Page 1 of 20

This working document prepared by NIOSH’s Division of Compensation Analysis and Support (DCAS) or its contractor for use in discussions with the 

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper documents are not final NIOSH or ABRWH (or their 

technical support and review contractors) positions unless specifically marked as such. This document represents preliminary positions taken on technical 

issues prepared by NIOSH or its contractor. NOTICE: This information is protected by the Privacy Act 5 USC §552a; disclosure to any third party 

without the written consent of the individual(s) to whom the information pertains is strictly prohibited

Dose Reconstruction Methods for

Joslyn Manufacturing and Supply Co.

NIOSH White Paper, Rev. 0

April 17, 2014

Mutty M. Sharfi, Gene Potter, and Billy Smith, ORAUT

Reviewed by:

Sam Glover, DCAS
White Paper, Rev. 0 Dose Reconstruction Methods for Joslyn Manufacturing and Supply Co. April 2014

Page 2 of 20 

This working document prepared by NIOSH or its contractor for use in discussions with the ABRWH or its Working Groups or Subcommittees. Draft, 

preliminary, interim, and White Paper documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions unless 

specifically marked as such. This document represents preliminary positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This 

information is protected by the Privacy Act 5 USC §552a; disclosure to any third party without the written consent of the individual(s) to whom the 

information pertains is strictly prohibited

Purpose

NIOSH found that it is not possible to completely reconstruct uranium and thorium internal radiation doses at

Joslyn Manufacturing and Supply Co. (Joslyn), in Fort Wayne, Indiana, for the time period of March 1, 1943 

through July 31, 1947. NIOSH finds that dose reconstruction is possible for the remaining covered time period of 

August 1, 1948 through December 31, 1952. This White Paper discusses the NIOSH-proposed dose 

reconstruction (DR) methods at the Joslyn facility for the workers not included in the Special Exposure Cohort, as 

well as for the partial DR methods for the SEC time period. The methods described in this document are intended

to supplement (and in some cases replace) the methods provided in the Joslyn SEC ER and ER Addendum1.

Internal Dose

There was no bioassay monitoring at Joslyn and a limited number of air samples taken during the entire covered

period. In the ER, NIOSH compared the Joslyn-specific air sampling data to the air sampling data for the 

corresponding time periods in Battelle-TBD-6000, Site Profiles for Atomic Weapons Employers that Worked 

Uranium Metals. Because the Joslyn dataset has limitations on its use for dose reconstruction, NIOSH chose to 

initiate this comparison to verify if the well-validated data set of Battelle-TBD-6000 was an appropriate upper 

bound for the available Joslyn data. NOSH compared the 1952 Joslyn un-weighted breathing zone (BZ) air 

concentration data for rolling operations to the Battelle-TBD-6000 Finishing Roll Operator and Rouging Roll 

Operator air concentration data, which are the two highest-exposure rolling jobs documented in Battelle TBD6000. While the purpose and end uses of the uranium products coming out of Joslyn after 1948 changed, the basic 

product (rolled and finished rods) did not. While it is reasonable to presume that the Rolling Operator values 

would continue to represent the highest-exposure jobs at Joslyn following the production rolling period in 1948, 

NIOSH has included both the Rolling and Machining Operator categories. Table A-1 of Attachment A provides a 

listing of uranium rolling days. Table A-2 of Attachment A lists uranium machining days. Table A-3 of the same 

attachment provides a list of thorium rolling and machining days for the covered time period at Joslyn. 

Tables A-4 and A-5 of Attachment A provide a comparison between the Joslyn rolling operation air concentration

data and the Battelle-TBD-6000 air concentration data that was depicted in the ER. The 1952 study presented in 

Table A-4 is the only time-weighted-average (TWA) study located for Joslyn. As can be seen, each arithmetic 

mean (AM) of the distribution with the given geometric mean (GM) and a geometric standard deviation (GSD) of 

5 is generally much higher than the 1952 TWA values obtained at Joslyn. In one location (“9-inch finishing roll 

east”), the Joslyn value was higher. A similar comparison was also made for the limited centerless grinding data 

in 1951. In this case, TWA values were not available, but the average and maximum values of the Joslyn data 

were compared to Battelle-TBD-6000. The results are provided in Table A-5. The conclusion is that results 

favorable to claimants at Joslyn would be obtained by using the machining and rolling operator categories from

Battelle-TBD-6000. Only the operator category shall be used for dose reconstruction in order to insure that the 

data is bounding for internal dose beginning in August of 1948. These are reproductions of tables 7-8 [inhalation] 

and Table 7-9 [ingestion], which appeared in ER Rev. 1. The conclusion was that results favorable to claimants at 

Joslyn would be obtained by using Battelle-TBD-6000. The intake rates from Battelle-TBD-6000 (Table 7-8 

[inhalation] and Table 7-9 [ingestion]) appeared in Rev. 1 of the Joslyn ER as Table 7-3; this table is reproduced 

as Table A-6.

