ORAU TEAM

Dose Reconstruction

Project for NIOSH

Oak Ridge Associated Universities I Dade Moeller I MJW Technical Services

Page 1 of 68

DOE Review Release 02/20/2014

Document Title:

Response of Dosimeters to Aged Fission 

Products in a Tank Farm Environment at the 

Savannah River Site

Document Number: ORAUT-RPRT-0062

Revision: 00

Effective Date: 02/11/2014

Type of Document: Report

Supersedes: None

Subject Expert(s): James M. Mahathy, Roger Halsey, Robert L. Morris

Approval: Signature on File Approval Date: 02/03/2014

James M. Mahathy, Document Owner

Concurrence: Signature on File Concurrence Date: 01/29/2014

Daniel H. Stempfley, Objective 4 Representative

Concurrence: Vickie S. Short Signature on File for Concurrence Date: 01/31/2014

Kate Kimpan, Project Director

Approval: Signature on File Approval Date: 02/11/2014

James W. Neton, Associate Director for Science

New Total Rewrite Revision Page Change

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

REVISION AND DISCARD / DESTROY ALL COPIES OF THE PRIOR REVISION.
Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 2 of 68

PUBLICATION RECORD

EFFECTIVE 

DATE

REVISION 

NUMBER DESCRIPTION

02/11/2014 00 New report initiated to document the response of the Savannah River 

Site multielement film dosimeter to external penetrating photon 

radiation in the tank farm environment. Incorporates formal internal 

and NIOSH review comments. Training required: As determined by 

the Objective Manager. Initiated by James M. Mahathy.
Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 3 of 68

TABLE OF CONTENTS

SECTION TITLE PAGE

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

1.0 Introduction .............................................................................................................................. 6

2.0 Fission Product Source ............................................................................................................ 6

2.1 Photons ........................................................................................................................ 6

2.2 Bremsstrahlung Photons .............................................................................................. 9

2.3 Combined Gamma and X-ray Photon Spectrum........................................................... 9

2.4 Mathematical Model of the Work Environment.............................................................. 9

2.5 Results ....................................................................................................................... 12

2.6 Glovebag Data ........................................................................................................... 15

2.7 Mathematical Model of the Dosimeter......................................................................... 17

2.8 Dosimeter Response .................................................................................................. 18

3.0 Summary ............................................................................................................................... 20

4.0 Organ Dose Conversion Factors............................................................................................ 21

5.0 Conclusions ........................................................................................................................... 21

References ........................................................................................................................................ 22

ATTACHMENT A, ENERGY SPECTRA CALCULATED FROM TANK MODELS FOR FILM BADGE

 MODELS.............................................................................................................. 24

ATTACHMENT B, DOSE MODELS................................................................................................... 28

ATTACHMENT C, FILM BADGE MODEL.......................................................................................... 63
Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 4 of 68

LIST OF TABLES

TABLE TITLE PAGE

2-1 ORIGEN-S irradiation parameters for the five SRS cases........................................................ 6

2-2 Fission product mixture used to define the radiation source term............................................. 7

2-3 Intensity of gamma and X-ray components of the photon spectrum ......................................... 8

2-4 Tank contents—elements and relative abundances ............................................................... 10

2-5 Dose ratios for the 30- to 250-keV energy range.................................................................... 14

2-6 Dose ratios for the greater than 250-keV energy range.......................................................... 14

2-7 The fractions of total dose by energy range for each scenario ............................................... 15

2-8 Survey readings taken above ports on SRS tanks ................................................................. 16

2-9 Silver-shielded film ratios ....................................................................................................... 20

A-1 Standing worker, no port, 140 and 90 cm............................................................................... 24

A-2 Kneeling worker, no port, 90 and 40 cm................................................................................. 25

A-3 Standing worker, near port, 140 and 90 cm............................................................................ 26

A-4 Kneeling worker, near port, 90 and 40 cm.............................................................................. 27

LIST OF FIGURES

FIGURE TITLE PAGE

2-1 Semi-log plot of the combined photon spectrum....................................................................... 8

2-2 Cross-sectional diagram of a Type III tank ............................................................................... 9

2-3 SRS workers measuring the level of waste in a tank.............................................................. 11

2-4 Model of standing worker ....................................................................................................... 11

2-5 Model of kneeling worker ....................................................................................................... 11

2-6 Standing worker, no port ........................................................................................................ 12

2-7 Kneeling worker, no port ........................................................................................................ 12

2-8 Standing worker, near a port.................................................................................................. 13

2-9 Kneeling worker, near a port .................................................................................................. 13

2-10 Diagram of glovebag and reading locations ........................................................................... 16

2-11 Ratios from Survey Forms and MCNP calculations................................................................ 17

2-12 Exploded view of SRS film badge model................................................................................ 18

2-13 Comparison of the actual curve of two-element film dosimeter OW response to an 

MCNP simulation ...................................................................................................................19
Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 5 of 68

ACRONYMS AND ABBREVIATIONS

AP anterior-posterior

cm centimeter

d day

DOE U.S. Department of Energy

g gram

ICRP International Commission on Radiological Protection

keV kiloelectron-volt, 1,000 electron-volts

MCNP Monte Carlo N-Particle (computer program)

MeV megaelectron-volt, 1 million electron-volts

mm millimeter

MTU metric tons of uranium

MW megawatt

MWd megawatt-day

NIOSH National Institute for Occupational Safety and Health

NTA nuclear track emulsion, Type A

ORAU Oak Ridge Associated Universities

OW open window

ROT rotational

SRDB Ref ID Site Research Database Reference Identification (number)

SRS Savannah River Site
Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 6 of 68

1.0 INTRODUCTION

At the Savannah River Site (SRS), liquid wastes containing fission products were stored in large 

underground tanks. When a worker was in the Tank Farm area and the dosimeter was routinely worn 

at the worker’s collar, it is reasonable to expect based on distance from the below source that it will 

record a lower dose in comparison with a dosimeter worn at the worker’s beltline. In addition, when 

near an open sampling port, the badge can overestimate the dose at the abdomen due to the 

streaming effect of a beam created by the opening. The differences in response as a function of 

position on the worker’s torso were evaluated using the MCNP5 code, version 1.60 and MCNPX 

code, version 2.6.0. MCNP is a Fortran90 Monte Carlo radiation transport computer code developed 

and maintained by Los Alamos National Laboratory.

2.0 FISSION PRODUCT SOURCE

The fission product source represents external penetrating photons from gamma rays and 

bremsstrahlung X-rays associated with high-energy beta emitters.

The fission product mixture that was used to develop the source term was extracted from the 

ORIGEN-S program for the SRS reactors. Two sets of irradiation parameters were selected for the 

Mark 16 and Mark VI-B cases. The selected irradiation parameters for the five SRS cases are given 

in Table 2-1. For each reactor, the inventory was normalized to the 137Cs activity and then averaged 

across all reactors to provide an estimate of the expected source that would have been encountered. 

All radionuclides from ORIGEN-S that have activity for the SRS reactor cases were used. Table 2-2

shows SRS reactor radionuclides and their relative activities normalized to the activity of 137Cs. Table

2-2 is sorted by highest average relative activity to 137Cs. Note that about 90% of the total activity 

comes from the first 10 radionuclides through 137Cs. The beta emitter 90Sr and its equilibrated 

progeny 90Y are also included in the fission product source term due to their relatively high abundance 

and ability to produce bremsstrahlung X-rays.

Table 2-1. ORIGEN-S irradiation parameters for the five SRS cases.

Case Parameters Basis

Mark V-B Specific power = 25.5 MW/MTU

Irradiation time = 43.14 d

Burnup = 1,100 MWd/MTU

Production of weapons-grade plutonium (nominal 6% 240Pu content) at nominal power.

Mark 16 1 Specific power = 896.08 MW/MTU

Irradiation time = 240 d

Burnup = 215,059 MWd/MTU

Typical Mark 16/31 core irradiated for four subcycles of 

60 days each, representing the high-burnup case.

Mark 16 2 Specific power = 896.08 MW/MTU

Irradiation time = 160 d

Burnup = 143,373 MWd/MTU

Typical Mark 16/31 core irradiated for four subcycles of 

40 days each, representing the low-burnup case. 

Mark VI-B 1 Specific power = 1392.9 MW/MTU

Irradiation time = 182 d

Burnup = 253,508 MWd/MTU

Maximum assembly power for a typical cycle duration.

Mark VI-B 2 Specific power = 1160.32 MW/MTU

Irradiation time = 182 d

Burnup = 211,178 MWd/MTU

Nominal assembly power for a typical cycle duration.

2.1 PHOTONS

The gamma and X-ray photon contributions for all radionuclides in Table 2-2 were used to create a 

30-segment histogram spectrum, which is shown in Table 2-3 and Figure 2-1. Radiation data tables 

were taken from the freeware program RADDECAY.EXE (Radiation Decay, Version 3.6). 

RADDECAY uses data from DOE/TIC-11026, Radioactive Decay Data Tables, A Handbook of Decay 

Data for Application to Radiation Dosimetry and Radiological Assessments (Kocher 1981). 
Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 7 of 68

Table 2-2. Fission product mixture used to define the radiation source term. Activity units are relative 

to 137Cs, which is normalized to equal 1. Table includes noble gases and volatile species regardless 

of whether they would actually be present in the tank farm wastes.

Radionuclide

Average 

activity Radionuclide

Average 

activity Radionuclide

Average 

activity Radionuclide

Average 

activity

Pr-144 1.18E+01 C-14 9.91E-06 Ag-108m 2.20E-11 Te-123 2.55E-19

Ce-144 1.18E+01 Ni-59 7.35E-06 Dy-159 1.91E-11 Xe-133 2.00E-19

Nb-95 3.74E+00 Ag-110 6.47E-06 Xe-127 1.39E-11 Tc-95m 1.57E-19

Pm-147 2.58E+00 Cd-113m 4.58E-06 Te-121m 1.07E-11 Ag-105 1.14E-19

Zr-95 1.74E+00 Gd-153 3.99E-06 Te-121 1.06E-11 Cs-131 8.55E-20

Ru-106 1.18E+00 Cr-51 3.98E-06 Sn-117m 7.36E-12 S-35 2.12E-20

Rh-106 1.18E+00 Sn-126 2.98E-06 La-137 6.44E-12 Tc-95 6.20E-21

Y-91 1.11E+00 Sb-126m 2.98E-06 Tc-98 6.42E-12 Sc-46 2.18E-21

Cs-137 1.00E+00 Rh-102 2.32E-06 Tb-157 5.77E-12 Cs-132 1.58E-21

Y-90 9.67E-01 Cs-135 1.89E-06 Se-75 4.29E-12 Ga-68 4.82E-22

Sr-90 9.66E-01 Pr-143 1.10E-06 As-73 2.91E-12 Ge-68 4.82E-22

Ba-137m 9.44E-01 Nb-93m 1.04E-06 Ag-108 1.91E-12 Ba-131 1.26E-22

Sr-89 4.77E-01 Pm-146 9.47E-07 P-32 1.53E-12 V-50 4.74E-23

Cs-134 4.51E-01 Se-79 7.48E-07 I-131 1.51E-12 Eu-147 1.87E-23

Pr-144m 1.65E-01 Sb-126 4.18E-07 Si-32 1.51E-12 Ag-106m 8.34E-25

Kr-85 1.23E-01 La-140 3.75E-07 Sn-125 1.21E-12 Rh-99 3.26E-25

Ru-103 9.05E-02 Te-123m 3.58E-07 Be-7 8.53E-13 Tm-167 6.28E-27

Rh-103m 9.03E-02 Ba-140 3.26E-07 Pd-103 3.90E-13 Sb-120m 4.83E-27

Sb-125 4.88E-02 Pd-107 1.89E-07 Kr-81 1.97E-13 K-42 5.62E-28

Ce-141 4.38E-02 I-129 1.80E-07 Tm-168 1.09E-13 Ar-42 5.62E-28

Te-127m 3.18E-02 Tm-171 1.66E-07 Zr-88 1.08E-13 Cl-36 4.98E-28

Te-127 3.12E-02 Y-88 1.30E-07 Pm-144 9.20E-14 Sb-127 1.28E-28

Nb-95m 2.05E-02 Eu-156 1.10E-07 Eu-149 5.84E-14 Tb-156 1.47E-30

Eu-154 1.85E-02 Ag-109m 8.13E-08 I-125 5.32E-14 Gd-149 1.57E-31

Eu-155 1.49E-02 Cd-109 8.13E-08 V-49 3.15E-14 Lu-171 6.35E-32

Te-125m 1.18E-02 Ce-139 2.78E-08 Ho-163 2.94E-14 Tb-155 2.24E-32

Fe-55 8.38E-03 Rb-86 2.66E-08 Nb-91 1.50E-14 I-132 1.97E-32

Sm-151 4.72E-03 Tm-170 1.65E-08 Sm-146 1.42E-14 Te-132 1.91E-32

H-3 4.19E-03 Nd-147 4.75E-09 Nd-144 9.91E-15 Lu-172 6.71E-34

Zn-65 3.56E-03 In-115m 3.53E-09 Na-22 9.02E-15 Ar-39 1.27E-34

Sn-123 2.06E-03 Pm-145 2.98E-09 As-74 6.40E-15 Ar-37 5.20E-35

Te-129m 1.05E-03 Cs-136 2.20E-09 I-126 3.74E-15 Rh-101m 4.12E-36

Pm-148m 9.82E-04 Be-10 1.84E-09 Mo-93 3.71E-15 Ho-166 1.54E-36

Ni-63 9.17E-04 Rb-83 1.32E-09 Tc-97 2.33E-15 Dy-166 1.04E-36

Te-129 6.75E-04 Xe-131m 1.31E-09 Ag-111 1.80E-15 Mo-99 1.41E-38

Ag-110m 4.76E-04 Ba-133 1.27E-09 La-138 1.47E-15 Tc-99m 1.37E-38

Mn-54 4.66E-04 Rb-84 1.16E-09 P-33 1.15E-15 Ca-41 8.69E-39

Co-58 3.52E-04 Rh-102m 6.04E-10 In-113m 2.59E-16 Sc-47 5.37E-39

Sn-119m 1.51E-04 In-114m 2.77E-10 Sn-113 2.58E-16 K-40 2.34E-39

Tc-99 1.42E-04 In-114 2.65E-10 In-115 1.19E-16 Ca-47 1.41E-39

Sn-121m 6.95E-05 Rb-87 2.61E-10 Sm-148 1.16E-16 I-124 6.60E-40

Sn-121 5.39E-05 Ba-136m 2.47E-10 Er-169 3.76E-17 Zr-89 2.56E-40

Pm-148 5.20E-05 Nb-94 1.58E-10 Xe-129m 3.38E-17 Tc-96 2.27E-40

Sb-124 4.44E-05 Sr-85 1.42E-10 Nb-92 2.87E-17 Te-118 5.53E-41

Y-89m 4.43E-05 Tc-97m 1.13E-10 Ge-71 2.31E-17 Sb-118 3.86E-41

Cd-115m 3.20E-05 Tb-158 8.09E-11 Yb-169 4.63E-18 Y-87 6.69E-42

Co-60 2.91E-05 Sm-145 6.46E-11 Pm-143 3.25E-18 As-72 2.12E-42

Tb-160 2.33E-05 Gd-151 4.74E-11 Ca-45 2.81E-18 Se-72 1.81E-42

Zr-93 2.03E-05 Rh-101 4.45E-11 Tb-161 1.56E-18 Sb-122 1.01E-43

Eu-152 2.03E-05 Ho-166m 3.26E-11 Gd-152 1.40E-18

Fe-59 1.15E-05 Sm-147 2.31E-11 Cd-113 4.25E-19
Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 8 of 68

Figure 2-1. Semi-log plot of the combined photon spectrum.

