ML18122A066
| ML18122A066 | |
| Person / Time | |
|---|---|
| Site: | 07109341 |
| Issue date: | 04/19/2018 |
| From: | Gonsiorowski E Orano Federal Services |
| To: | Office of Nuclear Material Safety and Safeguards |
| References | |
| FS-18-0056 CALC-3020462, Rev. 000 | |
| Download: ML18122A066 (45) | |
Text
0 orano Orano Federal Services CALCULATION Document No.:
CALC-3020462 Rev. No.
000 Pa e 1 of 45 Pro*ect No.:
01910.00.8001.28 Pro*ect Name:
BRRC Letter Amendment
Title:
BRR Fuel Rod Se ment Shieldin Anal sis Summary:
The Battelle Energy Alliance (BEA) Research Reactor (BRR) package is currently used to transport spent fuel from a variety of research reactors. A one-time NRC letter amendment has been requested to allow for the shipment of a spent fuel payload from Oak Ridge National Laboratory (ORNL) to Idaho National Laboratory (INL).
The following analysis demonstrates that the BRR package complies with the external radiation requirements of 10 CFR 71 for exclusive use transport of the spent fuel payload. In addition to the shielding analysis, a fissile mass assessment is performed to show that the spent fuel payload is exempt from criticality analysis per 10 CFR 71.
Safety [8]
Non-Safety D
Contains Unverified Input/ Assumptions:
Software Utilized: Yes Software Active in FS EASI: Yes: [8] NA*: 0
- Not Applicable per Section 5.7 of FS-EN-PRC-002 Error Notices & Associated Corrective Actions Reviewed: Yes: [8J No: 0 Printed Name Preparer:
E. Gonsiorowski Checker:
S. Gibboney Approver:
D. Hillstrom Other:
FS-EN-FRM-002 Rev. 10 (Effective March 1,2018)
Refer to FS-EN-PRC-002 Yes: 0 No: [8]
Version:
SCALE 6.2.1 MCNP6.1 Excel 2010*
Storage Media: Yes: [8]
No:0 Location:
COLDStor Signature Date RELEASED by RM APR 1 9 2018 UNCONTROLLED DUPLICATE
0 Orano Federal Services orano
Title:
BRR Fuel Rod Segment Shielding Analysis Doc./Rev.: CALC-3020462-000 Project:
01910.00.B001.28 -
BRRC Letter Amendment Page 2 of 45 Revision History Rev.
Changes 000 Initial Release
~--------------------------------------~
(}
Orano Federal Services orano
Title:
BRR Fuel Rod Segment Shielding Analysis Doc./Rev.: CALC-3020462-000 Project:
01910.00.B001.28 -
BRRC Letter Amendment Page 3 of 45 Table of Contents Page REVISION HISTORY............................................................................................................................. 2 LIST OF TABLES.................................................................................................................................. 4 LIST OF FIGURES................................................................................................................................ 4 1.0 PURPOSE.................................................................................................................................. 5 2.0 METHODOLOGY....................................................................................................................... 5 3.0 ASSUMPTIONS......................................................................................................................... 6 3.1 Unverified Assumptions..................................................................................................................... 6 3.2 Justified Assumptions........................................................................................................................ 6 4.0 DESIGN INPUTS........................................................................................................................ 7 4.1 Design Features................................................................................................................................ 7 4.1.1 BRR Packaging................................................................................................................... 7 4.1.2 Spent Fuel Payload............................................................................................................ 7 4.2 Source Specification........................................................................................................................ 14 4.2.1 Gamma Source................................................................................................................. 14 4.2.2 Neutron Source................................................................................................................. 15 4.2.3 Additional Source Characteristics..................................................................................... 16 4.3 Material Properties.......................................................................................................................... 16 5.0 CALCULATIONS...................................................................................................................... 17 5.1 Methods........................................................................................................................................... 17 5.2 Configuration of Source and Shielding............................................................................................ 17 5.3 Flux-to-Dose Rate Conversion........................................................................................................ 20 6.0 RESULTS AND CONCLUSIONS............................................................................................. 22 6.1 External Radiation Levels................................................................................................................ 22 6.2 Summary Table of Maximum Radiation Levels.............................................................................. 24 6.3 Fissile Mass Assessment................................................................................................................ 25 7.0 COMPUTER SOFTWARE USAGE........................................................................................... 25 7.1 In-Use Testing................................................................................................................................. 25 7.1.1 SCALE 6.2.1..................................................................................................................... 25 7.1.2 MCNP6.1.......................................................................................................................... 25 7.2 File Listing....................................................................................................................................... 26
8.0 REFERENCES
......................................................................................................................... 29 8.1 E-mail Reference 1.......................................................................................................................... 30 8.2 E-mail Reference 2.......................................................................................................................... 31 APPENDIX A: INPUT DATA................................................................................................................ 32
0 Orano Federal Services orano
Title:
BRR Fuel Rod Segment Shielding Analysis Doc./Rev.: CALC-3020462-000 Project:
01910.00.8001.28 - BRRC Letter Amendment Page 4 of 45 List of Tables Page Table 4-1 : Radioactive Isotope Set "605" (Evaluated 5/1/2000, fuel length of 12.5 inches).................. 11 Table 4-2: Radioactive Isotope Set "616" (Evaluated 8/1/2008, fuel length of 12 inches)..................... 12 Table 4-3: Radioactive Isotope Set "649/650" (Evaluated 5/1/2007, fuel length of 27 inches).............. 13 Table 4-4: Spent Fuel Payload Gamma Source................................................................................... 14 Table 4-5: Spent Fuel Payload Neutron Source................................................................................... 15 Table 4-6: Stainless Steel 304 Composition (Density= 7.94 g/cm 3
) * * ***** ** ** ** *** * **** ** * * *** ** * ** **** **** * *.*. *. *. *.
- 16 Table 4-7: Dry Air Composition (Density= 0.0012 g/cm 3).................................................................... 16 Table 5-1 : Key Cask Model Dimensions............................................. _................................................. 18 Table 5-2: ANSI/ANS-6.1.1-1977 Photon Flux-to-Dose Rate Conversion Factors................................ 20 Table 5-3: ANSI/ANS-6.1.1-1977 Neutron Flux-to-Dose Rate Conversion Factors.............................. 21 Table 6-1: Tally Maximum Dose Rates (mrem/hr), Bottom Case......................................................... 23 Table 6-2: Tally Maximum Dose Rates (mrem/hr), Drain Case............................................................ 23 Table 6-3: Tally Maximum Dose Rates (mrem/hr), Middle Case.......................................................... 23 Table 6-4: Tally Maximum Dose Rates (mrem/hr), Top Case............................................................... 23 Table 6-5: Tally Maximum Dose Rates (mrem/hr), Vent Case............................................................. 24 Table 6-6: Summary of Maximum NCT Total Dose Rates (Exclusive Use).......................................... 24 Table 6-7: Summary of Maximum HAC Total Dose Rates (Exclusive Use).......................................... 25 List of Figures Page Figure 4-1: BRR Packaging Components.............................................................................................. 8 Figure 4-2: BRR Package Cross-Section............................................................................................... 9 Figure 4-3: Square Fuel Basket........................................................................................................... 10 Figure 5-1 : BRR Package Model with Superimposed Source Locations.............................................. 19
Q Orano Federal Services orano
Title:
BRR Fuel Rod Segment Shielding Analysis Doc.I Rev.: CALC-3020462-000 Project:
01910.00.8001.28 -
BRRC Letter Amendment Page 5 of 45 1.0 PURPOSE The Battelle Energy Alliance (BEA) Research Reactor (BRR) package is currently used to transport spent fuel from a variety of research reactors. A one-time NRC letter amendment is requested to allow for the shipment of a spent fuel payload from Oak Ridge National Laboratory (ORNL) to Idaho National Laboratory (INL). The composition of the spent fuel payload is detailed in a spreadsheet attachment included with [l].