 

1

It should be noted that Tables 7-1 and 7-2 and Figures 7-1 and 7-2 from Rev. 1 of the Joslyn ER have been updated and corrected in this white paper as 

revised in the ER Addendum to address an uncertainty calculation correction and a TWA timeframe adjustment from 2,400 to 2,200 work hours per year for 

the purpose of converting Battelle-TBD-6000 intake rates to an estimated airborne concentration for comparison to the 1952 Joslyn air data.
White Paper, Rev. 0 Dose Reconstruction Methods for Joslyn Manufacturing and Supply Co. April 2014

Page 3 of 20 

This working document prepared by NIOSH or its contractor for use in discussions with the ABRWH or its Working Groups or Subcommittees. Draft, 

preliminary, interim, and White Paper documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions unless 

specifically marked as such. This document represents preliminary positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This 

information is protected by the Privacy Act 5 USC §552a; disclosure to any third party without the written consent of the individual(s) to whom the 

information pertains is strictly prohibited

Description of DR methods for internal dose:

 The uranium exposure rates in Table B-6 associated with rolling and machining operations are based 

on a single shift per workday. For situations where an employee may have worked multiple shifts, 

these intakes are to be adjusted to account for the longer exposures times. In addition, for situations 

where rolling and machining operations may have occurred on the same day, the larger of the two 

exposure rates (but not both) will be applied.

 For the worker’s employment period, determine the number of days that uranium was rolled and 

machined in each year based on research summarized in Tables A-1 and A-2.

 For each operational day, assign intakes based on the intake rates in Battelle-TBD-6000, Table 7.8 

(inhalation) and Table 7.9 (ingestion) also in ER Rev. 1 as Table 7-3 and here as Table A-6). Please 

note that since the intake rates in Battelle-TBD-6000 are based on 365 calendar days/year, it will be 

necessary to convert the intake rates to 250 workdays per year (i.e., to multiply the intake rates by 

365/250). These daily intakes will then be multiplied by the number of rolling or machining days to 

arrive at a total annual intake per year.

 The operator category shall be assumed for all workers.

 For each non-operational day (i.e., no rolling or machining), assign inhalation intakes based on the 

method described Battelle-TBD-6000, Section 7.1.5, using the operator category for all workers. 

Intakes should be based on the following assumptions: operational air concentration of 2,491 pCi/m3; 

deposition velocity of 7.5E-04 m/s; deposition time of 30 days; and a re-suspension factor of 1E-5 

m

-1

. This results in an intake rate for inhalation of 558 pCi per non-operational workday.

 For each non-operational day (i.e., no rolling or machining), ingestion intakes are assigned to be equal 

to the ingestion intakes for machining during the operational period. This results in an ingestion 

intake rate of 588 pCi per non-operational workday prior to 1951, and 539 pCi per non-operational 

workday for 1951 forward.

 For each year of employment, sum the inhalation and ingestion intakes for both operational and nonoperational days, as determined above, and assign assuming 100% uranium-234. 

 For determining the probability of causation (POC), the doses determined above are treated as the 

geometric mean (GM) of a lognormal distribution with geometric standard deviation (GSD) of 5.

Thorium

Extruded thorium rods were centerless ground and medart straightened on two occasions at Joslyn Manufacturing. 

Although the centerless grinding operations could have created respirable particles, the work was performed 

under wet conditions for cooling purposes. Furthermore, these operations occurred during the SEC period for 

which NIOSH has determined it is not feasible to reconstruct internal exposures adequately. Consequently, no 

internal dose is assigned from thorium operations. 
White Paper, Rev. 0 Dose Reconstruction Methods for Joslyn Manufacturing and Supply Co. April 2014

Page 4 of 20 

This working document prepared by NIOSH or its contractor for use in discussions with the ABRWH or its Working Groups or Subcommittees. Draft, 

preliminary, interim, and White Paper documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions unless 

specifically marked as such. This document represents preliminary positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This 

information is protected by the Privacy Act 5 USC §552a; disclosure to any third party without the written consent of the individual(s) to whom the 

information pertains is strictly prohibited

On-site Environmental

Environmental internal doses will not be assigned; only the occupational doses determined by using the above 

procedure, which accounts for any environmental internal exposures, will be employed for all claimants.

External Dose

The principal sources of external radiation doses for members of the evaluated class were exposure to gamma and 

beta radiation associated with handling and working in proximity to uranium and uranium compounds while 

involved in the hot rolling, quenching, straightening, grinding, and cutting of the materials. Some employees 

were also potentially externally exposed to the radiation from re-suspended contamination from uranium metal 

surfaces and the floor during the course of their work with these radioactive materials. The metal workers were

assumed to have been provided annual medical chest X-rays examinations as part of the hazard and health 

monitoring of these workers. 

Since no dosimetry information is available for Joslyn employees, NIOSH will bound the external exposures and 

reconstruct the doses to an employee by using the models, guidance, and default bounding values in BattelleTBD-6000, ORAUT-OTIB-0006, and ORAUT-OTIB-0079. NIOSH will employ these resources to calculate 

external beta and gamma doses from working, as an Operator in the Joslyn plant for all covered years. In 

addition, occupational medical doses from annual X-ray examinations will be assigned for this period of 

employment.

NIOSH understands that exposure to the uranium metal was not a continuous exposure over the course of the 

year; thus, annualized exposure calculations would be a significant overestimate of the actual exposure potential. 

Specific rolling dates are provided in the example DR below. 

DR methods for external dose:

 For each operational day, external doses are based on the exposure rate for the “long billet” at 30.48 

cm provided in Battelle-TBD-6000, Table 6.1. For purposes of dose reconstruction, the numbers of 

rolling days-per-year in the Example DR, Attachment A, Table A-1 are assumed to apply to both 

rolling and machining operations. (See Table A-7 for dose values.)

 Use 10 times the gamma exposure rates at one foot for the beta (skin) exposure rate per guidance in 

Battelle-TBD-6000, Section 3.3.1. (See Table A-7 for dose values.)

 For each non-operational day, external doses are based on the exposure rate associated with 

contaminated air and surfaces provided in Battelle-TBD-6000, Tables 3.9 and 3.10. The nonoperational days in Table B-1 represent the number of days that the workers were in the plant but not 

performing uranium rolling or machining operations. (See Table A-7 for dose values.)

