standard deviation

hr hour 

ICRP International Commission on Radiological Protection

IMBA Integrated Modules for Bioassay Analysis

IREP Interactive RadioEpidemiological Program

m meter

mL milliliter

NIOSH National Institute for Occupational Safety and Health

OCAS Office of Compensation Analysis and Support

ORISE Oak Ridge Institute for Science and Education

ORNL Oak Ridge National Laboratory

POC probability of causation

TIB technical information bulletin

U.S.C. United States Code

μCi microcurie

μm micrometer

§ section or sections
Document No. ORAUT-OTIB-0034 Revision No. 02 Effective Date: 01/21/2014 Page 6 of 37

1.0 PURPOSE

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 U.S.C. § 7384l(5) and (12)].

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 U.S. Department of Energy (DOE) 

facility, or whose records of such monitoring are incomplete or unavailable. In such cases, data from 

coworkers can be used to approximate an individual’s possible exposure. The purpose of this 

document is to provide the details of the calculation and assignment of intakes based on coworker 

data from Oak Ridge National Laboratory (ORNL) for the purpose of estimating unmonitored 

exposures or if records of monitoring are incomplete or unavailable, whether for discrete periods or for 

the entire period of employment.

2.0 OVERVIEW

Analysis of Coworker Bioassay Data for Internal Dose Assignment (ORAUT 2005) describes the 

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

coworker results.

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 for the 

purpose of conducting an epidemiology study of site workers. The database results are in units of 

disintegrations per minute (dpm)/24 hours. Because of the varied operations at the different ORNL 

facilities over time with the potential for exposure from numerous different radionuclides, 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 the X-10 site profile (ORAUT 2013a). 

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 TP0 and TP for transplutonium radionuclides, primarily 241Am 

(5,670 entries from 1968 to 1987). Transplutonium radionuclides are assumed to be and are modeled 

as 241Am for this coworker study. Further review of these data indicated that, except for follow-up 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 (2005). The resultant values were input to the Integrated 

Modules for Bioassay Analysis (IMBA) Expert OCAS-Edition computer program, and a fit to the data 
Document No. ORAUT-OTIB-0034 Revision No. 02 Effective Date: 01/21/2014 Page 7 of 37

for each of the four radionuclides was performed to obtain intake rates for assigning dose 

distributions.

3.0 DATA

3.1 SELECTED BIOASSAY DATA

Data for each of the EDP codes considered were extracted from a series of Microsoft® Access files 

that contain a version of the ORISE/CER Dosimetry Database. These files were titled 

“tblORNL_Urinalysis_rawData,” for 1951–1978, 1979–1985, and 1986–1988. 

3.2 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 (2005). Tables A-1 

through A-4 in Attachment A show the statistical analysis results for strontium, uranium, plutonium, 

and americium, respectively. 

4.0 INTAKE MODELING

4.1 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, thus weighting all results equally. A chronic exposure pattern was 

assumed; while this is unlikely for workers at ORNL, it will approximate 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 (AMAD) particle size distribution.

4.2 BIOASSAY FITTING

The IMBA Expert OCAS-Edition computer program was 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 the Type S strontium, uranium, and plutonium isotopes and Type M plutonium and 

americium isotopes present 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 will result in an 

overestimate of intakes, particularly for assumed Type S exposures extending through multiple 

assumed intake periods.

4.3 RADIONUCLIDES AND MATERIAL TYPES

For each radionuclide considered, the bioassay results were entered into IMBA with assumed material 

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

result 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 
Document No. ORAUT-OTIB-0034 Revision No. 02 Effective Date: 01/21/2014 Page 8 of 37

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. 

4.3.1 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 titanite form, bioassay results for 90Sr were fit using 

Type F and S material. Figure A-1 in Attachment A shows the individual fits to the 50th-percentile 

intake values for Type F 90Sr. Table A-5 summarizes the intake periods and corresponding intake 

rates for the 50th- and 84th-percentile values, and the geometric standard deviations (GSDs) for 

Type F 90Sr . The GSDs were determined by dividing the 84th-percentile intake rates by the 50thpercentile 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 corresponding intake rates for 

the 50th- and 84th-percentile values, and 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 was, therefore, omitted from the sample set. 

4.3.2 Uranium-234

Because a variety of uranium enrichments and exposure conditions are 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 does not affect the fitting of the data for intake 

determination (i.e., 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. The International Commission 

on Radiological Protection (ICRP) Publication 68 (ICRP 1994) 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 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 is found in many 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 individual fits for the 50th-percentile values 

for Type F and M 234U, respectively. Table A-7 summarizes the intake periods for the 50th- and 84thpercentile values, and the calculated GSDs for Type F 234U, while Table A-8 lists similar information 

for Type M 234U. Again, the GSDs were determined by dividing the 84th-percentile intake rates by the 

50th-percentile intake rates. For Type S 234U, 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 50thpercentile intake values. Table A-9 summarizes the intake periods and corresponding intake rates for 

the 50th- and 84th-percentile values, and the calculated GSDs for Type S 234U. Plots of the results of 

the individual fits to the 84th-percentile values for all three solubility types are not shown here 

because they were largely in agreement. 

