ML26050A487

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006 Comparing Dose Rates for Carbon Vs Stainless Steel Ccc
ML26050A487
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Site: 07109218, 07109279
Issue date: 02/19/2026
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Salado Isolation Mining Contractors (SIMCO) LLC
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Office of Nuclear Material Safety and Safeguards
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CCO-CAL-0006 List:
References
TS:26:03002 CCO-CAL-0006
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Calculation Cover Sheet

1. Document

Title:

Comparing Dose Rates for Carbon vs. Stainless Steel CCC

2. System Number:

PT01

2. Document Number:

CCO-CAL-0006

3. Document Revision:

0

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5. Summary Description This calculation evaluates the Criticality Control Component (CCC), the confinement boundary for the Criticality Control Overpack (CCO), to determine the effect on dose rates when comparing a CCC optionally fabricated entirely of carbon steel versus the certified CCC fabricated entirely of stainless steel. This evaluation considers normal conditions of transport (NCT) regulatory dose rate limits under exclusive use requirements, i.e., dose rates at the surface of the TRUPACT-II and HalfPACT packages, and 2 meters from the surface of the packages.
7. Software Usage Software Name Version
1. MCNP6 6.2.0
2. Microsoft Excel 2016
3.
4.
5.
8. Preparer Name Signature Date Steve Porter
9. Independent Reviewer(s)

Name Signature Date Kyle Moyant

10. Project Representative Name Signature Date Michael Lastra
11. QA Representative Name Signature Date Steve Tanner Digitally signed by STEVEN PORTER (Affiliate)

Date: 2022.08.01 08:53:40 -07'00' KYLE MOYANT (Affiliate)

Digitally signed by KYLE MOYANT (Affiliate)

Date: 2022.08.01 12:27:00 -06'00' MICHAEL LASTRA (Affiliate)

Digitally signed by MICHAEL LASTRA (Affiliate)

Date: 2022.08.03 11:45:11 -06'00' David S. Tanner Digitally signed by David S. Tanner Date: 2022.08.03 17:00:52 -06'00'

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2 of 30 TABLE OF CONTENTS

1.0 INTRODUCTION

................................................................................................................... 4

2.0 DESCRIPTION

OF SHIELDING DESIGN........................................................................ 5 2.1 TRUPACT-II and HalfPACT Packagings............................................................................. 5 2.2 Criticality Control Overpack.................................................................................................. 5 3.0 SOURCE SPECIFICATION................................................................................................. 9 3.1 Gamma Source....................................................................................................................... 9 3.2 Neutron Source...................................................................................................................... 9 4.0 SHIELDING MODELS....................................................................................................... 10 4.1 Configuration of Source and Shielding................................................................................ 10 4.1.1 TRUPACT-II and HalfPACT Package Models............................................................. 10 4.1.2 CCO Model.................................................................................................................... 10 4.2 Material Properties............................................................................................................... 15 5.0 SHIELDING EVALUATION.............................................................................................. 16 5.1 Methods................................................................................................................................ 16 5.2 Input and Output Data.......................................................................................................... 16 5.3 Flux-to-Dose Conversion..................................................................................................... 17 5.4 External Radiation Levels.................................................................................................... 18 5.5 Summary.............................................................................................................................. 20 6.0 APPENDICES....................................................................................................................... 21 6.1 MCNP Input Files................................................................................................................ 22 6.1.1 TRUPACT-II Package Models...................................................................................... 22 6.1.2 HalfPACT Package Models........................................................................................... 27 LIST OF TABLES Table 4 Summary of Shield Regional Densities......................................................................15 Table 5 CCO Case Naming Conventions for a Carbon Steel CCC.........................................17 Table 5 Neutron Flux-to-Dose Rate Conversion Factors from ANSI/ANS 6.1.1-1977..........17 Table 5 Gamma Flux-to-Dose Rate Conversion Factors from ANSI/ANS 6.1.1-1977..........18

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3 of 30 Table 5 TRUPACT-II - Carbon vs. Stainless Steel CCC Comparison...................................19 Table 5 HalfPACT - Carbon vs. Stainless Steel CCC Comparison........................................19 LIST OF FIGURES Figure 2 TRUPACT-II Packaging Configuration.....................................................................6 Figure 2 HalfPACT Packaging Configuration..........................................................................7 Figure 2 Criticality Control Overpack.......................................................................................8 Figure 4 MCNP Model of the TRUPACT-II with 14 CCCs (Side View)..............................11 Figure 4 MCNP Model of the TRUPACT-II with 14 CCCs (Top View)...............................12 Figure 4 MCNP Model of the HalfPACT with 7 CCCs (Side View).....................................13 Figure 4 MCNP Model of the HalfPACT with 7 CCCs (Top View)......................................14 TABLE OF REVISIONS Revision Number Pages Affected Revision Description 0

All New Issue

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1.0 INTRODUCTION

The TRUPACT-II and HalfPACT package licenses are planned for revision to authorize the optional use of carbon steel to fabricate the Criticality Control Component (CCC) of the Criticality Control Overpack (CCO). The purpose of this calculation is to determine the increase in dose rate for a carbon steel CCC compared to a stainless steel CCC, if any, for both gamma and neutron emitters, to meet normal conditions of transport (NCT) regulatory dose rate requirements under exclusive use shipping requirements. Based on previous analyses,1 hypothetical accident condition (HAC) dose rate analyses have been extensively shown to be less restrictive than NCT dose rate analyses and are, therefore, not considered in this calculaton.

This calculation documents the shielding analyses for the TRUPACT-II package carrying 14 CCC assemblies, and for the HalfPACT package carrying 7 CCC assemblies, utilizing a concentrated 60Co gamma and a 252Cf neutron source; related CCO components are ignored for the purpose of this calculation. NCT dose rates per 10 CFR §71.472 are calculated at the surface of the TRUPACT-II and HalfPACT packages, and at 2 meters from the package surfaces, utilizing the models that were used for the original CCO payload-based TRUPACT-II and HalfPACT package shielding analyses.1 1 B. A. Day, TRUPACT-II and HalfPACT Shielding Analysis, CHG-CAL-0001, Rev. 4, Nuclear Waste Partnership LLC, Carlsbad, NM, January 2021.

2 Title 10, Code of Federal Regulations, Part 71 (10 CFR 71), Packaging and Transportation of Radioactive Material, 01-01-21 Edition.

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2.0 DESCRIPTION

OF SHIELDING DESIGN 2.1 TRUPACT-II and HalfPACT Packagings The TRUPACT-II and HalfPACT packagings are not designed to provide significant gamma or neutron shielding. The packagings are comprised of an outer confinement assembly (OCA) that provides both free drop and thermal protection, and an inner containment vessel (ICV) that provides the containment boundary. Two aluminum honeycomb spacer assemblies are used within the ICV, one inside each ICV torispherical head to attenuate impact loads. The only significant difference between the TRUPACT-II and HalfPACT packagings is their height (length); the HalfPACT packaging is 30 inches shorter than the TRUPACT-II packaging (443/4 vs.

743/4 payload cavity height). A complete description of the two packagings is provided in the TRUPACT-II and HalfPACT Safety Analysis Reports (SARs).3,4 As illustrated in Figure 2-1 and Figure 2-2, the principal shielding characteristic of these two packagings is associated with the structural materials of the containment boundary and protective overpack. The packagings utilize two relatively thin confinement/containment vessels with shell thicknesses of 3/16 and 1/4 inch. Torispherical head thicknesses are all 1/4 inch. Both the ICV and outer confinement vessel (OCV) shells and heads are constructed of Type 304 stainless steel.