Table 2-3. Intensity of gamma and X-ray 

components of the photon spectrum.

Top of energy 

bin, MeV

Gamma ray 

intensity

Bremsstrahlung 

x-ray intensity

0.10 1.96E+09 1.55E+04

0.20 1.47E+09 9.51E+03

0.25 7.56E+06 2.16E+03

0.30 5.86E+05 1.46E+03

0.40 2.36E+06 1.87E+03

0.60 5.19E+08 2.00E+03

0.70 1.81E+09 5.14E+02

0.80 6.57E+09 3.25E+02

0.90 5.39E+07 2.30E+02

1.00 2.79E+06 1.57E+02

1.10 3.47E+07 1.29E+02

1.20 1.66E+07 7.07E+01

1.25 3.95E+06 2.32E+01

1.30 7.41E+06 3.21E+01

1.40 2.33E+07 6.40E+01

1.60 4.28E+07 8.40E+01

1.70 2.66E+04 1.69E+01

1.80 3.82E-10 5.47E+00

1.90 1.48E+02 5.10E+00

2.00 8.04E+00 1.75E+01

2.10 2.87E+03 3.10E+00

2.20 1.03E+08 2.89E+00

2.25 1.23E+00 2.91E-01

2.30 1.38E+00 6.13E-01

2.40 3.59E+00 0.00E+00

2.60 1.50E+01 1.03E+00

The nuclides in Table 2-2 were compared to the RADDECAY tables, and a list of all photons and the 

associated probabilities was created. The probability was multiplied by the relative activity present for 

each nuclide to provide a probability for each photon energy. A histogram of 30 elements was 

created, representing 30 energy bins divided evenly between 0 and 3 MeV. For each bin, the total 

1.E+00

1.E+01

1.E+02

1.E+03

1.E+04

1.E+05

1.E+06

1.E+07

1.E+08

1.E+09

1.E+10

0.10 0.25 0.40 0.70 0.90 1.10 1.25 1.40 1.70 1.90 2.10 2.25 2.40

Relative Intensity

MeV

Source Spectrum
Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 9 of 68

probability of all photons within that bin was summed together to provide the relative probability for 

that energy range, essentially averaging the energy within the range. 

Note that MCNP discards photons with energies below 0.015 MeV by default. Photons with energies 

at or below this level are stopped by the plastic cover over the film and do not contribute to the energy 

deposited in the film.

2.2 BREMSSTRAHLUNG PHOTONS

Bremsstrahlung X-ray photons are produced when the beta radiations from the nuclides present strike 

atoms in the wastes. The total activity from the beta-emitting nuclides in Table 2-2 was summed 

together to provide a beta source. An MCNP calculation was run with this source diffused evenly 

within the tank volume as described in Section 2.4 to provide the expected X-ray spectrum that would 

have resulted from the interaction of the beta particles in the chemistry of the sludge.

The bremsstrahlung X-ray spectrum, normalized by the fraction of total activity in the mixture, is 

included in the spectrum shown in Figure 2-1.

2.3 COMBINED GAMMA AND X-RAY PHOTON SPECTRUM

Figure 2-1 illustrates the combined gamma and bremsstrahlung X-ray components of the photon 

spectrum. The same data are listed in Table 2-3 above. Almost all of the spectral intensity of the 

photon source is due to the gamma ray component. The bremsstrahlung contribution is an important 

component for some of the lower-energy bins. The vertical scale indicates the relative flux for each 

energy bin.

2.4 MATHEMATICAL MODEL OF THE WORK ENVIRONMENT

The model describes workers on the “roof” above a below-grade Type III tank filled with a sludgeliquid mixture (Figure 2-2). The tank is 33 ft deep and 85 ft in diameter. Over the tank is a 4-ft layer 

of concrete (Bebbington 1990, p. 129). Penetrating the concrete are openings used for examination 

or for sampling the contents. The model included a 6-in.-radius port, filled with air extending through 

the concrete shielding to the surface to simulate one of these openings.

Figure 2-2. Cross-sectional diagram of a Type III tank.
Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 10 of 68

The elemental composition of the sludge-liquid mixture was based on actual chemical sampling and 

contained significant amounts of aluminum, calcium, and iron in addition to many other elements 

(Pasala 2011, pp. 52–53, 55). For the model, the sludge and the liquid phase were mixed at a 

70%:30% ratio, respectively, and were distributed evenly through the volume of the tank. In practice, 

the tanks were not full. Table 2-4 lists the relative abundance of the elements in the modeled tank. 

Other elements known to be present at much smaller concentrations were not included in the model.

Table 2-4. Tank contents — elements 

and relative abundances.

Relative abundance Element

0.363615 O

0.24777 Na

0.139552 H

0.132923 K

0.076349 N

0.015899 Al

0.009262 Fe

0.008161 C

0.001907 S

0.001869 Mn

0.00133 Ca

0.000331 F

0.000268 Cl

0.000181 P

9.98E-05 Cu

9.90E-05 Cr

8.03E-05 Zn

7.22E-05 Mg

5.94E-05 Ag

3.79E-05 Ce

2.89E-05 Se

2.73E-05 Ba

2.33E-05 La

1.06E-05 Si

8.98E-06 Hg

5.24E-06 Cs

5.13E-06 Co

4.90E-06 As

4.83E-06 Nd

4.58E-06 Pb

3.11E-06 Sr

2.80E-06 Ra

1.73E-06 Zr

6.15E-07 Ni

1.75E-07 Cd

Workers were present atop the tanks performing their duties while standing or, in some instances, 

squatting or kneeling. Figure 2-3 is a photograph of such activity and includes an example of both a 

standing and a kneeling worker.

The workers were each modeled as a set of stacked cylinders based on the BOMAB phantom. This 

phantom was filled with a mixture of hydrogen, carbon, and oxygen to simulate the shielding and 

backscatter effect of a worker in the ambient field. The relative exposure at the abdomen or waist 

level and at the chest level was modeled for both a standing worker and a kneeling worker. For the 

standing worker, these points were approximated as 140 cm (55 in.) and 90 cm (35 in.) above the 
Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 11 of 68

Figure 2-3. SRS workers measuring the level 

of waste in a tank.

ground surface. For the kneeling worker, the points were 90 cm (35 in.) and at 40 cm (16 in.) above 

the ground surface.

In Figures 2-4 and 2-5, the worker models are shown on top of the tank. Circles at the chest and 

abdomen indicate the measurement points. In both figures the worker is shown near a 6-in.-radius

opening that extends downward uninterrupted through the concrete shield to the sludge. 

Figure 2-4. Model of standing worker. Figure 2-5. Model of kneeling worker.

This opening simulates the ports that were used for sample removal and for tank volume 

measurements, as in the pictures above. The lateral distance between the vertical plane of the 

measurement points and the center of the port is 50 cm (20 in.).
Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 12 of 68

2.5 RESULTS

Four cases were examined: the standing worker near a port, the kneeling worker near a port, the 

standing worker without the port, and the kneeling worker without the port. In the latter two cases, the 

worker phantom was left in place and the opening was removed from the model. Results at the chest 

and abdomen locations for each of the four cases are graphed in Figures 2-6 through 2-9. These are 

the dose values plotted as a function of energy.

Figure 2-6. Standing worker, no port.

Figure 2-7. Kneeling worker, no port.

1.00E-20

1.00E-19

1.00E-18

1.00E-17

1.00E-16

1.00E-15

0.000 0.500 1.000 1.500 2.000 2.500

Dose, pSv

MeV

Standing, no port 

Chest

Abdomen

1.00E-20

1.00E-19

1.00E-18

1.00E-17

1.00E-16

1.00E-15

0.000 0.500 1.000 1.500 2.000 2.500

Dose, pSv

MeV

Kneeling, no port

Chest

Abdomen
Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 13 of 68

Figure 2-8. Standing worker, near a port.

Figure 2-9. Kneeling worker, near a port.

At each measurement point, the total dose, the dose between 30 and 250 keV (Table 2-5), and the 

dose above 250 keV (Table 2-6) were measured. These were calculated using International 

Commission on Radiological Protection (ICRP) Publication 74 dose conversion factors (ICRP 1996) 

for results as Hp(10,0°) in picosieverts per source photon. For each, the chest result was divided by 

the abdomen result to obtain the dose to the abdomen relative to the dose at the chest. The 

contribution of the dose from the energy range less than 30 keV was much less than the total. For 

each of the four cases, the fraction of the dose from this range was less than 0.3%.

1.00E-17

1.00E-16

1.00E-15

1.00E-14

1.00E-13

1.00E-12

0.000 0.500 1.000 1.500 2.000 2.500

Dose, pSv

MeV

Standing, Port

Chest

Abdomen

1.00E-17

1.00E-16

1.00E-15

1.00E-14

1.00E-13

1.00E-12

0.000 0.500 1.000 1.500 2.000 2.500

Dose, pSv

MeV

Kneeling, Port

Chest

Abdomen
Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 14 of 68

Table 2-5. Dose ratios for the 30- to 250-keV energy range.

Position Chest Abdomen Ratio

Standing, no port 1.16 × 10-15 1.67 × 10-15 1.44

Kneeling, no port 9.48 × 10-16 1.28 × 10-15 1.35

Standing, port 1.73 × 10-12 1.86 × 10-12 1.08

Kneeling, port 1.51 × 10-12 1.90 × 10-12 1.26

Table 2-6. Dose ratios for the greater than 250-keV energy 

range.

Position Chest Abdomen Ratio

Standing, no port 5.70 × 10-16 6.58 × 10-16 1.16

Kneeling, no port 5.90 × 10-16 6.94 × 10-16 1.18

Standing, port 1.05 × 10-12 4.54 × 10-13 0.43

Kneeling, port 4.53 × 10-13 2.77 × 10-13 0.61

For the cases where the worker was not near a port, all ratios indicate a higher exposure to the 

abdomen than to the chest where the film badge was worn. The highest ratio for the 30- to 250-keV 

range is 1.44. The highest ratio for the greater than 250 keV energy range is 1.18.

When a port was included in the model, the ratios are not as straightforward. For the lower energy 

range, the ratios indicate a higher exposure at the abdomen. However, doses from photons with 

energies greater than 250 keV are equal to or higher at the chest than at the abdomen. This is due to 

beaming effect of the open port. It was observed that the doses diminished with increasing height 

when measured directly over the port or when there was no port present. However, when measured 

at a short distance from a port, doses increased with increasing height in the greater than 250-keV

range. This is apparently due to the beam created by the port spreading out laterally with increasing 

elevation. The highest ratio for the 30- to 250-keV range is 1.26. For the greater than 250-keV range, 

it is 0.61.

The values in Tables 2-5 and 2-6 show roughly a factor of 1,000 increase to the measurement points 

when the port was present. This indicates that the majority of photons came through the port. There 

is not a direct path from any of the measurement points to the sludge. All dose comes from photons 

either passing through the shield or scattered from the walls of the port. Photons that interact with 

matter and then result in a photon on a different path, “scattered” photons, undergo Compton 

scattering. The reversed ratios for the cases near the port are explained by two known effects of 

Compton scattering. The equations that describe this process indicate that the probability of the 

resultant path decreases with increased angle. That is, more photons scatter along a shallow angle 

than a large angle. Photons that scattered along the sides of the port underwent a shallower angle to 

reach the chest than the abdomen so there were more photons received at the chest. The second 

effect can be seen in the graphs for the port cases. In Compton scattering, the resultant photon has 

less energy than the originating photon. The energy decreases with increasing angle. Therefore, 

photons that scattered toward the abdomen had, on average, less energy than those that scattered 

toward the chest.

The model is based on the best estimate of radioactivity in the tanks and actual chemical constituent 

measurements within a tank. The tank dimensions and concrete thicknesses are modeled accurately 

according to the published information. However, there are two conservative assumptions built into 

this model that are favorable to claimants: (1) the tanks were modeled as filled to the top with an 

even mixture of the sludge and liquid phase, and (2) the port was filled with air for its entire length and 

had no cap.

For the first item, any increase in distance between the worker and the source should bring any ratio 

closer to 1. The sludge, which contained the greatest amount of the radioactivity, would have settled 
Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 15 of 68

to some degree within the liquid phase, and the top of the liquid would have been further away from 

the worker.

For the second item, any shielding in or over the port would reduce the streaming effect.

To obtain ratios that may be used to split total dose to the fraction that is between 30 and 250 keV 

and the fraction that is greater than 250 keV, the above data in Tables 2-5 and 2-6 may be used. It is 

assumed that the total dose is a sum of the two regions. The fraction for each region for the chest 

results are shown in Table 2-7. The chest location is used as the badge is presumed to have been 

worn at the chest.

Table 2-7. The fractions of total dose by energy

range for each scenario. 

Position 30–250 keV >250 keV

Standing, no port 67% 33%

Kneeling, no port 62% 38%

Standing port 62% 38%

Kneeling port 77% 23%

As the greatest exposure to workers atop the tanks would be from work near an open port, the open 

port scenarios are averaged together to obtain a 70% fraction for the 30 to 250 keV range and 30% 

for the range greater than 250 keV.

These factors are independent of the above dose ratios and would be applied prior to their use. For 

example, a total dose of 100 millirem could be fractioned into 70 millirem for the 30 to 250 keV range 

and 30 millirem for the greater than 250 keV range. The 70 millirem would then be multiplied by an 

adjustment factor based on the limiting ratio in Table 2-5. The same process would apply to the 30 

millirem fraction based on the factor based on the limiting ratio in Table 2-6.

2.6 GLOVEBAG DATA

Survey forms from the SRS for work on top of tanks in the tank farm contain a few survey readings 

that were taken during actual operations. Although these are from recent years, these are included as 

a verification of the modeling process (WSRC 2006a, 2006b).

Surveys were done in conjunction with sampling of the tank contents. A glovebag was assembled 

over the open sampling hole and samples were withdrawn into this controlled area (Figure 2-10). 

Survey readings were taken over the open hole and over and around the glovebag after its assembly. 

These readings were recorded as millirem per hour. 
Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 16 of 68

Figure 2-10. Diagram of glovebag and reading locations.

The survey forms contained a diagram of the glovebag arrangement and survey locations. Direct 

reading measurements were indicated as “DR”. Note that in Figure 2-10, are the location of the open 

hole readings and for location 2. In the document location 2 readings were labeled as “top of 

glovebag” (WSRC 2006b).