The following analysis demonstrates that the BRR package complies with the external radiation requirements of IO CFR 71 for exclusive use transport of the spent fuel payload. A fissile mass assessment is also performed to show that the spent fuel payload is exempt from criticality analysis per 10 CFR 71.
2.0 METHODOLOGY The shielding performance of the BRR package during transport of the spent fuel payload is evaluated using SCALE and MCNP. SCALE is used to decay the payload contents and generate gamma and neutron source terms. SCALE is also used to determine the fissile mass content of the payload. The MCNP model is based on the current SAR shielding model (taken from Section 5, Shielding Evaluation, of [2]). The SAR model cask dimensions are maintained, while new source terms and tallies are developed to accurately model and evaluate the new payload. The spent fuel and fuel basket geometry are conservatively ignored, bounding real-world shielding performance.
The BRR package shielding performance is evaluated in accordance with 10 CFR 71 [3] and documented per the requirements in NUREG-1609 [4] and Regulatory Guide 7.9 [5]. The package is shipped vertically-oriented under exclusive use requirements using an open (flat-bed) transport vehicle. The requirements for exclusive use under normal conditions for transport (NCT) and hypothetical accident conditions (HAC), per 10 CFR 71.47(b) and 10 CFR 71.51 ( a)(2), are summarized and applied as follows:
Limits for Normal Conditions for Transport 200 mrem/hr on the external surface of the package 200 mrem/hr for the projected outer surfaces of the transport vehicle (trailer side edges and the top and bottom surfaces of the impact limiters) 10 mrem/hr at any point 2 meters from the projected side surfaces of the transport vehicle 2 mrem/hr in any normally occupied space (assumed 25 feet from the package centerline consistent with previous analysis in Section 5 of [2])
Limits for Hypothetical Accident Conditions 1000 mrem/hr at any point 1 meter from the outer surfaces of the package (i.e. the cask only as no credit for the impact limiters is taken during HAC)
The BRR package is shown to be exempt from criticality analysis per 10 CFR 71.15(b ).
Q Orano Federal Services orano
Title:
BRR Fuel Rod Segment Shielding Analysis Doc./Rev.: CALC-3020462-000 Project:
01910.00.8001.28 -
BRRC Letter Amendment Page 6 of 45 3.0 ASSUMPTIONS 3.1 Unverified Assumptions There are no unverified assumptions.
3.2 Justified Assumptions I. The vehicle width is assumed 8 feet, consistent with Section 5 of [2]. This is the standard width of a trailer.
- 2.
The cask lead radial shrinkage gap is 0.0625 inches and the cask lead axial gap is 1. 18 inches, consistent with Section 5 of [2].
- 3. The occupied location (i.e. vehicle driver) is assumed to be 25 feet from the centerline of the cask, consistent with Section 5 of [2]. This is a reasonable assumption based on the transportation configuration.
- 4. All spent fuel and fuel basket geometry is conservatively ignored. The spent fuel source is modeled as a point source within a I cm diameter sphere. The source is able to move to any location within the cask inner cavity, bounding any possible reconfiguration of the spent fuel during NCT or HAC. The real-world spent fuel will be contained within a robust, sealed container. The container will be constrained within one of the openings of the square fuel basket.
- 5.
Subcritical multiplication is not accounted for. The package payload is exempt from criticality analysis, and thus it is reasonable to assume that the effective multiplication factor is low enough that subcritical multiplication does not have a significant effect on dose rates. The steady-state neutron level, N, is equal to the product of the neutron source strength, S, and the subcritical multiplication factor, M(see module 4 of[14]).
N=S*M=S*(
l
)
1 - keff Neutron and secondary gamma dose rates, D, vary proportionally with the neutron level. Based on the limiting results in Section 6.2 (NCT side surface dose rate), an effective multiplication factor greater than 0.85 would be necessary to exceed regulatory limits (in the limiting case, Dp,imary y is 0.01 mrem/hr).
i)M s
- M i) calculated S
[
[)limit -
[)primary y
]
Dlimit
(
1
)
to solve for k effmax:
~ -.-- =
Dneutron + Dsecondary y NCT,Side Surface Dtotal l - keff,max rnrern Dtotal 29* 7 ---;i:;;-
~ keff,max = l - -.-- = 1 -
rnrern = 0.8515 D limit 2 0 0 ---;i:;;-
0 Orano Federal Services orono
Title:
BRR Fuel Rod Segment Shielding Analysis Doc./Rev.: CALC-3020462-000 Project:
0191 O.OO.B001.28 -
BRRC Letter Amendment Page 7 of 45 4.0 DESIGN INPUTS 4.1 Design Features 4.1.1 BRR Packaging The principal design features of the BRR package are a thick lead-filled shield plug, lead-filled cask, and lead-filled bottom. The lead in the side wall of the cask is 8-in thick. Also in the side wall, the inner steel shell is I -in thick and the outer stainless steel shell is 2-in thick.
The top plug consists of approximately 9.5-in lead with a I-in stainless steel bottom cover plate and 0.5-in stainless steel top plate. The lid is constructed of stainless steel 2-in thick. The cask bottom consists of7.7-in of lead through the centerline, with a I-in stainless steel bottom cover plate, and approximately 1.2-in stainless steel inner forging.
An external view of the BRR package is shown in Figure 4-1, while a cross-section of the package is shown in Figure 4-2.
4.1.2 Spent Fuel Payload Per Section 4 of[l] and [15], the spent fuel payload consists offuel segments between 1.0 and 13 inches in length. The fuel segments have a - 0.4-in outer diameter and may be open ended. The spent fuel payload will be transported using the Square Fuel Basket shown in Figure 4-3. The spent fuel payload and Square Fuel Basket are not geometrically modeled.
The spent fuel payload is composed of three radioactive isotope sets corresponding to payload fuel segments, labeled "605", "616", and "649/650". The radioactive isotope composition of the payload is per a spreadsheet attachment, Proposed ORNL Shipment to HFEF.xlsx, included with [I]. Radioactive isotope sets "605", "616",
and "649/650" are shown in Table 4-1, Table 4-2, and Table 4-3, respectively. Per discussion with the customer
[13], an additional 20 inches of set "616" and 9 inches of set "649/650" may be included in the payload (Table 4-1 and Table 4-3 show the customer-provided radioisotope sets corresponding to total aggregate fuel lengths of 12 inches for "616" and 27 inches for "649/650").
