ORAU TEAM

Dose Reconstruction

Project for NIOSH

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

Page 1 of 29

Document Title:

Internal Dosimetry Coworker Data for X-10

Document Number: ORAUT-OTIB-0034

Revision: 00

Effective Date: 12/13/2005

Type of Document: OTIB

Supersedes: None

Subject Expert: William E. Kennedy, Jr.

Document Owner

Approval: Signature on File Approval Date: 12/07/2005

Judson L. Kenoyer, Task 3 Manager

Concurrence: Signature on File Concurrence Date: 12/07/2005

Kate Kimpan, Project Director

Approval: Signature on File Approval Date: 12/13/2005

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. 00 Effective Date: 12/13/2005 Page 2 of 29

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.
Document No. ORAUT-OTIB-0034 Revision No. 00 Effective Date: 12/13/2005 Page 3 of 29

TABLE OF CONTENTS

SECTION TITLE

1.0 Purpose ...................................................................................................................................

PAGE

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...................................................................................................9

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

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

5.0 Assignment of Intakes and Doses .......................................................................................... 10

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

 5.2 Dose Assignment .......................................................................................................11

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

ATTACHMENT A...............................................................................................................................15
Document No. ORAUT-OTIB-0034 Revision No. 00 Effective Date: 12/13/2005 Page 4 of 29

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.......................................................... 11

5-4 Annual 239Pu Type M intakes and rates.................................................................................. 12

5-5 Annual 239Pu Type S intakes and rates................................................................................... 12

5-6 Combined 241Am Type M intake periods and rates ................................................................. 12

5-7 Evaluation of the contribution of additional radionuclides ....................................................... 13

A-1 Statistical summary of annual ORNL strontiumX-10 90Sr 24-hour urinary excretion 

rates, 1951-1988....................................................................................................................15

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

1951-1987..............................................................................................................................15

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

1951-1988..............................................................................................................................16

A-4 Statistical summary of annual ORNL transplutonium 24-hour urinary excretion 

rates, 1968-1987....................................................................................................................16

A-5 Type F 90Sr intake periods and rates...................................................................................... 17

A-6 Type S 90Sr intake periods and rates...................................................................................... 19

A-7 Type F 234U intake periods and rates...................................................................................... 20

A-8 Type M 234U intake periods and rates..................................................................................... 21

A-9 Type S 234U intake periods and rates ..................................................................................... 25

A-10 Type M 239Pu intake periods and rates ................................................................................... 27

A-11 Type S 239Pu intake period and rates ..................................................................................... 28

A-12 Type M 241Am intake periods and rates .................................................................................. 29
Document No. ORAUT-OTIB-0034 Revision No. 00 Effective Date: 12/13/2005 Page 5 of 29

LIST OF FIGURES

FIGURE TITLE PAGE

A-1 Assumed 90Sr intake, 1951 to 1988, 50th-percentile results, Type F ...................................... 17

A-2 Assumed 90Sr intake, 1951 to 1953, 50th-percentile results, Type S...................................... 17

A-3 Assumed 90Sr intake, 1954, 50th-percentile results, Type S................................................... 18

A-4 Assumed 90Sr intake, 1955 to 1964, 50th-percentile results, Type S...................................... 18

A-5 Assumed 90Sr intake, 1965 to 1983, 50th-percentile results, Type S...................................... 18

A-6 Assumed 90Sr intake, 1983 to 1988, 50th-percentile results, Type S...................................... 19

A-7 Predicted strontium excretion rate from independently fit intakes, 1951 to 1988, 

50th-percentile, Type S.......................................................................................................... 19

A-8 Assumed 234U intake, 1951 to 1988, 50th-percentile results, Type F...................................... 20

A-9 Assumed 234U intake, 1951 to 1988, 50th-percentile results, Type M ..................................... 21

A-10 Assumed 234U intake, 1951 to 1952, 50th-percentile results, Type S...................................... 22

A-11 Assumed 234U intake, 1953 to 1956, 50th-percentile results, Type S...................................... 22

A-12 Assumed 234U intake, 1957 to 1958, 50th-percentile results, Type S...................................... 22

A-13 Assumed 234U intake, 1959 to 1961, 50th-percentile results, Type S...................................... 23