 Occupational X-ray doses are extracted from ORAUT-OTIB-0006 Appendix A in Table A-7 for the 

Lung and Entrance Skin for the PA X-ray projection; each is multiplied by the number of years 

employed for a total dose for the two organs for the number of years worked.

 The dose from submersion in the contaminated plant air for the employment period is determined 

from Battelle-TBD-6000, Table 3.9, and is found to be trivial.
White Paper, Rev. 0 Dose Reconstruction Methods for Joslyn Manufacturing and Supply Co. April 2014

Page 5 of 20 

This working document prepared by NIOSH or its contractor for use in discussions with the ABRWH or its Working Groups or Subcommittees. Draft, 

preliminary, interim, and White Paper documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions unless 

specifically marked as such. This document represents preliminary positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This 

information is protected by the Privacy Act 5 USC §552a; disclosure to any third party without the written consent of the individual(s) to whom the 

information pertains is strictly prohibited

 For each year of employment, sum the annual dose for both rolling and non-operational days, as 

determined above, making sure that any annual dose rates from Battelle-TBD-6000 have been 

normalized to 250 days of exposure.

 For determining the probability of causation (POC), the doses determined above are treated as the 

geometric mean (GM) of a lognormal distribution with geometric standard deviation (GSD) of 5.

Thorium

The Battelle-TBD-6000 modeling for uranium metal was adjusted to thorium dose rates using a computer model 

MCNPX. The estimated dose rate is provided in Table B-8. These doses are applied in IREP as a lognormal 

distribution with a GSD of 5. 

Thorium has a significant number of higher-energy photons in the Th-232 decay chain. Based on the half-lives of 

the progeny, only a partial equilibrium is possible; therefore, it is conservative to state that equilibrium would be 

reached in this decay chain. It has been assumed that Ra-228 and Th-228 progeny were in equilibrium with Th232. Under this assumption, the progeny are the major source of both penetrating and non-penetrating external 

exposure. 

Photon Dose

Photon dose at Joslyn would be primarily made up of Operator exposure to photons from the uranium metal being 

worked at the site, with exposure to contaminated surfaces being a lesser dose contributor. While the preferred 

indicators of external dose are dosimetry measurements, NIOSH has not identified any personnel external 

monitoring records or personal dosimetry data associated with the uranium processing conducted during the 

period under evaluation. Battelle-TBD-6000, Section 6.2, provides guidance on estimating external dose rates 

due to penetrating radiation emitted from the surface of uranium metal. Using the results of Monte Carlo NParticle Transport Code (MCNP) calculations performed for a number of basic shapes, it provides calculated dose 

rates for distances of one centimeter, one foot, and one meter from the surface of the natural uranium metal. 

These dose rates are used to estimate the component of whole-body dose that a worker would receive while 

handling or near uranium metal, applying information that may be available about the specific conditions of a 

worker’s likely exposure. If no information is available about the specific conditions of exposure, Battelle-TBD6000 provides for generic worst-case assumptions to be made about a worker’s exposure conditions. 

Dose reconstruction at Jolsyn will use the operator category for all employees. The potential exposure accrued 

from the presence of contamination on work surfaces would be minor in comparison with the primary exposure to 

the uranium metal.

Beta Dose

Non-penetrating beta dose is primarily associated with the hands and forearms, and then other skin surfaces, of a 

worker who handles uranium metal in close proximity. Battelle-TBD-6000, Section 6.3, details a method to 

estimate skin doses for the hands and forearms of a worker who handles uranium metal as well as the other skin 

surfaces.

Medical X-ray Dose 

Although NIOSH has not located specific parameters associated with occupational medical X-rays (i.e., specific 

information on the X-ray devices), default values of entrance kerma, developed for the most commonly-used 
White Paper, Rev. 0 Dose Reconstruction Methods for Joslyn Manufacturing and Supply Co. April 2014

Page 6 of 20 

This working document prepared by NIOSH or its contractor for use in discussions with the ABRWH or its Working Groups or Subcommittees. Draft, 

preliminary, interim, and White Paper documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions unless 

specifically marked as such. This document represents preliminary positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This 

information is protected by the Privacy Act 5 USC §552a; disclosure to any third party without the written consent of the individual(s) to whom the 

information pertains is strictly prohibited

occupational medical diagnostic procedures, are available in ORAUT-OTIB-0006. These values can be used to 

support bounding the medical X-ray dose for the time period under evaluation. These default values are 

maximum or upper limit values developed from: review of patient doses reported in the literature; machine 

characteristics; and knowledge of X-ray procedures used during different historical time periods. These default 

values can be used in lieu of actual measurement data, or entrance kerma derived from technique factors, to bound 

the occupational X-ray exposures for Joslyn uranium and thorium workers from March 1, 1943 through 

December 31, 1952. For dose reconstruction purposes, a pre-employment, post-employment, and annual 

examination is assumed during the operational period, per guidance in ORAUT-OTIB-0079.