()
Orano Federal Services orano
Title:
BRR Fuel Rod Segment Shielding Analysis Doc./Rev.: CALC-3020462-000 Project:
01910. 00. 8001.28 -
BRRC Letter Amendment UPPER IMPACT LIMITER CASK BODY ATIACHMENT PIN AND CLIP, TYP OWERIMPACT LIMITER Figure 4-1: BRR Packaging Components Page 8 of 45
0 orano
Title:
Doc./Rev.: CALC-3020462-000 Project:
0191 O.OO.B001.28 UPPER ENO STRUCTURE SIDE LEAD SHIELD LOWER END STRUCTURE Orano Federal Services BRR Fuel Rod Segment Shielding Analysis BRRC Letter Amendment Figure 4-2: BRR Package Cross-Section CLOSURE UO SHIELD PLUG UPPER IMPACT LIMITER OUTER SHELL Page 9 of 45 LOWER IMPACT LIMITER DRAIN PORT POLYURETHANE FOAM
Q Orano Federal Services orano
Title:
BRR Fuel Rod Segment Shielding Analysis Doc./Rev.: CALC-3020462-000 Project:
0191 O.OO.B001.28 -
BRRC Letter Amendment Page 10 of 45 Figure 4-3: Square Fuel Basket
(}
Orano Federal Services orano
Title:
BRR Fuel Rod Segment Shielding Analysis Doc./Rev.: CALC-3020462-000 Project:
01910.00.B001.28 -
BRRC Letter Amendment Page 11 of 45 Table 4-1: Radioactive Isotope Set "605" (Evaluated 5/1/2000, fuel length of 12.5 inches)
Isotope Activity (Ci)
Isotope Activity (Ci)
Isotope Activity (Ci)
Isotope Activity (Ci)
Isotope Activity (Ci)
Ac-225 3.27E-10 Cf-251 1.83E-07 Nb-94 7.13E-12 Pu-240 1.05E-01 Tc-99 4.66E-03 Ac-227 5.72E-10 Cf-252 2.54E-05 Nb-95 1.14E-06 Pu-241 2.18E+01 Te-123m 1.51 E-08 Ac-228 2.60E-14 Cf-254 2.34E-18 Nb-95m 1.09E-08 Pu-242 7.82E-04 Te-125m 2.00E-01 Ag-109m 4.30E-09 Cm-242 2.23E-02 Ni-63 5.82E-12 Pu-243 1.42E-08 Te-127 2.14E-05 Ag-110 1.44E-03 Cm-243 1.00E-02 Np-237 1.04E-04 Pu-244 7.93E-15 Te-127m 2.17E-05 Ag-110m 1.10E-02 Cm-244 7.77E+OO Np-239 2.38E-02 Ra-223 5.72E-10 Te-129 3.17E-16 Am-241 2.46E-01 Cm-245 2.23E-03 Np-240m 7.93E-15 Ra-224 1.04E-05 Te-129m 4.93E-16 Am-242 6.51 E-03 Cm-246 1.55E-03 Pa-231 2.66E-09 Ra-225 3.27E-10 Th-227 5.67E-10 Am-242m 6.51 E-03 Cm-247 1.42E-08 Pa-233 1.04E-04 Ra-226 1.01E-11 Th-228 1.04E-05
-~
Am-243 2.38E-02 Cm-248 1.52E-07 Pa-234 5.22E-08 Ra-228 2.60E-14 Th-229 3.27E-10 Am-244 1.03E-17 Cm-250 5.56E-14 Pa-234m 5.22E-05 Rb-87 5.52E-09 Th-230 3.50E-09 Am-245 3.26E-10 Co-60 1.45E-04 Pb-209 3.27E-10 Rh-103m 2.14E-12 Th-231 2.93E-07 Ar-39 3.17E-25 Cr-51 3.03E-21 Pb-21 0 1.63E-12 Rh-106 3.29E+OO Th-232 4.32E-14 At-217 3.27E-10 Cs-134 1.46E+01 Pb-211 5.72E-10 Rn-219 5.72E-10 Th-234 5.22E-05 Ba-137m 2.64E+01 Cs-135 9.68E-05 Pb-212 1.04E-05 Rn-220 1.04E-05 Tl-207 5.72E-10 Be-10 1.27E-12 Cs-137 2.83E+01 Pb-214 1.01E-11 Rn-222 1.01E-11 Tl-208 3.76E-06 Bi-210 1.63E-1 2 Eu-152 3.18E-03 Pd-107 5.92E-05 Ru-103 2.14E-12 Tl-209 7.18E-12 Bi-2 11 5.72E-10 Eu-154 2.92E+OO Pm-147 3.89E+OO Ru-106 3.29E+OO U-232 1.27E-05 Bi-212 1.04E-05 Eu-155 5.22E-01 Pm-148 3.29E-14 Sb-124 1.25E-10 U-233 6.02E-09 Bi-213 3.27E-10 Fe-55 1.31 E-02 Pm-1 48m 4.0?E-13 Sb-125 4.82E-01 U-234 6.82E-05 Bi-214 1.01E-11 Fe-59 2.21 E-15 Po-210 1.63E-12 Sb-126 2.63E-04 U-235 2.93E-07 Bk-249 2.18E-05 Fr-221 3.27E-10 Po-211 1.72E-12 Sb-126m 2.66E-04 U-236 4.24E-05 Bk-250 5.56E-14 Fr-223 8.02E-12 Po-212 6.73E-06 Sc-46 1.91 E-22 U-237 5.22E-04 C-14 1.0?E-07 Gd-153 4.81 E-04 Po-213 3.20E-10 Se-79 1.29E-04 U-238 5.22E-05 Ca-45 9.0SE-18 H-3 1.42E-01 Po-214 1.01 E-11 Sm-151 3.21 E-01 U-240 7.93E-15 Cd-109 4.30E-09 Ho-166M 3.27E-06 Po-215 5.72E-10 Sn-119m 4.47E-05 Y-90 1.50E+01 Cd-113m 1.04E-02 1-129 1.41 E-05 Po-216 1.04E-05 Sn-121 m 1.60E-04 Y-91 3.58E-08 Cd-115m 1.52E-14 ln-114 9.59E-14 Po-218 1.01E-11 Sn-123 5.42E-05 Zn-65 9.0SE-20 Ce-141 1.57E-15 ln-114m 9.93E-14 Pr-144 1.27E+OO Sn-126 2.66E-04 Zr-93 6.32E-04 Ce-144 1.27E+OO Kr-85 1.28E+OO Pu-236 6.73E-05 Sr-89 1.51E-09 Zr-95 5.27E-07 Cf-249 3.?0E-06 Mn-54 1.21 E-04 Pu-238 2.64E+OO Sr-90 1.50E+01 Cf-250 1.40E-05 Nb-93m 3.46E-04 Pu-239 5.87E-02 Tb-160 1.35E-08
()
Orano Federal Services orano
Title:
BRR Fuel Rod Segment Shielding Analysis Doc./Rev.: CALC-3020462-000 Project:
01910.00.8001.28 -
BRRC Letter Amendment Page 12 of 45 Table 4-2: Radioactive Isotope Set "616" (Evaluated 8/1 /2008, fuel length of 12 inches)
Isotope Activity (Ci)
Isotope Activity (Ci)
Isotope Activity (Ci)
Isotope Activity (Ci)
Isotope Activity (Ci)
Ag-110 1.03E-03 Cm-244 6.64E+OO Np-237 8.33E-05 Rb-87 4.17E-09 Te-127 1.59E-05 Ag-110m 8.01 E-03 Cm-245 2.13E-03 Np-239 2.18E-02 Rh-103m 1.58E-12 Te-127m 1.60E-05 Am-241 2.00E-01 Cm-246 1.17E-03 Pa-233 8.15E-05 Ru-106 2.49E+OO Te-129 2.32E-16 Am-242 6.62E-03 Cs-134 1.09E+01 Pb-212 7.54E-06 Sb-124 8.94E-11 Te-129m 3.63E-16 Am-243
- 8. 15E-03 Cs-135 7.41 E-05 Pd-107 4.33E-05 Sb-125 3.63E-08 Th-228 7.54E-06 Bi-212 7.54E-06 Cs-137 2.58E+01 Pm-147 3.01 E+OO Sb-126m 1.96E-04 Th-234 4.13E-05 Bk-249 1.36E-05 Eu-152 2.51 E-03 Pm-148 2.44E-14 Se-79 9.71 E-05 U-232 1.16E-05 Cd-109 2.87E-09 Eu-154 2.16E+OO Pm-148m 3.04E-13 Sm-151 5.74E-02 U-234 2.04E-04 Cd-113m 7.13E-03 Eu-155 3.87E-01 Po-210 1.16E-12 Sn-119m 1.28E-05 U-235 2.43E-06 Cd-115m 1.10E-14 Gd-153 3.42E-04 Pu-236 6.27E-05 Sn-121m 4.31E-07 U-236 6.00E-05 Ce-141 1.17E-15 H-3 1.06E-01 Pu-238 9.19E-01 Sn-126 1.93E-04 U-237 5.09E-04 Ce-144 9.71 E-01 ln-113m 5.75E-14 Pu-239 5.76E-02 Sr-89 1.12E-09 U-238 5.33E-05 Cf-251 1.12E-07 ln-114m 6.25E-14 Pu-240 2.69E-01 Sr-90 1.13E+01 Y-90 1.13E+01 Cf-252 6.13E-05 Nb-93m 2.40E-04 Pu-241 2.45E+01 Tb-160 9.28E-03 Y-91 2.67E-08 Cm-242 2.15E-02 Nb-95 8.22E-07 Pu-242 6.01E-04 Tc-99 3.06E-03 Zr-93 4.36E-04 Cm-243 9.71 E-03 Nb-95m 6.61 E-09 Ra-224 7.54E-06 Te-125m 1.51 E-01 Zr-95 3.81 E-07
