ORAU Team

NIOSH Dose Reconstruction Project

Technical Basis Document: 

Basis for Development of an Exposure Matrix for 

Bethlehem Steel Corporation

Document Number:

ORAUT-TKBS-0001

Effective Date: 03/31/2003

Revision No.: 00

Controlled Copy No.: _____

Page 1 of 14

Subject Expert: Jeri L. Anderson

Approval: Signature on File ______Date: _03/27/2003__ James P. Griffin, Task 5 Manager

Concurrence: Signature on File____Date: _03/31/2003__ Richard E. Toohey, Project Director

Approval: _Signature on File______Date: _03/31/2003__ James W. Neton, NIOSH, OCAS Health Science Administrator

Supersedes:

None

RECORD OF ISSUE/REVISIONS

ISSUE

AUTHORIZATION

DATE

EFFECTIVE

DATE

REV.

NO. DESCRIPTION

Draft 12/17/2002 0-A New document to establish the technical basis 

for the development of a radiation exposure 

matrix for Bethlehem Steel Corporation. Initiated 

by Jeri L. Anderson.

Draft 12/17/2002 0-B Changes in response to internal and NIOSH 

review comments.

Draft 12/17/2002 0-C Changes in response to NIOSH review 

comments.

Draft 12/17/2002 0-D Changes in response to NIOSH review 

comments.

Draft 12/17/2002 0-E Changes in response to NIOSH review 

comments.

03/31/2003 03/31/2003 00 First approved issue.
Effective Date: 03/31/2003 Revision No. 00 Document No. ORAUT-TKBS-0001 Page 2 of 14

Basis for Development of an Exposure Matrix for 

BETHLEHEM STEEL CORPORATION

Lackawanna, New York

Period of Operation: 1949-1952 

Site Description and Operational History

The Atomic Energy Commission (AEC) contracted with the Bethlehem Steel Corporation 

(BSC) in 1949 to develop improved rolling mill pass schedules. This work was 

conducted under contracts AT(30-1)-1279 and AT(30-1)-1156, which were subcontracts 

with National Lead of Ohio (US DOE 1985). The pass schedules were for the rolling of 

5-inch natural uranium billets into 1.5-inch rods to be used in nuclear reactors (LaMastra 

1976, US DOE 1985) for production of plutonium. The billets were prepared by 

Mallinckrodt Chemical in St. Louis, MO and shipped to Lackawanna in freight cars. The 

freight cars were spotted within the plant and served as storage for the uranium billets 

during the week (Range 1976, ORNL 1980, US DOE 1985). The rolling experiments 

took place only on weekends because the mills were already in full use 5 days per week 

and involved only the 10” bar mill and associated billet preparation and handling 

equipment (LaMastra 1976, Range 1976, Thornton 1977, ORNL 1980, US DOE 1985). 

Because of material accountability procedures, scale, residue and cropped ends were 

collected and fine debris was vacuumed, packaged and sent back to the AEC (LaMastra 

1976, Range 1976, ORNL 1980, US DOE 1985). Radiological surveys were conducted 

in 1976 and 1980 of the original facility and equipment, which were still in existence. 

These surveys identified no residual contamination above natural background levels 

(LaMastra 1976, ORNL 1980, US DOE 1985). 

Some references indicate that all work was done between 1949 and 1951 (Summary 

1951, LaMastra 1976, ORNL 1980). However, there are reports that indicate that seven 

additional rollings took place in 1952 (Bowman et al. 1952, NLO 1952b, US DOE 1985) 

although these were reported to be production rollings. A letter from a labor 

representative from October 1979 claims that six to eight rollings took place in 1955 

although no verification of these dates have been found (Kosanovich 1979). The work 

was supposedly transferred to the Fernald Plant around September 1952 (NLO 1952b, 

LaMastra 1976, Range 1976). The information obtained from the rolling experiments at 

BSC was used in designing a rolling mill at the National Lead Company plant in Fernald, 

Ohio, which began production in 1953 (LaMastra 1976, Range 1976). Table 1 provides 

the dates of the rollings at BSC for which actual documentation has been found. 
Effective Date: 03/31/2003 Revision No. 00 Document No. ORAUT-TKBS-0001 Page 3 of 14

Table 1. Documented rollings at Bethlehem Steel Corporation, Lackawanna, NY. 