A-14 Assumed 234U intake, 1962 to 1963, 50th-percentile results, Type S...................................... 23

A-15 Assumed 234U intake, 1964 to 1982, 50th-percentile results, Type S...................................... 23

A-16 Assumed 234U intake, 1983 to 1987, 50th-percentile results, Type S...................................... 24

A-17 Predicted uranium excretion rate from independently fit intakes, 1951 to 1988, 

50th-percentile, Type S.......................................................................................................... 24

A-18 Assumed 239Pu intake, 1951 to 1952, 50th-percentile results, Type M.................................... 25

A-19 Assumed 239Pu intake, 1953 to 1968, 50th-percentile results, Type M.................................... 26

A-20 Assumed 239Pu intake, 1969 to 1984, 50th-percentile results, Type M.................................... 26

A-21 Assumed 239Pu intake, 1985 to 1988, 50th-percentile results, Type M.................................... 26

A-22 Predicted 239Pu intake, 1951 to 1988, 50th-percentile composite results, Type M .................. 27

A-23 Assumed 239Pu intake, 1951 to 1988, 50th-percentile composite results, Type S................... 28

A-24 Assumed 241Am intake, 1968 to 1984, 50th-percentile results, Type M................................... 28

A-25 Assumed 241Am intake, 1985 to 1988, 50th-percentile results, Type M................................... 29

A-26 Predicted 241Am intake, 1968 to 1988, 50th-percentile composite results, Type M ................. 29
Document No. ORAUT-OTIB-0034 Revision No. 00 Effective Date: 12/13/2005 Page 6 of 29

1.0

Technical Information Bulletins (TIBs) are general working documents that provide guidance

concerning the preparation of dose reconstructions at particular sites or categories of sites. They will 

be revised in the event additional relevant information is obtained. TIBs may be used to assist the 

National Institute for Occupational Safety and Health in the completion of individual dose 

reconstructions.

PURPOSE

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 facility" as defined in the Energy Employees 

Occupational Illness Compensation Program Act of 2000 [42 U.S.C. § 7384I(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 may 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 where records of monitoring are incomplete or unavailable, whether for discrete periods 

or for the entire period of employment.

2.0

Analysis of Coworker Bioassay Data for Internal Dose Assignment (ORAU 2004a) describes the 

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

coworker results.

OVERVIEW

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 the period 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 5.1.5.2 of the X-10 Technical Basis 

Document (TBD) (ORAU 2004b). In summary, data were stored under 64 different 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 of the EDP codes contained enough entries to allow 

statistical evaluation for purposes of dose reconstruction. These EDP codes 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). 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 ORAU (2004a). The resultant values were input to the Integrated Modules for 

Bioassay Analysis (IMBA) Expert OCAS-Edition computer program, and a fit to the data for each of 

the four radionuclides was performed to obtain intake rates for assigning dose distributions.
Document No. ORAUT-OTIB-0034 Revision No. 00 Effective Date: 12/13/2005 Page 7 of 29

3.0

 3.1

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 the periods 1951-1978, 1979-1985, 

and 1986-1988. 

Selected Bioassay Data

3.2

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 ORAU (2004a). Tables A-1 through A-4 in Attachment A show the 

statistical analysis results for strontium, uranium, plutonium, and transplutonium.

Analysis

4.0

 4.1

INTAKE MODELING

All results were assumed to be representative of a full day (24 hr) 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.

Assumptions

4.2

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. 

Bioassay Fitting

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

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 displayed in the figures in Attachment 

A. In these figures, annual bioassay data used in the fits are shown as the 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 of the intake periods to the bioassay data. 

Radionuclides And Material Types
Document No. ORAUT-OTIB-0034 Revision No. 00 Effective Date: 12/13/2005 Page 8 of 29

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. 

4.3.1

Strontium results were assumed to be Sr-90. 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 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 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 since they were largely in agreement. It is 

noted that the urinalysis data for 1964 were insufficient to support a complete 

analysis and was therefore was omitted from the sample set. 

Strontium-90

4.3.2

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 

relative to the assumed intake period. The ICRP 68 (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 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 claimant-favorability of the doses.

