Draft

ADVISORY BOARD ON 

RADIATION AND WORKER HEALTH 

National Institute for Occupational Safety and Health 

SC&A’s Evaluation of the Pantex External Coworker Model: 

ORAUT-OTIB-0086

Contract No. 211-2014-58081 

Document No. SCA-TR-SP2015-0047, Revision 0 

Prepared by 

Ron Buchanan, PhD, CHP

S. Cohen & Associates 

1608 Spring Hill Road, Suite 400 

Vienna, Virginia 22182 

Saliant, Inc.

5579 Catholic Church Road 

Jefferson, Maryland 21755 

September 2015 

DISCLAIMER

This is a working document provided by the Centers for Disease Control and Prevention (CDC) technical 

support contractor, SC&A for use in discussions with the National Institute for Occupational Safety and 

Health (NIOSH) and the Advisory Board on Radiation and Worker Health (ABRWH), including its 

Working Groups or Subcommittees. Documents produced by SC&A, such as memorandum, white paper, 

draft or working documents are not final NIOSH or ABRWH products or positions, unless specifically 

marked as such. This document prepared by SC&A represents its preliminary evaluation on technical 

issues.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 U.S.C. § 552a and has been cleared for distribution..
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S. COHEN & ASSOCIATES: Technical Support for the Advisory Board on Radiation & 

Worker Health Review of NIOSH Dose Reconstruction Program

DOCUMENT TITLE: 

SC&A’s Evaluation of the Pantex External Coworker Model: 

ORAUT-OTIB-0086

DOCUMENT NUMBER/

DESCRIPTION:

SCA-TR-SP2015-0047

REVISION NO.: 0

SUPERSEDES: N/A

EFFECTIVE DATE: 09/23/2015

TASK MANAGER: Joe Fitzgerald

PROJECT MANAGER: John Stiver

DOCUMENT 

REVIEWER(S):

Joe Fitzgerald

John Stiver

Record of Revisions

Revision 

Number

Effective 

Date Description of Revision

0 (Draft) 09/23/2015 Initial issue
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TABLE OF CONTENTS 

Abbreviations and Acronyms ..........................................................................................................4

1.0 Introduction and Background ..............................................................................................5

2.0 NIOSH’s Recommendations Concerning Dose Record Entries Containing Zeros, 

Blanks, or Marks ..................................................................................................................6

3.0 External Dose Data Development Methodology .................................................................7

4.0 Tables of Coworker Photon, Neutron, and Skin Doses for 1960–2010...............................8

5.0 Details of Coworker Dose Development for Photon, Neutron, and Skin Exposures – 

Attachment A of OTIB-0086 ...............................................................................................9

6.0 Details of neutron NTA film (1960–1977) correction factors for energy response, 

angular response, and fading – Attachment B of OTIB-0086 ...........................................12

6.1 SC&A’s Evaluation of NTA Film Correction Factors ..........................................12

6.2 Summary ................................................................................................................13

6.3 Conclusions and Issues ..........................................................................................14

7.0 References ..........................................................................................................................16
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ABBREVIATIONS AND ACRONYMS

AP anterior-posterior 

BWXT Babcock & Wilcock Transmission Technologies 

cm centimeter

DOE (U.S.) Department of Energy 

DOELAP Department of Energy Laboratory Accreditation Program

DoRMs Dosimetry Records Management System

eV electron volt 

GM geometric mean

GDS geometric standard deviation 

keV kilo electron volt 

LANL Los Alamos National Laboratory 

LOD limit of detection

MCNP Monte Carlo n-particle

MeV million electron volts

MDL minimum detectable level

MRD minimum recordable dose 

N number of workers

NIOSH National Institute for Occupational Safety and Health

NTA Neutron Track Emulsion, Type A (film)

ORAU Oak Ridge Associated Universities

ORAUT Oak Ridge Associated Universities Team

OTIB ORAUT Technical Information Bulletin

PA posterior-anterior 

PuO2 plutonium oxide 

PuF4 plutonium tetrafluoride 

SC&A S. Cohen & Associates (SC&A, Inc.)