Example DR:

Attachment B on the beginning provides an example dose reconstruction using the approach described in this 

white paper.
White Paper, Rev. 0 Dose Reconstruction Methods for Joslyn Manufacturing and Supply Co. April 2014

Page 7 of 20 

This working document prepared by NIOSH or its contractor for use in discussions with the ABRWH or its Working Groups or Subcommittees. Draft, 

preliminary, interim, and White Paper documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions unless 

specifically marked as such. This document represents preliminary positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This 

information is protected by the Privacy Act 5 USC §552a; disclosure to any third party without the written consent of the individual(s) to whom the 

information pertains is strictly prohibited

References

42 CFR 82, Methods for Radiation Dose Reconstruction Under the Energy Employees Occupational Illness 

Compensation Program Act of 2000; Final Rule, Federal Register/Vol.67, No. 85/Thursday, May 2, 2002, p 

22314, SRDB Ref ID: 19392

42 CFR 81, Guidelines for Determining the Probability of Causation Under the Energy Employees Occupational 

Illness Compensation Program Act of 2000; Final Rule, Federal Register/Vol.67, No. 85/Thursday, May 2, 2002, 

p 22296, SRDB Ref ID: 19391

Battelle, 2011, Battelle-TBD-6000, Rev 1, Site Profiles for Atomic Weapons Employers that Worked Uranium 

Metals, June 17, 2011

NIOSH, (2007) External Dose Reconstruction Implementation Guideline, Rev 3, OCAS-IG-001, National 

Institute for Occupational Safety and Health, Office of Compensation Analysis and Support, Cincinnati, Ohio, 

SRDB Ref ID: 38864

NIOSH Web page, SEC Petition Evaluation Report, Petition SEC-00200 (Joslyn Manufacturing and Supply 

Company), Rev 1, December 3, 2012. [Class Evaluated By NIOSH: May 1, 1943 – December 31, 1952]

NIOSH, Addendum, SEC Petition Evaluation Report, Petition SEC-00200 (Joslyn Manufacturing and Supply 

Company). [Class Evaluated By NIOSH: March 1, 1943 – December 31, 1952]; document currently submitted for 

Board review

ORAUT (Oak Ridge Associated Universities Team), ORAUT-OTIB-0005, Technical Information Bulletin: 

Internal Dosimetry Organ, External Dosimetry Organ, and IREP Model Selection by ICD-9 Code, Rev 02 PC-1, 

February 10, 2006, SRDB Ref ID: 22595

ORAUT (Oak Ridge Associated Universities Team), ORAUT-OTIB-0006, Rev.4; Dose Reconstruction from 

Occupational Medical X-Ray Procedures, June 20, 2011; SRDB Ref ID: 98147

ORAUT (Oak Ridge Associated Universities Team), ORAUT-OTIB-0079, Rev. 00; Guidance on Assigning 

Occupational X-ray Dose Under EEOICPA for X-Rays Administered Off Site; January 3, 2011; SRDB Ref ID: 

89563

ORAUT (Oak Ridge Associated Universities Team), ORAUT-OTIB-0017, Interpretation of Dosimetry Data for 

Assignment of Shallow Dose, Rev 01, October 11, 2005, SRDB Ref ID: 19434

Rad Handbook, 1998, Handbook of Health Physics and Radiological Health, 3rd Edition; editors include Bernard 

Schleien, Lester Slaback, and Brian Kent; 1998; SRDB Ref ID: 22737
White Paper, Rev. 0 Dose Reconstruction Methods for Joslyn Manufacturing and Supply Co. April 2014

Page 8 of 20 

This working document prepared by NIOSH or its contractor for use in discussions with the ABRWH or its Working Groups or Subcommittees. Draft, 

preliminary, interim, and White Paper documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions unless 

specifically marked as such. This document represents preliminary positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This 

information is protected by the Privacy Act 5 USC §552a; disclosure to any third party without the written consent of the individual(s) to whom the 

information pertains is strictly prohibited

Attachment A

Table A-1: Uranium Rolling Days at Joslyn (pages 8 and 9)

Time Period

Rolling 

Days SRDB Ref ID

March 13, 1943 1 82362

June 29, 1943 1 11036, pdf p. 42; 33190, pdf p. 66; 33190, pdf p. 244

January 3 - 14, 1944 1 11036, pdf p. 53

May 3-6, 1944 4 11036, pdf p. 216

May 9 - June 24, 1944 7 33190, pdf p. 67

June 1 - 5, 1944 5 17594, pdf p. 4

June 19 - 20, 1944 2 118502, pdf p. 2

December 7, 1944 1 118144, pdf p.4

December 11 - 28, 

1944 13 34028, pdf p. 42

March - May, 1945 54 31145, pdf p. 196

Unknown date, 1946 ~10-20 90948, pdf p. 8

October 28,1946 ~1-2 93775, pdf p. 6

November, 1946 ~5-10 31145, pdf p. 16

January, 1947 ~5-10 90948, pdf p. 2

August 5 – 6, 1947 2 37411, pdf p. 44; 126764, pdf p. 5; 37374, pdf p. 43; 16511, pdf pp. 3, 5; 37390, pdf p. 44

January 28 - March 4, 

1948 16

37587, pdf p. 54; 36762, pdf p. 35; 36762, pdf p. 38; 37586, pdf p. 35; 129759, pdf p. 9; 85872, 

pdf p. 2; 11996, pdf p. 129; 37587, pdf p. 23

April 3 - 5, 1948 3 16288, pdf p. 5
White Paper, Rev. 0 Dose Reconstruction Methods for Joslyn Manufacturing and Supply Co. April 2014

Page 9 of 20 

This working document prepared by NIOSH or its contractor for use in discussions with the ABRWH or its Working Groups or Subcommittees. Draft, 

preliminary, interim, and White Paper documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions unless 

specifically marked as such. This document represents preliminary positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This 

information is protected by the Privacy Act 5 USC §552a; disclosure to any third party without the written consent of the individual(s) to whom the 

information pertains is strictly prohibited

Table A-1: Uranium Rolling Days at Joslyn (pages 8 and 9)