4.3.3 Plutonium-239 

For this analysis, the analyzed material types for 239Pu are assumed to be types M and S. 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 
Document No. ORAUT-OTIB-0034 Revision No. 02 Effective Date: 01/21/2014 Page 9 of 37

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 239Pu. Table A-10 summarizes the intake 

periods and corresponding intake rates for the 50th- and 84th-percentile values, and the GSDs for 

Type M 239Pu. The GSDs were determined by dividing the 84th-percentile intake rates by the 50thpercentile intake rates. Again, the same intake periods were applied to the 84th-percentile values for 

Type M 239Pu because the values followed a similar pattern; results of the individual fits 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 239Pu. Table A-11 summarizes the intake period and corresponding intake rate for the 50thand 84th-percentile values, and the GSDs for Type S 239Pu. 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 S 239Pu because the values followed a similar 

pattern; results of the fit are not shown here because they were largely in agreement.

4.3.4 Americium-241

ICRP Publication 68 (ICRP 1994) assigns all forms of americium to Type M. Figures A-28 and A-29 

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-30 shows the composite of the subsets of selected 

years used to fit the 50th-percentile intake values for Type M 241Am. Table A-12 summarizes the 

intake periods and corresponding intake rates for the 50th- and 84th-percentile values, and 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 because the values followed a similar pattern; results of the individual fits are not 

shown here because they were largely in agreement.

4.3.5 Additional Radionuclides 

Hundreds of different radionuclides were 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 DoseRelated Gross Beta and Gross Gamma Analyses (ORAUT 2013b). 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 3030-3047) or at the Pilot 

Plant (former Plutonium Separations Building).

5.0 ASSIGNMENT OF INTAKES AND DOSES

The resulting calculated intake rate information, useful in dose reconstruction for the radionuclides 

identified for ORNL, is discussed in this section. For each radionuclide, the 50th- and 95th-percentile 

intake rates, and 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 solubility type that results in the largest probability of causation (POC)1

. The GSD 

values have been adjusted from the values in the tables in Appendix 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 

 

1 The U.S. Department of Labor (DOL) is responsible under EEOICPA for determining the POC.
Document No. ORAUT-OTIB-0034 Revision No. 02 Effective Date: 01/21/2014 Page 10 of 37

there is justification that the individual might have had larger intakes 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 5-1 for Type F 

material and Table 5-2 for Type S material. There were five intake periods defined for 90Sr 

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

Table 5-1. Combined 90Sr Type F intake periods and rates

(dpm/d). 

Date range 90Sr Type F intake rate 

From To 50th percentile GSD 95th percentile

1/1/1951 12/31/1953 475.2 10.0 20,983

1/1/1954 12/31/1954 80.99 10.0 3,576

1/1/1955 12/31/1960 47.34 4.17 496

1/1/1961 12/31/1964 47.34 3.00 288

1/1/1965 12/31/1988 15.52 3.00 94.57

Table 5-2. Combined 90Sr Type S intake periods and rates

(dpm/d). 

Date range 90Sr Type S intake rate 

From To 50th percentile GSD 95th percentile

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

1/1/1954 12/31/1954 7,232 9.53 295,030

1/1/1955 12/31/1960 2,379 5.73 42,030

1/1/1961 12/31/1964 2,379 3.00 14,496

1/1/1965 12/31/1983 795.0 3.00 4,844

1/1/1984 12/31/1988 425.5 4.51 5,070

• Uranium-234. Table 5-3 lists the calculated annual intake rates for 234U for 1951 through 

1987 for Types F, M, and S material.

• Plutonium-239.

 Tables 5-4 and 5-5 list the calculated annual intake rates for 239Pu for 

Types M and S material, respectively, for 1951 through 1988. 

• Americium-241.

 Table 5-6 lists the combined 241Am Type M material intake periods and rates 

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

5.1 CONTRIBUTION FROM ADDITIONAL RADIONUCLIDES

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 2013b) applied to the strontium 

intakes given above.

5.2 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 (which is determined by DOL) is selected. A comparison of the intake rates shows:

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

unless Computer Aided Telephone Interview information or related bioassay results indicate 

there was a potential for exposure to strontium titanate (SrTiO3) or the individual worked in a 

location where it was found (Building 3517), in which case Type S intakes should be assigned. 
Document No. ORAUT-OTIB-0034 Revision No. 02 Effective Date: 01/21/2014 Page 11 of 37

If an individual was exposed only to Type S material (titanate), intakes of associated 

radionuclides as discussed in ORAUT-OTIB-0054 (ORAUT 2013b) should not be included. 

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 3030-3047) or at the Pilot Plant (former Plutonium Separations 

Building). 

• For 234U, the calculated intake rates for Type S material are one to two orders of magnitude 

higher than the intake rates of Type F and M material for all intake periods. Again, because 

Type S material remains in the lungs while Type F and M material is transferred to the 

systemic organs, it is necessary to compare the annual doses on a case-by-case basis to 

determine which will deliver the larger dose to the organ of interest. 