0 Orano Federal Services orano
Title:
BRR Fuel Rod Segment Shielding Analysis Doc.I Rev.: CALC-3020462-000 Project:
01910.00.8001.28 -
BRRC Letter Amendment Page 13 of 45 Table 4-3: Radioactive Isotope Set "649/650" (Evaluated 5/1/2007, fuel length of 27 inches)
Isotope Activity (Ci)
Isotope Activity (Ci)
Isotope Activity (Ci)
Isotope Activity (Ci)
Isotope Activity (Ci)
Ag-110 2.17E-03 Co-60 2.87E-01 Mo-93 1.84E-05 Pu-240 2.70E-01 Ta-182 7.25E-04 Ag-110m 1.60E-01 Cr-51 1.85E-12 Nb-93m 1.30E-01 Pu-241 6.30E+01 Tb-160 3.25E-05 Am-241 4.65E-01 Cs-134 4.46E+01 Nb-94 3.98E-03 Pu-242 2.20E-03 Tc-99 8.44E-03 Am-242 9.79E-03 Cs-135 3.20E-04 Nb-95 7.18E-03 Rb-86 2.54E-18 Te-123m 2.72E-05 Am-242m 9.79E-03 Cs-136 3.15E-24 Nb-95m 3.84E-05 Re-188 5.99E-08 Te-125m 4.35E-01 Am-243 4.01 E-02 Cs-137 6.83E+01 Nd-147 1.89E-28 Rh-102 7.39E-04 Te-127 4.91 E-03 Ar-37 3.96E-13 Eu-152 4.28E-03 Ni-59 1.41 E-04 Rh-103m 2.26E-06 Te-127m 5.03E-03 Ba-136m 3.52E-25 Eu-154 4.80E+OO Ni-63 2.16E-02 Rh-106 3.02E+01 Te-129 2.04E-09 Ba-137m 6.45E+01 Eu-155 1.56E+OO Np-235 3.25E-06 Ru-103 2.26E-06 Te-129m 3.18E-09 Ba-140 7.46E-24 Eu-156 3.86E-20 Np-237 2.42E-04 Ru-106 3.02E+01 Th-234 1.01 E-04 Bk-249 7.61 E-05 Fe-55 2.30E-01 Np-238 4.43E-05 S-35 1.52E-06 U-232 2.SOE-05 C-14 2.20E-04 Fe-59 1.43E-09 Np-239 4.01 E-02 Sb-124 2.19E-06 U-234 2.76E-04 Ca-45 5.25E-06 Gd-153 1.16E-03 Pa-233 2.42E-04 Sb-125 1.79E+OO U-236 1.26E-04 Cd-113m 2.61 E-02 H-3 2.61 E-01 Pa-234m 1.01 E-04 Sb-126m 4.46E-04 U-237 1.51 E-03 Cd-115m 7.09E-09 Hf-175 3.67E-08 Pm-146 1.87E-03 Sc-46 3.11 E-08 U-238 1.01 E-04 Ce-141 3.42E-08 Hf-181 9.36E-09 Pm-147 2.35E+01 Sm-151 2.17E-01 W-181 3.79E-06 Ce-144 1.95E+01 ln-1 13m 2.84E-06 Pm-148 4.54E-09 Sn-113 2.84E-06 W-185 4.32E-06 Cf-252 2.19E-05 ln-114 1.20E-09 Pm-148m 8.59E-08 Sn-117m 9.44E-27 W-188 5.94E-08 Cl-36 6.35E-06 ln-114m 1.26E-09 Pr-143 2.28E-22 Sn-119m 5.70E-03 Xe-131m 2.40E-27 Cm-242 6.64E-01 lr-192 3.34E-08 Pr-144 1.95E+01 Sn-121 1.39E-03 Y-89m 5.36E-09 Cm-243 4.16E-02 lr-194m 2.76E-08 Pr-144m 2.73E-01 Sn-121m 1.79E-03 Y-90 4.13E+01 Cm-244 9.79E+OO Kr-85 3.90E+OO Pu-236 2.95E-04 Sn-123 5.26E-04 Y-91 6.26E-04 Cm-245 1.22E-03 La-140 8.59E-24 Pu-237 5.36E-10 Sn-126 4.46E-04 Zn-65 8.67E-06 Cm-246 7.31 E-04 Lu-177m 3.23E-08 Pu-238 4.39E+OO Sr-89 5.78E-05 Zr-93 8.53E-04 Co-58 5.17E-06 Mn-54 8.54E-03 Pu-239 1.34E-01 Sr-90 4.13E+01 Zr-95 3.27E-03
()
Orano Federal Services orano
Title:
BRR Fuel Rod Segment Shielding Analysis Doc./Rev.: CALC-3020462-000 Project:
01910.00.8001.28 -
BRRC Letter Amendment Page 14 of 45 4.2 Source Specification The spent fuel payload source term is generated in two steps. First, decay modeling is performed to determine the current radioactive isotope inventory of the spent fuel payload (as of January 1 s1, 2018). Set "605" is decayed 17.67 years, set "616" is decayed 9.42 years, and set "649/650" is decayed 10.67 years. Second, all isotope sets are combined to generate gamma and neutron source spectrums. Sets "616" and "649/650" are multiplied by factors of 2.67 and 1.33, respectively, to account for possible additional lengths of fuel beyond that described in
[l]. All source term data is calculated using the ORI GEN module of SCALE 6.2.1 code package [6].
Decay of the "605", "616", and "649/650" isotope sets are performed using input files 605_Decay. inp, 616 _Decay.inp, and 649 _650 _Decay.inp. Generation of the payload source term is calculated using the input file Combined_Shipment.inp. All source term data processing is contained in the spreadsheet Source Term.xlsx.
4.2.1 Gamma Source The gamma source spectrum is shown in Table 4-4. An ENDF/B-Vll.1 19-group energy distribution is used, closely resembling the energy grouping used in Section 5 of [2]. The source term includes modeling of Bremsstrahlung but does not include secondary gamma radiation, which is instead modeled within MCNP.
Table 4-4: Spent Fuel Payload Gamma Source Gamma Energy Gamma Source (MeV)
(y/s) 2.00E+01 1.00E+01 2.2075E+02 1.00E+01 -
8.00E+OO 3.0158E+03 8.00E+OO 6.SOE+OO 1.4042E+04 6.50E+OO -
5.00E+OO 7.2039E+04 5.00E+OO -
4.00E+OO 1.7670E+05 4.00E+OO -
3.00E+OO 6.1175E+05 3.00E+OO -
2.50E+OO 2.4912E+06 2.50E+OO -
2.00E+OO 2.5469E+07 2.00E+OO 1.66E+OO 2.7277E+08 1.66E+OO -
1.33E+OO 1.4272E+10 1.33E+OO -
1.00E+OO 1.3684E+11 1.00E+OO 8.00E-01 7.8785E+10 8.00E-01 6.00E-01 4.8675E+12 6.00E-01 4.00E-01 1.0866E+11 4.00E-01 3.00E-01 8.1119E+10 3.00E-01 2.00E-01 1.3905E+11 2.00E-01 1.00E-01 4.6700E+11 1.00E-01 4.SOE-02 7.3578E+11 4.SOE-02 1.00E-02 2.5455E+12 Total 9.1748E+12
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BRRC Letter Amendment Page 15 of 45 4.2.2 Neutron Source The neutron source spectrum is shown in Table 4-5. An ENDF /B-VII.1 28-group energy distribution is used, closely resembling the energy grouping used in Section 5 of (2). Neutrons from subcritical multiplication are not accounted for due to the low mass of fissile material (see Section 4.2.3).