Date of Rolling Day of Week Type No. of Billets 

Rolled

Bath Type

April 26-27, 1951 Thurs., Fri. Experimental 26 Lead/Salt

July 29, 1951 Sun. Experimental 24 Lead/Salt

August 26, 1951 Sun. Experimental 32 Lead/Salt

September 30, 1951 Sun. Experimental 43 Lead/Salt

October 28, 1951 Sun. 93 Salt

January 26, 1952 Sat. Production Salt

March 15, 1952 Sat. Production 218 Salt

April 12, 1952 Sat. Production 220 Salt

August 17, 1952 Sun. Production 157 Salt

August 31, 1952 Sunday Production 219 Salt

September 14, 1952 Sunday Production 303 Salt

September 22, 1952 Monday Production 302 Salt

Several documents report that AEC personnel were present during all rolling operations. 

These personnel conducted air and surface radioactivity monitoring and checked 

personnel involved in the rolling for contamination (LaMastra 1976, ORNL 1980, US 

DOE 1985). Documents also indicate that no records are available of these monitoring 

activities (LaMastra 1976, Range 1976, ORNL 1980). If monitoring records ever existed, 

they were not retained (LaMastra 1976). It appears that the uranium metal accountability 

records were destroyed (Range 1976).

During the war, permissible levels for uranium dust in air were set at 500 μg/m3 for 

insoluble uranium compounds and 150 μg/m3

 for soluble uranium compounds. After the 

war, the University of Rochester lowered their recommendation for soluble uranium 

compounds to 50 μg/m3 on the basis of chemical toxicity, which is equivalent to 70 

disintegrations per minute per cubic meter. This level was based primarily on animal 

studies. The Medical Division of the New York Operations Office felt that a “maximum 

permissible level” was really unknown and should be based on human data. Therefore, 

the level 50 μg/m3

 was referred to as the “preferred level” (U.S. AEC 1949b). Many of 

the AEC contractors used the term Maximum Allowable (air) Concentration (MAC) 

interchangeably with the “preferred level” and often reported air-sampling results as 

multiples of the MAC (NLO 1952c, U.S. AEC 1953). 

A New York Operations Office (NYOO) report of a visit to Simonds Saw and Steel in 

Lockport, New York on October 27, 1948 describes occupational radioactive dust 

exposures between 8 and 190 times the MAC depending on the type of job performed 

(US AEC 1948a). This report indicates a 10-hour workday. The report also states 

“...where the maximum amount of alpha was present, a concentration of more than 1000 

times the preferred level, the beta activity of the same sample was less than 0.5 times the 

tolerance (40,000 beta disintegrations per cubic meter). For this reason it is felt that the 

exposure to beta emitting dust is of negligible consequence as compared to any 

concomitant alpha dust exposure” (US AEC 1948a). This survey was done during a 

production rolling. During experimental rollings, generally less than 50 billets were 
Effective Date: 03/31/2003 Revision No. 00 Document No. ORAUT-TKBS-0001 Page 4 of 14

rolled. It appears from the job analysis sheets that around 180 billets were rolled that 

day. 

After the October 1948 visit to Simonds, recommendations were made for the 

implementation of procedures to reduce the dust hazard. Surveys were subsequently 

done to determine the effectiveness of implemented control procedures. A survey in 

December 1948 showed reduction of air concentration to levels between 4 and 28 MAC. 

A survey in January of 1949 showed further reduction of air concentration to levels 

between 1.4 and 28 MAC (U.S. AEC 1949b). 