• For 239Pu, the calculated intake rates for Type S material are 1 to 2 orders of magnitude higher 

than the intake rates of Type M material for all intake periods. Again, because Type S material 

remains in the lungs while Type M material is transferred to the systemic organs, it is 

necessary to compare the annual doses on a case-by-case basis to determine which will 

deliver the larger dose to the organ of interest. The potential for Type Super S solubility 

plutonium should also be considered.

• For 241Am, the calculated intake rates for Type M material should be used for all organs and 

intake periods, as listed in Table 5-6.

• When a Type F 90Sr intake is assigned, the worker should also be assigned intakes of 

associated radionuclides as discussed in ORAUT-OTIB-0054 (ORAUT 2013b).

The lognormal distribution is 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 

2013b) intakes of associated radionuclides. 
Document No. ORAUT-OTIB-0034 Revision No. 02 Effective Date: 01/21/2014 Page 12 of 37

Table 5-3. 234U Type F, M, and S intake periods and rates (dpm/d). 

Year

U-234 Type F intake rate U-234 Type M intake rate U-234 Type S intake rate

50th percentile GSD 95th percentile 50th percentile GSD 95th percentile 50th percentile GSD 95th percentile

1951 11.19 3.08 71.20 47.03 3.33 340.2 850.7 3.0 5,184

1952 11.19 3.08 71.20 47.03 3.33 340.2 850.7 3.0 5,184

1953 11.19 3.08 71.20 47.03 3.33 340.2 850.7 3.00 5,184

1954 11.19 3.08 71.20 47.03 3.33 340.2 850.7 3.00 5,184

1955 11.19 3.08 71.20 47.03 3.33 340.2 850.7 3.00 5,184

1956 4.213 6.71 96.51 11.45 9.70 480.9 675.7 3.00 4,117

1957 1.942 9.25 75.43 7.49 9.70 314.6 247.7 7.74 7,176

1958 1.942 9.25 75.43 7.49 9.70 314.6 247.7 7.74 7,176

1959 5.171 3.48 40.22 21.81 3.33 157.8 509 4.17 5,331

1960 5.171 3.48 40.22 21.81 3.33 157.8 509 4.17 5,331

1961 5.171 3.48 40.22 21.81 3.33 157.8 509 4.17 5,331

1962 1.881 6.71 43.09 6.56 7.24 170.3 235.3 6.04 4,533

1963 1.881 6.71 43.09 6.56 7.24 170.3 235.3 6.04 4,533

1964 0.413 3.08 2.63 1.641 3.33 11.87 23.7 3.00 144.4

1965 0.413 3.08 2.63 1.641 3.33 11.87 23.7 3.00 144.4

1966 0.413 3.08 2.63 1.641 3.33 11.87 23.7 3.00 144.4

1967 0.413 3.08 2.63 1.641 3.33 11.87 23.7 3.00 144.4

1968 0.413 3.08 2.63 1.641 3.33 11.87 23.7 3.00 144.4

1969 0.413 3.08 2.63 1.641 3.33 11.87 23.7 3.00 144.4

1970 0.413 3.08 2.63 1.641 3.33 11.87 23.7 3.00 144.4

1971 0.413 3.08 2.63 1.641 3.33 11.87 23.7 3.00 144.4

1972 0.413 3.08 2.63 1.641 3.33 11.87 23.7 3.00 144.4

1973 0.413 3.08 2.63 1.641 3.33 11.87 23.7 3.00 144.4

1974 0.413 3.08 2.63 1.641 3.33 11.87 23.7 3.00 144.4

1975 0.413 3.08 2.63 1.641 3.33 11.87 23.7 3.00 144.4

1976 0.413 3.08 2.63 1.641 3.33 11.87 23.7 3.00 144.4

1977 0.413 3.08 2.63 1.641 3.33 11.87 23.7 3.00 144.4

1978 0.413 3.08 2.63 1.641 3.33 11.87 23.7 3.00 144.4

1979 0.413 3.08 2.63 1.641 3.33 11.87 23.7 3.00 144.4

1980 0.413 3.08 2.63 1.641 3.33 11.87 23.7 3.00 144.4

1981 0.413 3.08 2.63 1.641 3.33 11.87 23.7 3.00 144.4

1982 0.413 3.08 2.63 1.641 3.33 11.87 23.7 3.00 144.4

1983 0.413 3.08 2.63 1.641 3.33 11.87 15.25 4.67 192.4

1984 0.413 3.08 2.63 1.641 3.33 11.87 15.25 3.0 92.93

1985 0.0957 3.08 0.609 0.294 3.33 2.127 15.25 3.0 92.93

1986 0.0957 3.08 0.609 0.294 3.33 2.127 15.25 3.0 92.93

1987 0.0957 3.08 0.609 0.294 3.33 2.127 15.25 3.0 92.93
Document No. ORAUT-OTIB-0034 Revision No. 02 Effective Date: 01/21/2014 Page 13 of 37

Table 5-4. 239Pu Type M intake periods and rates 

(dpm/d). 