Uranium-234

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 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 84th-percentile values, and the 

calculated GSDs for Type F 234U, while Table A-8 shows 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 50th-percentile intake values. Table A-9 summarizes the intake periods 

and corresponding intake rates for the 50th- and 84th-percentile values, and the 
Document No. ORAUT-OTIB-0034 Revision No. 00 Effective Date: 12/13/2005 Page 9 of 29

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 since 

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 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 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 since they were largely 

in agreement.

Figure A-23 shows the fit for Type S material based on a chronic intake for the 

entire set of years fitted to the bioassay data for the last three years (1986 

through 1988). Table A-11 summarizes the intake period and corresponding 

intake rate for the 50th- and 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 since they were largely in 

agreement.

4.3.4

ICRP 68 (1995) assigns all forms of americium to Type M. Figures A-24 and A25 show the fits corresponding to each of the subsets of years across the intake 

period used to develop the composite figure. Figure A-26 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 since they were 

largely in agreement.

Americium-241

4.3.5 Additional Radionuclides

It is recognized that hundreds of different radionuclides were present at ORNL

at some point during its operations. However, bioassay data for additional 

radionuclides beyond 90Sr, 238U, 239Pu, and 241Am were deemed to be of little 

use for coworker estimations, largely because there were too few 

measurements to be statistically reliable for intake estimation. For this analysis, 

three additional radionuclides, both important to internal dosimetry and present 

in the reported air monitoring data, were considered. These are 106Ru, 137Cs, 

and 144Ce. 
Document No. ORAUT-OTIB-0034 Revision No. 00 Effective Date: 12/13/2005 Page 10 of 29

5.0

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 84th-percentile intake rates, and the GSDs, are provided in specific tables. The 

GSD values have been adjusted from the values given 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 

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.

ASSIGNMENT OF INTAKES AND DOSES

• Strontium-90. For 90Sr, several intake periods were defined as shown in Table 5-1 for 

Type F material and Table 5-2 for Type S material. Note that there were five intake 

periods defined for 90Sr Type F intakes and six intake periods defined for 90Sr Type S

intakes.

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

and rates.

Date range

90Sr Type F intake rate, 

dpm/d

From To 50th percentile GSD

1/1/1951 12/31/1953 475.2 10.0

1/1/1954 12/31/1954 80.99 10.0

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

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

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

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

and rates.

Date range

90Sr Type S intake rate, 

dpm/d

From To 50th percentile GSD

1/1/1951 12/31/1953 24646 9.53

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

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

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

1/1/1965 12/31/1983 795.0 3.00

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

• Uranium-234. Table 5-3 contains the calculated annual intake rates for the years 

1951 through 1987, for Types F, M, and S material.

• Plutonium-239.

 Tables 5-4 and 5-5 contains the calculated annual intake rates for 

239Pu for Types M and S material respectively for the years 1951 through 1988. 

• Americium-241.

 Table 5-6 contains the combined 241Am Type M material intake 

periods and rates for 1968 through 1988. Note that there were two intake periods 

defined.

5.1

To account for additional intakes, an evaluation of air monitoring data from the ORNL 

perimeter reporting stations for the period 1975 through 1984 was conducted. The 

approach was to develop the ratios of the isotopic concentration ratios of other 

radionuclides to the concentration ratio of 90Sr reported in the air monitoring data. The 

Contribution From Additional Radionuclides
Document No. ORAUT-OTIB-0034 Revision No. 00 Effective Date: 12/13/2005 Page 11 of 29

results of this evaluation are summarized in Table 5-7, which shows the reported 

radionuclide concentrations, the ratio of the concentrations of the three selected 

radionuclides to 90Sr, the peak concentration ratio, range of the concentration ratios, 

and the average concentration ratio. 

5.2

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 the Department of Labor) is 

selected. A comparison of the intake rates shows:

Dose Assignment

• For 90Sr, the calculated intake rates for Type S material are one to two orders of 

magnitude higher than the intake rates of Type F material for all intake periods. 

However, because the Type S material remains in the lungs for an extended period 

while the Type F 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.