7KH,&9KDVDLQFKLQVLGHGLDPHWHU:LWKD-LQFKLQVLGHGLDPHWHU-inch outside diameter, and 1211/2-inch overall height for the TRUPACT-II packaging (911/2-inch overall height for the HalfPACT packaging), the OCA is completely encased in polyurethane foam with a density of approximately 81/4 lb/ft3. The outer shell of the OCA is comprised of 1/4-to-3/8-inch thick, Type 304, stainless steel that serves to protect the polyurethane foam from damage encountered during normal handling and shipping operations.

Under NCT, material and distance attenuation credit is taken for the TRUPACT-II and HalfPACT packaging ICV, OCV, and OCA shells and heads and polyurethane foam.

2.2 Criticality Control Overpack As illustrated in Figure 2-3, the CCO is an approximately 24-inch diameter, 35-inch tall steel 55-gallon drum with a steel CCC, and plywood upper and lower dunnage assemblies. The CCC is constructed of 304/304L stainless steel (or carbon steel), 6-inch Class 150 standard blind (1.0-inch flange thickness), and slip flanges and Schedule 40 pipe (0.28-inch wall thickness).

The lid of the CCC is sealed with an aramid-inorganic/nbr standard ring gasket and heavy hex head steel bolts.

Under NCT, material and distance attenuation credit is taken for the CCC components, but only distance attenuation is credited for the 55-gallon drum and dunnage assemblies.

3 U.S. Department of Energy, Safety Analysis Report for the TRUPACT-II Shipping Package, Rev. 25, USNRC Certificate of Compliance 71-9218, U.S. Department of Energy, Carlsbad Field Office, Carlsbad, New Mexico.

4 U.S. Department of Energy, HalfPACT Safety Analysis Report, Rev. 8, USNRC Certificate of Compliance 71-9279, U.S. Department of Energy, Carlsbad Area Office, Carlsbad, New Mexico.

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6 of 30 Figure 2 TRUPACT-II Packaging Configuration

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7 of 30 Figure 2 HalfPACT Packaging Configuration

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8 of 30 Figure 2 Criticality Control Overpack

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9 of 30 3.0 SOURCE SPECIFICATION The gamma and neutron source terms are taken directly from Section 5.2 of the TRUPACT-II SAR.3 3.1 Gamma Source The concentrated gamma source utilized for evaluation of the CCO payloads is 60Co with the following photon energies and associated intensities:

Radionuclide Photon Energy (MeV)

Intensity (%)

60Co 3.469300E-01 7.600000E-03 8.262800E-01 7.600000E-03 1.173237E+00 9.997360E+01 1.332501E+00 9.998560E+01 2.158770E+00 1.110000E-03 2.505000E+00 2.000000E-06 3.2 Neutron Source The concentrated neutron source utilized for evaluation of the CCO payloads is 252Cf (D/n plus spontaneous fission), as a function of energy per gram of material, is provided below:

Radionuclide Neutron Energy Interval (MeV)

Neutron Source Strength (n/s/g) 252Cf 0.0 - 0.1 0.00E+00 0.1 - 0.5 1.80E+11 0.5 - 1.0 2.71E+11 1.0 - 2.0 5.36E+11 2.0 - 3.0 4.10E+11 3.0 - 4.0 2.73E+11 4.0 - 6.0 2.66E+11 6.0 - 8.0 8.53E+10 8.0 - 10.0 2.44E+10 10.0 - 15.0 8.36E+09

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10 of 30 4.0 SHIELDING MODELS The shielding models and associated materials are a copy of what is used in Section 5.3 of the TRUPACT-II SAR.3 4.1 Configuration of Source and Shielding 4.1.1 TRUPACT-II and HalfPACT Package Models Damage to the packagings under NCT conditions is negligible, so the SAR drawing dimensions for the packagings are utilized. The torispherical ICV/OCV and OCA heads are treated as flat plates to maintain the TRUPACT-II overall packaging height of 1201/2 inches, and the HalfPACT overall packaging height of 901/2 inches. The inside diameter of the 1/4-inch thick ICV shell is modeled as Ø72 inches. Eliminating the gap between the ICV and OCV shells and combining the ICV shell with the 3/16-inch thick OCV shell results in an ICV/OCV outside diameter of

Ø731/2 inches. Rigid urethane foam with a density of 81/4 lb/ft3 is modeled between the ICV/OCV and OCA shells. The outside diameter of the 1/4-inch thick OCA outer shell is modeled as Ø94 inches. The aluminum honeycomb end spacers are not explicitly modeled, but credit for the spacing provided by the honeycomb ensures that the radial package dose rates are the most limiting. Due to the greater material thickness of the ICV/OCV/OCA heads (as compared to the radial shells) and axial distances to detectors, only radial shielding configurations and dose rates are necessarily evaluated.

4.1.2 CCO Model The TRUPACT-II and HalfPACT package models with a CCO payload utilize the package dimensions and materials discussed in Section 4.1.1, TRUPACT-II and HalfPACT Package Models. The CCO models are illustrated in Figure 4-1 through Figure 4-4. A 1 inch stub-cylinder source (i.e., 1-inch diameter x 1-inch long) is modeled at the center of each CCO payload cavity.

Damage to the CCOs under NCT conditions is negligible, so the SAR drawing dimensions for the CCO are utilized. The array spacing provided by the CCO drum is utilized to spatially locate the CCCs within the TRUPACT-II and HalfPACT package models. Each CCC is centered within the CCO drum, and the 0.28-inch thick CCC body shell and 1.00-inch thick base and lid are credited for material attenuation. The CCC body shell is modeled with a 6-inch outside diameter. The CCC is modeled with a 26.943-inch cavity height. The plywood upper and lower dunnage components are credited for centering the CCC within the CCO, but no credit is taken for material attenuation of the plywood, nor for the steel 55-gallon drum. Due to the greater material thickness of the CCC lid/base (as compared to the body shell) and axial distances to detectors, only radial shielding configurations and dose rates are necessarily evaluated.

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11 of 30 Figure 4 MCNP Model of the TRUPACT-II with 14 CCOs (Side View)

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12 of 30 Figure 4 MCNP Model of the TRUPACT-II with 14 CCOs (Top View)

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13 of 30 Figure 4 MCNP Model of the HalfPACT with 7 CCOs (Side View)

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14 of 30 Figure 4 MCNP Model of the HalfPACT with 7 CCOs (Top View)

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15 of 30 4.2 Material Properties The shielding models are comprised of plain carbon steel, Type 304 stainless steel, and rigid urethane foam; with material densities of 490 lb/ft³ (7.8526 g/cc), 500 lb/ft³ (8.0128 g/cc), and 8.25 lb/ft3 (0.1322 g/cc), respectively. Table 4-1 summarizes the shield regional densities for each of these attenuating materials. Zirconium is modeled in the source region at 1.0 g/cc to represent a conservative basis for self-shielding of the concentrated 1-inch stub-cylinder source.5 Table 4 Summary of Shield Regional Densities Element Zirconium (Source)

Carbon Steel Type 304 Stainless Steel Rigid Urethane Foamc Percent Partial Density (g/cc) Percent Partial Density (g/cc) Percent Partial Density (g/cc) Percent Partial Density (g/cc)

Hydrogen 7%

0.0093 Carbon 60%

0.0793 Nitrogen 8%

0.0106 Oxygen 24%

0.0317 Silicon 1%

0.0801 1%

0.0013 Chromium 19%

1.5224 Manganese 2%

0.1603 Iron 100%

7.8526 68%

5.4487 Nickel 10%

0.8013 Zirconium 100%

1.0000 Total 100%

1.0000 100%

7.8526 100%

8.0128 100%

0.1322 Notes:

c Weight percent from chemical composition (median of range) from Section 8.1.4.1.1.1, Polyurethane Foam Chemical Composition, of the TRUPACT-II SAR.3 5 Nuclear Waste Partnership, Self-shielding Surrogate Material Evaluation for TRUPACT-II and HalfPACT, CHG-CAL-0002, Rev. 0, September 2012.