Table 4-5: Spent Fuel Payload Neutron Source Neutron Energy Neutron Source (MeV)
(n/s) 2.000E+01 6.376E+OO 7.9778E+04 6.376E+OO -
3.012E+OO 7.8487E+05 3.012Et00 -
1.827E+OO 8.9950E+05 1.827E+OO -
1.423E+OO 4.2093E+05 1.423E+OO -
9.072E-01 6.0368E+05 9.072E-01 4.076E-01 5.8829E+05 4.076E-01 1.111E-01 2.7052E+05 1.111E-01 1.503E-02 4.7356E+04 1.503E-02 3.035E-03 2.3234E+03 3.035E 5.830E-04 2.1302E+02 5.830E-04 1.013E-04 1.8174E+01 1.013E 2.902E-05 1.2029E+OO 2.902E 1.068E-05 1.6888E-01 1.068E-05 5.000E-06 3.2900E-02 5.000E-06 3.059E-06 8.0911 E-03 3.059E-06 1.855E-06 3.9178E-03 1.855E-06 1.300E-06 1.4505E-03 1.300E-06 1.125E-06 4.0044E-04 1.125E-06 1.000E-06 2.6888E-04 1.000E 8.000E-07 3.9483E-04 8.000E-07 4.140E-07 6.2350E-04 4.140E-07 3.250E-07 1.1258E-04 3.250E-07 2.250E-07 1.0906E-04 2.250E-07 1.000E-07 1.0426E-04 1.000E 5.000E-08 2.8366E-05 5.000E-08 3.000E-08 8.3033E-06 3.000E-08 1.000E-08 5.8228E-06 1.000E-08 1.000E-11 1.3876E-06 Total 3.6975E+06
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BRRC Letter Amendment Page 16 of 45 4.2.3 Additional Source Characteristics Per JO CFR 71.4, fissile material is defined as "the radionuclides uranium-233, uranium-235, plutonium-239, and plutonium-241, or any combination ofthese radionuclides". The spent fuel payload contains 3.14 grams U-235, 6.30 grams Pu-239, and 0.97 grams Pu-241. The spent fuel payload does not contain a significant amount of U-233. The package is exempt from the criticality analysis requirements of 10 CFR 71 due to meeting the following exemption requirements per 10 CFR 71.15(b):
The total fissile material mass is 10.41 grams, which is less than the maximum allowable of 15 grams The total nonfissile material mass (which includes cask body steel but not lead) is greater than 200 grams per gram of fissile material (total empty cask weight is greater than 26,000 lbs per Table 2.1-2, BRR Package Component Weights, of [2])
The spent fuel payload decay heat is 2.68 watts. The heat load of the Square Fuel Basket is limited to 30 watts per compartment per Section 1.2.2.5, Square Fuel and Loose Plates, of [2].
4.3 Material Properties The cask is constructed of stainless steel and lead. The stainless steel composition and density utilized in the MCNP models is obtained from [7] and provided in Table 4-6. The lead is modeled as pure with a density of 11.35 g/cm3 [8]. All empty space within the cask is modeled as dry air. Empty space outside the cask is modeled as void. The impact limiters are also modeled as void. The air composition and density utilized is obtained from
[7] and provided in Table 4-7.
Table 4-6: Stainless Steel 304 Composition (Density= 7.94 g/cm 3
)
Element Wt.%
C 0.08 Si 1.0 p
0.045 Cr 19.0 Mn 2.0 Fe 68.375 Ni 9.5 Table 4-7: Dry Air Composition (Density= 0.0012 g/cm 3)
Element Wt.%
N 76.508 0
23.4793 C
0.0126
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BRRC Letter Amendment Page 17 of 45 5.0 CALCULATIONS 5.1 Methods The dose rates for the spent fuel payload are computed using MCNP6.1 [9]. The spent fuel point source is evaluated in five worst-case locations with three runs per location (primary gamma dose rates, neutron dose rates, and secondary gamma dose rates), resulting in 15 total unique runs. All relevant package features are modeled in three-dimensions except for the spent fuel and fuel basket. The impact limiters are modeled as void. All space outside of the package is modeled as void.
For NCT dose rates, credit is taken for the geometry of the impact limiters (i.e. applicable surface dose rates are measured at the location of the impact limiter surface). For HAC dose rates, no cred it for the geometry of the impact limiters is taken, bounding the crush of the impact limiters during an accident. As a result, the same MCNP model is used to calculate both NCT and HAC dose rates. All reconfiguration of the cask internal cavity during an accident condition is bounded by the evaluated worst-case locations (due to the non-physical concentration of the spent fuel source term).
Dose rates are computed using segmented mesh tallies (except for conical surfaces, which use segmented surface tallies) to ensure that the maximum dose rates are properly captured. Mesh tallies compute fluxes in thin, non-physical volumes (using track-length estimates) before converting to dose rates using the flux-to-dose rate conversion factors found in Section 5.3. Cylindrical tallies are split into six circumferential segments to properly capture circumferential variations in dose rates.
5.2 Configuration of Source and Shielding All relevant design features of the BRR cask are modeled in MCNP while the spent fuel and fuel basket geometries are conservatively ignored. The key dimensions relevant to the modeled cask are summarized in Table 5-1, which is identical to Table 5.3-1, Key Cask Model Dimensions, from [2] (except for impact limiter diameter). The modeled package is shown in Figure 5-1. Some details are not included in the dimension table but may be inferred from the figure. The yellow dots superimposed on Figure 5-1 roughly correspond to the five evaluated source locations. The five source locations within the cask cavity are:
- 1.
Source shifted to the lower wall and radial wall ("Bottom" case)
- 2.
Source shifted to the lower wall and aligned with the drain port ("Drain" case)
- 3.
Source shifted to the radial wall in the axial center of the cavity ("Middle" case)
- 4.
Source shifted to the upper wall and radial wall ("Top" case)
- 5.
Source shifted to the upper wall and aligned with the vent port ("Vent" case)
The approved SAR model is taken from Section 5 of [2] and modified as necessary. The only geometry change made to the existing SAR model is the correction of the impact limiters. The impact limiter diameter is changed to 78 inches and chamfered corners are added. Chamfered corners are added to ensure dose rates are measured as close as possible to the source. The dimensions for the impact limiters are taken from the impact limiter drawings in Section 1.3.3, Packaging General Arrangement Drawings, of [2). All air outside of the package in the original SAR model has been converted to void to simplify variance reduction.
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BRRC Letter Amendment Page 18 of 45 Table 5-1: Key Cask Model Dimensions Item Dimension (in)
Cask Radial Cask inner diameter 16.0 Cask inner steel thickness 1.0 Cask lead thickness 8.0, modeled as 7.9375 Cask lead radial shrinkage gap (assumed) 0.0625 Cask outer steel thickness 2.0 Cask outer diameter (w/o heat shield) 38.0 Cask to heat shield gap 0.105 Heat shield thickness 0.105 Upper and lower impact limiter diameter 78.0 Cask Axial Top Shield plug bottom plate thickness 1.0 Shield plug lead thickness 9.7, modeled as 9.58 Shield plug top plate thickness 0.5 Shield plug overall height 11.2, modeled as 11.08 Shield plug vent pipe inner diameter 0.824 (schedule 40S)
Lid thickness 2.0 Upper impact limiter thickness at centerline 21.2 Overall height (including impact limiters) 119.5 Cask Axial Bottom Bottom outer plate thickness 1.0 Bottom lead thickness at centerline 7.7, modeled as 7.72 Bottom casting inner thickness 1.1, modeled as 1.22 (after machining)
Bottom lead major diameter 23.7 Bottom lead minor diameter 10.3, modeled as 9.75 Drain hole diameter 0.5 Lower impact limiter thickness at centerline 21.2
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BRRC Letter Amendment Page 19 of 45 Figure 5-1: BRR Package Model with Superimposed Source Locations
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BRRC Letter Amendment Page 20 of 45 5.3 Flux-to-Dose Rate Conversion ANSI/ANS-6.1.1 -1977 photon and neutron flux-to-dose rate conversion factors are used in this analysis. These factors are obtained from the MCNP6 User's Manual, Appendix D, Tables 11-1 and 11-2 [9]. The conversion factors in [9] have been multiplied by a factor of 1000 to generate dose rates in units of mrem/hr rather than rem/hr. The conversion factors are provided in Table 5-2 and Table 5-3.