One of the many purposes of the Experimental Rolling #1 at BSC on April 26-27, 1951 

was to explore the feasibility of using fused salt as a protective medium during rolling to 

prevent oxidation and minimize the health hazard (Summary 1951). An additional 

rolling was done on April 17, 1951 at Simonds Saw and Steel Company in Lockport, NY 

using 18” bar mills. This rolling was also considered part of Experimental Rolling #1 

(Summary 1951). A NYOO report showed results from a survey done during rolling 

operations on a 16” bar mill at Simonds on August 20, 1951. The survey indicated 

exposures between 0.81 MAC to 2.5 MAC depending on the type of job performed (US 

AEC 1953). The same report gives the results of another survey done on December 9, 

1952 at Simonds showing exposure levels between 0.93 and 4.2 MAC (US AEC 1953). 

The average exposures were 1.48 MAC for August 20, 1951 and 2.1 MAC for December 

9, 1952. This report also indicates that workdays were generally eight hours (US AEC 

1953). 

Air dust data reports from rollings done in 1951 and 1952 at BSC were found in 

documents submitted by a claimant. Alpha air concentration values ranged from 0 to 130 

dpm/m3

 (1.9 MAC) in 1951 and 0 and 4900 dpm/m3 (70 MAC) in 1952 (NLO 1952a, US 

AEC 1951-1952). All data were collected by the AEC New York Operations Office 

Medical Division with the exception of data obtained on September 14, 1952, which was 

collected by National Lead Company of Ohio Health and Safety Division. 

Estimation of Internal Exposure 

The triangular distribution is used to represent subjective judgments about uncertainty 

when it is possible to estimate an upper and lower bound and a most likely value for a 

quantity (Frey and Cullen 1995). Because there were few records of air monitoring for 

BSC, a triangular distribution is used to represent the distribution of possible air 

concentration values during operations at BSC. 

Tables 2a and 2b below show the internal exposure matrix for the Bethlehem Steel site. 

Table 2a is considered to be a lower bound for estimation of internal exposure and Table 

2b is considered to be an upper bound. For 1949 through 1952, the most likely value, or 

mode, was assumed to be 140 dpm/m3

, which corresponds to 2 MAC. The minimum 

value was assumed to be 0 dpm/m3, which takes into account the possibility that there 

was no exposure. The maximum value for the lower bound matrix was assumed to be 

4900 dpm/m3 (70 MAC), which is the maximum reading found in the Bethlehem Steel air 
Effective Date: 03/31/2003 Revision No. 00 Document No. ORAUT-TKBS-0001 Page 5 of 14

monitoring data (U.S. AEC 1951-1952). The maximum value for the upper bound matrix 

was assumed to be 70,000 dpm/m3

 (1000 MAC) because of the reported maximum levels 

during rolling operations in 1948 at the Simonds facility (US AEC 1948a). Although the 

exposure levels in 1948 were reportedly higher than the mode value of 2 MAC used in 

the matrices, it was assumed that several recommended improvements were made to the 

process in the interim (US AEC 1948a), which is evident in the 1951 and 1952 

Bethlehem Steel data. Another factor in the difference in air concentration levels is the 

fact that the rollings at Simonds were production runs as opposed to experimental runs 

that involved much less material.

The number of exposure hours per year was determined by assuming 12 10-hour 

workdays per year for 1949 and 1950. This assumption is conservative considering that 

there is no documentation that indicates any rollings actually took place during those 

years. If there were any rollings, it is assumed they only took place on weekends. 

Reports from 1951 and 1952 indicate that, with the exception of the April 1951 

(Summary 1951), August 1952 (Bowman et al. 1952), and September 1952 (Schneider 

and Yocce) rollings, only one weekend day per month was utilized. For 1951, an 

additional 10 hours was added to account for the additional weekday in April, resulting in 

13 10-hour workdays. For 1952, in addition to the seven documented rollings, it was 

assumed that one rolling each took place in February, March, June, and July resulting in 

11 10-hour workdays. It is assumed that no rollings took place after September 1952 

because the work was transferred to the Fernald Plant around that time (NLO 1952a, 

LaMastra 1976, Range 1976). 

The breathing rate was calculated from the volume of air breathed for an adult light 

worker shown in ICRP Publication 66, Table 6 on pg. 23 (ICRP 1994). This category 

assumes an activity distribution of 1/3 sitting and 2/3 light exercise. The minimum and 

mode intakes, in pCi, were calculated by multiplying the appropriate air concentration by 

the breathing rate and the hours worked, and dividing by 2.2 dpm/pCi. The maximum 

intakes were calculated using the same method but substituting the breathing rate for an 

adult heavy worker, which assumes an activity distribution of 7/8 light exercise and 1/8 

heavy exercise.