Time Period

Rolling 

Days SRDB Ref ID

May, 1948 26 59249, pdf p. 7; 129474; 11036, pdf p. 19

June 4 – 18, 1948 15 16509; 129748; pdf p. 10; 11036, pdf p. 177

July 9 – 11, 1948 3 118155, pdf p. 2

July 27 – 30, 1948 4 115156, pdf p. 2

1947 – 1950a~10 days 112574, pdf p. 25 (see also 116843)

May 26 – 27, 1949 2 116843

February and July, 

1950 2 36889, pdf p. 109; 36834, pdf p. 131

April 26 – 27, 1950 2 116844b

August 10 – 11, 1950 2 120484

August 4, 1950 1 118159

September 5, 1950 1 28071, pdf p. 2

October 24, 1951 1 11036, pdf p. 23

January 8 – 9, 1952 2 9664

January 16, 1952 1 9664
White Paper, Rev. 0 Dose Reconstruction Methods for Joslyn Manufacturing and Supply Co. April 2014

Page 10 of 20 

This working document prepared by NIOSH or its contractor for use in discussions with the ABRWH or its Working Groups or Subcommittees. Draft, 

preliminary, interim, and White Paper documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions unless 

specifically marked as such. This document represents preliminary positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This 

information is protected by the Privacy Act 5 USC §552a; disclosure to any third party without the written consent of the individual(s) to whom the 

information pertains is strictly prohibited

Table A-2 Uranium Machining Days (pages 9 and 10)

Time Period Machining 

Days SRDB Ref ID

June 29, 1943 1 11036, pdf p. 42; 33190, pdf p. 66; 33190, pdf p. 244

September 7, 1943 1 11036, pdf p. 85

November 29 – December 

15, 1943 15 11036, pdf pp. 59, 69, 222-3

Unknown date, 1944 1 33190, pdf p. 74

January 3 - 14, 1944 12 11036, pdf p. 53

January 7, 1944 1 11036, pdf p. 135

February 23 - 26, 1944 4 11036, pdf p. 130

May 3 - 6, 1944 4 11036, pdf p. 216

June 1 - 5, 1944 5 17594, pdf p. 4

March - May, 1945 54 31145, pdf p. 196

Unknown date, 1946 ~10-20 90948, pdf p. 8

May, 1946 1 80171, pdf p. 3

October 28,1946 1-2 93775, pdf p. 6

November, 1946 ~5-10 31145, pdf p. 16

January, 1947 ~5-10 90948, pdf p. 2

August 5 – 6, 1947 2 37411, pdf p. 44; 126764, pdf p. 5; 37374, pdf p. 43; 16511, pdf p. 3, 5; 37390, pdf p. 44

January 28 – March 4, 

1948 16 37587, pdf p.54; 36762, pdf p. 35; 36762, pdf p. 38; 37586, pdf p. 35; 129759, pdf p. 9; 85872, pdf p. 2; 11996, pdf p. 129; 37587, pdf p. 23

April 3 – 5, 1948 3 16288, pdf p. 5

April 10-17, 1948 8 37591, pdf p. 164

May, 1948 26 59249, pdf p. 7; 129474; 11036, pdf p. 19

June 4 – 18, 1948 15 16509; 129748; pdf p. 10; 11036, pdf p. 177

July 9 – 11, 1948 3 118155, pdf p. 2
White Paper, Rev. 0 Dose Reconstruction Methods for Joslyn Manufacturing and Supply Co. April 2014

Page 11 of 20 

This working document prepared by NIOSH or its contractor for use in discussions with the ABRWH or its Working Groups or Subcommittees. Draft, 

preliminary, interim, and White Paper documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions unless 

specifically marked as such. This document represents preliminary positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This 

information is protected by the Privacy Act 5 USC §552a; disclosure to any third party without the written consent of the individual(s) to whom the 

information pertains is strictly prohibited

Table A-2 Uranium Machining Days (pages 9 and 10)

Time Period Machining 

Days SRDB Ref ID

July 27 – 30, 1948 4 115156, pdf p. 2

August 5, 1950 1 11036, pdf p. 15

August 10 – 11, 1950 2 120484

August 24, 1951 1 11036, pdf p. 23

July 16, 1952 1 91923, pdf p. 2

Table A-3 Thorium Rolling and Machining

Time Period Rolling Days Machining Days SRDB Ref ID

May, 1946 0 2.5 80171, pdf p. 3

January, 1947 0 2.5 81068, pdf p. 2

Table A-4 Comparison of 1952 Time-Weighted Average (TWA) Study with Battelle-TBD-6000

(Joslyn ER, Rev. 1, Table 7-1)

Joslyn Work Area/Job 

Description

TWA

(pCi/m3)

Battelle-TBD-6000

Equivalent Description

GM

(pCi/m3)

95%

(pCi/m3)

AM

(pCi/m3)

18" rough roll east 1496 Rolling Operator 1606 22675 5864

18" rough roll west 169 Rolling Operator 1606 22675 5864

Roller Forman 327 Rolling Supervisor 148 2090 540

Asst Roller

(Ass't Foreman)

327 Rolling Supervisor 148 2090 540

Furnace Heaters 7 Rolling General Labor 296 4179 1081

Recorder 7 Rolling General Labor 296 4179 1081

12" rough roll east 273 Rolling Operator 1606 22675 5864

12" rough roll west 257 Rolling Operator 1606 22675 5864

Drag Down (Billet) 140 Rolling General Labor 296 4179 1081
White Paper, Rev. 0 Dose Reconstruction Methods for Joslyn Manufacturing and Supply Co. April 2014