Readings labeled “over open hole” were paired with readings labeled “top of glovebag” and ratios 

were calculated (WSRC 2006a, 2006b, 2006c). These readings are listed in Table 2-8. The ratios 

ranged from 10 to 70 for the whole-body results. Note that there is no indication in these documents 

that workers worked directly over these open holes; rather, they were positioned to one side.

Table 2-8. Survey readings taken above ports on SRS 

tanks.

Open Hole

mrem/hr

Top of glovebag

mrem/hr Ratio

15 1 15

15 1 15

10 1 10

350 5 70

.

Using the open port model, points were measured in the vertical centerline over the open port. The 

80 centimeter value was compared to the value directly over the hole to obtain a ratio of 10. The 215 

centimeter value provided a ratio of 90.
Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 17 of 68

In Figure 2-11, the ratios obtained from the survey forms and the ratios calculated from MCNP are 

shown with an approximation of their distances above the open port. These are based on an 

assumption that the top of the glovebag is 20 inches from the base. The documents do not state the 

height of the glovebag.

Figure 2-11. Ratios from Survey Forms and MCNP calculations.

Although the ratios from the actual measurements do not match exactly for the distances involved, 

they are well within the expected range and can therefore be considered a verification of the process.

2.7 MATHEMATICAL MODEL OF THE DOSIMETER

The SRS dosimeter is described by Richardson, Wing, and Daniels (2006) and Taulbee (2009). 

Taulbee’s MCNP dosimeter model was intended to register neutron dose and included nuclear track 

emulsion, type A (NTA) film. For this photon dose analysis, the NTA film in Taulbee’s MCNP 

dosimeter model was replaced with DuPont Type 555 film. DuPont films (predominantly Type 555 

and at times Type 55x) were used in the SRS dosimeter (Wells 2000). Figure 2-12 is an exploded 

view of the film badge model.
Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 18 of 68

Figure 2-12. Exploded view of SRS film badge model.

Five different portions of the film, each with different coverings or “filters” were tallied. Each portion of 

the film had the same filtration in front and back of the film:

• Upper portion of the film covered front and back by 1 mm of lead,

• Open window (OW) region covered by no filter (other than the thin Mylar light enclosure and 

surrounding plastic cover),

• Portion of the film covered front and back by 1 mm of silver,

• Portion covered front and back by 2 mm of aluminum, and

• Portion filtered covered front and back by 1 mm of nylon plastic.

In this analysis, only the energy deposition in the OW and silver filter portions of the film are important. 

The OW film was used to define the penetrating plus nonpenetrating dose, while the silver filter film 

defined the penetrating dose. The other portions of the film were not routinely analyzed (Richardson, 

Wing, and Daniels 2006).

A planar source was placed immediately in front of the badge and constrained to provide photons 

traveling toward the film perpendicular to the film plane. Behind the film was modeled a rectangular 

solid 15 cm thick, 30 cm tall, and 30 cm wide and filled with the same material as the worker phantom 

to provide realistic backscatter to the film badge as it was worn.

2.8 DOSIMETER RESPONSE

Fundamental to this problem was the selection of the correct MCNP tally type to represent the 

quantity of interest. The beginning assumption was that a tally designed to register the energy 

deposition in the cell representing the film was appropriate. This would be either an *F4 tally or the F6 

tally. The *F4 tally is reported in units of megaelectron-volts per square centimeter, and the F6 tally is 

in units of megaelectron-volts per gram. The F6 tally includes a microscopic total cross section in its 
Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 19 of 68

computation. A simple simulation was run to select a tally that reacts proportionally to optical density

observed in the exposed film.

It is well known that dosimeter film has a nonlinear response with photon energy as shown on the OW 

line on the left hand side of Figure 2-13, which was taken from Figure A-1 of ORAUT-OTIB-0010, A 

Standard Complex-Wide Methodology for Overestimating External Doses Measured with Film Badge 

Dosimeters (ORAUT 2006). The natural logarithm of the actual responses was used for Figure 2-13, 

and the magnitude of the MCNP values is smaller. The simulation measured the response of a 

sphere of unshielded Kodak Type AA dosimeter film around a point source of monoenergetic photons. 

The photon energy was varied, and both the *F4 and F6 tally results were obtained. The *F4 tally 

displayed a linear response. The F6 tally showed a nonlinear response with a peak at the same 

energy as the Kodak Type AA film. This confirmed that the F6 tally is appropriate to represent energy 

deposited in the film. For reporting purposes, the F6 tally result is multiplied by 1.603 × 10-10 to 

convert from megaelectron-volts per gram per source photon to gray per source photon.

Figure 2-13. Comparison of the actual curve of two-element film 

dosimeter OW response (ORAUT 2006) to an MCNP simulation. 

Similarity of shape confirms that the F6 tally is appropriate.

As the film thickness is 38 microns, the film badge models tallied the total energy deposited from 

electrons rather than from the incident photons. For an F6 photon tally, MCNP calculates the energy 

deposited within a volume as the energy left by the photon. Some of that energy may subsequently 

escape if the electron path length is significant relative to the volume size. However, the electron 

energy may be tallied instead to account for this effect. When using an F6 electron tally, MCNP 

measures only the energy deposited within the volume only for the portion of the electron path within 

the volume, providing a more accurate estimate of the energy imparted to the thin film.

To create the energies that would be seen by the film badge, a histogram energy spectrum was 

created for each of the measurement points (the chest and abdomen locations) of the standing and 

kneeling workers for both of the “port” and “no port” cases, a total of eight full spectra. Each spectrum 

was created from information captured by MCNP at each measurement point tallying the number of 

photons within select energy bands. These bands were divided into 10-keV bands between 0 and 

250 keV, 50-keV bands up to 500 keV, and 100-keV bands above 500 keV. The lower energies were 

more finely divided to create ranges appropriate for the film’s response curve. The spectrum was 

created as a histogram of these energy regions with the value of each the relative flux of photons 

within that range.

0.00E+00

5.00E-01

1.00E+00

1.50E+00

2.00E+00

2.50E+00

3.00E+00

3.50E+00

4.00E+00

4.50E+00

0 0.1 0.2 0.3 0.4 0.5 0.6

F6

Actual
Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 20 of 68

Data used to create these spectra are listed in Attachment A. The film badge model was run in 

MCNP using each of these spectra as a description of the source of photon radiation. The film badge 

model was run with each spectrum for each of the eight measurement locations. 

The energy deposited in each area within the film was calculated. Ratios of the chest and abdomen 

location results were calculated to assess the relative film response of a badge that would have been 

in the abdomen area to a badge that would have been at the chest. Note that this does not include 

the relative intensities of the radiation fields at those locations, only the relative response of the film 

badge to the spectra estimated to have been present at those locations. The MCNP results that 

formed the basis of the ratios were calculated on a per-photon basis, normalizing each spectrum. 

Because the greatest majority of the dose was in the region greater than 30 keV, and the silvershielded area would have been used for the penetrating exposure results, the relative response of film 

to the chest and abdomen spectra was calculated. Table 2-9 lists the ratios that were obtained for the 

silver-shielded area of the film.

Table 2-9. Silver-shielded film ratios.

Position Ratio

Standing, no port 1.00

Kneeling, no port 1.02

Standing, port 1.05

Kneeling, port 1.03

These ratios indicate that the film response was most similar between the chest and abdomen 

locations when there was no port present. The relative response was greater at the chest location 

than would have been seen if the dosimeter was placed at the abdomen location for the cases when a 

port was present. This can be explained by the resultant energy of the scattered photons when a port 

was present, as explained in Section 2-5, above. Photons that were scattered toward the abdomen,

had on average, less energy than those scattered toward the chest.

3.0 SUMMARY

For routine work in radiological areas, radiation workers are normally instructed to wear their 

dosimeter at a location on the front of the torso between the collar and belt. The difference in 

dosimeter response to the penetrating photon spectrum in the SRS tank farms that is attributable to 

dosimeter placement was modeled using MCNP. The model produced the following results:

• The contribution to the total dose from the dose in the range from 0 to 30 keV is less than 

0.3%.

• The photon flux drops as the elevation increases for areas away from tank penetrations.

• The photon flux increases as the elevation increases for areas near tank penetrations.

• For dosimetry at a site in the abdomen when the badge was worn at the collar, the badge dose 

should be adjusted upward by a factor of 1.44. The relative response at the chest in 

comparison with the waist of the film badge component used for penetrating exposure is 0.43

to 1.18 for photon energies encountered over the tank.

• A total dose result may be fractioned into two doses; 70% of the dose may be assumed to 

have been in the 30 to 250 keV range and 30% in the greater than 250 keV range.
Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 21 of 68

• The modeled response of the silver-shielded film in the calculated spectra indicates a ratio of 

1.05 for workers near a port and 1.02 for workers not near a port.

• These factors are based only on the geometry of working over a tank at the SRS Tank Farm 

and are independent of all other modifying factors.

4.0 ORGAN DOSE CONVERSION FACTORS

Chen (1991) performed detailed analyses of the effective bean beam orientation from an underfoot 

infinite planar source and resulting radiation doses. From the analyses, Chen concluded that the 

rotational (ROT) beam geometry provided the most realistic organ dose conversion factors. Chen 

also reported the anterior-posterior (AP) geometry resulted in dose conversion factors that exceeded 

those using ROT by as much as a factor or 2. Eckerman and Ryman (1993) independently verified 

that dose equivalents based on the ROT geometry were in excellent comparison to dose equivalents 

reported by Chen.

To be favorable to claimants, the National Institute for Occupational Safety and Health (NIOSH) has 

stated that dose conversion factors using the AP geometry when the dosimeter was worn on the chest 

does not result in underestimation of dose with the exception of four organs; those are bone surface, 

bone red marrow, esophagus, and lung. In the case of these four organs, dose conversion factors for 

the ROT geometry should be used. AP and ROT dose conversion factors are provided in Appendix A 

of OCAS-IG-001, External Dose Reconstruction Implementation Guideline (NIOSH 2007). ROT dose 

conversion factors should also be multiplied by the appropriate energy range correction factors in 

Table 4.1a of NIOSH (2007).

5.0 CONCLUSIONS

It is reasonable to expect that a common exposure scenario in the SRS tank farm was one involving a 

worker standing over a tank in a normal posture and working near a tank opening. It is favorable to 

claimants to apply the adjustment factors to all workers who were associated with tank farm 

operations. Total dose results may be fractioned into a 70% component in the 30 to 250 keV range 

and 30% for the greater than 250 keV range. An adjustment factor of 1.5 is recommended for doses 

in the 30 to 250 keV range and a factor of 1.2 for doses in the greater than 250 keV range. These are 

rounded upward to account for the film badge response and to be claimant favorable. 
Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 22 of 68

REFERENCES

Bebbington, W. P., 1990, History of Du Pont at the Savannah River Plant, E. I. du Pont de Nemours 

and Company, Wilmington, Delaware. [SRDB Ref ID: 11249]

Chen, S. Y., 1991, “Calculation of Effective Dose-Equivalent Responses for External Exposure from 

Residual Photon Emitters in Soil,” Health Physics, volume 60, number 3, pp. 411–426.

Eckerman, K. F., and J. C. Ryman, 1993, External Exposure to Radionuclides in Air, Water, and Soil, 

Federal Guidance Report No. 12, EPA-402-R-93-081, U. S. Environmental Protection Agency, 

Office of Radiation and Indoor Air, Washington, D.C., September. [SRDB Ref ID: 11997]

ICRP (International Commission on Radiological Protection), 1996, Conversion Coefficients for Use in 

Radiological Protection Against External Radiation, Publication 74, Pergamon Press, Oxford, 

England.

Kocher, D. C., 1981, Radioactive Decay Data Tables, A Handbook of Decay Data for Application to 

Radiation Dosimetry and Radiological Assessments, DOE/TIC-11026, U.S. Department of 

Energy, Technical Information Center, Oak Ridge, Tennessee, April. [SRDB Ref ID: 32563]

NIOSH (National Institute for Occupational Health and Safety), 2007, External Dose Reconstruction 

Implementation Guideline, OCAS-IG-001, Rev. 03, Cincinnati, Ohio, November 21.

ORAUT (Oak Ridge Associated Universities Team), 2006, A Standard Complex-Wide Methodology 

for Overestimating External Doses Measured with Film Badge Dosimeters, ORAUT-OTIB0010, Rev. 01, Oak Ridge, Tennessee, June 5.

Pasala, N. R., 2011, Information on the Radiological and Chemical Characterization of the Savannah 

River Site Tank Waste, As of July 5, 2011, SRR-LWE-2011-00201, Rev. 0, Savannah River 

Remediation, Savannah River Site, Aiken, South Carolina, September 26. [SRDB Ref ID: 

111851]

Richardson, D. B., S. Wing, and R. D. Daniels, 2006, “Evaluation of External Radiation Dosimetry 

Records at the Savannah River Site, 1951–1989,” Journal of Exposure Science and 

Environmental Epidemiology, volume 17, pp. 13–24. [SRDB Ref ID: 46009]

Taulbee, T. D., 2009, Measurement and Model Prediction of Proton-Recoil Track Length Distributions 

in NTA Film Dosimeters for Neutron Energy Spectroscopy and Retrospective Dose 

Assessment, University of Cincinnati, Cincinnati, Ohio, March. [SRDB Ref ID: 118570]

Wells, D. W., 2000, “Advances in External Dosimetry at the Savannah River Site,” p. 247, 

Proceedings of the Symposium, May 17, 2000, 50 Years of Excellence in Science and 

Engineering at SRS, WSRC-MS-2000-00061, Westinghouse Savannah River Company, 

Aiken, South Carolina. [SRDB Ref ID: 46147]

WSRC (Westinghouse Savannah River Company), 2006a, Tank 32 H-Riser Dip Samples, Survey 

TKFM-M-20060410-14, Savannah River Site, Aiken, South Carolina, April 11. [SRDB Ref ID: 

108763]

WSRC (Westinghouse Savannah River Company), 2006b, Dip Samples @ Tank 47, Survey TKFMM-20060224-4, Savannah River Site, Aiken, South Carolina, February 25. [SRDB Ref ID: 

108720]
Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 23 of 68

WSRC (Westinghouse Savannah River Company), 2006c, Tank 43 G-Riser Dip Sampling, Survey 

TKFM-M-20060403-9, Savannah River Site, Aiken, South Carolina, April 3. [SRDB Ref ID: 

108762]
Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 24 of 68

Table A-1. Standing worker, no port, 140 and 90 cm.