Years

Pu-239 Type M intake rate

50th percentile GSD 95th percentile

1951–1952 40.75 3.0 248

1953–1959 10.98 7.9 329

1960–1968 10.98 3.0 66.9

1969–1984 7.35 3.0 44.8

1985–1988 1.614 4.2 17.1

Table 5-5. 239Pu Type S intake periods and rates

(dpm/d). 

Year

Pu-239 Type S intake rate

50th percentile GSD 95th percentile

1951–1952 1,489 3.00 9,073

1953–1959 159.8 11.06 8,325

1960–1968 159.8 3.00 973

1969–1972 118.5 3.40 886

1973–1984 118.5 3.00 722

1985–1988 36.26 5.46 592

Table 5-6. 241Am Type M intake periods and rates (dpm/d). 

Year

Am-241 Type M intake rate

50th percentile GSD 95th percentile 

1968–1984 6.673 3.00 40.66

1985–1988 2.207 3.00 13.45
Document No. ORAUT-OTIB-0034 Revision No. 02 Effective Date: 01/21/2014 Page 14 of 37

REFERENCES

ICRP (International Commission on Radiological Protection), 1994, Dose Coefficients for Intakes of 

Radionuclides by Workers, Publication 68, Pergamon Press, Oxford, England.

ORAUT (Oak Ridge Associated Universities Team), 2005, Analysis of Coworker Bioassay Data for 

Internal Dose Assignment, ORAUT-OTIB-0019, Rev. 01, Oak Ridge, Tennessee, October 7.

ORAUT (Oak Ridge Associated Universities Team), 2013a, Oak Ridge National Laboratory – 

Occupational Internal Dose, ORAUT-TKBS-0012-5, Rev. 02, Oak Ridge, Tennessee, February 

8.

ORAUT (Oak Ridge Associated Universities Team), 2013b, Fission and Activation Product 

Assignment for Internal Dose-Related Gross Beta and Gross Gamma Analyses, ORAUTOTIB-0054, Rev 01, Oak Ridge, Tennessee, June 13.
Document No. ORAUT-OTIB-0034 Revision No. 02 Effective Date: 01/21/2014 Page 15 of 37

Table A-1. Statistical summary of annual ORNL strontium 

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

Effective 

bioassay 

date

GM 

(50th) 

GM × GSD

(84th) 

No. of 

samples

No. of 

employees

7/1/1952 109.15 1,008.55 134 16

7/1/1954 24.68 241.98 246 162

7/1/1955 13.10 63.17 722 534

7/1/1956 13.54 82.88 705 538

7/1/1957 15.71 68.85 879 566

7/1/1958 17.01 75.45 1,394 620

7/1/1959 12.20 59.03 1,035 623

7/1/1960 15.67 65.07 624 364

7/1/1961 9.48 28.06 1,328 952

7/1/1962 12.04 29.49 2,440 1,579

7/1/1963 10.08 26.23 2,328 1,524

N/Aa N/Aa N/Aa

7/1/1965 4.86 15.75 2,203 1,649

7/1/1966 3.62 17.78 1,619 1,274

7/1/1967 3.35 12.86 1,609 1,332

7/1/1968 1.02 7.77 1,147 915

7/1/1969 3.89 8.96 1,295 1,028

7/1/1970 6.07 13.96 636 456

7/1/1971 6.91 15.08 607 437

7/1/1972 7.54 22.75 358 211

7/1/1973 5.18 13.45 397 316

7/1/1974 7.66 24.76 282 217

7/1/1975 5.27 10.68 290 239

7/1/1976 5.14 11.59 270 201

7/1/1977 5.19 11.58 168 120

7/1/1978 5.04 9.61 149 109

7/1/1979 2.44 6.68 215 169

7/1/1980 5.69 23.05 242 162

7/1/1981 3.04 7.22 159 127

7/1/1982 5.23 12.06 146 98

7/1/1983 5.71 14.48 145 96

7/1/1984 4.38 14.14 136 88

7/1/1985 2.11 5.93 161 134

7/1/1986 0.67 2.88 221 168

7/1/1987 3.37 15.98 228 151

7/1/1988 0.56 1.96 275 225

a. Insufficient data for analysis.