Table 2a. Internal Exposure Matrix-Lower Bound

Work 

Period

Air Concentration

(dpm/m3)

Breathing 

Rate 

(m3/h)*

Hours

(h)

Annual

Intake

(pCi)

min. mode max Light/heavy min. mode max.

1949 0 140 4900 1.2/1.7 120 0.00E+00 9.16E+03 4.54E+05

1950 0 140 4900 1.2/1.7 120 0.00E+00 9.16E+03 4.54E+05

1951 0 140 4900 1.2/1.7 130 0.00E+00 9.93E+03 4.92E+05

1952 0 140 4900 1.2/1.7 110 0.00E+00 8.40E+03 4.17E+05

*The breathing rate of 1.2 m3/h was used to calculate the minimum and mode intake. 

The breathing rate of 1.7 m3

/h was used to calculate the maximum intake.
Effective Date: 03/31/2003 Revision No. 00 Document No. ORAUT-TKBS-0001 Page 6 of 14

Table 2b. Internal Exposure Matrix-Upper Bound

Work 

Period

Air Concentration

(dpm/m3)

Breathing 

Rate 

(m3/h)*

Hours

(h)

Annual

Intake

(pCi)

min. mode max Light/heavy min. mode max.

1949 0 140 70,000 1.2/1.7 120 0.00E+00 9.16E+03 6.49E+06

1950 0 140 70,000 1.2/1.7 120 0.00E+00 9.16E+03 6.49E+06

1951 0 140 70,000 1.2/1.7 130 0.00E+00 9.93E+03 7.03E+06

1952 0 140 70,000 1.2/1.7 110 0.00E+00 8.40E+03 5.95E+06

*The breathing rate of 1.2 m3/h was used to calculate the minimum and mode intake. 

The breathing rate of 1.7 m3

/h was used to calculate the maximum intake.

In order to make use of the information in Tables 2a and 2b for estimation of internal 

dose, the annual doses for the organ of interest should be calculated in the IMBA NIOSH 

program for the minimum, mode, and maximum intake of natural uranium assuming a 

chronic exposure. If the claimant has a likely compensable cancer, the exposure should 

be calculated using the lower bound matrix (Table 2a). If the claimant has a likely noncompensable cancer, the exposure should be calculated using the upper bound matrix. 

The three sets of annual organ doses can then be entered into the NIOSH IREP program 

as the annual dose due to alpha radiation using a triangular distribution and the minimum, 

mode, and maximum doses as parameters 1, 2, and 3 respectively. If the lower bound 

matrix was used to calculate exposure, and the probability of causation is determined to 

be less than 50%, then the exposure should be recalculated using the upper bound matrix. 

Human and animal studies have indicated that oxides of uranium can be very insoluble 

(ICRP 1995). However, to be claimant-favorable, the selection of absorption type should 

be dependent on the organ of interest. For example, Absorption Type S should be 

selected for respiratory tract dose calculations and Absorption Type M for all other organ 

dose calculations. ICRP 66 default parameters should be selected for particle deposition 

parameters in the IMBA NIOSH program.

Contamination of the uranium metal by fission products and transuranics is not 

considered an issue at Bethlehem Steel Corporation because recycling of uranium in the 

weapons complex did not begin until after March 1952 (US DOE 2001b). 

Although the values shown above in Tables 2a and 2b may seem to be excessive 

overestimates, they are consistent with NIOSH’s approach of making claimant favorable 

assumptions when monitoring data are lacking or incomplete.