Table 5-2: ANSI/ANS-6.1.1-1977 Photon Flux-to-Dose Rate Conversion Factors Energy Gamma Factors (MeV)
(mrem/hr)/(y/cm 2-s)
Energy Gamma Factors (MeV)
(mrem/hr)/(y/cm 2-s) 0.01 3.96E-03 1.40 2.51E-03 0.03 5..82E-04 1.80 2.9fil:-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 4.01 E-03 0.15 3.79E-04 3.25 4.41 E-03 0.20 5.01E-04 3.75 4.83E-03 0.25 6.31 E-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 6.01 E-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 7.11 E-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
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BRRC Letter Amendment Page 21 of 45 Table 5-3: ANSI/ANS-6.1.1-1977 Neutron Flux-to-Dose Rate Conversion Factors Energy Neutron Factors (MeV)
(mrem/hr)/(n/cm 2-s) 2.5E-08 3.67E-03 1.0E-07 3.67E-03 1.0E-06 4.46E-03 1.0E-05 4.54E-03 1.0E-04 4.18E-03 1.0E-03 3.76E-03 1.0E-02 3.56E-03 1.0E-01 2.17E-02 5.0E-01 9.26E-02 1.0 1.32E-01 2.5 1.25E-01 5.0 1.56E-01 7.0 1.47E-01 10.0 1.47E-01 14.0 2.08E-01 20.0 2.27E-01
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BRRC Letter Amendment Page 22 of 45 6.0 RESULTS AND CONCLUSIONS 6.1 External Radiation Levels The objective is to determine bounding maximum dose rates resulting from transport of the spent fuel payload.
The evaluated worst-case source locations are described in Section 5.2. The applicable dose rate limits are discussed in Section 2.
Tallies are divided into sub-tallies to ensure all local maximum dose rates are properly captured. All side tallies are vertically segmented into in (- 10 cm) subdivisions. Similarly, top and bottom tallies are radially segmented into in (- 10 cm) subdivisions. All mesh tallies are rotationally segmented into six 60° subdivisions. The only exceptions to these rules are the impact limiter conical surface tally (which is not rotationally segmented) and the occupied space tally (no rotational subdivisions and a foot height).
For NCT, package surface dose rates are measured using five mesh tallies at the following locations: the cask side surface, the top surface of the top impact limiter, the bottom surface of the bottom impact limiter, the impacL limiter side surfaces, and the impact limiter ' underside' surfaces. The impact limiter 'underside' surfaces are,
considered to be part of the package side surface. Additionally, two segmented surface tallies are used on the conical surfaces of the top and bottom impact limiters. These conical surfaces are considered to be parts of the top and bottom surfaces of the package (rather than the side). Vehicle surface dose rates are measured using one mesh tally at the projected transport vehicle side surface (4 feet from cask centerline). The vehicle top surface is the same as the package top surface, while the vehicle bottom surface is conservatively measured at the package bottom surface. 2 meter dose rates are measured using one mesh tally 2 meters from the transport vehicle projected side surface. For HAC, 1 meter dose rates are measured using three mesh tallies at the following locations: 1 meter from the cask side, 1 meter from the cask top surface, and 1 meter from the cask bottom surface.
All tallies are processed in individual spreadsheets before being compiled in the spreadsheet Compiled Shielding Results.xlsx. The maximum total dose rates for each location (naming per Section 5.2) are shown in Table 6-1,
Table 6-2, Table 6-3, Table 6-4, and Table 6-5. Tally total dose rates are calculated by summing the maximum primary gamma, neutron, and secondary gamma dose rates within each tally. Total dose rate relative errors are a function of the component dose rates, b, and their associated relative errors, R. The associated relative errors output by MCNP are equal to the standard deviation as a fraction of the output dose (R = alb). The total dose rate relative errors are calculated using the following equation (derived from the fundamental error propagation formula in [1 2] and converted to MCNP output terms):
j(D1y
- R1y) 2 + (bn
- Rn) 2 + (1\\y
- R2y) 2 Rtotal =
Dtotal Relative errors for maximum total dose rates are all less than 5%, with typical relative errors Jess than 1 %.
The dose rate at the normally occupied space (25 feet from the cask centerline) is 0.04 to 0.05 mrem/hr (0.3%
max relative error) for all configurations.
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BRRC Letter Amendment Page 23 of 45 Table 6-1: Tally Maximum Dose Rates (mrem/hr), Bottom Case NCT HAC Package Vehicle Surface 2 meter 1 meter Surface Reference Location Result Error Result Error Result Error Result Error Side 22.6 0.1%
2.7 0.1%
0.3 0.8%
1.5 0.4%
Top 0.1 0.2%
0.1 0.2%
0.1 3.1 %
Bottom 4.3 0.2%
4.3 0.2%
1.8 0.3%
Table 6-2: Tally Maximum Dose Rates (mrem/hr), Drain Case NCT HAC Package Vehicle Surface 2 meter 1 meter Surface Reference Location Result Error Result Error Result Error Result Error Side 20.6 0.1%
2.6 0.2%
0.3 1.3%
1.5 0.8%
Top 0.2 0.3%
0.2 0.3%
0.1 3.1%
Bottom 4.4 0.2%
4.4 0.2%
1.8 0.3%
Table 6-3: Tally Maximum Dose Rates (mrem/hr), Middle Case NCT HAC Package Vehicle Surface 2 meter 1 meter Surface Reference Location Result Error Result Error Result Error Result Error Side 25.7 0.1%
2.5 0.1%
0.3 0.2%
1.6 0.1%
Top 0.5 0.1%
0.5 0.1%
0.2 1.9%
Bottom 0.7 1.0%
0.7 1.0%
0.3 1.5%
Table 6-4: Tally Maximum Dose Rates (mrem/hr), Top Case NCT HAC Package Vehicle Surface 2 meter 1 meter Surface Reference Location Result Error Result Error Result Error Result Error Side 29.7 0.1 %
2.5 0.1%
0.3 0.2%
1.6 0.1%
Top 2.5 0.3%
2.5 0.3%
1.1 0.4%
Bottom 0.2 1.6%
0.2 1.6%
0.1 1.5%
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BRRC Letter Amendment Page 24 of 45 Table 6-5: Tally Maximum Dose Rates (mrem/hr), Vent Case NCT HAC Package Vehicle Surface 2 meter 1 meter Surface Reference Location Result Error Result Error Result Error Result Error Side 23.9 0.1%
3.5 1.4%
0.3 0.4%
1.4 0.1%
Top 15.3 2.9%
15.3 2.9%
5.2 2.8%
Bottom 0.2 1.7%
0.2 1.7%
0.1 2.6%
6.2 Summary Table of Maximum Radiation Levels The summary of the maximum dose rates are shown in Table 6-6 and Table 6-7 for NCT and HAC, respectively.