ATTACHMENT A

Page 1 of 23
Document No. ORAUT-OTIB-0034 Revision No. 02 Effective Date: 01/21/2014 Page 16 of 37

Table A-2. Statistical summary of annual ORNL uranium 

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

Effective

bioassay

date

GM

(50th)

GM × GSD 

(84th)

No. of

samples

No. of

employees

7/1/1951 3.41 7.81 351 262

7/1/1952 2.88 8.01 722 419

7/1/1953 3.64 7.54 615 494

7/1/1954 2.27 5.46 851 665

7/1/1955 3.07 9.34 823 591

7/1/1956 1.20 8.16 783 531

7/1/1957 0.50 3.65 942 664

7/1/1958 0.64 4.74 992 553

7/1/1959 1.43 6.93 745 461

7/1/1960 1.36 3.97 506 324

7/1/1961 1.52 5.73 686 456

7/1/1962 0.52 3.57 439 290

7/1/1963 0.58 3.24 698 389

7/1/1964 0.25 1.29 875 541

7/1/1965 0.17 0.62 1462 1178

7/1/1966 0.18 0.52 782 597

7/1/1967 0.09 0.21 687 530

7/1/1968 0.13 0.34 512 324

7/1/1969 0.10 0.33 457 268

7/1/1970 0.16 0.65 281 176

7/1/1971 0.09 0.26 288 201

7/1/1972 0.13 0.39 256 145

7/1/1973 0.07 0.30 278 206

7/1/1974 0.06 0.22 188 138

7/1/1975 0.08 0.32 219 149

7/1/1976 0.10 0.46 229 135

7/1/1977 0.20 0.48 191 131

7/1/1978 0.14 0.31 240 165

7/1/1979 0.14 0.52 318 213

7/1/1980 0.11 0.39 261 189

7/1/1981 0.13 0.22 179 145

7/1/1982 0.17 0.31 141 99

7/1/1983 0.12 0.28 167 106

7/1/1984 0.10 0.19 203 141

7/1/1985 0.07 0.17 217 158

7/1/1986 0.04 0.08 163 128

7/1/1987 0.00 0.03 212 164

ATTACHMENT A

Page 2 of 23
Document No. ORAUT-OTIB-0034 Revision No. 02 Effective Date: 01/21/2014 Page 17 of 37

Table A-3. Statistical summary of annual ORNL plutonium 

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

Effective 

bioassay 

date

GM 

(50th)

GM × GSD 

(84th) 

No. of 

samples

No. of 

employees

7/1/1951 0.13 0.30 507 260

7/1/1952 0.11 0.31 668 394

7/1/1953 0.04 0.14 446 394

7/1/1954 0.07 0.36 972 583

7/1/1955 0.07 0.26 740 525

7/1/1956 0.04 0.36 627 473

7/1/1957 0.14 0.73 674 423

7/1/1958 0.15 0.52 785 400

7/1/1959 0.12 0.62 889 460

7/1/1960 0.13 0.28 1927 595

7/1/1961 0.07 0.21 1758 983

7/1/1962 0.01 0.08 2680 1658

7/1/1963 0.01 0.09 2825 1624

7/1/1964 0.08 0.23 2147 1446

7/1/1965 0.13 0.26 1237 746

7/1/1966 0.12 0.21 1179 803

7/1/1967 0.10 0.19 1247 927

7/1/1968 0.12 0.24 1262 775

7/1/1969 0.04 0.17 1356 927

7/1/1970 0.08 0.19 828 481

7/1/1971 0.06 0.23 792 484

7/1/1972 0.06 0.18 686 350

7/1/1973 0.03 0.11 675 420

7/1/1974 0.06 0.12 529 350

7/1/1975 0.04 0.12 487 335

7/1/1976 0.05 0.13 532 341

7/1/1977 0.07 0.15 418 272

7/1/1978 0.06 0.15 431 262

7/1/1979 0.08 0.14 380 219

7/1/1980 0.05 0.11 320 215

7/1/1981 0.09 0.16 323 224

7/1/1982 0.10 0.17 345 226

7/1/1983 0.07 0.13 329 211

7/1/1984 0.07 0.11 370 237

7/1/1985 0.01 0.05 368 253

7/1/1986 0.01 0.04 297 212

7/1/1987 0.01 0.04 234 185

7/1/1988 0.00 0.03 169 128

ATTACHMENT A

Page 3 of 23
Document No. ORAUT-OTIB-0034 Revision No. 02 Effective Date: 01/21/2014 Page 18 of 37

Table A-4. Statistical summary of annual ORNL americium

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

Effective 

bioassay 

date

GM 

(50th) 

GM × GSD 

(84th) 

No. of 

samples

No. of 

employees

7/1/1968 0.12 0.31 405 216

7/1/1969 0.10 0.42 455 253

7/1/1970 0.10 0.33 514 267

7/1/1971 0.09 0.24 444 262

7/1/1972 0.12 0.27 503 271

7/1/1973 0.09 0.16 547 336

7/1/1974 0.08 0.15 351 206

7/1/1975 0.12 0.30 367 246

7/1/1976 0.15 0.52 475 274

7/1/1977 0.11 0.18 358 223

7/1/1978 0.10 0.18 403 241

7/1/1979 0.10 0.17 279 196

7/1/1980 0.10 0.14 267 189

7/1/1981 0.07 0.17 289 213

1/1/1983 0.10 0.17 561 272

7/1/1984 0.10 0.15 345 225

7/1/1985 0.05 0.09 342 258

7/1/1986 0.01 0.05 280 217

7/1/1987 0.01 0.04 199 181

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

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

Start date End date

Sr-90 intake rate

50th percentile 84th percentile GSD

1/1/1951 12/31/1953 475.2 4,389 9.24

1/1/1954 12/31/1954 80.99 810.4 10.04

1/1/1955 12/31/1960 47.34 197.3 4.17

1/1/1961 12/31/1964 47.34 62.43 1.32

1/1/1965 12/31/1988 15.52 36.88 2.38

• annual bioassay

value (50th percentile)

● not used in fit

____ fit

ATTACHMENT A

Page 4 of 23
Document No. ORAUT-OTIB-0034 Revision No. 02 Effective Date: 01/21/2014 Page 19 of 37

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

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.