Page 12 of 20 

This working document prepared by NIOSH or its contractor for use in discussions with the ABRWH or its Working Groups or Subcommittees. Draft, 

preliminary, interim, and White Paper documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions unless 

specifically marked as such. This document represents preliminary positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This 

information is protected by the Privacy Act 5 USC §552a; disclosure to any third party without the written consent of the individual(s) to whom the 

information pertains is strictly prohibited

Table A-4 Comparison of 1952 Time-Weighted Average (TWA) Study with Battelle-TBD-6000

(Joslyn ER, Rev. 1, Table 7-1)

Joslyn Work Area/Job 

Description

TWA

(pCi/m3)

Battelle-TBD-6000

Equivalent Description

GM

(pCi/m3)

95%

(pCi/m3)

AM

(pCi/m3)

9" finishing roll east 7451 Rolling Operator 1606 22675 5864

9" finishing roll west 2609 Rolling Operator 1606 22675 5864

Quench Tank 70 Rolling General Labor 296 4179 1081

Draggers 374 Rolling General Labor 296 4179 1081

Rod Stamper 109 Rolling General Labor 296 4179 1081

Rod Bundler 58 Rolling General Labor 296 4179 1081

Lathe Operation 5 Machining Operator 2491 35171 9096

Centerless Grinder 45 Machining Operator 2491 35171 9096

Grinder (portable) 125 Machining Operator 2491 35171 9096

Cutomatic 86 Machining Operator 2491 35171 9096

The 1952 study presented in Table 4 above is the only time-weighted-average (TWA) study located for Joslyn. As can be seen, each arithmetic mean (AM) 

of the distribution with the given geometric mean (GM) and a geometric standard deviation (GSD) of 5 is generally much higher than the 1952 TWA values 

obtained at Joslyn. In one location (“9-inch finishing roll east”), the Joslyn value is higher.

Table A- 5: Comparison of 1951 Air Concentrations to Battelle-TBD-6000

(Joslyn ER, Rev. 1, Table 7-2)

Joslyn Work Area/Job 

Description

Average

(pCi/m3)

Maximum

(pCi/m3)

Battelle-TBD-6000

Equivalent Description

GM

(pCi/m3)

95%

(pCi/m3)

AM

(pCi/m3)

Centerless grinding, 1951

General Area 20 23 Machining Operator1/1/1951 to 12/31/55 2491 35171 9096

Centerless grinding, 1951

Operator 486 811 Machining Operator1/1/1951 to 12/31/55 2491 35171 9096
White Paper, Rev. 0 Dose Reconstruction Methods for Joslyn Manufacturing and Supply Co. April 2014

Page 13 of 20 

This working document prepared by NIOSH or its contractor for use in discussions with the ABRWH or its Working Groups or Subcommittees. Draft, 

preliminary, interim, and White Paper documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions unless 

specifically marked as such. This document represents preliminary positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This 

information is protected by the Privacy Act 5 USC §552a; disclosure to any third party without the written consent of the individual(s) to whom the 

information pertains is strictly prohibited

Table A-6: Daily Intake Rates for Joslyn from Battelle-TBD-6000

(Joslyn ER, Rev. 1, Table 7-3)

Job Description

Inhalation Ingestion Inhalation Ingestion

8/1/1948-12/31/1950 1/1/1951-12/31/1952

(pCi/cal. day) (pCi/cal. day) (pCi/cal. day) (pCi/cal. day)

Rolling Operator 12671 260 11615 238

Machining Operator 19654 403 18016 369

Table A-7: External Dose from Uranium

Rolling or Machining Workday?

Penetrating Dose Rate

(mrad/workday)

Non-Penetrating Dose Rate

(mrad/workday)

No (1943-1950) 0.041 3.942

No (1951-1952) 0.037 3.614

Table A-8: External Dose from Thorium

Work Area/Job Description

Penetrating Dose

(mremd/workday)

Non-Penetrating Dose

(mrad/workday)

Operator 20.812 6.56
White Paper, Rev. 0 Dose Reconstruction Methods for Joslyn Manufacturing and Supply Co. April 2014

Page 14 of 20 

This working document prepared by NIOSH or its contractor for use in discussions with the ABRWH or its Working Groups or Subcommittees. Draft, 

preliminary, interim, and White Paper documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions unless 

specifically marked as such. This document represents preliminary positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This 

information is protected by the Privacy Act 5 USC §552a; disclosure to any third party without the written consent of the individual(s) to whom the 

information pertains is strictly prohibited

Attachment B

Joslyn Example Dose Reconstruction for the Post-SEC Period (August 1948 on)

Employee Information

Cancer Description: Lung (ICD-9: 162); diagnosed 12/31/1977

Prostate diagnosed (ICD9 185); diagnosed 12/31/1977

BCC of the back (ICD-9: 173); diagnosed 12/31/1977

SCC of the back (ICD-9: 173); diagnosed 12/31/1977

Kidney; diagnosed 12/31/1977

Liver; diagnosed 12/31/1977

Year of birth: 1923

Gender: Male

Smoking: Former Smoker

Ethnicity: “White, non-Hispanic”

Employment Information

Employer: Joslyn

Start date: 03/01/1943

End date: 12/31/1952

Occupation: Operator

Dosimetry Data: None
White Paper, Rev. 0 Dose Reconstruction Methods for Joslyn Manufacturing and Supply Co. April 2014

Page 15 of 20 

This working document prepared by NIOSH or its contractor for use in discussions with the ABRWH or its Working Groups or Subcommittees. Draft, 

preliminary, interim, and White Paper documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions unless 

specifically marked as such. This document represents preliminary positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This 

information is protected by the Privacy Act 5 USC §552a; disclosure to any third party without the written consent of the individual(s) to whom the 

information pertains is strictly prohibited

Organ Dose Assessed 3

The organs evaluated in the Example DR are shown in Table B-1.