SSN Social Security Number

TLD thermoluminescent dosimeter

WB whole body 

β beta particle

γ gamma ray
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1.0 INTRODUCTION AND BACKGROUND 

ORAUT-OTIB-0086 (ORAUT 2015a), which will be referred to as OTIB-0086 in this report, 

provides information and coworker data for the dose reconstructor concerning assigning dose to 

Pantex workers that had no, or limited, external dose records; this information can also be used 

to assign dose when there are gaps in the monitored worker’s records. OTIB-0086 also provides 

some recommendations on how to handle zeros, blanks, dashes, slashes, and hash marks in the 

dose records.

The major items in OTIB-0086 are:

• Recommendations concerning entries containing zeros, blanks, or marks 

• External dose data development methodology 

• Coworker photon, neutron, and skin doses for 1960–2010 (Tables 7-1, 7-2, and 7-3, 

respectively)

• Attachment A: Details of coworker dose development for photon, neutron, and skin 

exposures 

• Attachment B: Details of neutron NTA film (1960–1976) correction factors for energy 

response, angular response, and fading 

An evaluation of each item is provided in the following sections.
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2.0 NIOSH’S RECOMMENDATIONS CONCERNING DOSE RECORD 

ENTRIES CONTAINING ZEROS, BLANKS, OR MARKS

Section 1.1 of OTIB-0086 recommends: 

• Recorded “0” – This entry is assumed to mean that the dosimeter was issued and 

processed, and that no exposure or dose was detected in excess of the dosimeter limits of 

detection (LOD). 

• Blanks – Indicates that no dosimeter was issued during this exchange cycle, or that the 

dosimeter was lost, damaged, or a processing error occurred. 

• Marks – Dash, slash, or hash marks indicate that no dosimeter was issued during this 

exchange cycle, or that the dosimeter was lost, damaged, or a processing error occurred. 

According to page 5 of OTIB-0086, the dose reconstructor will assign dose before1

 1988 as 

follows: 

1 According to ORAUT-TKBS-0013-6 (ORAUT 2007), Section 6.4, page 11, starting in 1989, all 

personnel entering the operational areas were required to wear a dosimeter; therefore, the terms “before 1988” 

should be changed to “before 1989” and “in 1988” should be changed to “in 1989” in this section of OTIB-0086.

In such cases for years before 1988, NIOSH intends to apply (after consideration of the 

worker’s job title and the totality of the monitoring record), either: 

(1) Unmonitored dose based on external coworker data 

(2) Missed dose 

(3) Ambient dose 

After 1988: 

After 1988, all personnel who entered the operational areas of the plant were 

required to wear a dosimeter as a condition for entry. The absence of a listed 

result, or the presence of a dash, slash, or hash mark for a given dosimeter 

exchange cycle in 1988 and later years, should be interpreted to mean that the 

worker was not monitored because he or she was not present in the operational 

areas. Therefore, ambient dose should be assigned for those exchange cycles. 

SC&A finds NIOSH’s recommendations concerning zero, blank, or marks in the entries to be 

consistent with those used for other Department of Energy (DOE) sites and dosimetry records in 

general, and has not found data that are in conflict with these recommendations. However, it 

appears that the term ‘before 1988’ should be changed to ‘before 1989’ and the term ‘in 1988’ 

should be changed to ‘in 1989’ on page 5 of OTIB-0086.

 
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3.0 EXTERNAL DOSE DATA DEVELOPMENT METHODOLOGY 

Sections 3.0 through 7.0, pages 6–8, of OTIB-0086 provide the general approach to the 

development of the Pantex coworker external doses. In summary: 

• NIOSH used ORAUT-RPRT-0071 (ORAUT 2015b) to analyze recorded values less than 

the LOD, instead of the former method that used 1⁄2 LOD values. 

• The greater of the dose in BWXT 2011 or BWXT 2013 was used if there was a 

difference in dose for a given person for a given badge cycle. 

• The neutron dose results using the Stanford algorithm [applicable to thermoluminescent 

dosimeter (TLD) results only] are likely biased high, because an unmoderated Cf-252 

source was used for calibration, rather than a moderated Cf-252 source that would have 

been more representative of Pantex workplace neutron spectra ( 2004).