• 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

ATTACHMENT A

Page 5 of 23
Document No. ORAUT-OTIB-0034 Revision No. 02 Effective Date: 01/21/2014 Page 20 of 37

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

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

Figure A-7. Predicted strontium excretion rate from independently fit intakes, 

1951 to 1988, 50th-percentile results, Type S.

• 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

ATTACHMENT A

Page 6 of 23
Document No. ORAUT-OTIB-0034 Revision No. 02 Effective Date: 01/21/2014 Page 21 of 37

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

Start date End date

Sr-90 intake rate

50th percentile 84th percentile GSD

1/1/1951 12/31/1953 24,646 227,730 9.24

1/1/1954 12/31/1954 7,232 68,924 9.53

1/1/1955 12/31/1960 2379 13,628 5.73

1/1/1961 12/31/1964 2,389 6,431 2.69

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

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

Figure A-8. Assumed 234U intake, 1951 to 1987, 50th-percentile results, Type F.

• annual bioassay

value (50th percentile)

● not used in fit

____ fit

ATTACHMENT A

Page 7 of 23
Document No. ORAUT-OTIB-0034 Revision No. 02 Effective Date: 01/21/2014 Page 22 of 37

Table A-7. Type F 234U intake periods and rates

(dpm/d).

Year

Type F U-234 intake rate

50th percentile 84th percentile GSD

1951 11.19 28.28 2.53

1952 11.19 28.28 2.53

1953 11.19 28.28 2.53

1954 11.19 28.28 2.53

1955 11.19 28.28 2.53

1956 4.213 28.28 6.71

1957 1.942 17.97 9.25

1958 1.942 17.97 9.25

1959 5.171 17.97 3.48

1960 5.171 17.97 3.48

1961 5.171 17.97 3.48

1962 1.881 12.05 6.41

1963 1.881 12.05 6.41

1964 0.413 1.272 3.08

1965 0.413 1.272 3.08

1966 0.413 1.272 3.08

1967 0.413 1.272 3.08

1968 0.413 1.272 3.08

1969 0.413 1.272 3.08

1970 0.413 1.272 3.08

1971 0.413 1.272 3.08

1972 0.413 1.272 3.08

1973 0.413 1.272 3.08

1974 0.413 1.272 3.08

1975 0.413 1.272 3.08

1976 0.413 1.272 3.08

1977 0.413 1.272 3.08

1978 0.413 1.272 3.08

1979 0.413 1.272 3.08

1980 0.413 1.272 3.08

1981 0.413 1.272 3.08

1982 0.413 1.272 3.08

1983 0.413 1.272 3.08

1984 0.413 1.272 3.08

1985 0.0957 0.227 2.37

1986 0.0957 0.227 2.37

1987 0.0957 0.227 2.37

ATTACHMENT A

Page 8 of 23
Document No. ORAUT-OTIB-0034 Revision No. 02 Effective Date: 01/21/2014 Page 23 of 37

Figure A-9. Assumed 234U intake, 1951 to 1987, 50th-percentile results, Type M.

• annual bioassay

value (50th percentile)

● not used in fit

____ fit

ATTACHMENT A

Page 9 of 23
Document No. ORAUT-OTIB-0034 Revision No. 02 Effective Date: 01/21/2014 Page 24 of 37

Table A-8. Type M 234U intake periods and rates

(dpm/d).

Year

Type M U-234 intake rate

50th percentile 84th percentile GSD

1951 47.03 117.8 2.50

1952 47.03 117.8 2.50

1953 47.03 117.8 2.50

1954 47.03 117.8 2.50

1955 47.03 117.8 2.50

1956 11.45 117.8 10.29

1957 7.49 72.66 9.70

1958 7.49 72.66 9.70

1959 21.81 72.66 3.33

1960 21.81 72.66 3.33

1961 21.81 72.66 3.33

1962 6.56 47.49 7.24

1963 6.56 47.49 7.24

1964 1.641 4.809 2.93

1965 1.641 4.809 2.93

1966 1.641 4.809 2.93

1967 1.641 4.809 2.93

1968 1.641 4.809 2.93

1969 1.641 4.809 2.93

1970 1.641 4.809 2.93

1971 1.641 4.809 2.93

1972 1.641 4.809 2.93

1973 1.641 4.809 2.93

1974 1.641 4.809 2.93

1975 1.641 4.809 2.93

1976 1.641 4.809 2.93

1977 1.641 4.809 2.93

1978 1.641 4.809 2.93

1979 1.641 4.809 2.93

1980 1.641 4.809 2.93

1981 1.641 4.809 2.93

1982 1.641 4.809 2.93

1983 1.641 4.809 2.93

1984 1.641 4.809 2.93

1985 0.294 0.659 2.24

1986 0.294 0.659 2.24

1987 0.294 0.659 2.24

ATTACHMENT A

Page 10 of 23
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Figure A-10. Assumed 234U intake, 1951 to 1955, 50th-percentile results, 

Type S.