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16 of 30 5.0 SHIELDING EVALUATION 5.1 Methods MCNP6 v6.2.0 is used for the shielding analysis of the carbon steel CCCs.6 MCNP6 is a standard, well-accepted shielding program utilized to compute dose rates for shielding licenses.

The existing three-dimensional shielding models used to certify the stainless steel CCCs per Chapter 5 of the TRUPACT-II SAR3 capture all of the relevant design parameters of the TRUPACT-II and HalfPACT packagings and the associated CCC configurations. The only changes made to the existing shielding models was to add carbon steel as a material and change the material reference for the CCCs from stainless to carbon steel. Otherwise, the model files are identical. Dose rate results for the stainless steel CCCs are taken from Tables 5.4-7 and 5.4-8 of the TRUPACT-II SAR.

Dose rates are calculated by tallying the gamma and neutron fluxes at regions of interest and converting these fluxes to dose rates. The models are run in either photon or neutron mode, depending upon the radionuclide being evaluated.

As discussed in the original calculation,1 combined photon/neutron mode evaluations are not employed for the neutron analyses as multiple test runs demonstrate that the gamma dose rate due to the interaction of neutrons in the shielding materials contributes a statistically insignificant

(<1%) change in the dose rate as compared to the neutron dose rate. The gamma energies and intensities for 252Cf are similarly ignored based on the same logic.

5.2 Input and Output Data Two input/output cases are used to generate the results for each TRUPACT-II and HalfPACT packaging/payload combination. Case naming conventions are defined in Table 5-1.

The carbon steel CCC input files are provided in Appendix 6.1, MCNP Input Files. Output files are too large for inclusion in the report, so they are provided on supplemental storage media. All cases are run with a one (1) particle/second (par/s) source.

6 LA-UR-17-29981, MCNP Users Manual, Code Version 6.2, Rev. 0; Los Alamos National Laboratory, October 27, 2017.

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17 of 30 Table 5 CCO Case Naming Conventions for a Carbon Steel CCC Case Name Description Case Name Variable, X Packaging / Payload Xng001c Gamma, 60Co, NCT c

TRUPACT-II / CCO Xnn001c Neutron, 252Cf, NCT d

HalfPACT / CCO File Extension Definitions Input File =.i Output File =.o Runtpe File =.r Tally File =.m 5.3 Flux-to-Dose Conversion ANSI/ANS-6.1.1-1977 flux-to-dose-rate conversion factors are utilized for both neutron and gamma radiation. These factors are provided in Table 5-2 and Table 5-3.

Table 5 Neutron Flux-to-Dose Rate Conversion Factors from ANSI/ANS 6.1.1-1977 n-Energy (MeV)

DFg(E)

(n/cm²-s to mrem/hr)

Quality Factor n-Energy (MeV)

DFg(E)

(n/cm²-s to mrem/hr)

Quality Factor 2.50E-08 3.67E-03 2.0 5.00E-01 9.26E-02 11.0 1.00E-07 3.67E-03 2.0 1.00E+00 1.32E-01 11.0 1.00E-06 4.46E-03 2.0 2.50E+00 1.25E-01 9.0 1.00E-05 4.54E-03 2.0 5.00E+00 1.56E-01 8.0 1.00E-04 4.18E-03 2.0 7.00E+00 1.47E-01 7.0 1.00E-03 3.76E-03 2.0 1.00E+01 1.47E-01 6.5 1.00E-02 3.56E-03 2.5 1.40E+01 2.08E-01 7.5 1.00E-01 2.17E-02 7.5 2.00E+01 2.27E-01 8.0

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18 of 30 Table 5 Gamma Flux-to-Dose Rate Conversion Factors from ANSI/ANS 6.1.1-1977 J-Energy (MeV)

DFg(E)

(J/cm²-s to mrem/hr)

J-Energy (MeV)

DFg(E)

(J/cm²-s to mrem/hr) 0.01 3.96E-03 1.40 2.51E-03 0.03 5.82E-04 1.80 2.99E-03 0.05 2.90E-04 2.20 3.42E-03 0.07 2.58E-04 2.60 3.82E-03 0.10 2.83E-04 2.80 4.01E-03 0.15 3.79E-04 3.25 4.41E-03 0.20 5.01E-04 3.75 4.83E-03 0.25 6.31E-04 4.25 5.23E-03 0.30 7.59E-04 4.75 5.60E-03 0.35 8.78E-04 5.00 5.80E-03 0.40 9.85E-04 5.25 6.01E-03 0.45 1.08E-03 5.75 6.37E-03 0.50 1.17E-03 6.25 6.74E-03 0.55 1.27E-03 6.75 7.11E-03 0.60 1.36E-03 7.50 7.66E-03 0.65 1.44E-03 9.00 8.77E-03 0.70 1.52E-03 11.00 1.03E-02 0.80 1.68E-03 13.00 1.18E-02 1.00 1.98E-03 15.00 1.33E-02 5.4 External Radiation Levels The MCNP6 models for determining external radiation levels use segmented surface detectors to calculate the radial dose rates at the surface of the TRUPACT-II and HalfPACT package, and at 2 meters from the surface of the TRUPACT-II and HalfPACT packages for NCT. The detectors are axially aligned with the centerline halfway between the sources in the lower and upper CCCs for the TRUPACT-II package, and axially aligned with the sources for the HalfPACT package to report the maximum dose rate.

Dose rates and the associated statistical uncertainty (i.e., tally error) are computed based on a 1 par/s source strength. Conservatively accounting for the tally error, dose rates at the surface of

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19 of 30 the packages and two meters from the surface of the package are compared for the optional carbon steel CCCs versus the certified stainless steel CCCs.