Table B-1: Example DR Evaluated Organs

Cancer External Organ Used Internal Organ Used

Lung ]Lung Lung

Prostate Urinary Bladder

Non-Metabolic Organ 

with Highest Dose 

(Adrenals/Brain)

Skin Skin Skin

Kidney Liver Kidney

Liver Liver Liver

Internal Dose

Internal dose during the residual period was assigned in accordance with methodology presented in the SEC00200 Joslyn SEC Evaluation Report.4

 Intake values tabulated in Battelle-TBD-6000 were used as a basis for the 

assigned inhalation and ingestion intakes6. Inhalation and ingestion intake rates from Battelle-TBD-6000, Tables 

7.8 and 7.9, were used to assign intakes during rolling days. Inhalation and ingestion intake rates used to assign 

intakes during non-operational days were based on guidance in Battelle-TBD-6000, Sections 7.1.5 and 7.1.6. The

number of operational and non-operational days was based on research summarized in the Joslyn ER, as indicated 

in the external dose section above. The resultant intake rates are presented in Table B-2 on the next page.
White Paper, Rev. 0 Dose Reconstruction Methods for Joslyn Manufacturing and Supply Co. April 2014

Page 16 of 20 

This working document prepared by NIOSH or its contractor for use in discussions with the ABRWH or its Working Groups or Subcommittees. Draft, 

preliminary, interim, and White Paper documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions unless 

specifically marked as such. This document represents preliminary positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This 

information is protected by the Privacy Act 5 USC §552a; disclosure to any third party without the written consent of the individual(s) to whom the 

information pertains is strictly prohibited

Table B-2: Estimated Annual Uranium Inhalation and Ingestion Intake Quantity for Joslyn

Year Rolling 

Days

Machining 

Days

Rolling and 

Machining Days

Non-Operational 

Days

Inhalation Intake Rate 

(pCi/year)

Ingestion Intake Rate

(pCi/year)

1943a,c 1 16 1 190 0 0

1944c23 10 6 207 0 0

1945c0 0 54 196 0 0

1946c0 1 32 217 0 0

1947c0 0 12 238 0 0

1/7/1948c0 8 67 71 0 0

8-

12/1948 10b

0 0 94 237,435 59,104

1949 2 0 0 248 175,348 146,677

1950 8 3 0 239 367,409 145,425

1951 1 1 0 248 170,081 134,494

1952 3 1 0 246 202,974 134,111

a. 1943 is a partial year (March through December); therefore, the 250 workdays were prorated by 10/12 to account for this.

b. SRDB 112574 indicates a rolling operation occurred sometime between 1947 and 1050 for 10 days. Therefore it was assumed to have all occurred in 

1948 to be claimant favorable, since 1947 is covered under the SEC.

c. During the SEC, internal dose assessment is considered infeasible. Therefore, no intakes are assessed during this period.

Thorium

Thorium operations occurred during the SEC period for which NIOSH has determined it is not feasible to 

reconstruct internal exposures adequately. Consequently, no internal dose is assigned from thorium operations. 

External Dose

External Dose (deep and shallow) was assigned in accordance with the SEC-00200 Joslyn SEC Evaluation 

Report.4 A photon dose of 7.03 mrem per uranium rolling/machining day and 1.08 mrem per non-operational day 

was assigned. An electron dose of 70.3 mrem per uranium rolling/machining day was assigned. External 

exposure during uranium rolling/machining days was based on the dose rate calculated at a distance of one foot 

from a Long Billet6, assuming a 10-hr working day. External exposure during non-operational days was based on 

the dose rate calculated at a distance of one meter from a Long Billet6, assuming a 10-hr working day. The 

number of operational and non-operational days was determined based on site research data4and is summarized in 

Table B-3 on the next page.
White Paper, Rev. 0 Dose Reconstruction Methods for Joslyn Manufacturing and Supply Co. April 2014

Page 17 of 20 

This working document prepared by NIOSH or its contractor for use in discussions with the ABRWH or its Working Groups or Subcommittees. Draft, 

preliminary, interim, and White Paper documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions unless 

specifically marked as such. This document represents preliminary positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This 

information is protected by the Privacy Act 5 USC §552a; disclosure to any third party without the written consent of the individual(s) to whom the 

information pertains is strictly prohibited

Table B-3: Estimated Annual Uranium External Exposures for Joslyn

Year Operational Days Non-Operational 

Days

Annual Deep 

(mrem)

Annual Shallow 

(mrem)

1943a18 190 134 2014

1944 43 207 311 3839

1945 54 196 388 4569

1946 33 217 241 3175

1947 12 238 94 1782

1948 85b165 604 6626

1949 2 248 24 1118

1950 11 239 87 1716

1951 2 248 23 1037

1952 4 246 37 1170

a. 1943 is a partial year (March through December); therefore, the 250 workdays were prorated by 10/12 to account for this.

b. SRDB 112574 indicates a rolling operation occurred sometime between 1947 and 1050 for 10 days. 

Therefore it was assumed to have all occurred in 1948 to be claimant favorable, since 1947 is covered under the SEC.