Estimation of External Exposure 

For estimating maximum external exposure due to submersion in air contaminated with 

uranium dust, the maximum air concentration value and work times per year in Table 2b 

(upper bound) were combined with Dose Conversion Factors for U-238 and the daughter 

radionuclides Th-234 and Pa-234m from Federal Guidance Report No. 12 (US EPA 

1993). Table 3 shows external dose estimates for 1949-1952. With the exception of dose 

to the skin, the cumulative four-year dose for each of the organs is less than 1 mrem and 
Effective Date: 03/31/2003 Revision No. 00 Document No. ORAUT-TKBS-0001 Page 7 of 14

is therefore not included in the dose estimation. The maximum annual dose to the skin 

shown in Table 3 is applied to both the electron (E>15 kev) and photon (E = 30-250 keV) 

annual dose in the NIOSH-IREP program using a constant distribution and assuming a 

chronic exposure. 

Table 3. Estimated maximum annual external dose due to submersion in air 

contaminated with natural uranium dust. 

Maximum AnnualOrgan Dose

(rem)

Organ 1949 1950 1951 1952

Adrenals 3.98E-05 3.98E-05 4.31E-05 3.65E-05

U Bladder 4.09E-05 4.09E-05 4.43E-05 3.75E-05

Bone Surface 1.19E-04 1.19E-04 1.29E-04 1.09E-04

Brain 5.18E-05 5.18E-05 5.61E-05 4.75E-05

Breast 6.13E-05 6.13E-05 6.64E-05 5.62E-05

Esophagus 3.89E-05 3.89E-05 4.22E-05 3.57E-05

Stomach Wall 4.39E-05 4.39E-05 4.75E-05 4.02E-05

Small Intestine Wall 3.83E-05 3.83E-05 4.15E-05 3.51E-05

Upper Large Intestine 

Wall

4.01E-05 4.01E-05 4.34E-05 3.68E-05

Lower Large Intestine 

Wall

3.90E-05 3.90E-05 4.22E-05 3.57E-05

Kidney 4.48E-05 4.48E-05 4.85E-05 4.11E-05

Liver 4.46E-05 4.46E-05 4.83E-05 4.09E-05

Lung 5.02E-05 5.02E-05 5.44E-05 4.60E-05

Muscle 4.97E-05 4.97E-05 5.39E-05 4.56E-05

Ovaries 3.81E-05 3.81E-05 4.12E-05 3.49E-05

Pancreas 3.76E-05 3.76E-05 4.07E-05 3.44E-05

Red Bone Marrow 4.64E-05 4.64E-05 5.02E-05 4.25E-05

Skin 2.80E-03 2.80E-03 3.03E-03 2.57E-03

Spleen 4.47E-05 4.47E-05 4.84E-05 4.10E-05

Testes 5.28E-05 5.28E-05 5.72E-05 4.84E-05

Thymus 4.73E-05 4.73E-05 5.13E-05 4.34E-05

Thyroid 5.27E-05 5.27E-05 5.71E-05 4.83E-05

Uterus 3.72E-05 3.72E-05 4.03E-05 3.41E-05

For estimating external exposure to a uranium source, the source was assumed to be an 

extended (semi-infinite plane) natural uranium source. Estimated surface dose rates of 

230 mrad/hr at a depth of 7 mg/cm2

 and 2 mrad/hr at a depth of 1000 mg/cm2were 

obtained from a search of the literature (Coleman et al. 1983, US Army 1989). Claimantfriendly values for the time that workers were located relative to the source were based 

on descriptions of processes and different job types (US AEC 1948b). 

A triangular distribution for electron exposure from uranium was determined in the 

following manner: 
Effective Date: 03/31/2003 Revision No. 00 Document No. ORAUT-TKBS-0001 Page 8 of 14

• The minimum was estimated by assuming the worker was 1 meter away from an 

extended uranium source for 1 hour (per 10 hour shift). The estimated dose rate 

for this scenario was 90 mrad/hr (US Army 1989). 

• Survey data of the Simonds facility were used to estimate the mode. The highest 

value measured during those surveys was 15 mrad/hr (US AEC 1949a). To be 

claimant-favorable, this dose rate was assumed for an entire 10-hour shift. 

• A maximum value was estimated by assuming the worker was 0.3 meters (1 foot) 

away from an extended uranium source for 6 hours (150 mrad/hr) and 1 meter 

away for 4 hours (90mrad/hr).