Standing, Port, 140 cm Standing, Port, 90 cm

Energy Result

Relative 

error Energy Result

Relative 

error

0.010 1.61E-20 0.38 0.010 4.29E-20 0.49

0.020 3.70E-19 0.35 0.020 3.62E-19 0.25

0.030 7.18E-18 0.04 0.030 1.27E-17 0.04

0.040 3.46E-17 0.03 0.040 5.92E-17 0.03

0.050 5.32E-17 0.02 0.050 8.88E-17 0.03

0.060 6.11E-17 0.02 0.060 9.42E-17 0.02

0.070 6.03E-17 0.02 0.070 9.10E-17 0.03

0.080 5.59E-17 0.02 0.080 8.09E-17 0.02

0.090 5.11E-17 0.02 0.090 7.26E-17 0.03

0.100 4.64E-17 0.02 0.100 6.41E-17 0.03

0.110 4.09E-17 0.02 0.110 5.57E-17 0.03

0.120 3.61E-17 0.02 0.120 4.81E-17 0.03

0.130 3.21E-17 0.02 0.130 4.23E-17 0.03

0.140 2.73E-17 0.02 0.140 3.76E-17 0.03

0.150 2.44E-17 0.02 0.150 3.27E-17 0.03

0.160 2.15E-17 0.02 0.160 2.97E-17 0.03

0.170 1.95E-17 0.02 0.170 2.62E-17 0.03

0.180 1.78E-17 0.02 0.180 2.44E-17 0.03

0.190 1.66E-17 0.03 0.190 2.22E-17 0.03

0.200 1.53E-17 0.02 0.200 2.04E-17 0.03

0.210 1.42E-17 0.02 0.210 1.91E-17 0.03

0.220 1.35E-17 0.02 0.220 1.71E-17 0.03

0.230 1.30E-17 0.03 0.230 1.64E-17 0.03

0.240 1.17E-17 0.02 0.240 1.51E-17 0.03

0.250 1.08E-17 0.02 0.250 1.36E-17 0.03

0.300 4.56E-17 0.02 0.300 5.86E-17 0.03

0.350 3.70E-17 0.02 0.350 4.51E-17 0.03

0.400 3.10E-17 0.02 0.400 3.77E-17 0.03

0.450 2.76E-17 0.02 0.450 3.21E-17 0.03

0.500 2.40E-17 0.03 0.500 2.72E-17 0.03

0.600 4.07E-17 0.02 0.600 4.66E-17 0.03

0.700 3.35E-17 0.03 0.700 3.70E-17 0.04

0.800 2.84E-17 0.03 0.800 3.11E-17 0.04

0.900 2.41E-17 0.03 0.900 2.59E-17 0.05

1.000 2.05E-17 0.03 1.000 2.34E-17 0.05

1.100 1.85E-17 0.04 1.100 1.98E-17 0.05

1.200 1.64E-17 0.04 1.200 1.83E-17 0.06

1.300 1.47E-17 0.05 1.300 1.61E-17 0.07

1.400 1.38E-17 0.06 1.400 1.51E-17 0.08

1.500 1.22E-17 0.07 1.500 1.48E-17 0.10

1.600 1.32E-17 0.10 1.600 1.53E-17 0.14

1.700 1.17E-17 0.11 1.700 1.40E-17 0.13

1.800 1.01E-17 0.10 1.800 1.14E-17 0.12

1.900 9.31E-18 0.15 1.900 1.14E-17 0.14

2.000 9.04E-18 0.13 2.000 9.66E-18 0.17

2.100 8.47E-18 0.19 2.100 7.74E-18 0.17

2.200 1.62E-17 0.04 2.200 1.87E-17 0.06

ATTACHMENT A

ENERGY SPECTRA CALCULATED FROM TANK MODELS FOR FILM BADGE MODELS

Page 1 of 4
Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 25 of 68

Table A-2. Kneeling worker, no port, 90 and 40 cm.

Kneeling, No port, 90 cm Kneeling, No port, 40 cm

Energy Result

Relative 

error Energy Result

Relative 

error

0.010 7.09E-20 0.43 0.010 2.07E-20 0.43

0.020 9.56E-19 0.51 0.020 9.37E-19 0.45

0.030 4.82E-18 0.09 0.030 7.37E-18 0.08

0.040 2.23E-17 0.06 0.040 3.42E-17 0.05

0.050 3.76E-17 0.04 0.050 5.52E-17 0.05

0.060 4.46E-17 0.03 0.060 6.55E-17 0.05

0.070 4.70E-17 0.03 0.070 6.54E-17 0.05

0.080 4.57E-17 0.04 0.080 6.03E-17 0.05

0.090 4.17E-17 0.03 0.090 5.54E-17 0.05

0.100 3.73E-17 0.03 0.100 5.01E-17 0.05

0.110 3.41E-17 0.03 0.110 4.34E-17 0.05

0.120 2.97E-17 0.03 0.120 4.02E-17 0.05

0.130 2.68E-17 0.03 0.130 3.53E-17 0.05

0.140 2.41E-17 0.03 0.140 3.16E-17 0.05

0.150 2.15E-17 0.03 0.150 2.79E-17 0.05

0.160 1.98E-17 0.03 0.160 2.41E-17 0.05

0.170 1.79E-17 0.03 0.170 2.24E-17 0.05

0.180 1.61E-17 0.04 0.180 2.11E-17 0.06

0.190 1.52E-17 0.03 0.190 1.96E-17 0.05

0.200 1.44E-17 0.04 0.200 1.79E-17 0.06

0.210 1.30E-17 0.03 0.210 1.70E-17 0.06

0.220 1.21E-17 0.04 0.220 1.58E-17 0.06

0.230 1.15E-17 0.04 0.230 1.53E-17 0.06

0.240 1.08E-17 0.04 0.240 1.40E-17 0.06

0.250 1.07E-17 0.05 0.250 1.27E-17 0.06

0.300 4.38E-17 0.03 0.300 5.28E-17 0.06

0.350 3.48E-17 0.03 0.350 4.32E-17 0.06

0.400 3.01E-17 0.03 0.400 3.55E-17 0.06

0.450 2.65E-17 0.03 0.450 3.10E-17 0.06

0.500 2.26E-17 0.03 0.500 2.78E-17 0.06

0.600 3.95E-17 0.03 0.600 4.76E-17 0.06

0.700 3.26E-17 0.04 0.700 3.93E-17 0.06

0.800 2.85E-17 0.04 0.800 3.26E-17 0.07

0.900 2.42E-17 0.04 0.900 2.90E-17 0.07

1.000 2.13E-17 0.05 1.000 2.60E-17 0.08

1.100 1.98E-17 0.06 1.100 2.41E-17 0.09

1.200 1.79E-17 0.07 1.200 2.17E-17 0.10

1.300 1.57E-17 0.08 1.300 1.97E-17 0.11

1.400 1.47E-17 0.09 1.400 1.89E-17 0.12

1.500 1.49E-17 0.10 1.500 1.84E-17 0.15

1.600 1.31E-17 0.12 1.600 1.60E-17 0.14

1.700 1.23E-17 0.12 1.700 1.43E-17 0.15

1.800 1.07E-17 0.14 1.800 1.43E-17 0.17

1.900 1.22E-17 0.20 1.900 1.11E-17 0.17

2.000 1.29E-17 0.22 2.000 1.06E-17 0.20

2.100 1.63E-17 0.25 2.100 1.29E-17 0.26

2.200 2.10E-17 0.10 2.200 2.36E-17 0.09

ATTACHMENT A

ENERGY SPECTRA CALCULATED FROM TANK MODELS FOR FILM BADGE MODELS

Page 2 of 4
Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 26 of 68

Table A-3. Standing worker, near port, 140 and 90 cm.

Standing, Port, 140 cm Standing, Port, 90 cm

Energy Result

Relative 

error Energy Result

Relative 

error

0.010 2.08E-17 0.18 0.010 2.41E-17 0.32

0.020 1.62E-16 0.12 0.020 1.83E-16 0.14

0.030 4.89E-15 0.04 0.030 1.07E-14 0.03

0.040 2.57E-14 0.04 0.040 5.38E-14 0.03

0.050 4.72E-14 0.04 0.050 8.88E-14 0.03

0.060 6.81E-14 0.04 0.060 1.04E-13 0.03

0.070 7.70E-14 0.03 0.070 1.06E-13 0.03

0.080 8.22E-14 0.05 0.080 9.87E-14 0.03

0.090 8.09E-14 0.05 0.090 8.56E-14 0.03

0.100 8.19E-14 0.07 0.100 7.87E-14 0.05

0.110 6.39E-14 0.04 0.110 6.40E-14 0.03

0.120 6.06E-14 0.04 0.120 5.59E-14 0.03

0.130 5.80E-14 0.11 0.130 4.86E-14 0.04

0.140 4.28E-14 0.05 0.140 3.98E-14 0.04

0.150 4.20E-14 0.06 0.150 3.59E-14 0.04

0.160 3.73E-14 0.06 0.160 3.23E-14 0.04

0.170 3.41E-14 0.05 0.170 2.97E-14 0.04

0.180 3.19E-14 0.05 0.180 2.59E-14 0.04

0.190 3.07E-14 0.07 0.190 2.37E-14 0.06

0.200 2.52E-14 0.05 0.200 1.97E-14 0.04

0.210 2.53E-14 0.08 0.210 1.85E-14 0.05

0.220 2.36E-14 0.06 0.220 1.73E-14 0.06

0.230 2.16E-14 0.06 0.230 1.70E-14 0.13

0.240 2.91E-14 0.13 0.240 1.56E-14 0.08

0.250 2.25E-14 0.08 0.250 1.53E-14 0.11

0.300 1.02E-13 0.07 0.300 6.66E-14 0.11

0.350 1.01E-13 0.17 0.350 5.07E-14 0.06

0.400 7.76E-14 0.05 0.400 4.94E-14 0.08

0.450 7.69E-14 0.06 0.450 3.62E-14 0.06

0.500 6.94E-14 0.05 0.500 3.45E-14 0.05

0.600 1.29E-13 0.04 0.600 6.12E-14 0.04

0.700 1.16E-13 0.07 0.700 2.52E-14 0.05

0.800 1.25E-13 0.03 0.800 1.49E-14 0.14

0.900 6.37E-15 0.21 0.900 2.08E-15 0.21

1.000 3.60E-15 0.23 1.000 3.54E-15 0.65

1.100 3.09E-15 0.19 1.100 1.99E-15 0.18

1.200 6.01E-15 0.38 1.200 1.52E-15 0.24

1.300 2.50E-15 0.31 1.300 9.80E-16 0.17

1.400 3.56E-15 0.18 1.400 9.44E-16 0.20

1.500 1.89E-15 0.11 1.500 7.80E-16 0.15

1.600 1.83E-15 0.10 1.600 5.92E-16 0.21

1.700 5.33E-16 0.25 1.700 2.58E-16 0.38

1.800 2.80E-16 0.23 1.800 2.38E-16 0.31

1.900 2.35E-16 0.35 1.900 1.39E-16 0.26

2.000 5.06E-16 0.45 2.000 1.05E-16 0.20

2.100 3.01E-16 0.46 2.100 1.81E-16 0.26

2.200 8.16E-15 0.04 2.200 2.29E-15 0.03

ATTACHMENT A

ENERGY SPECTRA CALCULATED FROM TANK MODELS FOR FILM BADGE MODELS

Page 3 of 4
Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 27 of 68

Table A-4. Kneeling worker, near port, 90 and 40 cm.

Kneeling, Port, 90 cm Kneeling, Port, 40 cm

Energy Result Relative 

error

Energy Result Relative 

error

0.010 2.17E-17 0.24 0.010 1.58E-17 0.19

0.020 1.40E-16 0.11 0.020 2.23E-16 0.37

0.030 6.74E-15 0.03 0.030 1.25E-14 0.04

0.040 3.51E-14 0.04 0.040 6.31E-14 0.04

0.050 6.19E-14 0.04 0.050 1.04E-13 0.04

0.060 7.81E-14 0.04 0.060 1.20E-13 0.04

0.070 8.21E-14 0.04 0.070 1.16E-13 0.04

0.080 7.87E-14 0.03 0.080 1.04E-13 0.04

0.090 7.19E-14 0.04 0.090 8.78E-14 0.04

0.100 6.19E-14 0.03 0.100 7.54E-14 0.04

0.110 5.62E-14 0.04 0.110 6.33E-14 0.04

0.120 4.90E-14 0.04 0.120 5.48E-14 0.04

0.130 4.15E-14 0.04 0.130 4.53E-14 0.04

0.140 3.54E-14 0.05 0.140 4.26E-14 0.10

0.150 3.09E-14 0.07 0.150 3.45E-14 0.04

0.160 2.66E-14 0.03 0.160 3.16E-14 0.06

0.170 2.70E-14 0.08 0.170 2.55E-14 0.04

0.180 2.19E-14 0.04 0.180 2.23E-14 0.04

0.190 1.90E-14 0.04 0.190 1.91E-14 0.06

0.200 1.82E-14 0.06 0.200 1.61E-14 0.05

0.210 1.80E-14 0.08 0.210 1.35E-14 0.05

0.220 1.65E-14 0.07 0.220 1.26E-14 0.07

0.230 1.51E-14 0.06 0.230 1.09E-14 0.06

0.240 1.37E-14 0.06 0.240 1.14E-14 0.09

0.250 1.24E-14 0.06 0.250 1.20E-14 0.12

0.300 6.07E-14 0.05 0.300 4.67E-14 0.08

0.350 5.38E-14 0.10 0.350 3.84E-14 0.10

0.400 4.47E-14 0.06 0.400 3.50E-14 0.08

0.450 3.95E-14 0.09 0.450 3.27E-14 0.07

0.500 3.71E-14 0.09 0.500 2.10E-14 0.07

0.600 6.25E-14 0.04 0.600 2.33E-14 0.11

0.700 2.56E-14 0.05 0.700 9.86E-15 0.21

0.800 1.39E-14 0.10 0.800 2.07E-15 0.10

0.900 2.22E-15 0.22 0.900 8.72E-16 0.16

1.000 3.59E-15 0.64 1.000 7.82E-16 0.19

1.100 2.19E-15 0.21 1.100 6.86E-16 0.37

1.200 1.60E-15 0.29 1.200 4.95E-16 0.35

1.300 1.14E-15 0.17 1.300 1.96E-16 0.12

1.400 1.03E-15 0.22 1.400 2.19E-16 0.26

1.500 7.08E-16 0.14 1.500 1.48E-16 0.16

1.600 4.88E-16 0.15 1.600 1.22E-16 0.11

1.700 1.83E-16 0.29 1.700 8.87E-17 0.14

1.800 2.49E-16 0.28 1.800 1.15E-16 0.26

1.900 1.31E-16 0.28 1.900 1.12E-16 0.30

2.000 1.06E-16 0.20 2.000 9.89E-17 0.19

2.100 1.56E-16 0.21 2.100 7.04E-17 0.22

2.200 2.29E-15 0.03 2.200 4.10E-16 0.04

ATTACHMENT A

ENERGY SPECTRA CALCULATED FROM TANK MODELS FOR FILM BADGE MODELS

Page 4 of 4
Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 28 of 68

Dose Model for a Standing Worker – No Port

SRS Dosimeter Ratio Worker on top of Type III Tank

C 

C Roger Halsey - March 2013

C

C Film Badge Model from Robert Morris

C BOMAB Model from Tim Taulbee

C

C ==================================Cells=======================================

C 

C BOMAB Phantom

 120 208 -1.19 -80:-81:-82:-83:-84:-85:-86:-87:-88:-89:-90:-91 TRCL=3

C

C Air

 163 101 -0.001205 -55 40.2 #120 

 164 101 -0.001205 55 -56 40.2 #120

 165 101 -0.001205 56 -57 -50 40.2

 166 101 -0.001205 57 -58 -50 40.2

 167 101 -0.001205 58 -59 -50 40.2

 168 101 -0.001205 59 -50 40.2

C

C Concrete

 169 350 -2.3 -40 60

 170 350 -2.3 -40 -60 61

 171 350 -2.3 -40 -61 62

 172 350 -2.3 -40 -62 69

 181 350 -2.3 -40 -69 70

 182 350 -2.3 -40 -70 71

 183 350 -2.3 -40 -71 72

 184 350 -2.3 (-40 41 -72) 