A photon dose of 20.9 mrem per thorium rolling/machining day was assigned. A shallow dose of 6.3 mrem per 

thorium rolling/machining day was assigned. External exposure during thorium rolling/machining days was 

based on the BattelleTBD-6000 modeling for uranium metal and adjusted to thorium dose rates using a computer 

model MCNPX. The number of rolling and non-operational days was determined based on site research data and 

is summarized in Table B-4 below.

Table B-4: Estimated Annual Thorium External Exposures for Joslyn

Year Operational Days Annual Deep (mrem) Annual Shallow 

(mrem)

1946 2.5 52 16

1947 2.5 52 16
White Paper, Rev. 0 Dose Reconstruction Methods for Joslyn Manufacturing and Supply Co. April 2014

Page 18 of 20 

This working document prepared by NIOSH or its contractor for use in discussions with the ABRWH or its Working Groups or Subcommittees. Draft, 

preliminary, interim, and White Paper documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions unless 

specifically marked as such. This document represents preliminary positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This 

information is protected by the Privacy Act 5 USC §552a; disclosure to any third party without the written consent of the individual(s) to whom the 

information pertains is strictly prohibited

Penetrating Dose

For the purpose of estimating probability of causation, all photon doses are assumed to be acute.2Photon doses 

were determined by applying a 100% 30–250 keV energy distribution to the reported photon doses2. The dose 

rate was multiplied by the deep dose mode organ dose conversion factor. An organ dose conversion factor value 

of 1 was used for the skin in conjunction with guidance in ORAUT-OTIB-0017. The organ dose conversion 

factors are shown in Table B-5 on this page.

Non-Penetrating Dose

For the determination of non-penetrating dose, an energy distribution of 100% > 15 keV electrons has been 

assumed for all non-penetrating doses. The electron radiation was only considered in the dose reconstruction of 

the skin because it would not have added dose to the other cancer sites. 

For skin cancer claims, ethnicity is necessary to determine the probability of causation.1,5 The hypothetical

covered employee was assumed to be “white, non-Hispanic” for the purposes of this example dose reconstruction. 

Table B-5: Organ Dose Conversion Factors

Organ 30-250 keV (mode) Electron>15 keV

Lung 0.695 n/a

Prostate 0.873 n/a

Skin 1.000 1.000

Kidney 0.748 n/a

Liver 0.748 n/a

The total doses for photon and beta dose (skin only) are given in Table B-6 below.

Table B-6: Total Assigned External Dose

Organ Photons (rem) Electrons (rem)

Lung 1.422 n/a

Prostate 1.788 n/a

Skin 2.080 27.047

Kidney 1.531 n/a

Liver 1.531 n/a
White Paper, Rev. 0 Dose Reconstruction Methods for Joslyn Manufacturing and Supply Co. April 2014

Page 19 of 20 

This working document prepared by NIOSH or its contractor for use in discussions with the ABRWH or its Working Groups or Subcommittees. Draft, 

preliminary, interim, and White Paper documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions unless 

specifically marked as such. This document represents preliminary positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This 

information is protected by the Privacy Act 5 USC §552a; disclosure to any third party without the written consent of the individual(s) to whom the 

information pertains is strictly prohibited

Medical Dose

Table B-7 presents the estimated annual medical dose for Joslyn.

Table B-7: Estimated Annual Medical Dose for Joslyn

Year Lung Prostate Skin Kidney Liver

1943 0.084 0.025 0.270 0.090 0.090

1944 0.084 0.025 0.270 0.090 0.090

1945 0.084 0.025 0.270 0.090 0.090

1946 0.084 0.025 0.270 0.090 0.090

1947 0.084 0.025 0.270 0.090 0.090

1948 0.084 0.025 0.270 0.090 0.090

1949 0.084 0.025 0.270 0.090 0.090

1950 0.084 0.025 0.270 0.090 0.090

1951 0.084 0.025 0.270 0.090 0.090

1952 0.084 0.025 0.270 0.090 0.090

TOTAL 0.838 0.250 2.700 0.902 0.902

Uncertainty 

External photon dose for uranium was applied as a lognormal distribution with a GSD of 5. Internal dose was 

applied as a lognormal distribution with a GSD of 5. Occupational medical X-ray doses were assigned as a 

normal distribution with an uncertainty of 30%. 
White Paper, Rev. 0 Dose Reconstruction Methods for Joslyn Manufacturing and Supply Co. April 2014

Page 20 of 20 

This working document prepared by NIOSH or its contractor for use in discussions with the ABRWH or its Working Groups or Subcommittees. Draft, 

preliminary, interim, and White Paper documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions unless 

specifically marked as such. This document represents preliminary positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This 

information is protected by the Privacy Act 5 USC §552a; disclosure to any third party without the written consent of the individual(s) to whom the 

information pertains is strictly prohibited

Summary 

The assessment methods presented in this report define the methods by which a dose estimate can be determined 

for employees of Joslyn during the covered period. These methods support NIOSH’s conclusion that the 

operationally-related internal dose for the evaluated worker class can be bounded. A summary of the doses and 

probability of causations are provided in Table B-8 on the next page.

Table B-8: Summary of the Doses and Probability of Causations

Cancer External (rem) Internal (rem) Medical (rem) Total (rem) Probability of 

Causation

Lung 1.422 170.658 0.838 172.918 97.67%

Prostate 1.788 1.057 0.250 3.094 29.21%

Skin BCC

29.127 1.057 2.700 32.884

94.04%

Skin SCC 29.75%

Kidney 1.531 17.787 0.902 20.219 74.27%

Liver 1.531 5.952 0.902 8.384 80.22%