Table 4 is a summary of the annual values for estimated external shallow dose due to 

electron exposure from uranium. The target organs for this type of exposure are the skin, 

male genitals, and breast. In the case of cancer of the male genitals or female breast 

cancer, additional evaluation may be needed to consider shielding and attenuation 

provided by clothing. 

Table 4. Estimated external shallow dose due to electron exposure from a natural uranium 

source.

Organ Annual Dose

(rem)

Work Period Min. Mode Max.

1949 1.08 1.80 15.12

1950 1.08 1.80 15.12

1951 1.17 1.95 16.38

1952 0.99 1.65 13.86

For cases where the target organ is the skin, male genitals, or breast, the values in Table 4 

above are entered into the NIOSH-IREP program as the annual dose due to electrons 

(E>15 keV) using a triangular distribution and assuming a chronic exposure. 

The assumption was also made that workers received an annual occupationally related 

diagnostic x-ray (Simonds 1948). The exposure geometry was assumed to be posterioranterior (PA) (DHHS 2002). The entrance skin exposure from the diagnostic chest x-ray 

was estimated to be 0.027 R (range 0-0.090 R) (NCRP 1989). The organ doses were 

calculated by multiplying the entrance skin exposure by the “Exposure (R) to Organ Dose 

(HT)” photon dose conversion factors for 30-250 keV photons found in Appendix B of 

the NIOSH External Dose Reconstruction Implementation Guideline (DHHS 2002). 

Table 5 below shows the annual organ doses due to the assumed annual diagnostic chest 

x-ray. The lower and upper bounds of the entrance skin exposure range were multiplied 

by the lower and upper bounds of the dose conversion factor to produce a minimum and 

maximum dose. The values in Table 5 are entered into the NIOSH-IREP program as the 

annual dose due to photons with energies between 30 and 250 keV using a triangular 

distribution and assuming an acute exposure. 
Effective Date: 03/31/2003 Revision No. 00 Document No. ORAUT-TKBS-0001 Page 9 of 14

Table 5. Annual organ doses due to the assumed annual diagnostic chest x-ray.

Organ Dose (rem)

Organ Minimum Mode Maximum

Bladder 0.000 0.016 0.062

Red Bone Marrow 0.000 0.027 0.105

Bone Surface 0.000 0.039 0.210

Breast 0.000 0.013 0.050

Colon 0.000 0.021 0.081

Esophagus 0.000 0.023 0.089

Eye 0.000 0.005 0.022

Ovaries 0.000 0.024 0.096

Testes 0.000 0.013 0.051

Liver 0.000 0.022 0.086

Lung 0.000 0.029 0.113

Remainder organs 0.000 0.024 0.093

Skin 0.000 0.024 0.087

Stomach 0.000 0.017 0.064

Thymus 0.000 0.010 0.040

Thyroid 0.000 0.011 0.043

Uterus 0.000 0.021 0.082

The deep dose rate due to photon exposure (dose rate at 1000 mg/cm2

) from natural 

uranium was estimated to be 2 mrad/hr (US Army 1989). Table 6 shows the annual 

organ doses due to photons from the natural uranium source. A triangular distribution for 

these doses was determined by applying the minimum and maximum dose conversion 

factors (DCFmin and DCFmax) for 30-250 keV photons (US DHHS 2002) to the estimated 

2 mrad/hr deep dose rate multiplied by the estimated work times shown in Tables 2a and 

2b. To calculate the mode value, the dose conversion factor for anterior-posterior 

geometry (DCFAP) was used.
Effective Date: 03/31/2003 Revision No. 00 Document No. ORAUT-TKBS-0001 Page 10 of 14

Table 6. Annual organ doses due to photons from a natural uranium source. 