Figure A-11. Assumed 234U intake, 1956, 50th-percentile results, Type S.

• annual bioassay

value (50th percentile)

● not used in fit

____ fit

• annual bioassay

value (50th percentile)

● not used in fit

____ fit

ATTACHMENT A

Page 11 of 23
Document No. ORAUT-OTIB-0034 Revision No. 02 Effective Date: 01/21/2014 Page 26 of 37

Figure A-12. Assumed 234U intake, 1957 to 1958, 50th-percentile results, 

Type S.

Figure A-13. Assumed 234U intake, 1959 to 1961, 50th-percentile results, 

Type S.

• annual bioassay

value (50th percentile)

● not used in fit

____ fit

• annual bioassay

value (50th percentile)

● not used in fit

____ fit

ATTACHMENT A

Page 12 of 23
Document No. ORAUT-OTIB-0034 Revision No. 02 Effective Date: 01/21/2014 Page 27 of 37

Figure A-14. Assumed 234U intake, 1962 to 1963, 50th-percentile results, 

Type S.

Figure A-15. Assumed 234U intake, 1964 to 1982, 50th-percentile results, 

Type S.

• annual bioassay

value (50th percentile)

● not used in fit

____ fit

• annual bioassay

value (50th percentile)

● not used in fit

____ fit

ATTACHMENT A

Page 13 of 23
Document No. ORAUT-OTIB-0034 Revision No. 02 Effective Date: 01/21/2014 Page 28 of 37

Figure A-16. Assumed 234U intake, 1983 to 1987, 50th-percentile results, Type S.

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

1951 to 1987, 50th-percentile, Type S.

• annual bioassay

value (50th percentile)

● not used in fit

____ fit

• annual bioassay

value (50th percentile)

● not used in fit

____ fit

ATTACHMENT A

Page 14 of 23
Document No. ORAUT-OTIB-0034 Revision No. 02 Effective Date: 01/21/2014 Page 29 of 37

Table A-9. Type S 234U intake periods and rates

(dpm/d).

Year

Type S U-234 intake rate

50th percentile 84th percentile GSD

1951 850.7 2048 2.41

1952 850.7 2048 2.41

1953 850.7 2048 2.41

1954 850.7 2048 2.41

1955 850.7 2048 2.41

1956 675.7 2048 3.03

1957 247.7 1,917 7.74

1958 247.7 1,917 7.74

1959 509 1,917 3.77

1960 509 2,125 4.17

1961 509 2,125 4.17

1962 235.3 1,422 6.04

1963 235.3 1,422 6.04

1964 23.7 71.203 3.00

1965 23.7 71.203 3.00

1966 23.7 71.203 3.00

1967 23.7 71.203 3.00

1968 23.7 71.203 3.00

1969 23.7 71.203 3.00

1970 23.7 71.203 3.00

1971 23.7 71.203 3.00

1972 23.7 71.203 3.00

1973 23.7 71.203 3.00

1974 23.7 71.203 3.00

1975 23.7 71.203 3.00

1976 23.7 71.203 3.00

1977 23.7 71.203 3.00

1978 23.7 71.203 3.00

1979 23.7 71.203 3.00

1980 23.7 71.203 3.00

1981 23.7 71.203 3.00

1982 23.7 71.203 3.00

1983 15.25 71.203 4.67

1984 15.25 31.58 2.07

1985 15.25 31.58 2.07

1986 15.25 31.58 2.07

1987 15.25 31.58 2.07

ATTACHMENT A

Page 15 of 23
Document No. ORAUT-OTIB-0034 Revision No. 02 Effective Date: 01/21/2014 Page 30 of 37

Figure A-18. Assumed 239Pu intake, 1951 to 1952, 50th-percentile results, Type M.

Figure A-19. Assumed 239Pu intake, 1953 to 1968, 50th-percentile results, 

Type M.

Figure A-20. Assumed 239Pu intake, 1969 to 1984, 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

• annual bioassay

value (50th percentile)

● not used in fit

____ fit

ATTACHMENT A

Page 16 of 23
Document No. ORAUT-OTIB-0034 Revision No. 02 Effective Date: 01/21/2014 Page 31 of 37

Figure A-21. Assumed 239Pu intake, 1985 to 1988, 50th-percentile results, 

Type M.

Figure A-22. Predicted 239Pu intake, 1951 to 1988, 50th-percentile composite 

results, Type M.

• annual bioassay

value (50th percentile)

● not used in fit

____ fit

ATTACHMENT A

Page 17 of 23
Document No. ORAUT-OTIB-0034 Revision No. 02 Effective Date: 01/21/2014 Page 32 of 37

Table A-10. Type M 239Pu intake periods and rates

(dpm/d).