The dose rates and tally errors computed for 14 CCCs within a TRUPACT-II package, and 7 CCCs within a HalfPACT package with concentrated gamma and neutron sources having a 1 par/s source strength, are provided in Table 5-4 and Table 5-5, respectively. The stainless steel CCC results come from Table 5.4-7 and Table 5.4-8 of the TRUPACT-II SAR.3 Table 5 TRUPACT-II - Carbon vs. Stainless Steel CCC Comparison Stainless Steel (SS) CCCs Carbon Steel (CS) CCCs Dose Rate Change CS vs. SS NCT Tally Location Calculated Dose Rate (mrem/hr

/ par/s)

Tally Error Adjusted Dose Rate (mrem/hr

/ par/s)

Calculated Dose Rate (mrem/hr

/ par/s)

Tally Error Adjusted Dose Rate (mrem/hr

/ par/s)

Results for 60Co Gamma Sources Surface 5.78E-09 0.2%

5.79E-09 5.82E-09 0.2%

5.83E-09

+0.69%

2-Meters 8.31E-10 0.2%

8.33E-10 8.36E-10 0.2%

8.38E-10

+0.60%

Results for 252Cf Neutron Sources Surface 5.69E-07 0.2%

5.70E-07 5.70E-07 0.2%

5.71E-07

+0.18%

2-Meters 7.56E-08 0.2%

7.58E-08 7.59E-08 0.2%

7.61E-08

+0.40%

Table 5 HalfPACT - Carbon vs. Stainless Steel CCC Comparison Stainless Steel (SS) CCCs Carbon Steel (CS) CCCs Dose Rate Change CS vs. SS NCT Tally Location Calculated Dose Rate (mrem/hr

/ par/s)

Tally Error Adjusted Dose Rate (mrem/hr

/ par/s)

Calculated Dose Rate (mrem/hr

/ par/s)

Tally Error Adjusted Dose Rate (mrem/hr

/ par/s)

Results for 60Co Gamma Sources Surface 8.48E-09 0.1%

8.49E-09 8.52E-09 0.1%

8.53E-09

+0.47%

2-Meters 8.51E-10 0.2%

8.53E-10 8.56E-10 0.2%

8.58E-10

+0.59%

Results for 252Cf Neutron Sources Surface 7.96E-07 0.2%

7.98E-07 7.96E-07 0.1%

7.97E-07

-0.13%

2-Meters 7.57E-08 0.2%

7.59E-08 7.60E-08 0.2%

7.61E-08

+0.26%

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20 of 30 5.5 Summary Based on the geometry, materials of construction, configuration of the TRUPACT-II and HalfPACT packagings, and configuration of the CCO assembly, the maximum 0.69% increase in dose rate for the optional carbon steel CCCs versus the certified stainless steel CCCs will necessitate increasing the 10% administrative margin discussed in Paragraph 10 of Section 5.5.10 of the TRUPACT-II SAR3. The increase is from 10% to 11 % to account for the aforementioned small dose rate increase for CCCs fabricated with the optional carbon steel, as well as any uncertainties associated with this evaluation. Thus, the combined sum of the sum of fractions for the gamma and the neutron source term shall be less than or equal to 0.89.

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21 of 30 6.0 APPENDICES 6.0 APPENDICES....................................................................................................................... 21 6.1 MCNP Input Files................................................................................................................ 22 6.1.1 TRUPACT-II Package Models...................................................................................... 22 6.1.1.1 Carbon Steel CCCs with 60Co Sources - cng001c.i.................................................22 6.1.1.2 Carbon Steel CCCs with 252Cf Sources - cnn001c.i.................................................24 6.1.2 HalfPACT Package Models........................................................................................... 27 6.1.2.1 Carbon Steel CCCs with 60Co Sources - dng001c.i.................................................27 6.1.2.2 Carbon Steel CCCs with 252Cf Sources - dnn001c.i.................................................29

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22 of 30 6.1 MCNP Input Files 6.1.1 TRUPACT-II Package Models 6.1.1.1 Carbon Steel CCCs with 60Co Sources - cng001c.i title TRUPACT-II CCO NCT Gamma Concentrated 1 g/cc Co60; CS CCC C

C Cell Cards C

1 1 -1 10 -11 -14 u=1 imp:p=1 $ Lower Source 2 4 -7.85260 30 -32 -34 (-31:33:35) u=1 imp:p=1 $ Lower CCC 3 0 31 -33 -35 (-10:11:14) u=1 imp:p=1 $ Lower CCC cavity 4 0 #1 #2 #3 u=1 imp:p=1 $ Lower Drum cavity 5 1 -1 20 -21 -24 u=2 imp:p=1 $ Upper Source 6 4 -7.85260 30 -32 -34 (-31:33:35) u=2 imp:p=1 $ Upper CCC 7 0 31 -33 -35 (-20:21:24) u=2 imp:p=1 $ Upper CCC cavity 8 0 #5 #6 #7 u=2 imp:p=1 $ Upper Drum cavity 11 0 50 -51 -52 trcl=1 fill=1 imp:p=1 $ CCO #1 12 0 50 -51 -52 trcl=2 fill=1 imp:p=1 $ CCO #2 13 0 50 -51 -52 trcl=3 fill=1 imp:p=1 $ CCO #3 14 0 50 -51 -52 trcl=4 fill=1 imp:p=1 $ CCO #4 15 0 50 -51 -52 trcl=5 fill=1 imp:p=1 $ CCO #5 16 0 50 -51 -52 trcl=6 fill=1 imp:p=1 $ CCO #6 17 0 50 -51 -52 trcl=7 fill=1 imp:p=1 $ CCO #7 18 0 50 -51 -52 trcl=8 fill=2 imp:p=1 $ CCO #8 19 0 50 -51 -52 trcl=9 fill=2 imp:p=1 $ CCO #9 20 0 50 -51 -52 trcl=10 fill=2 imp:p=1 $ CCO #10 21 0 50 -51 -52 trcl=11 fill=2 imp:p=1 $ CCO #11 22 0 50 -51 -52 trcl=12 fill=2 imp:p=1 $ CCO #12 23 0 50 -51 -52 trcl=13 fill=2 imp:p=1 $ CCO #13 24 0 50 -51 -52 trcl=14 fill=2 imp:p=1 $ CCO #14 200 0 210 -250 -230

  1. 11 #12 #13 #14 #15 #16 #17
  1. 18 #19 #20 #21 #22 #23 #24 imp:p=1 $ ICV cavity 210 2 -8.01280 200 -210 -220 imp:p=1 $ ICV/OCV bottom 220 2 -8.01280 250 -240 -220 imp:p=1 $ ICV/OCV top 230 2 -8.01280 210 -250 230 -220 imp:p=4 $ ICV/OCV shell 240 3 -0.13215 110 -150 -130 (-200:220:240) imp:p=8 $ OCA annulus 250 2 -8.01280 100 -110 -120 imp:p=1 $ OCA bottom 260 2 -8.01280 150 -140 -120 imp:p=1 $ OCA top 270 2 -8.01280 110 -150 130 -120 imp:p=16 $ OCA shell 777 0 120 -160 100 -140 imp:p=32 $ Outside to tally 888 0 -999 (-100:160:140) imp:p=8 $ Outside pkg 999 0 999 imp:p=0 $ Outside world C

C Geometry Cards C

10 pz 147.955 $ Lower Source bottom 11 pz 150.495 $ Lower Source top 14 c/z 0 0 1.27 $ Lower Source radius 20 pz 147.955 $ Upper Source bottom 21 pz 150.495 $ Upper Source top 24 c/z 0 0 1.27 $ Upper Source radius C

30 pz 112.467 $ CCC base (outside) 31 pz 115.007 $ CCC base (inside) 32 pz 185.983 $ CCC lid (outside) 33 pz 183.443 $ CCC lid (inside) 34 cz 8.414 $ CCC shell (outside) 35 cz 7.703 $ CCC shell (inside)