Table 6-6: Summary of Maximum NCT Total Dose Rates (Exclusive Use)
Normal Conditions Package Surface Vehicle Surface of Transport (mremlhr)
(mremlhr)
Radiation Top Side Bottom Top Side Bottom Gamma 12.9 0.1 0.3 12.9 1.3 0.3 Neutron 2.5 29.6 4.0 2.5 2.2 4.0 Total 15.3 29.7 4.4 15.3 3.5 4.4 10 CFR 71.47 (b) Limit 200 200 200 200 200 200 Normal Conditions 2 Meters from Vehicle Surface Occupied Location of Transport (mremlhr)
(mremlhr)
Radiation Top Side Bottom 25 ft from cask center Gamma 2.85E-02 8.69E-05 Neutron 0.3 4.94E-02 Total 0.3 4.95E-02 10 CFR 71.47 (b) Limit 10 10 10 2
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BRRC Letter Amendment Page 25 of 45 Table 6-7: Summary of Maximum HAC Total Dose Rates (Exclusive Use)
Hypothetical Accident 1 Meter from Package Surface Conditions (mrem/hr)
Radiation Top Side Bottom Gamma 4.2 2.80E-03 0.2 Neutron 1.0 1.6 1.6 Total 5.2 1.6 1.8 10 CFR 71.51 (a)(2) Limit 1000 1000 1000 Note: The total dose rates listed in Table 6-6 and Table 6-7 are the sum of the unrounded gamma and neutron dose rates.
6.3 Fissile Mass Assessment The fissile mass assessment performed in Section 4.2.3 demonstrates that the spent fuel payload is exempt from criticality analysis per 10 CFR 71.
7.0 COMPUTER SOFTWARE USAGE Computer Name:
Hardware Profile of Computer:
Operating System:
7.1 In-Use Testing 7.1.1 SCALE 6.2.1 EGONSIOROWSKI 1 Intel Xeon CPO ES-1650 @ 3.50 GHz, 16.0 GB RAM 64-bit Windows 7 Enterprise, Service Pack 1 Input fi les Jcc_PuBe.inp and JCi_Csl 37.inp are taken from the SCALE 6.2.1 software dedication report [1 O] for in-use testing. Both files are run on 2/27/2018. The resulting output fi les are identical to those in (10] except for run-unique parameters (such as date and time of run), indicating that SCALE 6.2.1 performs as expected and is acceptable for use.
7.1.2 MCNP6.1 Input files buildupJe_5 _mfp.i and buildup_yb_J_mfp.i are taken from the MCNP6.1 software dedication report (11] for in-use testing. Both files are run on 2/27/2018. The resulting output files are identical to those in [11]
except for run-unique parameters (such as date and time of run), indicating that MCNP6.1 performs as expected and is acceptable for use.
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BRRC Letter Amendment 7.2 File Listing Directory : Runs\\MCNP\\In-Use Testing Mode
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LastWriteTime 9/21/2017 2 : 20 PM 2/27/2018 2 : 07 PM 9/21/2017 2 : 20 PM 2/27/2018 2 : 08 PM Length Name 2974 buildup_fe_5_mfp. i 26440 buildup_fe_5_mfp. o 2706 buildup_pb_l_mfp.i 23829 buildup_pb_l_mfp. o Directory : Runs\\MCNP\\Shielding\\Bottom Mode LastWriteTime Length Name
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BRRC Letter Amendment
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3/2/2018 7:49 AM 2886 BRR_rodlet_pg_vent. m
-a---
3/2/2018 7 : 49 AM 113507 BRR_rodlet_pg_vent.mt
-a---
3/2/2018 7 : 49 AM 198860 BRR rodlet _pg_vent. o
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2/27/2018 4 : 01 PM 33452 BRR rodlet _sg_vent. i
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3/1/2018 9 : 11 AM 2366 BRR rodlet sg_vent. m
-a---
3/1/2018 9 : 11 AM 113507 BRR rodlet _ sg_vent. mt
-a---
3/1/2018 9 : 11 AM 292214 BRR rodlet sg_vent.o Directory : Runs\\SCALE\\In-Use Testing Mode LastWriteTime Length Name
- a - --
11/16/2016 3 : 30 PM 621 lee PuBe. inp
-a---
2/27/2018 2 : 11 PM 35481 lee PuBe. out
-a---
11/16/2016 11 : 43 AM 556 lCi Cs137. inp
-a---
2/27/2018 2 : 11 PM 22783 lCi Csl37. out Directory : Runs\\SCALE\\Source Term Mode LastWriteTime Length Name
- a ---
2/8/2018 2 : 04 PM 189448 605 Decay. f71
-a---
2/8/2018 1 : 10 PM 6341 605 Decay. inp
-a---
2/8/2018 2 : 04 PM 52068 605 Decay.out
-a---
2/8/2018 2 : 04 PM 189448 616 Decay.f71
-a---
2/8/2018 1 : 43 PM 3453 616 Decay. inp
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2/8/2018 2 : 04 PM 44950 616 Decay. out
-a---
2/8/2018 2 : 04 PM 189448 649 650 Decay. f71
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2/8/2018 1 : 22 PM 5124 649 650 Decay. inp
-a---
2/8/2018 2 : 04 PM 53142 649 650 Decay.out Page 27 of 45
Q Orano Federal Services orano
Title:
BRR Fuel Rod Segment Shielding Analysis Doc./Rev.: CALC-3020462-000 Project:
0191 O.OO.B001.28 -
BRRC Letter Amendment Page 28 of 45
-a---
-a---
2/27/2018 12 : 46 PM 2/27/2018 12 :4 6 PM Directory : Spreadsheets Mode LastWriteTime
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3/6/2018 4 : 16 PM
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2/12/2018 10 : 24 AM
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2/6/2018 10 : 55 AM
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12/22/2017 9 : 11 AM
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2/27/2018 1 : 17 PM 1927 Combined_Shipment. inp 223216 Combined_Shipment. out Length Name 38844 Compiled Shielding Results. xlsx 33183 Formatted Isotopes Table. xlsx 14746 General Tables.xlsx 11507 Materials. xlsx 16475 Source Term. xlsx Directory : Spreadsheets\\Shielding Results Mode LastWriteTime Length Name
-a---
3/5/2018 8 : 04 AM 493520 Bottom Shielding Results. xlsx
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3/5/2018 8 : 07 AM 493094 Drain Shielding Results. xlsx
-a---
3/5/2018 8 : 12 AM 490954 Middle Shielding Results. xlsx
-a---
3/5/2018 8 : 17 AM 493439 Top Shielding Results. x l sx
-a---
3/5/2018 8 : 30 AM 491218 Vent Shielding Results. xlsx
0 Orano Federal Services orano
Title:
BRR Fuel Rod Segment Shielding Analysis Doc./Rev.: CALC-3020462-000 Project:
01910.00.8001.28 -
BRRC Letter Amendment Page 29 of 45 8.0
- 1.
- 2.
- 3.
- 4.
- 5.
- 6.
- 7.
- 8.
- 9.
REFERENCES INL/EXT-17-44054, Sample Selection Report for the Irradiation and Post Irradiation Examination of Ultra High Burnup Fuel, Project Number 32792, Revision 1, January 2018 AREY A Federal Services SAR, BEA Research Reactor Package Safety Analysis Report, Revision 10, May 2016 Title 10, "Energy", Code of Federal Regulations, Part 71, Packaging and Transportation of Radioactive Material NUREG-1609, Standard Review Plan/or Transportation Packages for Radioactive Material, March 1999 Regulatory Guide 7.9, Standard Format and Content of Part 71 Applications for Approval of Packages for Radioactive Material, Revision 2, March 2005 ORNL/TM-2005/39, SCALE Code System, Oak Ridge National Laboratory, Version 6.2.1, August 2016, RSICC Package ID C00834MNYCP02 ORNL/TM-2005/39, Version 6, Volume III, Section M8, Standard Composition Library, Oak Ridge National Laboratory, January 2009 PNNL-15870, Compendium of Material Composition Data for Radiation Transport Modeling, Pacific Northwest National Laboratory, Revision 1, March 20 11 LA-CP-13-00634, MCNP6' User 's Manual, Los Alamos National Laboratory, Version 1.0, May 2013, RSICC Package ID C8 l OMNYCPOO
- 10. AREVA Federal Services Calculation, CALC-3018409, Software Dedication Report for SCALE 6.2.1, Revision 0
- 11. AREVA Federal Services Calculation, CALC-3012588, Software Dedication Report for MCNP v6.1.00, Revision 0
- 12. NISTISEMATECH e-Handbook of Statistical Methods, http://www.itl.nist.gov/div898/handbook/mpc/section5/mpc55.htm, January 17, 2018.