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

Year

234U Type F intake rate, dpm/d 234U Type M intake rate, dpm/d 234U Type S intake rate, dpm/d

50th 

percentile GSD

50th 

percentile GSD

50th 

percentile GSD

1951 11.19 3.08 47.03 3.33 850.7 3.0

1952 11.19 3.08 47.03 3.33 850.7 3.0

1953 11.19 3.08 47.03 3.33 850.7 3.00

1954 11.19 3.08 47.03 3.33 850.7 3.00

1955 11.19 3.08 47.03 3.33 850.7 3.00

1956 4.213 6.71 11.45 9.70 675.7 3.00

1957 1.942 9.25 7.49 9.70 247.7 7.74

1958 1.942 9.25 7.49 9.70 247.7 7.74

1959 5.171 3.48 21.81 3.33 509 4.17

1960 5.171 3.48 21.81 3.33 509 4.17

1961 5.171 3.48 21.81 3.33 509 4.17

1962 1.881 6.71 6.56 7.24 235.3 6.04

1963 1.881 6.71 6.56 7.24 235.3 6.04

1964 0.413 3.08 1.641 3.33 23.7 3.00

1965 0.413 3.08 1.641 3.33 23.7 3.00

1966 0.413 3.08 1.641 3.33 23.7 3.00

1967 0.413 3.08 1.641 3.33 23.7 3.00

1968 0.413 3.08 1.641 3.33 23.7 3.00

1969 0.413 3.08 1.641 3.33 23.7 3.00

1970 0.413 3.08 1.641 3.33 23.7 3.00

1971 0.413 3.08 1.641 3.33 23.7 3.00

1972 0.413 3.08 1.641 3.33 23.7 3.00

1973 0.413 3.08 1.641 3.33 23.7 3.00

1974 0.413 3.08 1.641 3.33 23.7 3.00

1975 0.413 3.08 1.641 3.33 23.7 3.00

1976 0.413 3.08 1.641 3.33 23.7 3.00

1977 0.413 3.08 1.641 3.33 23.7 3.00

1978 0.413 3.08 1.641 3.33 23.7 3.00

1979 0.413 3.08 1.641 3.33 23.7 3.00

1980 0.413 3.08 1.641 3.33 23.7 3.00

1981 0.413 3.08 1.641 3.33 23.7 3.00

1982 0.413 3.08 1.641 3.33 23.7 3.00

1983 0.413 3.08 1.641 3.33 15.25 4.67
Document No. ORAUT-OTIB-0034 Revision No. 00 Effective Date: 12/13/2005 Page 12 of 29

1984 0.413 3.08 1.641 3.33 15.25 3.0

1985 0.0957 3.08 0.294 3.33 15.25 3.0

1986 0.0957 3.08 0.294 3.33 15.25 3.0

1987 0.0957 3.08 0.294 3.33 15.25 3.0

Table 5-4. Annual 239Pu Type M intakes and 

rates.

Years

239Pu Type M intake rate, dpm/d

50th percentile GSD

1951-1952 40.75 3.0

1953-1959 10.98 7.9

1960-1968 10.98 3.0

1969-1984 7.35 3.0

1985-1988 1.614 4.2

Table 5-5. Annual 239Pu Type S intakes and 

rates.

Year

239Pu Type S intake rate, 

dpm/d

50th 

percentile GSD

1951-

1988 4.15 5.50

• 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 M material should be used for all 

systemic organs and intake periods. For non-systemic (respiratory and GI tracts) 

organs, the type S intake rate may only be used as an underestimate. If an 

overestimate or best estimate is needed for non-systemic organs, an individualized fit 

to the bioassay data, assuming type S material, for the specific work period of the 

Energy Employee being evaluated must be performed. Table A-3 provides the 

bioassay data to be used to perform the individualized fit. Both the 50th- and 84thpercentile values must be fit using the same intake dates and/or periods; the 50thpercentile intakes are used to assign the intake and the 84th-percentile is used to 

determine the GSD for each intake. The GSD for each intake will be the ratio of the 

84th percentile intake rate to the 50th percentile intake rate. For input into IREP, the 

dose from each intake must be determined separately.

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

and intake periods as given in Table 5-6.

Table 5-6. Combined 241Am Type M intake periods and 

rates.