C 50 pz 104.775 $ Drum bottom 51 pz 193.675 $ Drum top 52 cz 30.48 $ Drum radius (outside)

C 100 pz 0 $ OCA bottom (outside) 110 pz 0.635 $ OCA bottom (inside) 120 cz 119.38 $ OCA shell (outside) 130 cz 118.745 $ OCA shell (inside) 140 pz 306.07 $ OCA top (outside) 150 pz 305.435 $ OCA top (inside) 160 cz 319.38 $ 2-meter from OCA C

Calculation Continuation Sheet

1. Document

Title:

Shielding Analysis Comparing Dose Rates for Carbon Steel vs. Stainless Steel CCC

2. Document Number:

CCO-CAL-0006

3. Document Revision:

0

4. Page:

23 of 30 200 pz 22.86 $ ICV/OCV bottom (outside) 210 pz 24.13 $ ICV/OCV bottom (inside) 220 cz 93.345 $ ICV/OCV shell (outside) 230 cz 92.234 $ ICV/OCV shell (inside) 240 pz 275.59 $ ICV/OCV top (outside) 250 pz 274.32 $ ICV/OCV top (inside)

C 777 pz 146.685 $ Ring tally (lower) 888 pz 151.765 $ Ring tally (upper) 999 sz 149.225 446.38 $ Outside world C

C Translation Cards C

  • tr1 0 0 -44.609
  • tr2 52.793 30.48 -44.609
  • tr3 0 60.96 -44.609
  • tr4 -52.793 30.48 -44.609
  • tr5 -52.793 -30.48 -44.609
  • tr6 0 -60.96 -44.609
  • tr7 52.793 -30.48 -44.609
  • tr8 0 0 44.609
  • tr9 52.793 30.48 44.609
  • tr10 0 60.96 44.609
  • tr11 -52.793 30.48 44.609
  • tr12 -52.793 -30.48 44.609
  • tr13 0 -60.96 44.609
  • tr14 52.793 -30.48 44.609 C

C Physics Cards C

mode p C

C Source Cards C

C Cylindrical Sources sdef pos=d1 erg=d2 par=2 axs=0 0 1 rad=d3 ext=d4 sc1 Co60 C Source Position and Fraction si1 L 0 0 104.616 52.793 30.48 104.616 0 60.96 104.616

-52.793 30.48 104.616

-52.793 -30.48 104.616 0 -60.96 104.616 52.793 -30.48 104.616 0 0 193.834 52.793 30.48 193.834 0 60.96 193.834

-52.793 30.48 193.834

-52.793 -30.48 193.834 0 -60.96 193.834 52.793 -30.48 193.834 sp1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 C Source Energy (MeV) and Intensity (%)

si2 L 3.469300E-01 8.262800E-01 1.173237E+00 1.332501E+00 2.158770E+00 2.505000E+00 sp2 7.600000E-03 7.600000E-03 9.997360E+01 9.998560E+01 1.110000E-03 2.000000E-06 C Source Radius si3 0 1.27 sp3 -21 1 C Source Extent si4 -1.27 1.27 sp4 -21 0 C

C Tally Cards C

f2:p 120 fc2 Surface Dose (mrem/hr) $ Surface detector fs2 888 777 t sd2 1.0 3810.44 1.0 1.0 $ Surface tally area f22:p 160 fc22 2-meter Dose (mrem/hr) $ 2-m detector fs22 888 777 t sd22 1.0 10194.144 1.0 1.0 $ Surface tally area C

C ANSI/ANS-6.1.1-1977 Gamma Flux to Dose Factors (mrem/hr) de0 1.0e-02 3.0e-02 5.0e-02 7.0e-02 1.0e-01 $ Energy (Mev) 1.5e-01 2.0e-01 2.5e-01 3.0e-01 3.5e-01 4.0e-01 4.5e-01 5.0e-01 5.5e-01 6.0e-01

Calculation Continuation Sheet

1. Document

Title:

Shielding Analysis Comparing Dose Rates for Carbon Steel vs. Stainless Steel CCC

2. Document Number:

CCO-CAL-0006

3. Document Revision:

0

4. Page:

24 of 30 6.5e-01 7.0e-01 8.0e-01 1.00 1.40 1.80 2.20 2.60 2.80 3.25 3.75 4.25 4.75 5.00 5.25 5.75 6.25 6.75 7.50 9.00 11.00 13.00 15.0000 df0 3.96e-03 5.82e-04 2.90e-04 2.58e-04 2.83e-04 $ Conversion (mrem/hr) 3.79e-04 5.01e-04 6.31e-04 7.59e-04 8.78e-04 9.85e-04 1.08e-03 1.17e-03 1.27e-03 1.36e-03 1.44e-03 1.52e-03 1.68e-03 1.98e-03 2.51e-03 2.99e-03 3.42e-03 3.82e-03 4.01e-03 4.41e-03 4.83e-03 5.23e-03 5.60e-03 5.80e-03 6.01e-03 6.37e-03 6.74e-03 7.11e-03 7.66e-03 8.77e-03 1.03e-02 1.18e-02 1.33e-02 C

C Material Cards C

m1 40000 -1.00 $ Zirconium m2 14000 -0.01 $ Stainless Steel 24000 -0.19 25000 -0.02 26000 -0.68 28000 -0.10 m3 6000 -0.60 $ Urethane Foam 7000 -0.08 8000 -0.24 1000 -0.07 14000 -0.01 m4 26000 -1.00 $ Carbon Steel (iron)

C C Runtime and Print Cards C

prdmp j j 1 2 ctme 30 6.1.1.2 Carbon Steel CCCs with 252Cf Sources - cnn001c.i title TRUPACT-II CCO NCT Neutron Concentrated 1 g/cc Cf252; CS CCC C

C Cell Cards C

1 1 -1 10 -11 -14 u=1 imp:n=1 $ Lower Source 2 4 -7.85260 30 -32 -34 (-31:33:35) u=1 imp:n=1 $ Lower CCC 3 0 31 -33 -35 (-10:11:14) u=1 imp:n=1 $ Lower CCC cavity 4 0 #1 #2 #3 u=1 imp:n=1 $ Lower Drum cavity 5 1 -1 20 -21 -24 u=2 imp:n=1 $ Upper Source 6 4 -7.85260 30 -32 -34 (-31:33:35) u=2 imp:n=1 $ Upper CCC 7 0 31 -33 -35 (-20:21:24) u=2 imp:n=1 $ Upper CCC cavity 8 0 #5 #6 #7 u=2 imp:n=1 $ Upper Drum cavity 11 0 50 -51 -52 trcl=1 fill=1 imp:n=1 $ CCO #1 12 0 50 -51 -52 trcl=2 fill=1 imp:n=1 $ CCO #2 13 0 50 -51 -52 trcl=3 fill=1 imp:n=1 $ CCO #3 14 0 50 -51 -52 trcl=4 fill=1 imp:n=1 $ CCO #4 15 0 50 -51 -52 trcl=5 fill=1 imp:n=1 $ CCO #5 16 0 50 -51 -52 trcl=6 fill=1 imp:n=1 $ CCO #6 17 0 50 -51 -52 trcl=7 fill=1 imp:n=1 $ CCO #7 18 0 50 -51 -52 trcl=8 fill=2 imp:n=1 $ CCO #8 19 0 50 -51 -52 trcl=9 fill=2 imp:n=1 $ CCO #9 20 0 50 -51 -52 trcl=10 fill=2 imp:n=1 $ CCO #10 21 0 50 -51 -52 trcl=11 fill=2 imp:n=1 $ CCO #11 22 0 50 -51 -52 trcl=12 fill=2 imp:n=1 $ CCO #12 23 0 50 -51 -52 trcl=13 fill=2 imp:n=1 $ CCO #13 24 0 50 -51 -52 trcl=14 fill=2 imp:n=1 $ CCO #14 200 0 210 -250 -230