The details of the coworker dose analyses are provided in Attachments A and B of OTIB-0086, 

which will be evaluated in the following sections of this report. SC&A did not evaluate 

ORAUT-RPRT-0071 (ORAUT 2015b) in this report; this would be evaluated under a separate 

tasking.
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4.0 TABLES OF COWORKER PHOTON, NEUTRON, AND SKIN 

DOSES FOR 1960–2010

Tables 7-1, 7-2, and 7-3 of OTIB-0086 provide the recommended coworker doses for photon, 

neutron, and skin, respectively, for the time period 1960–2010. The data for these tables were 

obtained from the BWXT Pantex 2011 database (BWXT 2011) (which contained the original 

recorded photon, neutron, and skin doses), and the BWXT Pantex 2013 database (BWXT 2013), 

which contains the algorithm-modified TLD doses for 1980–1993. The results of analyzing the 

data in these databases are detailed in plots for each type of radiation for each year in ORAUT 

2015c. These plots show the annual geometric mean (GM), the geometric standard deviation 

(GSD), and number of workers (N) for each year for photon, neutron, and skin doses. An 

example of one of the plots is provided here as Exhibit A. 

Exhibit A. Example of Dose Plot from ORAUT-RPRT-0071 

Source: ORAUT 2015c

SC&A spot checked the tables and the plots and did not locate any abnormalities; except for the 

1975 neutron dose. The 1975 neutron dose in Table 7-2 of OTIB-0086 and in the plot on page 

64 of ORAUT 2015c is a factor of 10 to 100 times the other annual neutron doses; whereas, the 

photon and skin doses for 1975 did not show any increase for this year. Additionally, the 1975 

neutron dose in Table 6-5 of Pantex TKBS-0013-6 (ORAUT 2007) does not indicate any 

abnormalities for 1975. SC&A recommends that the neutron dose for 1975 be reviewed to 

determine why there is such an increase for that one year.
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5.0 DETAILS OF COWORKER DOSE DEVELOPMENT FOR PHOTON, 

NEUTRON, AND SKIN EXPOSURES – ATTACHMENT A OF OTIB0086

The dosimetry systems used at Pantex are summarized in Table A-1, page 17, of OTIB-0086, 

which is reproduced here as Exhibit B. 

Exhibit B. Summary of Dosimetry Systems Used at Pantex 

Source: ORAUT 2015a, Table A-1 

In general, OTIB-0086 separates the dosimetry at Pantex into the following eras. However, 

SC&A noted that the text in Table A-1 in OTIB-0086 and the text in Table 6-2 in ORAUTTKBS-0013-6 (ORAUT 2007) do not always agree on the year NTA film ended, and also on the 

years 2-element TLDs were used:

• 1952–1959: Used film for photons and betas, no adjustment factor to be applied (use 

BWXT 2011 dose data as is). 

• 1960–1972: Used film for photons, betas and neutrons; NTA film requires adjustment 

factors (neutron and skin doses were assigned for one period during 1960–1963, because 
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of insufficient data for any given year) (use BWXT 2011 dose data with no adjustment 

factor for photons or betas). 

• 1973–1977: Used 2-element TLDs for photons and betas, and used NTA film for 

neutrons; NTA film requires adjustment factors (use BWXT 2011 dose data with no 

adjustment factor for photons or betas). Note that in Column 2 of Table A-1 of OTIB0086, the year 1976 is omitted and the TLD 6-element is included in 1977. 

• 1978–1979: Used 6-element TLDs with no adjustment factors for photons, betas, or 

neutrons (use BWXT 2011 dose data as is). 

• 1980–1993: Used Panasonic-802 TLDs with algorithm applied later after recording of 

TLD element readouts (for 1983, use interpolation between 1982 and 1984 because of the 

lack of 1983 original TLD readings) (use BWXT 2013 dose data that have Stanford 

algorithm applied).

• 1994–2010: Used Panasonic-809 TLDs with algorithm applied at time of TLD readouts 

(use BWXT 2011 dose data as is). 

The databases used for Pantex coworker modeling were the BWXT Pantex 2011 database 

(BWXT 2011), which contained the original recorded photon, neutron, and skin doses, and the 

BWXT Pantex 2013 database (BWXT 2013), which contained the doses from BWXT Pantex 

2011 modified by using an algorithm (called the Stanford Algorithm developed by Stanford 

Dosimetry, LLC, for Pantex’s in-house Panasonic dosimetry system). 