Year

Pu-239 intake rate

50th percentile 84th percentile GSD

1951 40.75 109.8 2.69

1952 40.75 109.8 2.69

1953 10.98 86.42 7.87

1954 10.98 86.42 7.87

1955 10.98 86.42 7.87

1956 10.98 86.42 7.87

1957 10.98 86.42 7.87

1958 10.98 86.42 7.87

1959 10.98 86.42 7.87

1960 10.98 22.45 2.04

1961 10.98 22.45 2.04

1962 10.98 22.45 2.04

1963 10.98 22.45 2.04

1964 10.98 22.45 2.04

1965 10.98 22.45 2.04

1966 10.98 22.45 2.04

1967 10.98 22.45 2.04

1968 10.98 22.45 2.04

1969 7.35 22.45 3.05

1970 7.35 22.45 3.05

1971 7.35 22.45 3.05

1972 7.35 22.45 3.05

1973 7.35 18.4 2.50

1974 7.35 18.4 2.50

1975 7.35 18.4 2.50

1976 7.35 18.4 2.50

1977 7.35 18.4 2.50

1978 7.35 18.4 2.50

1979 7.35 18.4 2.50

1980 7.35 18.4 2.50

1981 7.35 18.4 2.50

1982 7.35 18.4 2.50

1983 7.35 18.4 2.50

1984 7.35 18.4 2.50

1985 1.614 6.811 4.22

1986 1.614 6.811 4.22

1987 1.614 6.811 4.22

1988 1.614 6.811 4.22

ATTACHMENT A

Page 18 of 23
Document No. ORAUT-OTIB-0034 Revision No. 02 Effective Date: 01/21/2014 Page 33 of 37

Figure A-23. Assumed 239Pu intake, 1951 to 1952, 50th-percentile results, Type S.

Figure A-24. Assumed 239Pu intake, 1953 to 1968, 50th-percentile results, Type S.

Figure A-25. Assumed 239Pu intake, 1969 to 1984, 50th-percentile results, Type S.

ATTACHMENT A

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Document No. ORAUT-OTIB-0034 Revision No. 02 Effective Date: 01/21/2014 Page 34 of 37

Figure A-26. Assumed 239Pu intake, 1985 to 1988, 50th-percentile results, Type S.

Figure A-27. Predicted 239Pu intake, 1951 to 1988, 50th-percentile composite results, Type S.

ATTACHMENT A

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Document No. ORAUT-OTIB-0034 Revision No. 02 Effective Date: 01/21/2014 Page 35 of 37

Table A-11. Type S 239Pu intake periods and rates

(dpm/d).

Year

Pu-239 intake rate

50th percentile 84th percentile GSD

1951 1489 3874 2.60

1952 1489 3874 2.60

1953 159.8 1767 11.06

1954 159.8 1767 11.06

1955 159.8 1767 11.06

1956 159.8 1767 11.06

1957 159.8 1767 11.06

1958 159.8 1767 11.06

1959 159.8 1767 11.06

1960 159.8 402.5 2.52

1961 159.8 402.5 2.52

1962 159.8 402.5 2.52

1963 159.8 402.5 2.52

1964 159.8 402.5 2.52

1965 159.8 402.5 2.52

1966 159.8 402.5 2.52

1967 159.8 402.5 2.52

1968 159.8 402.5 2.52

1969 118.5 402.5 3.40

1970 118.5 402.5 3.40

1971 118.5 402.5 3.40

1972 118.5 402.5 3.40

1973 118.5 296.5 2.5

1974 118.5 296.5 2.5

1975 118.5 296.5 2.5

1976 118.5 296.5 2.5

1977 118.5 296.5 2.5

1978 118.5 296.5 2.5

1979 118.5 296.5 2.5

1980 118.5 296.5 2.5

1981 118.5 296.5 2.5

1982 118.5 296.5 2.5

1983 118.5 296.5 2.5

1984 118.5 296.5 2.5

1985 36.26 198 5.46

1986 36.26 198 5.46

1987 36.26 198 5.46

1988 36.26 198 5.46

ATTACHMENT A

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Document No. ORAUT-OTIB-0034 Revision No. 02 Effective Date: 01/21/2014 Page 36 of 37

Figure A-28. Assumed 241Am intake, 1968 to 1984, 50th-percentile results, 

Type M.

Figure A-29. Assumed 241Am intake, 1985 to 1988, 50th-percentile results, 

Type M.

Figure A-30. Predicted 241Am intake, 1968 to 1988, 50th-percentile composite 

results, Type M.

• 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

ATTACHMENT A

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Document No. ORAUT-OTIB-0034 Revision No. 02 Effective Date: 01/21/2014 Page 37 of 37

Table A-12. Type M 241Am intake periods and rates

(dpm/d).

Start Stop

Am-241 intake rate

50th percentile 84th percentile GSD

1968 1984 6.673 14.61 2.19

1985 1988 2.207 6.659 2.99

ATTACHMENT A

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