Annual Organ Dose

(rem)

1949 1950 1951 1952

Organ Min Mode Max Min Mode Max Min Mode Max Min Mode Max

Bladder 0.01 0.23 0.24 0.01 0.23 0.24 0.01 0.24 0.26 0.01 0.21 0.22

Red Bone 

Marrow

0.02 0.11 0.20 0.02 0.11 0.20 0.02 0.12 0.22 0.01 0.11 0.19

Bone 

Surface

0.09 0.22 0.36 0.09 0.22 0.36 0.10 0.24 0.39 0.08 0.20 0.33

Breast 0.01 0.23 0.23 0.01 0.23 0.23 0.01 0.25 0.25 0.01 0.21 0.21

Colon 0.01 0.19 0.21 0.01 0.19 0.21 0.01 0.21 0.22 0.01 0.18 0.19

Esophagus 0.01 0.13 0.17 0.01 0.13 0.17 0.01 0.14 0.19 0.01 0.12 0.16

Eye 0.00 0.23 0.26 0.00 0.23 0.26 0.00 0.25 0.28 0.00 0.21 0.24

Ovaries 0.01 0.17 0.19 0.01 0.17 0.19 0.01 0.19 0.21 0.01 0.16 0.17

Testes 0.01 0.26 0.27 0.01 0.26 0.27 0.01 0.28 0.30 0.01 0.24 0.25

Liver 0.02 0.19 0.20 0.02 0.19 0.20 0.03 0.21 0.22 0.02 0.18 0.19

Lung 0.03 0.18 0.21 0.03 0.18 0.21 0.03 0.19 0.22 0.03 0.16 0.19

Remainder 

organs 

0.02 0.16 0.17 0.02 0.16 0.17 0.02 0.17 0.19 0.02 0.15 0.16

Skin 0.11 0.16 0.18 0.11 0.16 0.18 0.12 0.18 0.19 0.10 0.15 0.16

Stomach 0.01 0.23 0.24 0.01 0.23 0.24 0.01 0.25 0.26 0.01 0.21 0.22

Thymus 0.00 0.26 0.27 0.00 0.26 0.27 0.00 0.28 0.29 0.00 0.23 0.25

Thyroid 0.00 0.26 0.27 0.00 0.26 0.27 0.00 0.28 0.30 0.00 0.24 0.25

Uterus 0.01 0.18 0.20 0.01 0.18 0.20 0.01 0.20 0.22 0.01 0.17 0.18

For likely non-compensable cases, the values in Table 6 above are entered into the 

NIOSH-IREP program as the annual organ dose due to photons with energy between 30 

and 250 keV using a triangular distribution and assuming a chronic exposure. 

For likely compensable cases, the estimated 2 mrad/hr deep dose rate from the uranium 

source is evenly divided between photons with energies E= 30-250 keV and E>250 keV. 

The dose conversion factors, DCFmin, DCFmax, and DCFAP, for 30-350 keV photons were 

used to calculate the doses in Table 7a. The dose conversion factors, DCFmin, DCFmax, 

and DCFAP, for E>250 keV photons were used to calculate the doses in Table 7b. The 

values in Tables 7a and 7b are entered into the NIOSH-IREP program as organ doses due 

to the appropriate energy photons, using a triangular distribution and assuming a chronic 

exposure. 
Effective Date: 03/31/2003 Revision No. 00 Document No. ORAUT-TKBS-0001 Page 11 of 14

Table 7a. Annual organ doses due to photons (30-250 keV) from a natural uranium 

source.

Annual Organ Dose

(rem)