C

C Sludge

 174 400 -1.23 -41 

C 

C Void 

 199 0 (50 40.2) : (-40.2 40)

C ================================Surfaces====================================== 

C

C BOMAB Phantom, Standing

 80 rcc -7.5 0 0 0 0 40 6 $Right Calf

 81 rcc 7.5 0 0 0 0 40 6 $Left Calf

 82 rcc -7.5 0 40 0 0 40 7.5 $Right Thigh

 83 rcc 7.5 0 40 0 0 40 7.5 $Left Thigh

 84 rec 0 0 80 0 0 20 18 0 0 0 10 0 $Pelvis

 85 rec 0 0 100 0 0 45 15 0 0 0 10 0 $Chest

ATTACHMENT B

DOSE MODELS

Page 1 of 35
Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 29 of 68

 86 rcc 0 0 145 0 0 5 6.5 $Neck

 87 rec 0 0 150 0 0 20 7 0 0 0 9.5 0 $Head

 88 rcc -21.25 0 145 0 0 -35 6.25 $Upper R Arm

 89 rcc 21.25 0 145 0 0 -35 6.25 $Upper L Arm

 90 rcc -22.75 0 110 0 0 -35 4.85 $Lower R Arm

 91 rcc 22.75 0 110 0 0 -35 4.85 $Lower L Arm

C 

C Tank, surrounding concrete annulus

 40 rcc 0 0 -1127.76 0 0 1127.76 1374.6 $ Outer cylinder

 41 rcc 0 0 -1127.76 0 0 1015.84 1295.4 $ Inner cylinder

C Concrete (and port) Importance surfaces

 60 pz -13

 61 pz -27

 62 pz -40

 69 pz -54

 70 pz -67

 71 pz -80

 72 pz -93

C Sludge Importance surfaces

 63 pz -271

 64 pz -416

 65 pz -561

 66 pz -706

 67 pz -851

 68 pz -996

C Air Importance Surfaces

 55 sph 450 0 90 100

 56 sph 450 0 90 200

 57 sph 450 0 90 300

 58 sph 450 0 90 400

 59 sph 450 0 90 500 

C

C Outer Void

 50 rcc 0 0 -15 0 0 400 1374.6 $ Coincide with tank radius

C ==================================Data========================================

C

C 

C *** PMMA *** (Lucite) 

m208 1000 -0.080538 $PMMA

 6000 -0.599848 

 8000 -0.319614 

C 

C Air, density=1.205e-3 g/cc 

m101 7000 -0.755636 $N 

 8000 -0.231475 $O

 18000 -0.012889 $Ar 

ATTACHMENT B

DOSE MODELS

Page 2 of 35
Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 30 of 68

C 

C Ordinary Concrete, density = 2.3

m350 1000 -0.022100 $H

 6000 -0.002484 $C

 8000 -0.574930 $O

 11000 -0.015208 $Na

 12000 -0.001266 $Mg

 13000 -0.019953 $Al

 14000 -0.304627 $Si

 19000 -0.010045 $K

 20000 -0.042951 $Ca

 26000 -0.006435 $Fe

C

C Sludge, density = 1.23

m400

 8000 0.363615281 $O

 1000 0.139552217 $H

 26000 0.009262229 $Fe

 13000 0.015899426 $Al

 25000 0.001868927 $Mn

 20000 0.001329805 $Ca

 6000 0.008161102 $C

 9000 0.000331044 $F

 7000 0.076349422 $N 

 19000 0.13292332 $K

 16000 0.001907384 $S

 24000 9.90221E-05 $Cr

 47000 5.94086E-05 $Ag

 12000 7.22305E-05 $Mg

 29000 9.97572E-05 $Cu

 58000 3.7862E-05 $Ce

 15000 0.000181322 $P

 56000 2.72846E-05 $Ba

 57000 2.33286E-05 $La

 80000 8.98041E-06 $Hg

 27000 5.12576E-06 $Co

 11000 0.247769977 $Na

 14000 1.05915E-05 $Si

 17000 0.000267783 $Cl

 28000 6.14648E-07 $Ni

 30000 8.03355E-05 $Zn

 33000 4.89961E-06 $As

 34000 2.8856E-05 $Se

 38000 3.10603E-06 $Sr

 40000 1.73449E-06 $Zr

 48000 1.74539E-07 $Cd

 55000 5.2383E-06 $Cs

 60000 4.82667E-06 $Nd

 82000 4.58187E-06 $Pb

ATTACHMENT B

DOSE MODELS

Page 3 of 35
Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 31 of 68

 88226 2.80048E-06 $Ra Note: radium requires isotope in zaid

C

C Translation for BOMAB Phantom

TR3 439 0 0 0 1 0 1 0 0 0 0 1 1 $ Moved near port, rotated 90 degrees

C

mode p

imp:p

 84934656 $ Cell 120, BOMAB Phantom

 84934656 $ Cell 163, air - closest

 56623104 $ Cell 164, air

 37748736 $ Cell 165, air

 25165824 $ Cell 166, air

 16777216 $ Cell 167, air

 16777216 $ Cell 168, air - furthest

 16777216 $ Cell 169, concrete -closest

 2097152 $ Cell 170, concrete

 262144 $ Cell 171, concrete

 32768 $ Cell 172, concrete

 4096 $ Cell 181, concrete

 512 $ Cell 182, concrete

 64 $ Cell 183, concrete

 8 $ Cell 184, concrete - furthest

 1 $ Cell 174, sludge - closest

 0 $ Cell 199, void 

sdef pos=450 0 0 erg=D10 rad=d20 axs=0 0 1 ext=d30

si20 0 700 $ radius

sp20 -21 1 $ even dist. radially

si30 L -1127 -127 $ thickness

sp30 -21 0 $ even dist. vertically

# si10 sp10 $ energy dist. in MeV

 H D $ energy bins then prob.

 0 0

 0.10 1.96E+01

 0.20 1.47E+01

 0.25 7.56E-02

 0.30 5.88E-03

 0.40 2.37E-02

 0.60 5.19E+00

 0.70 1.81E+01

 0.80 6.57E+01

 0.90 5.39E-01

 1.00 2.79E-02

 1.10 3.47E-01

 1.20 1.66E-01

 1.25 3.95E-02

 1.30 7.41E-02

 1.40 2.33E-01

 1.60 4.28E-01

 

ATTACHMENT B

DOSE MODELS

Page 4 of 35
Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 32 of 68

 1.70 2.66E-04

 1.80 5.47E-08

 1.90 1.53E-06

 2.00 2.56E-07

 2.10 2.87E-05

 2.20 1.03E+00

 2.25 1.52E-08

 2.30 2.00E-08

 2.40 3.59E-08

 2.60 1.61E-07

 2.70 9.20E-44

 2.80 8.71E-09

 2.90 0.00E+00

 3.00 6.88E-44

C 

C Weigt windows based on IMP values

wwp:p 5 3 5 0 1

C

C Exponential Transform for sludge volume only

ext:p 0 14R 0.8 0

C Tallys 

C 

F5:p 450 0 140 20

C Energy Bins, more frequent at 0 - 0.1 MeV

C Bins specified by Taulbee

C

E5 0.010

 0.020

 0.030

 0.040

 0.050

 0.060

 0.070

 0.080

 0.090

 0.100

 0.110

 0.120

 0.130

 0.140

 0.150

 0.160

 0.170

 0.180

 0.190

 0.200

 0.210

 0.220

 0.230

ATTACHMENT B

DOSE MODELS

Page 5 of 35
Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 33 of 68

 0.240

 0.250

 0.300

 0.350

 0.400

 0.450

 0.500

 1.000

 1.500

 2.000

 2.500

 3.000

 3.500

 4.000

FC5 ************ Flux at 140 cm above surface ****************

F15:p 450 0 90 20

C Energy Bins, more frequent at 0 - 0.1 MeV

C Bins specified by Taulbee

C

E15 0.010

 0.020

 0.030

 0.040

 0.050

 0.060

 0.070

 0.080

 0.090

 0.100

 0.110

 0.120

 0.130

 0.140

 0.150

 0.160

 0.170

 0.180

 0.190

 0.200

 0.210

 0.220

 0.230

 0.240

 0.250

 0.300

 0.350

 0.400

 0.450

 0.500

 

ATTACHMENT B

DOSE MODELS

Page 6 of 35
Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 34 of 68

 1.000

 1.500

 2.000

 2.500

 3.000

 3.500

 4.000

FC15 ************ Flux at 90 cm above surface ****************

C ICRP 74 Table A.21 for H*(10) dose per fluence in pSv / cm2 

# DE0 DF0

 0.01 0.0608

 0.015 0.8346

 0.02 1.0553

 0.03 0.8129

 0.04 0.64386

 0.05 0.54776

 0.06 0.50808

 0.08 0.52976

 0.1 0.6138

 0.15 0.894

 0.2 1.1984

 0.3 1.8078

 0.4 2.3814

 0.5 2.9274

 0.6 3.4364

 0.8 4.3911

 1 5.2299

 1.5 7.038

 2 8.5614

 3 11.1757

 4 13.44

 5 15.429

 6 17.538

 8 21.645

 10 25.52

F25:p 450 0 90 20

C Energy Bins

E25 0.03 0.25 3.5

F35:p 450 0 40 20

C Energy Bins

E35 0.03 0.25 3.5

C ICRP 74 Table A.21 for H*(10) dose per fluence in pSv / cm2 

# DE25 DF25

 0.01 0.0608

 0.015 0.8346

 0.02 1.0553

 0.03 0.8129

 0.04 0.64386

 0.05 0.54776

ATTACHMENT B

DOSE MODELS

Page 7 of 35
Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 35 of 68

 0.06 0.50808

 0.08 0.52976

 0.1 0.6138

 0.15 0.894

 0.2 1.1984

 0.3 1.8078

 0.4 2.3814

 0.5 2.9274

 0.6 3.4364

 0.8 4.3911

 1 5.2299

 1.5 7.038

 2 8.5614

 3 11.1757

 4 13.44

 5 15.429

 6 17.538

 8 21.645

 10 25.52

# DE35 DF35

 0.01 0.0608

 0.015 0.8346

 0.02 1.0553

 0.03 0.8129

 0.04 0.64386

 0.05 0.54776

 0.06 0.50808

 0.08 0.52976

 0.1 0.6138

 0.15 0.894

 0.2 1.1984

 0.3 1.8078

 0.4 2.3814

 0.5 2.9274

 0.6 3.4364

 0.8 4.3911

 1 5.2299

 1.5 7.038

 2 8.5614

 3 11.1757

 4 13.44

 5 15.429

 6 17.538

 8 21.645

 10 25.52

nps 1E10

ATTACHMENT B

DOSE MODELS

Page 8 of 35
Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 36 of 68

Dose Model for a Kneeling Worker – No Port

SRS Dosimeter Ratio Worker on top of Type III Tank

C 

C Roger Halsey - March 2013

C

C Film Badge Model from Robert Morris

C BOMAB Model from Tim Taulbee

C

C ==================================Cells=======================================

C 

C BOMAB Phantom

 120 208 -1.19 -80:-81:-82:-83:-84:-85:-86:-87:-88:-89:-90:-91 TRCL=3

C

C Air

 163 101 -0.001205 -55 40.2 #120 

 164 101 -0.001205 55 -56 40.2 #120

 165 101 -0.001205 56 -57 -50 40.2

 166 101 -0.001205 57 -58 -50 40.2

 167 101 -0.001205 58 -59 -50 40.2

 168 101 -0.001205 59 -50 40.2

C

C Concrete

 169 350 -2.3 -40 60

 170 350 -2.3 -40 -60 61

 171 350 -2.3 -40 -61 62

 172 350 -2.3 -40 -62 69

 181 350 -2.3 -40 -69 70

 182 350 -2.3 -40 -70 71

 183 350 -2.3 -40 -71 72

 184 350 -2.3 (-40 41 -72) 

C

C Sludge

 174 400 -1.23 -41 

C 

C Void 

 199 0 (50 40.2) : (-40.2 40)

C ================================Surfaces====================================== 

C

C BOMAB Phantom, Kneeling

 80 rcc -7.5 -7.5 6 0 -40 0 6 $Right Calf

 81 rcc 7.5 -7.5 6 0 -40 0 6 $Left Calf

 82 rcc -7.5 0 6 0 0 25 7.5 $Right Thigh

 83 rcc 7.5 0 6 0 0 25 7.5 $Left Thigh

 84 rec 0 0 31 0 0 20 18 0 0 0 10 0 $Pelvis

ATTACHMENT B

DOSE MODELS

Page 9 of 35
Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 37 of 68

 85 rec 0 0 51 0 0 45 15 0 0 0 10 0 $Chest

 86 rcc 0 0 96 0 0 5 6.5 $Neck

 87 rec 0 0 101 0 0 20 7 0 0 0 9.5 0 $Head

 88 rcc -21.25 0 96 0 0 -35 6.25 $Upper R Arm

 89 rcc 21.25 0 96 0 0 -35 6.25 $Upper L Arm

 90 rcc -22.75 0 61 0 0 -35 4.85 $Lower R Arm

 91 rcc 22.75 0 61 0 0 -35 4.85 $Lower L Arm

C 

C Tank, surrounding concrete annulus

 40 rcc 0 0 -1127.76 0 0 1127.76 1374.6 $ Outer cylinder

 41 rcc 0 0 -1127.76 0 0 1015.84 1295.4 $ Inner cylinder

C Concrete (and port) Importance surfaces

 60 pz -13

 61 pz -27

 62 pz -40

 69 pz -54

 70 pz -67

 71 pz -80

 72 pz -93

C Sludge Importance surfaces

 63 pz -271

 64 pz -416

 65 pz -561

 66 pz -706

 67 pz -851

 68 pz -996

C Air Importance Surfaces

 55 sph 450 0 90 100

 56 sph 450 0 90 200

 57 sph 450 0 90 300

 58 sph 450 0 90 400

 59 sph 450 0 90 500 

C

C Outer Void

 50 rcc 0 0 -15 0 0 400 1374.6 $ Coincide with tank radius

C ==================================Data========================================

C

C 

C *** PMMA *** (Lucite) 

m208 1000 -0.080538 $PMMA

 6000 -0.599848 

 8000 -0.319614 

C 

C Air, density=1.205e-3 g/cc 

m101 7000 -0.755636 $N 

 8000 -0.231475 $O

ATTACHMENT B

DOSE MODELS

Page 10 of 35
Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 38 of 68

 18000 -0.012889 $Ar 

C 

C Ordinary Concrete, density = 2.3

m350 1000 -0.022100 $H

 6000 -0.002484 $C

 8000 -0.574930 $O

 11000 -0.015208 $Na

 12000 -0.001266 $Mg

 13000 -0.019953 $Al

 14000 -0.304627 $Si

 19000 -0.010045 $K

 20000 -0.042951 $Ca

 26000 -0.006435 $Fe

C

C Sludge, density = 1.23

m400

 8000 0.363615281 $O

 1000 0.139552217 $H

 26000 0.009262229 $Fe

 13000 0.015899426 $Al

 25000 0.001868927 $Mn

 20000 0.001329805 $Ca

 6000 0.008161102 $C

 9000 0.000331044 $F

 7000 0.076349422 $N 

 19000 0.13292332 $K

 16000 0.001907384 $S

 24000 9.90221E-05 $Cr

 47000 5.94086E-05 $Ag

 12000 7.22305E-05 $Mg

 29000 9.97572E-05 $Cu

 58000 3.7862E-05 $Ce

 15000 0.000181322 $P

 56000 2.72846E-05 $Ba

 57000 2.33286E-05 $La

 80000 8.98041E-06 $Hg

 27000 5.12576E-06 $Co

 11000 0.247769977 $Na

 14000 1.05915E-05 $Si

 17000 0.000267783 $Cl

 28000 6.14648E-07 $Ni

 30000 8.03355E-05 $Zn

 33000 4.89961E-06 $As

 34000 2.8856E-05 $Se

 38000 3.10603E-06 $Sr

 40000 1.73449E-06 $Zr

 48000 1.74539E-07 $Cd

 55000 5.2383E-06 $Cs

 60000 4.82667E-06 $Nd

 