Data that appear in BWXT 2011 but not in BWXT 2013, or vice versa, are to be discarded 

( 2015), because the algorithm could only be applied to the original TLD element readout 

values, and not the final assigned dose value in the records.

A summary of the database usage is provided in Table A-2 of OTIB-0086, and reproduced here 

as Exhibit C.

Exhibit C. Summary of Data Used in Pantex Coworker Model

Source: ORAUT 2015a, Table A-2 
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These data, as described above, contained in the BWXT 2011 and BWXT 2013 databases were 

used to create the photon, neutron, and skin dose plots for 1960–2010, as shown in ORAUT 

2015c. These data were used to create the annual coworker doses in Tables 7-1, 7-2, and 7-3, of 

OTIB-0086, for photons, neutrons, and skin, respectively, for the time period 1960–2010. 

SC&A’s review of the resulting annual coworker doses in Tables 7-1, 7-2, and 7-3 of OTIB0086 for photons, neutrons, and skin, respectively, for the time period 1960–2010 did not 

identify any issues, except for the relatively large coworker neutron dose for 1975, as previously 

discussed. 
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6.0 DETAILS OF NEUTRON NTA FILM (1960–1977) CORRECTION 

FACTORS FOR ENERGY RESPONSE, ANGULAR RESPONSE, AND 

FADING – ATTACHMENT B OF OTIB-0086

1.5.1 NIOSH recommendations

In OTIB-0086, NIOSH recommends using the originally recorded neutron dose from NTA film, 

multiplied by a correction factor of 2.9, which was derived from an energy response factor of 

1.4, an angular response factor of 1.33, and a track fading factor of 1.56 (i.e., 1.4 × 1.33 × 1.56 = 

2.9). These factors were derived as follows: 

1. Energy response – NIOSH used their MCNP model generated for Mound Laboratory of 

an observer located at 240 cm from a glovebox (shielded with 4 inches of moderator) 

located in a concrete room. In this model, the NTA film would miss 29% of the dose 

equivalent because of the NTA film’s 500 keV neutron energy threshold. The correction 

factor would be 1/(1-0.29) = 1.4. 

2. Angular response – NIOSH used the angular correction factor of 1.33 for NTA film 

from Kathren et al. (1965) for anterior-posterior (AP) geometry neutron exposures. 

3. Track fading – NIOSH used the NTA film track fading correction factor of 9% per week 

(Kahle et al. 1969) for a total of 4 × 0.09 = 0.36 per month; for a derived track fading 

factor of 1/(1-0.36) = 1.56. 

At this point, it is uncertain if NIOSH plans to apply the 2.9 factor to all recorded neutron doses 

through 1977. Page 7 of OTIB-0086 recommends it be applied to 1960–1977, but Table A-1, 

page 17, of OTIB-0086 lists NTA film used through 1975, and ORAUT-TKBS-0013-6 (ORAUT 

2007), Table 6-2, page 15, lists NTA film used through 1976. This point needs to be clarified 

and consistent instructions provided to the dose reconstructors.

6.1 SC&A’s Evaluation of NTA Film Correction Factors

Following is SC&A’s evaluation of the NTA film correction factors recommended in OTIB0086. 

1. Energy response – OTIB-0086 uses the term “THERMAL NEUTRONS” on page 21; 

however, SC&A assumes that this is a general term referring to neutrons with energy 

below 500 keV, since thermal neutrons are defined as 0.025 eV in energy. In evaluating 

the recommended energy correction factor of 1.4, SC&A does not find that the MCNP 

model generated for Mound Laboratory of an observer located at 240 cm from a 

glovebox with 4 inches of moderator necessarily represents the situation and neutron 

energy fields for a worker at Pantex with potential exposure to multiple neutron sources 

(such as in a bay, cell, etc.). This is especially true for situations where a Pantex worker 

was exposed to posterior-anterior (PA) geometry neutron sources, because the Mound 

model was for AP geometry neutron sources. Additionally, SC&A could not find that 

NIOSH had performed an MCNP model particular to Pantex, as implied in the statement 

on page 21 of OTIB-0086: 
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A Monte Carlo n-particle (MCNP) model was developed to determine the 

amount of dose that was missed due to a sensitivity threshold of 500 keV for 

the conditions likely to have been encountered by workers who received 

neutron doses at Pantex (LANL 2003). [Emphasis added.] 