1949 1950 1951 1952

Organ Min Mode Max Min Mode Max Min Mode Max Min Mode Max

Bladder 0.00 0.11 0.12 0.00 0.11 0.12 0.00 0.12 0.13 0.00 0.10 0.11

Red Bone 

Marrow

0.01 0.06 0.10 0.01 0.06 0.10 0.01 0.06 0.11 0.01 0.05 0.09

Bone 

Surface

0.05 0.11 0.18 0.05 0.11 0.18 0.05 0.12 0.20 0.04 0.10 0.17

Breast 0.01 0.12 0.12 0.01 0.12 0.12 0.01 0.12 0.13 0.00 0.11 0.11

Colon 0.01 0.10 0.10 0.01 0.10 0.10 0.01 0.10 0.11 0.01 0.09 0.09

Esophagus 0.00 0.06 0.09 0.00 0.06 0.09 0.00 0.07 0.09 0.00 0.06 0.08

Eye 0.00 0.11 0.13 0.00 0.11 0.13 0.00 0.12 0.14 0.00 0.10 0.12

Ovaries 0.00 0.09 0.10 0.00 0.09 0.10 0.00 0.09 0.10 0.00 0.08 0.09

Testes 0.00 0.13 0.14 0.00 0.13 0.14 0.00 0.14 0.15 0.00 0.12 0.12

Liver 0.01 0.10 0.10 0.01 0.10 0.10 0.01 0.10 0.11 0.01 0.09 0.09

Lung 0.02 0.09 0.10 0.02 0.09 0.10 0.02 0.10 0.11 0.01 0.08 0.09

Remainder 

organs

0.01 0.08 0.09 0.01 0.08 0.09 0.01 0.09 0.09 0.01 0.07 0.08

Skin 0.05 0.08 0.09 0.05 0.08 0.09 0.06 0.09 0.10 0.05 0.07 0.08

Stomach 0.01 0.11 0.12 0.01 0.11 0.12 0.01 0.12 0.13 0.00 0.10 0.11

Thymus 0.00 0.13 0.14 0.00 0.13 0.14 0.00 0.14 0.15 0.00 0.12 0.12

Thyroid 0.00 0.13 0.14 0.00 0.13 0.14 0.00 0.14 0.15 0.00 0.12 0.12

Uterus 0.01 0.09 0.10 0.01 0.09 0.10 0.01 0.10 0.11 0.00 0.08 0.09

Table 7b. Annual organ doses due to photons (>250 keV) from a natural uranium source. 

Annual Organ Dose

(rem)

1949 1950 1951 1952

Organ Min Mode Max Min Mode Max Min Mode Max Min Mode Max

Bladder 0.05 0.11 0.11 0.05 0.11 0.11 0.06 0.12 0.12 0.05 0.10 0.10

Red Bone 

Marrow

0.06 0.09 0.11 0.06 0.09 0.11 0.07 0.10 0.12 0.06 0.08 0.10

Bone 

Surface

0.07 0.09 0.11 0.07 0.09 0.11 0.07 0.10 0.12 0.06 0.09 0.10

Breast 0.06 0.12 0.12 0.06 0.12 0.12 0.06 0.13 0.13 0.05 0.11 0.11

Colon 0.05 0.10 0.11 0.05 0.10 0.11 0.06 0.11 0.12 0.05 0.10 0.10

Esophagus 0.05 0.09 0.10 0.05 0.09 0.10 0.06 0.10 0.11 0.05 0.08 0.10

Eye 0.02 0.11 0.12 0.02 0.11 0.12 0.03 0.12 0.13 0.02 0.10 0.11

Ovaries 0.05 0.10 0.12 0.05 0.10 0.12 0.06 0.11 0.12 0.05 0.09 0.11

Testes 0.06 0.12 0.13 0.06 0.12 0.13 0.06 0.13 0.14 0.05 0.11 0.12

Liver 0.06 0.11 0.11 0.06 0.11 0.11 0.06 0.11 0.12 0.05 0.10 0.10

Lung 0.06 0.10 0.11 0.06 0.10 0.11 0.07 0.11 0.12 0.06 0.10 0.10

Remainder 

organs

0.06 0.10 0.10 0.06 0.10 0.10 0.06 0.11 0.11 0.05 0.09 0.09

Skin 0.07 0.10 0.11 0.07 0.10 0.11 0.08 0.11 0.12 0.07 0.09 0.10

Stomach 0.06 0.11 0.11 0.06 0.11 0.11 0.06 0.12 0.12 0.05 0.10 0.11

Thymus 0.04 0.11 0.13 0.04 0.11 0.13 0.05 0.12 0.14 0.04 0.10 0.12

Thyroid 0.05 0.12 0.13 0.05 0.12 0.13 0.05 0.13 0.14 0.04 0.11 0.12

Uterus 0.05 0.10 0.10 0.05 0.10 0.10 0.06 0.11 0.11 0.05 0.09 0.09
Effective Date: 03/31/2003 Revision No. 00 Document No. ORAUT-TKBS-0001 Page 12 of 14

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