Year

241Am Type M intake rate, dpm/d

50th percentile 84th percentile GSD

1968-1984 6.673 14.61 3.00

1985-1988 2.207 6.659 3.00
Document No. ORAUT-OTIB-0034 Revision No. 00 Effective Date: 12/13/2005 Page 13 of 29

• When a 90Sr intake is assigned, the worker should also be assigned intakes of 106Ru, 

137Cs, and 144Ce, consistent with the average isotopic ratios developed from the air 

monitoring data given in Table 5-7, using the 90Sr intake as the basis. For example, if a 

worker were exposed in 1965 to Type F 90Sr, the intake (from Table 5-1) would be 15.5 

dpm/d. Intake of 106Ru would also be assigned at a value of 103.8 dpm/d (i.e., 15.5 

dpm/d of 90Sr times 6.7, the average ratio of 106Ru to 90Sr from Table 5-7), along with a 

34.1 dpm/d intake of 137Cs and 170.5 dpm/d intake of 144Ce. Although Table 5-7 is 

based on data from 1975 through 1984, the average ratios calculated should be used 

for all years. 

The lognormal distribution is selected in the Interactive RadioEpidemiological Program 

(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. The GSD for 90Sr should be 

assigned when intakes of 106Ru, 137Cs, and/or 144Ce are included.

Table 5-7. Evaluation of the contribution of additional radionuclides.

Year

Reported 90Sr 

concentration 

(10-15 μCi/mL)

Reported 106Ru 

concentration 

(10-15 μCi/mL)

Ratio: 

106Ru to 

90Sr

Reported 137Cs 

concentration 

(10-15 μCi/mL)

Ratio: 

137Cs to 

90Sr

Reported 144Ce 

concentration 

(10-15 μCi/mL)

Ratio: 

144Ce to 

90Sr

1975a 0.78 6.7 8.6 1.4 1.8 11 14

1976 a 0.77 0.88 1.1 0.55 0.7 2.4 3.1

1977 a 1.30 11 8.5 1.60 1.2 21 16

1978 a 0.81 9.7 12 2.14 2.6 16 19

1979 a 0.15 1.56 10 0.67 4.5 1.8 12

1980 a 0.08 0.49 6.1 0.37 4.6 0.98 12

1981 a 0.46 4.40 9.6 1.2 2.6 11 24

1982 a 0.15 0.40 2.7 0.24 1.6 0.03 0.2

1983 a 0.08 0.12 1.5 0.10 1.2 N/A N/A

1984 a 0.07 N/A N/A 0.07 1.0 N/A N/A

Peak ratio - - 12 - 5 - 24

Ratio range - - 1.1 - 12 - 0.7 – 4.6 - 0.2 - 24

Average ratio - - 6.7 - 2.2 - 11

a. References: 1975 – (Union Carbide 1975); 1976 – (Union Carbide 1976); 1977 – (Union Carbide 1977); 1978 – (Union Carbide 1978); 

1979 – (Union Carbide 1979); 1980 – (Union Carbide 1980); 1981 – (Union Carbide 1981); 1982 – (Union Carbide 1982); 1983 –

(Martin Marietta 1983); and 1984 – (Martin Marietta 1984).
Document No. ORAUT-OTIB-0034 Revision No. 00 Effective Date: 12/13/2005 Page 14 of 29

REFERENCES

ICRP (International Commission on Radiological Protection), 1959, Report of ICRP Committee II on 

Permissible Dose for Internal Radiation, Publication 2, Pergamon Press, Oxford, England.

ICRP (International Commission on Radiological Protection), 1993, Report of a Task Group of ICRP 

Committee II on Dose Coefficients for Intakes of Radionuclides by Workers, Publication 68, 

Pergamon Press, Oxford, England.

Martin Marietta, 1983, Environmental Monitoring Report – United States Department of Energy, Oak 

Ridge Facilities – Calendar Year 1983, Y/UB-19, Oak Ridge, Tennessee.

Martin Marietta, 1984, Environmental Monitoring Report – United States Department of Energy, Oak 

Ridge Facilities – Calendar Year 1984, Y/UB-20, Oak Ridge, Tennessee.

ORAU (Oak Ridge Associated Universities), 2004a, Analysis of Coworker Bioassay Data for Internal 

Dose Assignment, ORAUT-OTIB-0019, Oak Ridge, Tennessee.