ATTACHMENT B

DOSE MODELS

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Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 39 of 68

 82000 4.58187E-06 $Pb

 88226 2.80048E-06 $Ra Note: radium requires isotope in zaid

C

C Translation for BOMAB Phantom

TR3 439 0 0 0 1 0 1 0 0 0 0 1 1 $ Moved near port, rotated 90 degrees

C

mode p

imp:p

 84934656 $ Cell 120, BOMAB Phantom

 84934656 $ Cell 163, air - closest

 56623104 $ Cell 164, air

 37748736 $ Cell 165, air

 25165824 $ Cell 166, air

 16777216 $ Cell 167, air

 16777216 $ Cell 168, air - furthest

 16777216 $ Cell 169, concrete -closest

 2097152 $ Cell 170, concrete

 262144 $ Cell 171, concrete

 32768 $ Cell 172, concrete

 4096 $ Cell 181, concrete

 512 $ Cell 182, concrete

 64 $ Cell 183, concrete

 8 $ Cell 184, concrete - furthest

 1 $ Cell 174, sludge - closest

 0 $ Cell 199, void 

sdef pos=450 0 0 erg=D10 rad=d20 axs=0 0 1 ext=d30

si20 0 700 $ radius

sp20 -21 1 $ even dist. radially

si30 L -1127 -127 $ thickness

sp30 -21 0 $ even dist. vertically

# si10 sp10 $ energy dist. in MeV

 H D $ energy bins then prob.

 0 0

 0.10 1.96E+01

 0.20 1.47E+01

 0.25 7.56E-02

 0.30 5.88E-03

 0.40 2.37E-02

 0.60 5.19E+00

 0.70 1.81E+01

 0.80 6.57E+01

 0.90 5.39E-01

 1.00 2.79E-02

 1.10 3.47E-01

 1.20 1.66E-01

 1.25 3.95E-02

 1.30 7.41E-02

 1.40 2.33E-01

ATTACHMENT B

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Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 40 of 68

 1.60 4.28E-01

 1.70 2.66E-04

 1.80 5.47E-08

 1.90 1.53E-06

 2.00 2.56E-07

 2.10 2.87E-05

 2.20 1.03E+00

 2.25 1.52E-08

 2.30 2.00E-08

 2.40 3.59E-08

 2.60 1.61E-07

 2.70 9.20E-44

 2.80 8.71E-09

 2.90 0.00E+00

 3.00 6.88E-44

C 

C Weigt windows based on IMP values

wwp:p 5 3 5 0 1

C

C Exponential Transform for sludge volume only

ext:p 0 14R 0.8 0

C Tallys 

C 

FC5 ************ Flux at 90 cm above surface ****************

F5:p 450 0 90 10

C Energy Bins, more frequent at 0 - 0.1 MeV

C Bins specified by Taulbee

C

E5 0.010

 0.020

 0.030

 0.040

 0.050

 0.060

 0.070

 0.080

 0.090

 0.100

 0.110

 0.120

 0.130

 0.140

 0.150

 0.160

 0.170

 0.180

 0.190

 0.200

 0.210

ATTACHMENT B

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Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 41 of 68

 0.220

 0.230

 0.240

 0.250

 0.300

 0.350

 0.400

 0.450

 0.500

 0.600

 0.700

 0.800

 0.900

 1.000

 1.100 

 1.200 

 1.300 

 1.400 

 1.500

 1.600 

 1.700 

 1.800 

 1.900 

 2.000

 2.100 

 2.200 

 2.300 

 2.400 

 2.500

 2.600 

 2.700 

 2.800 

 2.900 

 3.000

FC15 ************ Flux at 40 cm above surface ****************

F15:p 450 0 40 10

C Energy Bins, more frequent at 0 - 0.1 MeV

C Bins specified by Taulbee

C

E15 0.010

 0.020

 0.030

 0.040

 0.050

 0.060

 0.070

 0.080

 0.090

 0.100

ATTACHMENT B

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Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 42 of 68

 0.110

 0.120

 0.130

 0.140

 0.150

 0.160

 0.170

 0.180

 0.190

 0.200

 0.210

 0.220

 0.230

 0.240

 0.250

 0.300

 0.350

 0.400

 0.450

 0.500

 0.600

 0.700

 0.800

 0.900

 1.000

 1.100 

 1.200 

 1.300 

 1.400 

 1.500

 1.600 

 1.700 

 1.800 

 1.900 

 2.000

 2.100 

 2.200 

 2.300 

 2.400 

 2.500

 2.600 

 2.700 

 2.800 

 2.900 

 3.000

FC25 ************ ICRP 74 Dose at 90 cm above surface ****************

F25:p 450 0 90 10

C Energy Bins

E25 0.03 0.25 3.5

ATTACHMENT B

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Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 43 of 68

C ICRP 74 Table A.21 for H*(10) dose per fluence in pSv / cm2 

# DE25 DF25

 0.01 0.0608

 0.015 0.8346

 0.02 1.0553

 0.03 0.8129

 0.04 0.64386

 0.05 0.54776

 0.06 0.50808

 0.08 0.52976

 0.1 0.6138

 0.15 0.894

 0.2 1.1984

 0.3 1.8078

 0.4 2.3814

 0.5 2.9274

 0.6 3.4364

 0.8 4.3911

 1 5.2299

 1.5 7.038

 2 8.5614

 3 11.1757

 4 13.44

 5 15.429

 6 17.538

 8 21.645

 10 25.52

FC35 ************ ICRP 74 Dose at 40 cm above surface ****************

F35:p 450 0 40 10

C Energy Bins

E35 0.03 0.25 3.5

C ICRP 74 Table A.21 for H*(10) dose per fluence in pSv / cm2 

# DE35 DF35

 0.01 0.0608

 0.015 0.8346

 0.02 1.0553

 0.03 0.8129

 0.04 0.64386

 0.05 0.54776

 0.06 0.50808

 0.08 0.52976

 0.1 0.6138

 0.15 0.894

 0.2 1.1984

 0.3 1.8078

 0.4 2.3814

 0.5 2.9274

 0.6 3.4364

 0.8 4.3911

ATTACHMENT B

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Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 44 of 68

 1 5.2299

 1.5 7.038

 2 8.5614

 3 11.1757

 4 13.44

 5 15.429

 6 17.538

 8 21.645

 10 25.52

nps 1E10

rand seed = 7777777777777777

ATTACHMENT B

DOSE MODELS

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Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 45 of 68

Dose Model for a Standing Worker Near a Port

SRS Dosimeter Ratio Worker on top of Type III Tank

C 

C Roger Halsey - March 2013

C

C Film Badge Model from Robert Morris

C BOMAB Model from Tim Taulbee

C

C ==================================Cells=======================================

C 

C BOMAB Phantom

 120 208 -1.19 -80:-81:-82:-83:-84:-85:-86:-87:-88:-89:-90:-91 TRCL=3

C

C Air

 163 101 -0.001205 -55 40.2 #120 

 164 101 -0.001205 55 -56 40.2 #120

 165 101 -0.001205 56 -57 -50 40.2

 166 101 -0.001205 57 -58 -50 40.2

 167 101 -0.001205 58 -59 -50 40.2

 168 101 -0.001205 59 -50 40.2

C Port 

 103 101 -0.001205 -40.2 60 -43

 104 101 -0.001205 -60 61 -43

 105 101 -0.001205 -61 62 -43

 106 101 -0.001205 -62 69 -43

 107 101 -0.001205 -69 70 -43

 108 101 -0.001205 -70 71 -43

 109 101 -0.001205 -71 72 -43

 110 101 -0.001205 -72 41.2 -43

C

C Concrete

 169 350 -2.3 -40 43 60

 170 350 -2.3 -40 43 -60 61

 171 350 -2.3 -40 43 -61 62

 172 350 -2.3 -40 43 -62 69

 181 350 -2.3 -40 43 -69 70

 182 350 -2.3 -40 43 -70 71

 183 350 -2.3 -40 43 -71 72

 184 350 -2.3 (-40 41 43 -72) 

C

C Sludge

 174 400 -1.23 -41 

C

C Void 

 199 0 (50 40.2) : (-40.2 40)

C ================================Surfaces=====================================

ATTACHMENT B

DOSE MODELS

Page 18 of 35
Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 46 of 68

= 

C

C BOMAB Phantom, Standing

 80 rcc -7.5 0 0 0 0 40 6 $Right Calf

 81 rcc 7.5 0 0 0 0 40 6 $Left Calf

 82 rcc -7.5 0 40 0 0 40 7.5 $Right Thigh

 83 rcc 7.5 0 40 0 0 40 7.5 $Left Thigh

 84 rec 0 0 80 0 0 20 18 0 0 0 10 0 $Pelvis

 85 rec 0 0 100 0 0 45 15 0 0 0 10 0 $Chest

 86 rcc 0 0 145 0 0 5 6.5 $Neck

 87 rec 0 0 150 0 0 20 7 0 0 0 9.5 0 $Head

 88 rcc -21.25 0 145 0 0 -35 6.25 $Upper R Arm

 89 rcc 21.25 0 145 0 0 -35 6.25 $Upper L Arm

 90 rcc -22.75 0 110 0 0 -35 4.85 $Lower R Arm

 91 rcc 22.75 0 110 0 0 -35 4.85 $Lower L Arm

C 

C Tank, surrounding concrete annulus

 40 rcc 0 0 -1127.76 0 0 1127.76 1374.6 $ Outer cylinder

 41 rcc 0 0 -1127.76 0 0 1015.84 1295.4 $ Inner cylinder

 43 c/z 500 0 15 $ air sample port

C Concrete (and port) Importance surfaces

 60 pz -13

 61 pz -27

 62 pz -40

 69 pz -54

 70 pz -67

 71 pz -80

 72 pz -93

C Sludge Importance surfaces

 63 pz -271

 64 pz -416

 65 pz -561

 66 pz -706

 67 pz -851

 68 pz -996

C Air Importance Surfaces

 55 sph 450 0 90 100

 56 sph 450 0 90 200

 57 sph 450 0 90 300

 58 sph 450 0 90 400

 59 sph 450 0 90 500 

C

C Outer Void

 50 rcc 0 0 -15 0 0 400 1374.6 $ Coincide with tank radius

C ==================================Data========================================

C

ATTACHMENT B

DOSE MODELS

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Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 47 of 68

C 

C *** PMMA *** (Lucite) 

m208 1000 -0.080538 $PMMA

 6000 -0.599848 

 8000 -0.319614 

C 

C Air, density=1.205e-3 g/cc 

m101 7000 -0.755636 $N 

 8000 -0.231475 $O

 18000 -0.012889 $Ar 

C 

C Ordinary Concrete, density = 2.3

m350 1000 -0.022100 $H

 6000 -0.002484 $C

 8000 -0.574930 $O

 11000 -0.015208 $Na

 12000 -0.001266 $Mg

 13000 -0.019953 $Al

 14000 -0.304627 $Si

 19000 -0.010045 $K

 20000 -0.042951 $Ca

 26000 -0.006435 $Fe

C

C Sludge, density = 1.23

m400

 8000 0.363615281 $O

 1000 0.139552217 $H

 26000 0.009262229 $Fe

 13000 0.015899426 $Al

 25000 0.001868927 $Mn

 20000 0.001329805 $Ca

 6000 0.008161102 $C

 9000 0.000331044 $F

 7000 0.076349422 $N 

 19000 0.13292332 $K

 16000 0.001907384 $S

 24000 9.90221E-05 $Cr

 47000 5.94086E-05 $Ag

 12000 7.22305E-05 $Mg

 29000 9.97572E-05 $Cu

 58000 3.7862E-05 $Ce

 15000 0.000181322 $P

 56000 2.72846E-05 $Ba

 57000 2.33286E-05 $La

 80000 8.98041E-06 $Hg

 27000 5.12576E-06 $Co

 11000 0.247769977 $Na

 14000 1.05915E-05 $Si

 17000 0.000267783 $Cl

ATTACHMENT B

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Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 48 of 68

 28000 6.14648E-07 $Ni

 30000 8.03355E-05 $Zn

 33000 4.89961E-06 $As

 34000 2.8856E-05 $Se

 38000 3.10603E-06 $Sr

 40000 1.73449E-06 $Zr

 48000 1.74539E-07 $Cd

 55000 5.2383E-06 $Cs

 60000 4.82667E-06 $Nd

 82000 4.58187E-06 $Pb

 88226 2.80048E-06 $Ra Note: radium requires isotope in zaid

C

C Translation for BOMAB Phantom

TR3 439 0 0 0 1 0 1 0 0 0 0 1 1 $ Moved near port, rotated 90 degrees

C

mode p

imp:p

 84934656 $ Cell 120, BOMAB Phantom

 84934656 $ Cell 163, air - closest

 56623104 $ Cell 164, air

 37748736 $ Cell 165, air

 25165824 $ Cell 166, air

 16777216 $ Cell 167, air

 16777216 $ Cell 168, air - furthest

 16777216 $ Cell 103, Port- closest

 2097152 $ Cell 104, Port

 262144 $ Cell 105, Port

 32768 $ Cell 106, Port

 4096 $ Cell 107, Port

 512 $ Cell 108, Port

 64 $ Cell 109, Port

 8 $ Cell 110, Port - furthest

 16777216 $ Cell 169, concrete -closest

 2097152 $ Cell 170, concrete

 262144 $ Cell 171, concrete

 32768 $ Cell 172, concrete

 4096 $ Cell 181, concrete

 512 $ Cell 182, concrete

 64 $ Cell 183, concrete

 8 $ Cell 184, concrete - furthest

 1 $ Cell 174, sludge - closest

 0 $ Cell 199, void 

sdef pos=450 0 0 erg=D10 rad=d20 axs=0 0 1 ext=d30

si20 0 700 $ radius

sp20 -21 1 $ even dist. radially

si30 L -1127 -127 $ thickness

sp30 -21 0 $ even dist. vertically

# si10 sp10 $ energy dist. in MeV

ATTACHMENT B

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Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 49 of 68

 H D $ energy bins then prob.