SC&A found that NIOSH apparently applied the MCNP model for Mound to Pantex. 

SC&A also found that the reference of LANL 2003 in the above quoted statement was to 

the LANL MCNP program in general, which was not specific to either Mound 

Laboratory or Pantex.

2. Angular response – The angular correction factor of 1.33 for NTA film from Kathren et 

al. (1965) was derived for only AP geometry exposures. However, personnel at Pantex 

were potentially exposed to multiple sources of neutrons, which could include PA 

geometry. Neither the NTA film calibration nor the AP angular correction factor address 

PA geometry for neutron exposure. 

3. Track fading – OTIB-0086 used the moderated 238PuO2 (average energy of 0.9 MeV) 

exposed NTA film track fading correction factor of 9% per week (Kahle et al. 1969) for a 

total of 4 × 0.09 = 0.36 per month, for a derived track fading factor of 1/(1-0.36) = 1.56. 

However, the same referenced article (Kahle et al. 1969) also provides data that show that 

a 238PuF4 neutron source (average energy of 1.3 MeV), under identical exposure 

conditions, produced a fading factor of 33% after 1 week and 56% after 2 weeks. 

ORAUT-TKBS-0017-6 (ORAUT 2007) does not provide information concerning the 

timing of the neutron calibration cycle (i.e., if it was performed at the beginning, mid, or 

the end of the badging cycle); and Section 6.5.3.2 and Table 6-8 indicate that no detailed 

information was available concerning neutron dosimetry at Pantex prior to 1980. 

However, Table 6-13, page 36, of ORAUT-TKBS-0017-6 (ORAUT 2007), does 

recommend using a neutron energy range of 0.1–2 MeV; hence, both the 0.9 MeV 

238PuO2 and the 1.3 MeV 238PuF4 neutron sources fall in that energy range. There does 

not appear to be any supporting evidence to select the lower fading factor of 9%. In 

NIOSH’s Mound white paper (NIOSH 2010), it is stated on page 4: 

NIOSH continues to support the fading values of 33% in the first week after 

exposure and 56% after two weeks. This fading correction is to be applied 

independent of other corrections such as angular response or energy 

response. 

Therefore, it is not obvious why the value of 9% fading per week was selected to be 

applied at Pantex.

6.2 Summary

OTIB-0086 provides information concerning the following items at Pantex: 
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1. Zeros – Dose reconstruction recommendations for entries containing zero, blank, and 

marks in the dose records. 

2. Coworker doses – Coworker photon, neutron, and skin doses for the period 1960–2010 

are provided in Tables 1, 2, and 3, respectively. The information for these tables was 

obtained from the dose data from BWXT 2011 for the periods 1960–1979 and 1994–

2010 and from BWXT 2013 for the period 1980–1993. 

3. NTA film – Recommendations for application of neutron dose correction factors for 

energy response, angular response, and track fading for NTA film. 

6.3 Conclusions and Issues

1. Zeros – SC&A finds the recommendations in OTIB-0086 concerning zero, blank, or 

marks in the records to be consistent with those used for other DOE sites and dosimetry 

records in general, and has not found data that are in conflict with these 

recommendations. 

2. Coworker doses – SC&A’s spot review of the coworker photon, neutron, and skin doses 

for the period 1960–2010 in Tables 1, 2, and 3, respectively, did not reveal any issues; 

except for the fact that the neutron dose for 1975 was a factor of 10 to 100 times the 

other annual neutron doses (the photon and skin doses for 1975 did not show any 

increase for 1975). SC&A did not perform a complete recalculation of the data in the 

coworker tables because the use of resources for such a task was not warranted at this 

time. 