ORAU (Oak Ridge Associated Universities), 2004b, Technical Basis Document for the Oak Ridge 

National Laboratory – Occupational Internal Dose, ORAUT-TKBS-0012-5, Oak Ridge, 

Tennessee.

Union Carbide, 1975, Environmental Monitoring Report – United States Energy Research and 

Development Administration, Oak Ridge Facilities - Calendar Year 1975, Y/UB-4, Oak Ridge, 

Tennessee.

Union Carbide, 1976, Environmental Monitoring Report – United States Energy Research and 

Development Administration, Oak Ridge Facilities - Calendar Year 1976, Y/UB-6, Oak Ridge, 

Tennessee.

Union Carbide, 1977, Environmental Monitoring Report – United States Department of Energy, Oak 

Ridge Facilities - Calendar Year 1977, Y/UB-8, Oak Ridge, Tennessee.

Union Carbide, 1978, Environmental Monitoring Report – United States Department of Energy, Oak 

Ridge Facilities- Calendar Year 1978, Y/UB-10, Oak Ridge, Tennessee.

Union Carbide, 1979, Environmental Monitoring Report – United States Department of Energy, Oak 

Ridge Facilities - Calendar Year 1979, Y/UB-13, Oak Ridge, Tennessee.

Union Carbide, 1980, Environmental Monitoring Report – United States Department of Energy, Oak 

Ridge Facilities - Calendar Year 1980, Y/UB-15, Oak Ridge, Tennessee.

Union Carbide, 1981, Environmental Monitoring Report – United States Department of Energy, Oak 

Ridge Facilities - Calendar Year 1981, Y/UB-16, Oak Ridge, Tennessee.

Union Carbide, 1982, Environmental Monitoring Report – United States Energy Department of 

Energy, Oak Ridge Facilities - Calendar Year 1982, Y/UB-18, Oak Ridge, Tennessee.
Document No. ORAUT-OTIB-0034 Revision No. 00 Effective Date: 12/13/2005 Page 15 of 29

ATTACHMENT A

Table A-1. Statistical summary of annual ORNL strontium 24-hour urinary excretion rates, 1951-

1988.

Effective 

bioassay date

GM (50th) 

dpm/day

GM*GSD (84th) 

dpm/day

7/1/1952 109.15 1,008.55

7/1/1954 24.68 241.98

7/1/1955 13.10 63.17

7/1/1956 13.54 82.88

7/1/1957 15.71 68.85

7/1/1958 17.01 75.45

7/1/1959 12.20 59.03

7/1/1960 15.67 65.07

7/1/1961 9.48 28.06

7/1/1962 12.04 29.49

7/1/1963 10.08 26.23

N/A* N/A* N/A*

7/1/1965 4.86 15.75

7/1/1966 3.62 17.78

7/1/1967 3.35 12.86

7/1/1968 1.02 7.77

7/1/1969 3.89 8.96

7/1/1970 6.07 13.96

Effective 

bioassay date

GM (50th) 

dpm/day

GM*GSD (84th) 

dpm/day

7/1/1971 6.91 15.08

7/1/1972 7.54 22.75

7/1/1973 5.18 13.45

7/1/1974 7.66 24.76

7/1/1975 5.27 10.68

7/1/1976 5.14 11.59

7/1/1977 5.19 11.58

7/1/1978 5.04 9.61

7/1/1979 2.44 6.68

7/1/1980 5.69 23.05

7/1/1981 3.04 7.22

7/1/1982 5.23 12.06

7/1/1983 5.71 14.48

7/1/1984 4.38 14.14

7/1/1985 2.11 5.93

7/1/1986 0.67 2.88

7/1/1987 3.37 15.98

7/1/1988 0.56 1.96

* Insufficient data for analysis.