 0 0

 0.10 5.51E-04

 0.20 9.82E-04

 0.25 2.91E-04

 0.30 2.03E-04

 0.40 2.62E-04

 0.60 3.35E-04

 0.70 1.24E-04

 0.80 1.13E-04

 0.90 1.05E-04

 1.00 9.91E-05

 1.10 9.29E-05

 1.20 8.94E-05

 1.25 4.23E-05

 1.30 3.97E-05

 1.40 7.56E-05

 1.60 1.40E-04

 1.70 6.19E-05

 1.80 5.61E-05

 1.90 5.22E-05

 2.00 4.63E-05

 2.10 3.80E-05

 2.20 3.24E-05

 2.25 1.31E-05

 2.30 1.29E-05

 2.40 2.04E-05

 2.60 2.81E-05

 2.70 6.96E-06

 2.80 4.70E-06

 2.90 2.57E-06

 3.00 1.64E-06

 3.10 1.23E-06

 3.20 1.10E-06

 3.25 2.89E-07

 3.30 1.68E-07

 3.40 4.92E-07

 3.60 5.80E-08

C

C DXRAN Spheres at entrance and exit of port

DXT:p 500 0 0 15 15 500 0 -111.92 15 15 450 0 115 100 100

C 

C Weigt windows based on IMP values

wwp:p 5 3 5 0 1

C

C Exponential Transform for sludge volume only

ext:p 0 22R 0.8 0

C Tallys 

C 

ATTACHMENT B

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Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 50 of 68

F5:p 450 0 140 20

C Energy Bins, more frequent at 0 - 0.1 MeV

C Bins specified by Taulbee

C

E5 0.010

 0.020

 0.030

 0.040

 0.050

 0.060

 0.070

 0.080

 0.090

 0.100

 0.110

 0.120

 0.130

 0.140

 0.150

 0.160

 0.170

 0.180

 0.190

 0.200

 0.210

 0.220

 0.230

 0.240

 0.250

 0.300

 0.350

 0.400

 0.450

 0.500

 1.000

 1.500

 2.000

 2.500

 3.000

 3.500

 4.000

FC5 ************ Flux at 140 cm above surface ****************

F15:p 450 0 90 20

C Energy Bins, more frequent at 0 - 0.1 MeV

C Bins specified by Taulbee

C

E15 0.010

 0.020

 0.030

ATTACHMENT B

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Page 23 of 35
Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 51 of 68

 0.040

 0.050

 0.060

 0.070

 0.080

 0.090

 0.100

 0.110

 0.120

 0.130

 0.140

 0.150

 0.160

 0.170

 0.180

 0.190

 0.200

 0.210

 0.220

 0.230

 0.240

 0.250

 0.300

 0.350

 0.400

 0.450

 0.500

 1.000

 1.500

 2.000

 2.500

 3.000

 3.500

 4.000

FC15 ************ Flux at 90 cm above surface ****************

C ICRP 74 Table A.21 for H*(10) dose per fluence in pSv / cm2 

# DE0 DF0

 0.01 0.0608

 0.015 0.8346

 0.02 1.0553

 0.03 0.8129

 0.04 0.64386

 0.05 0.54776

 0.06 0.50808

 0.08 0.52976

 0.1 0.6138

 0.15 0.894

 0.2 1.1984

 0.3 1.8078

ATTACHMENT B

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Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 52 of 68

 0.4 2.3814

 0.5 2.9274

 0.6 3.4364

 0.8 4.3911

 1 5.2299

 1.5 7.038

 2 8.5614

 3 11.1757

 4 13.44

 5 15.429

 6 17.538

 8 21.645

 10 25.52

F25:p 450 0 90 20

C Energy Bins

E25 0.03 0.25 3.5

F35:p 450 0 40 20

C Energy Bins

E35 0.03 0.25 3.5

C ICRP 74 Table A.21 for H*(10) dose per fluence in pSv / cm2 

# DE25 DF25

 0.01 0.0608

 0.015 0.8346

 0.02 1.0553

 0.03 0.8129

 0.04 0.64386

 0.05 0.54776

 0.06 0.50808

 0.08 0.52976

 0.1 0.6138

 0.15 0.894

 0.2 1.1984

 0.3 1.8078

 0.4 2.3814

 0.5 2.9274

 0.6 3.4364

 0.8 4.3911

 1 5.2299

 1.5 7.038

 2 8.5614

 3 11.1757

 4 13.44

 5 15.429

 6 17.538

 8 21.645

 10 25.52

# DE35 DF35

 0.01 0.0608

 0.015 0.8346

ATTACHMENT B

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Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 53 of 68

 0.02 1.0553

 0.03 0.8129

 0.04 0.64386

 0.05 0.54776

 0.06 0.50808

 0.08 0.52976

 0.1 0.6138

 0.15 0.894

 0.2 1.1984

 0.3 1.8078

 0.4 2.3814

 0.5 2.9274

 0.6 3.4364

 0.8 4.3911

 1 5.2299

 1.5 7.038

 2 8.5614

 3 11.1757

 4 13.44

 5 15.429

 6 17.538

 8 21.645

 10 25.52

nps 1E10

ATTACHMENT B

DOSE MODELS

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Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 54 of 68

Dose Model for a Kneeling Worker Near a Port

SRS Dosimeter Ratio Worker on top of Type III Tank

C 

C Roger Halsey - March 2013

C

C Film Badge Model from Robert Morris

C BOMAB Model from Tim Taulbee

C

C ==================================Cells=======================================

C 

C BOMAB Phantom

 120 208 -1.19 -80:-81:-82:-83:-84:-85:-86:-87:-88:-89:-90:-91 TRCL=3

C

C Air

 163 101 -0.001205 -55 40.2 #120 

 164 101 -0.001205 55 -56 40.2 #120

 165 101 -0.001205 56 -57 -50 40.2

 166 101 -0.001205 57 -58 -50 40.2

 167 101 -0.001205 58 -59 -50 40.2

 168 101 -0.001205 59 -50 40.2

C Port 

 103 101 -0.001205 -40.2 60 -43

 104 101 -0.001205 -60 61 -43

 105 101 -0.001205 -61 62 -43

 106 101 -0.001205 -62 69 -43

 107 101 -0.001205 -69 70 -43

 108 101 -0.001205 -70 71 -43

 109 101 -0.001205 -71 72 -43

 110 101 -0.001205 -72 41.2 -43

C

C Concrete

 169 350 -2.3 -40 43 60

 170 350 -2.3 -40 43 -60 61

 171 350 -2.3 -40 43 -61 62

 172 350 -2.3 -40 43 -62 69

 181 350 -2.3 -40 43 -69 70

 182 350 -2.3 -40 43 -70 71

 183 350 -2.3 -40 43 -71 72

 184 350 -2.3 (-40 41 43 -72) 

C

C Sludge

 174 400 -1.23 -41 

C 

C Void 

 199 0 (50 40.2) : (-40.2 40)

C ================================Surfaces=====================================

ATTACHMENT B

DOSE MODELS

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Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 55 of 68

= 

C

C BOMAB Phantom, Kneeling

 80 rcc -7.5 -7.5 6 0 -40 0 6 $Right Calf

 81 rcc 7.5 -7.5 6 0 -40 0 6 $Left Calf

 82 rcc -7.5 0 6 0 0 25 7.5 $Right Thigh

 83 rcc 7.5 0 6 0 0 25 7.5 $Left Thigh

 84 rec 0 0 31 0 0 20 18 0 0 0 10 0 $Pelvis

 85 rec 0 0 51 0 0 45 15 0 0 0 10 0 $Chest

 86 rcc 0 0 96 0 0 5 6.5 $Neck

 87 rec 0 0 101 0 0 20 7 0 0 0 9.5 0 $Head

 88 rcc -21.25 0 96 0 0 -35 6.25 $Upper R Arm

 89 rcc 21.25 0 96 0 0 -35 6.25 $Upper L Arm

 90 rcc -22.75 0 61 0 0 -35 4.85 $Lower R Arm

 91 rcc 22.75 0 61 0 0 -35 4.85 $Lower L Arm

C 

C Tank, surrounding concrete annulus

 40 rcc 0 0 -1127.76 0 0 1127.76 1374.6 $ Outer cylinder

 41 rcc 0 0 -1127.76 0 0 1015.84 1295.4 $ Inner cylinder

 43 c/z 500 0 15 $ air sample port

C Concrete (and port) Importance surfaces

 60 pz -13

 61 pz -27

 62 pz -40

 69 pz -54

 70 pz -67

 71 pz -80

 72 pz -93

C Sludge Importance surfaces

 63 pz -271

 64 pz -416

 65 pz -561

 66 pz -706

 67 pz -851

 68 pz -996

C Air Importance Surfaces

 55 sph 450 0 90 100

 56 sph 450 0 90 200

 57 sph 450 0 90 300

 58 sph 450 0 90 400

 59 sph 450 0 90 500 

C

C Outer Void

 50 rcc 0 0 -15 0 0 400 1374.6 $ Coincide with tank radius

C ==================================Data========================================

C

ATTACHMENT B

DOSE MODELS

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Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 56 of 68

C 

C *** PMMA *** (Lucite) 

m208 1000 -0.080538 $PMMA

 6000 -0.599848 

 8000 -0.319614 

C 

C Air, density=1.205e-3 g/cc 

m101 7000 -0.755636 $N 

 8000 -0.231475 $O

 18000 -0.012889 $Ar 

C 

C Ordinary Concrete, density = 2.3

m350 1000 -0.022100 $H

 6000 -0.002484 $C

 8000 -0.574930 $O

 11000 -0.015208 $Na

 12000 -0.001266 $Mg

 13000 -0.019953 $Al

 14000 -0.304627 $Si

 19000 -0.010045 $K

 20000 -0.042951 $Ca

 26000 -0.006435 $Fe

C

C Sludge, density = 1.23

m400

 8000 0.363615281 $O

 1000 0.139552217 $H

 26000 0.009262229 $Fe

 13000 0.015899426 $Al

 25000 0.001868927 $Mn

 20000 0.001329805 $Ca

 6000 0.008161102 $C

 9000 0.000331044 $F

 7000 0.076349422 $N 

 19000 0.13292332 $K

 16000 0.001907384 $S

 24000 9.90221E-05 $Cr

 47000 5.94086E-05 $Ag

 12000 7.22305E-05 $Mg

 29000 9.97572E-05 $Cu

 58000 3.7862E-05 $Ce

 15000 0.000181322 $P

 56000 2.72846E-05 $Ba

 57000 2.33286E-05 $La

 80000 8.98041E-06 $Hg

 27000 5.12576E-06 $Co

 11000 0.247769977 $Na

 14000 1.05915E-05 $Si

 17000 0.000267783 $Cl

ATTACHMENT B

DOSE MODELS

Page 29 of 35
Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 57 of 68

 28000 6.14648E-07 $Ni

 30000 8.03355E-05 $Zn

 33000 4.89961E-06 $As

 34000 2.8856E-05 $Se

 38000 3.10603E-06 $Sr

 40000 1.73449E-06 $Zr

 48000 1.74539E-07 $Cd

 55000 5.2383E-06 $Cs

 60000 4.82667E-06 $Nd

 82000 4.58187E-06 $Pb

 88226 2.80048E-06 $Ra Note: radium requires isotope in zaid

C

C Translation for BOMAB Phantom

TR3 439 0 0 0 1 0 1 0 0 0 0 1 1 $ Moved near port, rotated 90 degrees

C

mode p

imp:p

 84934656 $ Cell 120, BOMAB Phantom

 84934656 $ Cell 163, air - closest

 56623104 $ Cell 164, air

 37748736 $ Cell 165, air

 25165824 $ Cell 166, air

 16777216 $ Cell 167, air

 16777216 $ Cell 168, air - furthest

 16777216 $ Cell 103, Port- closest

 2097152 $ Cell 104, Port

 262144 $ Cell 105, Port

 32768 $ Cell 106, Port

 4096 $ Cell 107, Port

 512 $ Cell 108, Port

 64 $ Cell 109, Port

 8 $ Cell 110, Port - furthest

 16777216 $ Cell 169, concrete -closest

 2097152 $ Cell 170, concrete

 262144 $ Cell 171, concrete

 32768 $ Cell 172, concrete

 4096 $ Cell 181, concrete

 512 $ Cell 182, concrete

 64 $ Cell 183, concrete

 8 $ Cell 184, concrete - furthest

 1 $ Cell 174, sludge - closest

 0 $ Cell 199, void 

sdef pos=450 0 0 erg=D10 rad=d20 axs=0 0 1 ext=d30

si20 0 700 $ radius

sp20 -21 1 $ even dist. radially

si30 L -1127 -127 $ thickness

sp30 -21 0 $ even dist. vertically

# si10 sp10 $ energy dist. in MeV

ATTACHMENT B

DOSE MODELS

Page 30 of 35
Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 58 of 68

 H D $ energy bins then prob.