3. NTA film – SC&A evaluated the recommendations in OTIB-0086 for application of 

neutron dose correction factors for energy response, angular response, and track fading 

for NTA film and found: 

• Energy response – In evaluating the recommended energy correction factor of 

1.4, SC&A does not find that the MCNP model generated for Mound Laboratory 

of an observer located at 240 cm from a glovebox with 4 inches of moderator 

necessarily represents the situation and neutron energy fields for a worker at 

Pantex with potential multiple sources of exposure. 

• Angular response – The angular correction factor of 1.33 for NTA film did not 

include the fact that Pantex workers were potentially exposed to multiple sources 

of neutrons, which could include PA geometry. Neither the NTA film calibration 

nor the AP angular correction factor addresses PA geometry for neutron 

exposure.

• Track fading – There does not appear to be any supporting evidence as to why 

the lower fading factor of 9% was selected, when other studies indicate higher 

fading factors. 
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• Period to apply – The time period that these adjustment factors should be 

applied to recorded neutron doses should be confirmed and provided to the dose 

reconstructor for consistency; i.e., 1960–197? This also requires determining the 

correct period that the 2-element TLD was used.
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7.0 REFERENCES

Adams, D., 2003. “Back of Old Reports Between 63-78,” facsimile to ORAU Team, Landauer, 

Glenwood, Illinois, October 6. [SRDB Ref ID: 11506, p. 4]. 

Ashton, M., 2003. Untitled facsimile to ORAU Team, University of Colorado at Boulder, 

Boulder, Colorado, October 7. [SRDB Ref ID: 11509, p. 4]. 

BWXT 2011. Pantex External Dosimetry Data from DoRMS, Consolidated Nuclear Security, 

Amarillo, Texas. January 5, 2011. SRDB Ref ID: 91261. 

BWXT 2013. Recalculated UD-802 Doses for 1980 - 1993 Using Stanford Dosimetry Algorithm 

Spreadsheet, Consolidated Nuclear Security, Amarillo, Texas. August 5, 2013. SRDB Ref ID: 

126957. 

Kahle, J.B., E.N. Arnett, and C.T. Meyer, 1969. “Latent Image Fading in Personnel Monitoring 

Neutron Film,” Health Physics, volume 17, number 5, pp. 735–736. 

Kathren, R.L., C.T. Prevo, and S. Block, 1965. “Angular Dependence of Eastman Type A (NTA) 

Personnel Monitoring Film,” Health Physics, volume 11, number 10, pp. 1067–1069. 

Lalos, G., editor, 1989. Film Badge Dosimetry in Atmospheric Nuclear Tests, National 

Research Council, National Academy Press, Washington, DC. [SRDB Ref ID: 1905]. 

LANL 2003. MCNP – A General Monte Carlo N-Particle Transport Code, Version 5, LA-UR03-1987, Los Alamos National Laboratory, Los Alamos, New Mexico. April 24, 2003. SRDB 

Ref ID: 22399. 

NIOSH 1993. NIOSH Research Issues Workshop: Epidemiologic Use of Nondetectable Values 

in Radiation Exposure Measurements, National Institute for Occupational Safety and Health 

Cincinnati, Ohio, September 9 and 10, 1993, Health-Related Energy Research Branch, 

Cincinnati, Ohio. [SRDB Ref ID: 13723]. 

NIOSH 2010. NIOSH Evaluation of NTA Neutron Film Fading at Mound: Response to SC&A 

Issues and Recommendations, National Institute for Occupational Safety and Health, Cincinnati, 

Ohio. December 2010. 

ORAUT 2007. Pantex Plant – Occupational External Dose, ORAUT-TKBS-0013-6, Rev. 01, 

Oak Ridge Associated Universities Team, Oak Ridge, Tennessee. June 22, 2007. 

ORAUT 2015a. Pantex External Coworker Model, ORAUT-OTIB-0086, Rev. 00, Oak Ridge 

Associated Universities Team, Oak Ridge, Tennessee. August 7, 2015. 

ORAUT 2015b. External Dose Coworker Methodology, ORAUT-RPRT-0071, Rev. 00, Oak 

Ridge Associated Universities Team, Oak Ridge, Tennessee. July 2, 2015. 
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ORAUT 2015c. Pantex Fit Plots, Oak Ridge Associated Universities Team, Cincinnati, Ohio. 

May 4, 2015. SRDB Ref ID: 142269. 

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