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

Effective 

bioassay date

GM (50th) 

dpm/day

GM*GSD (84th) 

dpm/day

7/1/1951 3.41 7.81

7/1/1952 2.88 8.01

7/1/1953 3.64 7.54

7/1/1954 2.27 5.46

7/1/1955 3.07 9.34

7/1/1956 1.20 8.16

7/1/1957 0.50 3.65

7/1/1958 0.64 4.74

7/1/1959 1.43 6.93

7/1/1960 1.36 3.97

7/1/1961 1.52 5.73

7/1/1962 0.52 3.57

7/1/1963 0.58 3.24

7/1/1964 0.25 1.29

7/1/1965 0.17 0.62

7/1/1966 0.18 0.52

7/1/1967 0.09 0.21

7/1/1968 0.13 0.34

7/1/1969 0.10 0.33

Effective 

bioassay date

GM (50th) 

dpm/day

GM*GSD (84th) 

dpm/day

7/1/1970 0.16 0.65

7/1/1971 0.09 0.26

7/1/1972 0.13 0.39

7/1/1973 0.07 0.30

7/1/1974 0.06 0.22

7/1/1975 0.08 0.32

7/1/1976 0.10 0.46

7/1/1977 0.20 0.48

7/1/1978 0.14 0.31

7/1/1979 0.14 0.52

7/1/1980 0.11 0.39

7/1/1981 0.13 0.22

7/1/1982 0.17 0.31

7/1/1983 0.12 0.28

7/1/1984 0.10 0.19

7/1/1985 0.07 0.17

7/1/1986 0.04 0.08

7/1/1987 0.00 0.03
Document No. ORAUT-OTIB-0034 Revision No. 00 Effective Date: 12/13/2005 Page 16 of 29

Table A-3. Statistical summary of annual ORNL plutonium 24-hour urinary excretion rates, 1951-

1988.

Effective 

bioassay date

GM (50th) 

dpm/day

GM*GSD (84th) 

dpm/day

7/1/1951 0.13 0.30

7/1/1952 0.11 0.31

7/1/1953 0.04 0.14

7/1/1954 0.07 0.36

7/1/1955 0.07 0.26

7/1/1956 0.04 0.36

7/1/1957 0.14 0.73

7/1/1958 0.15 0.52

7/1/1959 0.12 0.62

7/1/1960 0.13 0.28

7/1/1961 0.07 0.21

7/1/1962 0.01 0.08

7/1/1963 0.01 0.09

7/1/1964 0.08 0.23

7/1/1965 0.13 0.26

7/1/1966 0.12 0.21

7/1/1967 0.10 0.19

7/1/1968 0.12 0.24

7/1/1969 0.04 0.17

Effective 

bioassay date

GM (50th) 

dpm/day

GM*GSD (84th) 

dpm/day

7/1/1970 0.08 0.19

7/1/1971 0.06 0.23

7/1/1972 0.06 0.18

7/1/1973 0.03 0.11

7/1/1974 0.06 0.12

7/1/1975 0.04 0.12

7/1/1976 0.05 0.13

7/1/1977 0.07 0.15

7/1/1978 0.06 0.15

7/1/1979 0.08 0.14

7/1/1980 0.05 0.11

7/1/1981 0.09 0.16

7/1/1982 0.10 0.17

7/1/1983 0.07 0.13

7/1/1984 0.07 0.11

7/1/1985 0.01 0.05

7/1/1986 0.01 0.04

7/1/1987 0.01 0.04

7/1/1988 0.00 0.03

Table A-4. Statistical summary of annual 

ORNL transplutonium 24-hour urinary 

excretion rates, 1968-1987.

Effective 

bioassay date

GM (50th) 

dpm/day

GM*GSD (84th) 

dpm/day

7/1/1968 0.12 0.31

7/1/1969 0.10 0.42

7/1/1970 0.10 0.33

7/1/1971 0.09 0.24

7/1/1972 0.12 0.27

7/1/1973 0.09 0.16

7/1/1974 0.08 0.15

7/1/1975 0.12 0.30

7/1/1976 0.15 0.52

7/1/1977 0.11 0.18

7/1/1978 0.10 0.18

7/1/1979 0.10 0.17

7/1/1980 0.10 0.14

7/1/1981 0.07 0.17

1/1/1983 0.10 0.17

7/1/1984 0.10 0.15

7/1/1985 0.05 0.09

7/1/1986 0.01 0.05

7/1/1987 0.01 0.04
Document No. ORAUT-OTIB-0034 Revision No. 00 Effective Date: 12/13/2005 Page 17 of 29

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

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

Start date End date

90Sr intake rate (dpm/day)

50th percentile 84th percentile GSD

1/1/1951 12/31/1953 475.2 4389 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

Figure A-2. Assumed 90Sr intake, 1951 to 1953, 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
Document No. ORAUT-OTIB-0034 Revision No. 00 Effective Date: 12/13/2005 Page 18 of 29

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.