 0 0

 0.10 1.96E+01

 0.20 1.47E+01

 0.25 7.56E-02

 0.30 5.88E-03

 0.40 2.37E-02

 0.60 5.19E+00

 0.70 1.81E+01

 0.80 6.57E+01

 0.90 5.39E-01

 1.00 2.79E-02

 1.10 3.47E-01

 1.20 1.66E-01

 1.25 3.95E-02

 1.30 7.41E-02

 1.40 2.33E-01

 1.60 4.28E-01

 1.70 2.66E-04

 1.80 5.47E-08

 1.90 1.53E-06

 2.00 2.56E-07

 2.10 2.87E-05

 2.20 1.03E+00

 2.25 1.52E-08

 2.30 2.00E-08

 2.40 3.59E-08

 2.60 1.61E-07

 2.70 9.20E-44

 2.80 8.71E-09

 2.90 0.00E+00

 3.00 6.88E-44

C

C DXRAN Spheres at entrance and exit of port

DXT:p 500 0 0 15 15 500 0 -111.92 15 15 450 0 115 100 100

C 

C Weigt windows based on IMP values

wwp:p 5 3 5 0 1

C

C Exponential Transform for sludge volume only

ext:p 0 22R 0.8 0

C Tallys 

C 

F5:p 450 0 140 20

C Energy Bins, more frequent at 0 - 0.1 MeV

C Bins specified by Taulbee

C

E5 0.010

 0.020

ATTACHMENT B

DOSE MODELS

Page 31 of 35
Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 59 of 68

 0.030

 0.040

 0.050

 0.060

 0.070

 0.080

 0.090

 0.100

 0.110

 0.120

 0.130

 0.140

 0.150

 0.160

 0.170

 0.180

 0.190

 0.200

 0.210

 0.220

 0.230

 0.240

 0.250

 0.300

 0.350

 0.400

 0.450

 0.500

 1.000

 1.500

 2.000

 2.500

 3.000

 3.500

 4.000

FC5 ************ Flux at 140 cm above surface ****************

F15:p 450 0 90 20

C Energy Bins, more frequent at 0 - 0.1 MeV

C Bins specified by Taulbee

C

E15 0.010

 0.020

 0.030

 0.040

 0.050

 0.060

 0.070

 0.080

 0.090

ATTACHMENT B

DOSE MODELS

Page 32 of 35
Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 60 of 68

 0.100

 0.110

 0.120

 0.130

 0.140

 0.150

 0.160

 0.170

 0.180

 0.190

 0.200

 0.210

 0.220

 0.230

 0.240

 0.250

 0.300

 0.350

 0.400

 0.450

 0.500

 1.000

 1.500

 2.000

 2.500

 3.000

 3.500

 4.000

FC15 ************ Flux at 90 cm above surface ****************

C ICRP 74 Table A.21 for H*(10) dose per fluence in pSv / cm2 

# DE0 DF0

 0.01 0.0608

 0.015 0.8346

 0.02 1.0553

 0.03 0.8129

 0.04 0.64386

 0.05 0.54776

 0.06 0.50808

 0.08 0.52976

 0.1 0.6138

 0.15 0.894

 0.2 1.1984

 0.3 1.8078

 0.4 2.3814

 0.5 2.9274

 0.6 3.4364

 0.8 4.3911

 1 5.2299

 1.5 7.038

ATTACHMENT B

DOSE MODELS

Page 33 of 35
Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 61 of 68

ATTACHMENT B

DOSE MODELS

Page 34 of 35

 2 8.5614

 3 11.1757

 4 13.44

 5 15.429

 6 17.538

 8 21.645

 10 25.52

F25:p 450 0 90 20

C Energy Bins

E25 0.03 0.25 3.5

F35:p 450 0 40 20

C Energy Bins

E35 0.03 0.25 3.5

C ICRP 74 Table A.21 for H*(10) dose per fluence in pSv / cm2 

# DE25 DF25

 0.01 0.0608

 0.015 0.8346

 0.02 1.0553

 0.03 0.8129

 0.04 0.64386

 0.05 0.54776

 0.06 0.50808

 0.08 0.52976

 0.1 0.6138

 0.15 0.894

 0.2 1.1984

 0.3 1.8078

 0.4 2.3814

 0.5 2.9274

 0.6 3.4364

 0.8 4.3911

 1 5.2299

 1.5 7.038

 2 8.5614

 3 11.1757

 4 13.44

 5 15.429

 6 17.538

 8 21.645

 10 25.52

# DE35 DF35

 0.01 0.0608

 0.015 0.8346

 0.02 1.0553

 0.03 0.8129

 0.04 0.64386

 0.05 0.54776

 0.06 0.50808

 0.08 0.52976
Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 62 of 68

 0.1 0.6138

 0.15 0.894

 0.2 1.1984

 0.3 1.8078

 0.4 2.3814

 0.5 2.9274

 0.6 3.4364

 0.8 4.3911

 1 5.2299

 1.5 7.038

 2 8.5614

 3 11.1757

 4 13.44

 5 15.429

 6 17.538

 8 21.645

 10 25.52

nps 1E10

ATTACHMENT B

DOSE MODELS

Page 35 of 35
Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 63 of 68

This model was repeated for each measurement point using the values listed in Attachment A as the 

source spectrum.

MCNPX Visual Editor Version X_24E

C Created on: Monday, May 20, 2013 at 14:25 

C Savannah River Dosimeter Badge PHOTON VERSION 

C 

C 

C *** Film *** ( 7 Cell)

 21 2 -1.4 21 -22 23 -24 46 -49 $ Film (Pb region)

 22 2 -1.4 21 -22 23 -25 45 -46 $ Film (Ag)

 23 2 -1.4 21 -22 25 -24 45 -46 $ Film (Air)

 24 2 -1.4 21 -22 23 -25 44 -45 $ Film (Al)

 25 2 -1.4 21 -22 25 -24 44 -45 $ Film (Nylon)

 28 9 -1.39 31 -21 23 -24 44 -49 $ Front Mylar

 29 9 -1.39 22 -32 23 -24 44 -49 $ Back Mylar

C 

C *** Front Filter Set (9 cells) 

 31 252 -11.35 33 -31 23 -24 46 -49 $ Front Filter (Pb)

 32 7 -10.5 33 -31 23 -25 45 -46 $ Front Filter (Ag)

 33 204 -0.001205 33 -31 25 -24 45 -46 $ Front Open Filter (Air)

 34 208 -2.6989 33 -31 23 -25 44 -45 $ Front Filter (Al)

 35 4 -1.14 33 -31 25 -24 44 -45 $ Front Filter (Nylon)

 36 204 -0.001205 35 -33 23 -24 $ Air Volume Above Additional Al thickness

 45 -49

 37 204 -0.001205 35 -33 25 -24 $ Air Volume Beside additional Al thickness

 44 -45

 38 208 -2.6989 35 -33 23 -25 44 -45 $ Additional 1 mm Al thickness

 39 3 -1.42 37 -35 23 -24 44 -49 $ Plastic Identification Cover

C 

C *** Back Filter Set (9 cells) 

 41 252 -11.35 32 -34 23 -24 46 -49 $ Front Filter (Pb)

 42 7 -10.5 32 -34 23 -25 45 -46 $ Front Filter (Ag)

 43 204 -0.001205 32 -34 25 -24 45 -46 $ Front Open Filter (Air)

 44 208 -2.6989 32 -34 23 -25 44 -45 $ Front Filter (Al)

 45 4 -1.14 32 -34 25 -24 44 -45 $ Front Filter (Nylon)

 46 204 -0.001205 34 -36 23 -24 $ Air Volume Above Additional Al thickness

 45 -49

 47 204 -0.001205 34 -36 25 -24 $ Air Volume Beside additional Al thicknes

 44 -45

 48 208 -2.6989 34 -36 23 -25 44 -45 $ Additional 1 mm Al thickness

 49 3 -1.42 36 -38 23 -24 44 -49 $ Plastic Identification Cover 

C 

C *** Dosimeter Cover (Plastic) (4 Cells)

 52 4 -1.14 37 -38 23 -24 51 -44 $ Dosimeter Bottom

 53 4 -1.14 37 -38 23 -24 49 -52 $ Dosimeter Top

 54 4 -1.14 37 -38 24 -27 51 -52 $ Dosimeter Right Side

 55 4 -1.14 37 -38 26 -23 51 -52 $ Dosimeter Left Side

C 

C *** Modifier Cells (2 Cells) 

 61 8 -1.19 -61 $ PMMA Phantom

C 

C *** Outer Boundaries *** (2 Cells)

ATTACHMENT C

FILM BADGE MODEL

Page 1 of 6
Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 64 of 68

 

 98 204 -0.001205 (-37 :38 :-26 :27 :-51 :52 )61 -89 $ Air Volume

 99 0 89 $ Outside Universe

C ********* Surface Cards 

C *** Film Thickness 

 21 px -0.0019 

 22 px 0.0019 

C 

C *** Savannah Dosimeter y-axis planes 

 23 py -1.5 $ Film left boundary

 24 py 1.5 $ Film right boundary

 25 py 0 $ Film centerline

 26 py -1.75 $ Dosimeter left boundary

 27 py 1.75 $ Dosimeter right boundary 

C 

C *** Savannah Dosimeter x-axis Layers 

 31 px -0.0034 $ Front Mylar

 32 px 0.0034 $ Back Mylar

 33 px -0.1034 $ Front Filter (1 mm)

 34 px 0.1034 $ Back Filter (1 mm)

 35 px -0.2034 $ Additional Filter layer for Al (Front)

 36 px 0.2034 $ Additional Filter layer for Al (Back)

 37 px -0.3034 $ Badge Identification plate

 38 px 0.3034 $ Back of Badge

C 

C *** Savannah Dosimeter z axis planes 

 44 pz -2 $ Lower Boundary of Filter Set

 45 pz -1 $ Mid boundary of filter set

 46 pz 0 $ Separation between filter set and Pb Identification

 49 pz 2 $ Upper boundary of Pb identification

 51 pz -2.25 $ Lower boundary of dosimeter

 52 pz 4.75 $ Upper boundary of dosimeter 

C 

C PMMA Phantom 

 61 rpp 0.4034 15.4034 -15 15 -15 15 $ PMMA Phantom

C 

 89 so 30 $ Outer Air Sphere 

C Data Cards 

C 

C ********* Material Cards 

C *** Dry Air: Density = 1.205e-3 g/cc (ICRU 37, 1984) 

m204 7000 -0.755636 $air (US S. Atm at sea level)

 8000 -0.231475 

 18000 -0.012889 

C 

C *** Aluminum (Al) p=2.6989 g/cm3 

m208 13000 -1 $aluminum 

ATTACHMENT C

FILM BADGE MODEL

Page 2 of 6
Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 65 of 68

C 

C *** Lead (Pb) 11.35 g/cm3 

m252 82000 -1 $lead

C 

C *** Silver (Ag) p=10.50 (Natural) 

m7 47000 -1 $silver 

C 

C *** PMMA *** (Lucite) 

m8 1000 -0.080538 $PMMA

 6000 -0.599848 

 8000 -0.319614 

C 

C *** Alumized Mylar p=1.39g/cm3 

m9 1000 -0.03679458 $aluminized mylar

 6000 -0.5480593 

 8000 -0.2920269 

 13000 -0.1231192 

C 

C *** Cellulose p=1.42 g/cc 

m3 1000 -0.062162 $cellulose

 6000 -0.444462 

 8000 -0.493376 

C 

C *** DuPont Type 555 film emulsion, density = 1.4 

m2 1000 -0.0952 $H

 6000 -0.707 $C

 7000 -0.238 $N

 8000 -0.3528 $O

 35000 -0.3926 $Br

 47000 -0.53 $Ag 

C 

C *** Nylon (Plastic) 1.14 g/cm3 

m4 1000 -0.097976 $Nylon (plastic)

 6000 -0.636856 

 7000 -0.123779 

 8000 -0.141389 

mode p e 

C

C Importances, using a multiplier of 2 between layers approaching film

C

imp:p

 32 $ Cell 21, Film (Pb region)

 32 $ Cell 22, Film (Ag region)

 32 $ Cell 23, Film (Air region)

 32 $ Cell 24, Film (Al region)

 32 $ Cell 25, Film (Nylon region)

 16 $ Cell 28, Front Mylar

 16 $ Cell 29, Back Mylar

 8 $ Cell 31, Front Filter (Pb)

 

ATTACHMENT C

FILM BADGE MODEL

Page 3 of 6
Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 66 of 68

 8 $ Cell 32, Front Filter (Ag)

 8 $ Cell 33, Front Open Filter (Air)

 8 $ Cell 34, Front Filter (Al)

 8 $ Cell 35, Front Filter (Nylon)

 4 $ Cell 36, Air Volume Above Additional Al thickness

 4 $ Cell 37, Air Volume Beside additional Al thickness

 4 $ Cell 38, Additional 1 mm Al thickness

 2 $ Cell 39, Plastic Identification Cover

 8 $ Cell 41, Front Filter (Pb)

 8 $ Cell 42, Front Filter (Ag)

 8 $ Cell 43, Front Open Filter (Air)

 8 $ Cell 44, Front Filter (Al)

 8 $ Cell 45, Front Filter (Nylon)

 4 $ Cell 46, Air Volume Above Additional Al thickness

 4 $ Cell 47, Air Volume Beside additional Al thickness

 4 $ Cell 48, Additional 1 mm Al thickness

 2 $ Cell 49, Plastic Identification Cover

 1 $ Cell 52, Dosimeter Bottom

 1 $ Cell 53, Dosimeter Top

 1 $ Cell 54, Dosimeter Right Side

 1 $ Cell 55, Dosimeter Left Side

 1 $ Cell 61, PMMA Phantom

 1 $ Cell 98, Air Volume

 0 $ Cell 99, Outside Universe 

C 

C Source, as flat plane directly in front of badge

C

sdef pos -0.5 0 0 

 rad=d4 $ Starting position, radius for disk

 axs -1 0 0 

 ext=0.0 $ disk source is a cylinder source w/ 0.0 extent

 vec 1 0 0 $ Starting direction for particles

 dir=1.0 

 erg=D10 $ Use spectra from Geometry runs

si4 H 0.0 4 $ Disk from zero to 2.5 cm

sp4 -21 1 $ Power Law, power=1 for disk (area) source

# si10 sp10 $ energy dist. in MeV

 H D $ energy bins then prob.

 0 0

 0.010 2.40699E-17

 0.020 1.83079E-16

 0.030 1.06860E-14

 0.040 5.38261E-14

 0.050 8.88216E-14

 0.060 1.04498E-13

 0.070 1.05721E-13

 0.080 9.86906E-14

 0.090 8.55548E-14

 0.100 7.87470E-14

 

ATTACHMENT C

FILM BADGE MODEL

Page 4 of 6
Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 67 of 68

 0.110 6.40245E-14

 0.120 5.59481E-14

 0.130 4.85688E-14

 0.140 3.98014E-14

 0.150 3.58915E-14

 0.160 3.22578E-14

 0.170 2.97443E-14

 0.180 2.59220E-14

 0.190 2.36927E-14

 0.200 1.96994E-14

 0.210 1.84759E-14

 0.220 1.73283E-14

 0.230 1.69887E-14

 0.240 1.55532E-14

 0.250 1.53104E-14

 0.300 6.66064E-14

 0.350 5.06615E-14

 0.400 4.93796E-14

 0.450 3.62498E-14

 0.500 3.44993E-14

 0.600 6.11587E-14

 0.700 2.51803E-14

 0.800 1.49166E-14

 0.900 2.07992E-15

 1.000 3.54375E-15

 1.100 1.98845E-15

 1.200 1.52424E-15

 1.300 9.79980E-16

 1.400 9.43520E-16

 1.500 7.79964E-16

 1.600 5.92042E-16

 1.700 2.58030E-16

 1.800 2.37523E-16

 1.900 1.39327E-16

 2.000 1.04503E-16

 2.100 1.80974E-16

 2.200 2.29078E-15

C 

C Tallys 

C 

f6:e 21 

fm6 1.602E-10 $ convert (MeV per g) to J per kg 

fc6 Pb Region, J/kg per source photon 

C 

f16:e 22 

fm16 1.602E-10 $ convert (MeV per g) to J per kg 

fc16 Ag Region, J/kg per source photon 

C 

f26:p 23 

ATTACHMENT C

FILM BADGE MODEL

Page 5 of 6
Document No. ORAUT-RPRT-0062 Revision No. 00 Effective Date: 02/11/2014 Page 68 of 68

fm26 1.602E-10 $ convert (MeV per g) to J per kg 

fc26 Air Region, J/kg per source photon 

C 

f36:e 24 

fm36 1.602E-10 $ convert (MeV per g) to J per kg 

fc36 Al Region, J/kg per source photon 

C 

f46:e 25 

fm46 1.602E-10 $ convert (MeV per g) to J per kg 

fc46 Nylon Region, J/kg per source photon 

C 

C

nps 1E8

ATTACHMENT C

FILM BADGE MODEL

Page 6 of 6