  1. 11 #12 #13 #14 #15 #16 #17
  1. 18 #19 #20 #21 #22 #23 #24 imp:n=1 $ ICV cavity 210 2 -8.01280 200 -210 -220 imp:n=1 $ ICV/OCV bottom 220 2 -8.01280 250 -240 -220 imp:n=1 $ ICV/OCV top 230 2 -8.01280 210 -250 230 -220 imp:n=4 $ ICV/OCV shell 240 3 -0.13215 110 -150 -130 (-200:220:240) imp:n=8 $ OCA annulus 250 2 -8.01280 100 -110 -120 imp:n=1 $ OCA bottom 260 2 -8.01280 150 -140 -120 imp:n=1 $ OCA top 270 2 -8.01280 110 -150 130 -120 imp:n=16 $ OCA shell 777 0 120 -160 100 -140 imp:n=32 $ Outside to tally 888 0 -999 (-100:160:140) imp:n=8 $ Outside pkg 999 0 999 imp:n=0 $ Outside world C

C Geometry Cards C

Calculation Continuation Sheet

1. Document

Title:

Shielding Analysis Comparing Dose Rates for Carbon Steel vs. Stainless Steel CCC

2. Document Number:

CCO-CAL-0006

3. Document Revision:

0

4. Page:

25 of 30 10 pz 147.955 $ Lower Source bottom 11 pz 150.495 $ Lower Source top 14 c/z 0 0 1.27 $ Lower Source radius 20 pz 147.955 $ Upper Source bottom 21 pz 150.495 $ Upper Source top 24 c/z 0 0 1.27 $ Upper Source radius C

30 pz 112.467 $ CCC base (outside) 31 pz 115.007 $ CCC base (inside) 32 pz 185.983 $ CCC lid (outside) 33 pz 183.443 $ CCC lid (inside) 34 cz 8.414 $ CCC shell (outside) 35 cz 7.703 $ CCC shell (inside)

C 50 pz 104.775 $ Drum bottom 51 pz 193.675 $ Drum top 52 cz 30.48 $ Drum radius (outside)

C 100 pz 0 $ OCA bottom (outside) 110 pz 0.635 $ OCA bottom (inside) 120 cz 119.38 $ OCA shell (outside) 130 cz 118.745 $ OCA shell (inside) 140 pz 306.07 $ OCA top (outside) 150 pz 305.435 $ OCA top (inside) 160 cz 319.38 $ 2-meter from OCA C

200 pz 22.86 $ ICV/OCV bottom (outside) 210 pz 24.13 $ ICV/OCV bottom (inside) 220 cz 93.345 $ ICV/OCV shell (outside) 230 cz 92.234 $ ICV/OCV shell (inside) 240 pz 275.59 $ ICV/OCV top (outside) 250 pz 274.32 $ ICV/OCV top (inside)

C 777 pz 146.685 $ Ring tally (lower) 888 pz 151.765 $ Ring tally (upper) 999 sz 149.225 446.38 $ Outside world C

C Translation Cards C

  • tr1 0 0 -44.609
  • tr2 52.793 30.48 -44.609
  • tr3 0 60.96 -44.609
  • tr4 -52.793 30.48 -44.609
  • tr5 -52.793 -30.48 -44.609
  • tr6 0 -60.96 -44.609
  • tr7 52.793 -30.48 -44.609
  • tr8 0 0 44.609
  • tr9 52.793 30.48 44.609
  • tr10 0 60.96 44.609
  • tr11 -52.793 30.48 44.609
  • tr12 -52.793 -30.48 44.609
  • tr13 0 -60.96 44.609
  • tr14 52.793 -30.48 44.609 C

C Physics Cards C

mode n C

C Source Cards C

C Cylindrical Sources sdef pos=d1 erg=d2 par=1 axs=0 0 1 rad=d3 ext=d4 sc1 Cf252 C Source Position and Fraction si1 L 0 0 104.616 52.793 30.48 104.616 0 60.96 104.616

-52.793 30.48 104.616

-52.793 -30.48 104.616 0 -60.96 104.616 52.793 -30.48 104.616 0 0 193.834 52.793 30.48 193.834 0 60.96 193.834

-52.793 30.48 193.834

-52.793 -30.48 193.834 0 -60.96 193.834 52.793 -30.48 193.834 sp1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 C Source Energy (MeV) and Fraction

Calculation Continuation Sheet

1. Document

Title:

Shielding Analysis Comparing Dose Rates for Carbon Steel vs. Stainless Steel CCC

2. Document Number:

CCO-CAL-0006

3. Document Revision:

0

4. Page:

26 of 30 si2 0.1 0.5 1.0 2.0 3.0 4.0 6.0 8.0 10.0 15.0 sp2 0.00E+00 1.80E+11 2.71E+11 5.36E+11 4.10E+11 2.73E+11 2.66E+11 8.53E+10 2.44E+10 8.36E+09 C Source Radius si3 0 1.27 sp3 -21 1 C Source Extent si4 -1.27 1.27 sp4 -21 0 C

C Tally Cards C

f2:n 120 fc2 Surface Dose (mrem/hr) $ Surface detector fs2 888 777 t sd2 1.0 3810.44 1.0 1.0 $ Surface tally area f22:n 160 fc22 2-meter Dose (mrem/hr) $ 2-m detector fs22 888 777 t sd22 1.0 10194.144 1.0 1.0 $ Surface tally area C

C ANSI/ANS-6.1.1-1977 Neutron Flux to Dose Factors (mrem/hr) de0 2.5e-08 1.0e-07 1.0e-06 1.0e-05 1.0e-04 $ Energy (Mev) 1.0e-03 1.0e-02 1.0e-01 5.0e-01 1.0 2.5 5.0 7.0 10.0 14.0 20.0 df0 3.67e-03 3.67e-03 4.46e-03 4.54e-03 4.18e-03 $ Conversion (mrem/hr) 3.76e-03 3.56e-03 2.17e-02 9.26e-02 1.32e-01 1.25e-01 1.56e-01 1.47e-01 1.47e-01 2.08e-01 2.27e-01 C

C Material Cards C

m1 40000.60c -1.00 $ Zirconium m2 14000.60c -0.01 $ Stainless Steel 24052.60c -0.19 25055.60c -0.02 26057.60c -0.68 28058.60c -0.10 m3 6000.60c -0.60 $ Urethane Foam 7014.60c -0.08 8016.60c -0.24 1001.60c -0.07 14000.60c -0.01 mt3 poly.01t m4 26000 -1.00 $ Carbon Steel (iron)

C C Runtime and Print Cards C

prdmp j j 1 2 ctme 30

Calculation Continuation Sheet

1. Document

Title:

Shielding Analysis Comparing Dose Rates for Carbon Steel vs. Stainless Steel CCC

2. Document Number:

CCO-CAL-0006

3. Document Revision:

0

4. Page:

27 of 30 6.1.2 HalfPACT Package Models 6.1.2.1 Carbon Steel CCCs with 60Co Sources - dng001c.i title HalfPACT CCO NCT Gamma Concentrated 1 g/cc Co60; CS CCC C

C Cell Cards C

1 1 -1 10 -11 -14 u=1 imp:p=1 $ Source 2 4 -7.85260 30 -32 -34 (-31:33:35) u=1 imp:p=1 $ CCC 3 0 31 -33 -35 (-10:11:14) u=1 imp:p=1 $ CCC cavity 4 0 #1 #2 #3 u=1 imp:p=1 $ Drum cavity 11 0 50 -51 -52 trcl=1 fill=1 imp:p=1 $ CCO #1 12 0 50 -51 -52 trcl=2 fill=1 imp:p=1 $ CCO #2 13 0 50 -51 -52 trcl=3 fill=1 imp:p=1 $ CCO #3 14 0 50 -51 -52 trcl=4 fill=1 imp:p=1 $ CCO #4 15 0 50 -51 -52 trcl=5 fill=1 imp:p=1 $ CCO #5 16 0 50 -51 -52 trcl=6 fill=1 imp:p=1 $ CCO #6 17 0 50 -51 -52 trcl=7 fill=1 imp:p=1 $ CCO #7 200 0 210 -250 -230

  1. 11 #12 #13 #14 #15 #16 #17 imp:p=1 $ ICV cavity 210 2 -8.01280 200 -210 -220 imp:p=1 $ ICV/OCV bottom 220 2 -8.01280 250 -240 -220 imp:p=1 $ ICV/OCV top 230 2 -8.01280 210 -250 230 -220 imp:p=4 $ ICV/OCV shell 240 3 -0.13215 110 -150 -130 (-200:220:240) imp:p=8 $ OCA annulus 250 2 -8.01280 100 -110 -120 imp:p=1 $ OCA bottom 260 2 -8.01280 150 -140 -120 imp:p=1 $ OCA top 270 2 -8.01280 110 -150 130 -120 imp:p=16 $ OCA shell 777 0 120 -160 100 -140 imp:p=32 $ Outside to tally 888 0 -999 (-100:160:140) imp:p=8 $ Outside pkg 999 0 999 imp:p=0 $ Outside world C

C Geometry Cards C

10 pz 109.855 $ Source bottom 11 pz 112.395 $ Source top 14 c/z 0 0 1.27 $ Source radius C

30 pz 74.367 $ CCC base (outside) 31 pz 76.907 $ CCC base (inside) 32 pz 147.883 $ CCC lid (outside) 33 pz 145.343 $ CCC lid (inside) 34 cz 8.414 $ CCC shell (outside) 35 cz 7.703 $ CCC shell (inside)

C 50 pz 66.675 $ Drum bottom 51 pz 155.575 $ Drum top 52 cz 30.48 $ Drum radius (outside)

C 100 pz 0 $ OCA bottom (outside) 110 pz 0.635 $ OCA bottom (inside) 120 cz 119.38 $ OCA shell (outside) 130 cz 118.745 $ OCA shell (inside) 140 pz 229.87 $ OCA top (outside) 150 pz 229.235 $ OCA top (inside) 160 cz 319.38 $ 2-meter from OCA C

200 pz 22.86 $ ICV/OCV bottom (outside) 210 pz 24.13 $ ICV/OCV bottom (inside) 220 cz 93.345 $ ICV/OCV shell (outside) 230 cz 92.234 $ ICV/OCV shell (inside) 240 pz 199.39 $ ICV/OCV top (outside) 250 pz 198.12 $ ICV/OCV top (inside)

C 777 pz 108.585 $ Ring tally (lower) 888 pz 113.665 $ Ring tally (upper) 999 sz 111.125 446.38 $ Outside world C

C Translation Cards C

  • tr1 0 0 0
  • tr2 52.793 30.48 0
  • tr3 0 60.96 0
  • tr4 -52.793 30.48 0
  • tr5 -52.793 -30.48 0

Calculation Continuation Sheet

1. Document

Title:

Shielding Analysis Comparing Dose Rates for Carbon Steel vs. Stainless Steel CCC

2. Document Number:

CCO-CAL-0006

3. Document Revision:

0

4. Page:

28 of 30

  • tr6 0 -60.96 0
  • tr7 52.793 -30.48 0 C

C Physics Cards C

mode p C

C Source Cards C

C Cylindrical Sources sdef pos=d1 erg=d2 par=2 axs=0 0 1 rad=d3 ext=d4 sc1 Co60 C Source Position and Fraction si1 L 0 0 111.125 52.793 30.48 111.125 0 60.96 111.125

-52.793 30.48 111.125

-52.793 -30.48 111.125 0 -60.96 111.125 52.793 -30.48 111.125 sp1 1 1 1 1 1 1 1 C Source Energy (MeV) and Intensity (%)

si2 L 3.469300E-01 8.262800E-01 1.173237E+00 1.332501E+00 2.158770E+00 2.505000E+00 sp2 7.600000E-03 7.600000E-03 9.997360E+01 9.998560E+01 1.110000E-03 2.000000E-06 C Source Radius si3 0 1.27 sp3 -21 1 C Source Extent si4 -1.27 1.27 sp4 -21 0 C

C Tally Cards C

f2:p 120 fc2 Surface Dose (mrem/hr) $ Surface detector fs2 888 777 t sd2 1.0 3810.44 1.0 1.0 $ Surface tally area f22:p 160 fc22 2-meter Dose (mrem/hr) $ 2-m detector fs22 888 777 t sd22 1.0 10194.144 1.0 1.0 $ Surface tally area C

C ANSI/ANS-6.1.1-1977 Gamma Flux to Dose Factors (mrem/hr) de0 1.0e-02 3.0e-02 5.0e-02 7.0e-02 1.0e-01 $ Energy (Mev) 1.5e-01 2.0e-01 2.5e-01 3.0e-01 3.5e-01 4.0e-01 4.5e-01 5.0e-01 5.5e-01 6.0e-01 6.5e-01 7.0e-01 8.0e-01 1.00 1.40 1.80 2.20 2.60 2.80 3.25 3.75 4.25 4.75 5.00 5.25 5.75 6.25 6.75 7.50 9.00 11.00 13.00 15.0000 df0 3.96e-03 5.82e-04 2.90e-04 2.58e-04 2.83e-04 $ Conversion (mrem/hr) 3.79e-04 5.01e-04 6.31e-04 7.59e-04 8.78e-04 9.85e-04 1.08e-03 1.17e-03 1.27e-03 1.36e-03 1.44e-03 1.52e-03 1.68e-03 1.98e-03 2.51e-03 2.99e-03 3.42e-03 3.82e-03 4.01e-03 4.41e-03 4.83e-03 5.23e-03 5.60e-03 5.80e-03 6.01e-03 6.37e-03 6.74e-03 7.11e-03 7.66e-03 8.77e-03 1.03e-02 1.18e-02 1.33e-02 C

C Material Cards C

m1 40000 -1.00 $ Zirconium m2 14000 -0.01 $ Stainless Steel 24000 -0.19 25000 -0.02 26000 -0.68 28000 -0.10 m3 6000 -0.60 $ Urethane Foam 7000 -0.08 8000 -0.24 1000 -0.07 14000 -0.01 m4 26000 -1.00 $ Carbon Steel (iron)