• 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
Document No. ORAUT-OTIB-0034 Revision No. 00 Effective Date: 12/13/2005 Page 19 of 29

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, Type S.

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

Start date End date

90Sr intake rate (dpm/day)

50th percentile 84th percentile GSD

1/1/1951 12/31/1953 24646 227730 9.24

1/1/1954 12/31/1954 7,232 68924 9.53

1/1/1955 12/31/1960 2379 13628 5.73

1/1/1961 12/31/1964 2,389 6431 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

• annual bioassay

value (50th percentile)

● not used in fit

____ fit

• annual bioassay

value (50th percentile)

● not used in fit

____ fit
Document No. ORAUT-OTIB-0034 Revision No. 00 Effective Date: 12/13/2005 Page 20 of 29

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

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

Year

Type F 234U intake rate (dpm/day)

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

Year

Type F 234U intake rate (dpm/day)

50th percentile 84th percentile GSD

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

• annual bioassay

value (50th percentile)

● not used in fit

____ fit
Document No. ORAUT-OTIB-0034 Revision No. 00 Effective Date: 12/13/2005 Page 21 of 29

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

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

Year

Type M 234U intake rate (dpm/day)

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

Year

Type M 234U intake rate (dpm/day)

50th percentile 84th percentile GSD

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

• annual bioassay

value (50th percentile)

● not used in fit

____ fit
Document No. ORAUT-OTIB-0034 Revision No. 00 Effective Date: 12/13/2005 Page 22 of 29

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.

Figure A-12. Assumed 234

U intake, 1957 to 1958, 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
Document No. ORAUT-OTIB-0034 Revision No. 00 Effective Date: 12/13/2005 Page 23 of 29

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

Type S.

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

• annual bioassay

value (50th percentile)

● not used in fit

____ fit
Document No. ORAUT-OTIB-0034 Revision No. 00 Effective Date: 12/13/2005 Page 24 of 29

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
Document No. ORAUT-OTIB-0034 Revision No. 00 Effective Date: 12/13/2005 Page 25 of 29

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

Year

Type S 234U intake rate (dpm/day) GSD

50th percentile 84th percentile

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

Year

Type S 234U intake rate (dpm/day) GSD

50th percentile 84th percentile

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

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

• annual bioassay

value (50th percentile)

● not used in fit

____ fit
Document No. ORAUT-OTIB-0034 Revision No. 00 Effective Date: 12/13/2005 Page 26 of 29

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.

Figure A-21. Assumed 239Pu intake, 1985 to 1988, 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
Document No. ORAUT-OTIB-0034 Revision No. 00 Effective Date: 12/13/2005 Page 27 of 29

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

results, Type M.

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

Year

239Pu intake rate (dpm/day)

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

Year

239Pu intake rate (dpm/day)

50th percentile 84th percentile GSD

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
Document No. ORAUT-OTIB-0034 Revision No. 00 Effective Date: 12/13/2005 Page 28 of 29

Figure A-23. Assumed 239Pu intake, 1951 to 1988, 50th-percentile composite 

results, Type S.

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

Start date Stop date

241Am intake rate (dpm/day)

50th percentile 84th percentile GSD

1951 1988 4.15 22.86 5.50

Figure A-24. Assumed 241Am intake, 1968 to 1984, 50th-percentile results, 

Type M.

• annual bioassay

value (50th percentile)

● not used in fit

____ fit
Document No. ORAUT-OTIB-0034 Revision No. 00 Effective Date: 12/13/2005 Page 29 of 29

Figure A-25. Assumed 241Am intake, 1985 to 1988, 50th-percentile results, 

Type M.

Figure A-26. Predicted 241Am intake, 1968 to 1988, 50th-percentile composite

results, Type M.

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

Start date Stop date

241Am intake rate (dpm/day)

50th percentile 84th percentile GSD

1968 1984 6.673 14.61 2.19

1985 1988 2.207 6.659 2.99

• annual bioassay

value (50th percentile)

● not used in fit

____ fit

• annual bioassay

value (50th percentile)

● not used in fit

____ fit