C C Runtime and Print Cards C

prdmp j j 1 2 ctme 30

Calculation Continuation Sheet

1. Document

Title:

Shielding Analysis Comparing Dose Rates for Carbon Steel vs. Stainless Steel CCC

2. Document Number:

CCO-CAL-0006

3. Document Revision:

0

4. Page:

29 of 30 6.1.2.2 Carbon Steel CCCs with 252Cf Sources - dnn001c.i title HalfPACT CCO NCT Neutron Concentrated 1 g/cc Cf252; CS CCC C

C Cell Cards C

1 1 -1 10 -11 -14 u=1 imp:n=1 $ Source 2 4 -7.85260 30 -32 -34 (-31:33:35) u=1 imp:n=1 $ CCC 3 0 31 -33 -35 (-10:11:14) u=1 imp:n=1 $ CCC cavity 4 0 #1 #2 #3 u=1 imp:n=1 $ Drum cavity 11 0 50 -51 -52 trcl=1 fill=1 imp:n=1 $ CCO #1 12 0 50 -51 -52 trcl=2 fill=1 imp:n=1 $ CCO #2 13 0 50 -51 -52 trcl=3 fill=1 imp:n=1 $ CCO #3 14 0 50 -51 -52 trcl=4 fill=1 imp:n=1 $ CCO #4 15 0 50 -51 -52 trcl=5 fill=1 imp:n=1 $ CCO #5 16 0 50 -51 -52 trcl=6 fill=1 imp:n=1 $ CCO #6 17 0 50 -51 -52 trcl=7 fill=1 imp:n=1 $ CCO #7 200 0 210 -250 -230

  1. 11 #12 #13 #14 #15 #16 #17 imp:n=1 $ ICV cavity 210 2 -8.01280 200 -210 -220 imp:n=1 $ ICV/OCV bottom 220 2 -8.01280 250 -240 -220 imp:n=1 $ ICV/OCV top 230 2 -8.01280 210 -250 230 -220 imp:n=4 $ ICV/OCV shell 240 3 -0.13215 110 -150 -130 (-200:220:240) imp:n=8 $ OCA annulus 250 2 -8.01280 100 -110 -120 imp:n=1 $ OCA bottom 260 2 -8.01280 150 -140 -120 imp:n=1 $ OCA top 270 2 -8.01280 110 -150 130 -120 imp:n=16 $ OCA shell 777 0 120 -160 100 -140 imp:n=32 $ Outside to tally 888 0 -999 (-100:160:140) imp:n=8 $ Outside pkg 999 0 999 imp:n=0 $ Outside world C

C Geometry Cards C

10 pz 109.855 $ Source bottom 11 pz 112.395 $ Source top 14 c/z 0 0 1.27 $ Source radius C

30 pz 74.367 $ CCC base (outside) 31 pz 76.907 $ CCC base (inside) 32 pz 147.883 $ CCC lid (outside) 33 pz 145.343 $ CCC lid (inside) 34 cz 8.414 $ CCC shell (outside) 35 cz 7.703 $ CCC shell (inside)

C 50 pz 66.675 $ Drum bottom 51 pz 155.575 $ Drum top 52 cz 30.48 $ Drum radius (outside)

C 100 pz 0 $ OCA bottom (outside) 110 pz 0.635 $ OCA bottom (inside) 120 cz 119.38 $ OCA shell (outside) 130 cz 118.745 $ OCA shell (inside) 140 pz 229.87 $ OCA top (outside) 150 pz 229.235 $ OCA top (inside) 160 cz 319.38 $ 2-meter from OCA C

200 pz 22.86 $ ICV/OCV bottom (outside) 210 pz 24.13 $ ICV/OCV bottom (inside) 220 cz 93.345 $ ICV/OCV shell (outside) 230 cz 92.234 $ ICV/OCV shell (inside) 240 pz 199.39 $ ICV/OCV top (outside) 250 pz 198.12 $ ICV/OCV top (inside)

C 777 pz 108.585 $ Ring tally (lower) 888 pz 113.665 $ Ring tally (upper) 999 sz 111.125 446.38 $ Outside world C

C Translation Cards C

  • tr1 0 0 0
  • tr2 52.793 30.48 0
  • tr3 0 60.96 0
  • tr4 -52.793 30.48 0
  • tr5 -52.793 -30.48 0
  • tr6 0 -60.96 0
  • tr7 52.793 -30.48 0 C

C Physics Cards C

Calculation Continuation Sheet

1. Document

Title:

Shielding Analysis Comparing Dose Rates for Carbon Steel vs. Stainless Steel CCC

2. Document Number:

CCO-CAL-0006

3. Document Revision:

0

4. Page:

30 of 30 mode n C

C Source Cards C

C Cylindrical Sources sdef pos=d1 erg=d2 par=1 axs=0 0 1 rad=d3 ext=d4 sc1 Cf252 C Source Position and Fraction si1 L 0 0 111.125 52.793 30.48 111.125 0 60.96 111.125

-52.793 30.48 111.125

-52.793 -30.48 111.125 0 -60.96 111.125 52.793 -30.48 111.125 sp1 1 1 1 1 1 1 1 C Source Energy (MeV) and Fraction si2 0.1 0.5 1.0 2.0 3.0 4.0 6.0 8.0 10.0 15.0 sp2 0.00E+00 1.80E+11 2.71E+11 5.36E+11 4.10E+11 2.73E+11 2.66E+11 8.53E+10 2.44E+10 8.36E+09 C Source Radius si3 0 1.27 sp3 -21 1 C Source Extent si4 -1.27 1.27 sp4 -21 0 C

C Tally Cards C

f2:n 120 fc2 Surface Dose (mrem/hr) $ Surface detector fs2 888 777 t sd2 1.0 3810.44 1.0 1.0 $ Surface tally area f22:n 160 fc22 2-meter Dose (mrem/hr) $ 2-m detector fs22 888 777 t sd22 1.0 10194.144 1.0 1.0 $ Surface tally area C

C ANSI/ANS-6.1.1-1977 Neutron Flux to Dose Factors (mrem/hr) de0 2.5e-08 1.0e-07 1.0e-06 1.0e-05 1.0e-04 $ Energy (Mev) 1.0e-03 1.0e-02 1.0e-01 5.0e-01 1.0 2.5 5.0 7.0 10.0 14.0 20.0 df0 3.67e-03 3.67e-03 4.46e-03 4.54e-03 4.18e-03 $ Conversion (mrem/hr) 3.76e-03 3.56e-03 2.17e-02 9.26e-02 1.32e-01 1.25e-01 1.56e-01 1.47e-01 1.47e-01 2.08e-01 2.27e-01 C

C Material Cards C

m1 40000.60c -1.00 $ Zirconium m2 14000.60c -0.01 $ Stainless Steel 24052.60c -0.19 25055.60c -0.02 26057.60c -0.68 28058.60c -0.10 m3 6000.60c -0.60 $ Urethane Foam 7014.60c -0.08 8016.60c -0.24 1001.60c -0.07 14000.60c -0.01 mt3 poly.01t m4 26000 -1.00 $ Carbon Steel (iron)

C C Runtime and Print Cards C

prdmp j j 1 2 ctme 30

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