- 13. Knight, Collin J., "Re: Draft Rod Fragments Container", Message to Phil Noss, February 2018, E-mail (See Section 8.1 for email content)
- 14. DOE-HDBK-1019/2-93, DOE Fundamentals Handbook: Nuclear Physics and Reactor Theory, U.S.
Department of Energy, Volume 2, January 1993
- 15. Knight, Collin J., "LWR Fuel Shipping Details", Message to Phil Noss, March 2018, E-mail (see Section 8.2 for email content)
0 Orano Federal Services orano
Title:
BRR Fuel Rod Segment Shielding Analysis Doc./Rev.: CALC-3020462-000 Project:
01910.00.B001.28 -
BRRC Letter Amendment 8.1 E-mail Reference 1 From: Knight, Collin J Sent: Monday, February 26, 2018 3 : 42 PM To: NOSS Philip (ORN-RE)
Page 30 of 45 Cc: SMITH Richard (ORN-RE) ; Case, Susan M; Daniel M Wachs ; Nicholas Meacham
Subject:
Re : Draft Rod Fragments Container Phil,
Just wanted to touch base with you. I apologize for the slow response in getting you the information you have requested. I have had a difficult time in getting information from ORNL and INL has had some folks out as well. I haven ' t forgot that I owe you some information.
With regards to the small "buffer " or excess material, if we were to receive some additional fuel, it is expected that it would be in the form of 9 inches of fuel segment 650 and 20 inches of fuel segment 616. I hope this helps. If this gives us problems, p l ease let me know.
I still hope to get back to you this week with feedback on the container. In general, I haven ' t heard anyone say anything significant about the cont ainer design. I think there was some concern that the bolt which will be used to h ook and remove the spacer underneath t he container might gouge the basket. That might be something worth a slight modification.
Please let me know if you have any concerns or issues.
Thank you.
Collin
0 Orano Federal Services orano
Title:
BRR Fuel Rod Segment Shielding Analysis Doc./Rev.: CALC-3020462-000 Project:
01910.00.8001.28 -
BRRC Letter Amendment 8.2 E-mail Reference 2 From : Knight, Collin J Sent: Wednesday, March 07, 2018 10 : 27 AM To: NOSS Philip (ORN-RE)
Page 31 of 45 Cc : SMITH Ri c hard (ORN-RE) ; Daniel M Wachs ; David A Sell ; Nicholas Meacham Subjec t: LWR Fuel Shipping Details Phi l,
For clarification, shown in the table below are the 14 segments that are planned to be s hipped from ORNL to HFEF.
For t he "buffer ", we would l ike to add 3 segments.
These segments are found in t he cutting diagram below.
They i nclude the 9" cut shown for Rod A segment 650E2 - M3&H3, the 7 " cut shown for Rod C segment 616Cl - A7,
and the 13 " cut shown for Rod C segment 616D-A8.
These would be open ended like the smaller segments shown in the table.
I included the total shipment isotopics,
including the 3 additional segments, in the attached spr eadsheet.
Table 8. Tramt>Ortation plan with se2ment lerucths to be shipped to INL from ORNL.
s.,...
Sptcimu,m
""'"'"'-.ll 64\\lCI-A:!
........,.A3 649CJ-M d0!B&9-A.l 605BS-C.A6 6J<<:!-A7 61©-A&
""°M-?\\llhJ 650Cl-?ull:H2 Ml'C',J_:\\_.r...r,.u "'
&l5&'9-1'!4&H4 616Cl-Ml
.£'1.cn. ~r.!'i ColltllUll.g Otigml Sutplu s.i-mm
~1R-1 A1R-2 64PCJ 4 "Tl>.J
...ar, A1R-4
"""'"l A1R-l MjD R9 A1R-6 R\\<"-'<9 A"IR-7 6U!CI A1R-1 616D
!\\l!t-1 & H*a""'-'
MO<'l MM-2.& Hu.tri-2 6lOCI
?,,*rat-.., A,c Ua.. ~ &. 1
=...
1'1<<-4 & H*a lirl !>-4
@SB-S.9 lll!t*.l dll!CI lll*HI 5.0"
- >9U"'onl6SOE2 Sptcimtll Lugfh(i
- a.)
6.1 6.&
6.!
6.&....
6Jt 6.1 6.l 2.0 2.0
'11 25 1.0 1.0 Segmenl 6058-8111 Fllolt d Aq.Binq, Du(larp Lu,gfh.(ia..)
MWd'tgU Ye*
<.o 82 2004 5.0 11:2 1004 50 Tl 5.0 73 2004
<.o
@-ll 19,>l
<.o 60-7'
'~"
5.0 51 llll>i 5.0 51 1!9i 2.0 S2
-,,n,.
2.0 73 2004 i n 7'
,~~
l.5 69-72 111!!5 1.0 51 1997 1.0 51 1!97 Segmen165002 Segm,int 6058-7 Co*m.mtnt Ea!a-d Ema-d
"""~-~
Emaootd Ea!a-d E,xlann,d E<llaoood Ema"""d
"""!H!r.d,d
"""!><r.dld n..,._
--~
- n...,...,.dl!d n...,,..r.dld
°"!~r.d!d We met with the HFEF hot cel l folks today and got fe e dback from them on t he shi pping container.
When would you be available to discuss the results of our meeting?
Please advise.
Collin
Q Orano Federal Services orano
Title:
BRR Fuel Rod Segment Shielding Analysis Doc./Rev.: CALC-3020462-000 Project:
01910.00.B001.28 -
BRRC Letter Amendment APPENDIX A: INPUT DAT A A.1 Sample SCALE Input File (Combined_Shipment.inp)
=origen bounds{
gamma
' v7.l-28n19g ' % 19 Gamma Groups neutron= ' v7.l - 28n19g ' % 28 Neutr on Groups solver{
type= cram opt{
substeps 4
case{mat_605) {
lib{file= "end7dec " }
mat{
load{f i le= "C: \\SCALE-6. 2. l\\SCALE_Run_Folder\\BRR_Letter\\605_Decay. f71 " pos=7}
time{
uni ts t=O.l print{
seconds rel cutoff= no cutoffs [curies = l e-15 ]
nuc{
uni ts=[grams curies]
case{mat_616) {
l ib{fi l e= "end7dec " )
mat{
load{fi l e= "C: \\SCALE-6.2. l\\SCALE_Run_Folder\\BRR_Letter\\616_Decay. f71 " pos=7}
time{
units= seconds t =O. l print{
rel cutoff= no cutoffs[curies = le-15]
nuc{
units= [grams curies]
c a se(mat 649 650) {
lib {~ile:"e nd7dec " }
mat {
load{file= "C: \\SCALE-6.2. l\\SCALE_Run_Folder\\BRR_Letter\\649_ 650_Decay. f71 " pos=7) time{
uni ts t=0. 1 print{
seconds rel cutoff= no cutof fs [curies = le-15 )
nuc{
units= [grams curies]
Page 32 of 45
(}
Orano Federal Services orano
Title:
BRR Fuel Rod Segment Shielding Analysis Doc./Rev.: CALC-3020462-000 Project:
01910.00.8001.28 -
case{
lib{file="end7dec " }
time{
units = seconds t=O.l print{
rel cutoff= no gamma {
nuc{
spectra= yes summary yes BRRC Letter Amendment units
[curies watts grams]
total yes end neutron{
gamma{
spectra= yes summary= yes detailed = yes conserve_line_energy no brem medium= uo2 neutron{
alphan_medium = uo2 save{file="Combined_Shipment. f71 " }
mat{
blend[mat_605 = 1 mat 616 = 2.67 mat_649_650 = 1. 33]
Page 33 of 45
(}
Orano Federal Services orano
Title:
BRR Fuel Rod Segment Shielding Analysis Doc./Rev.: CALC-3020462-000 Project:
01910.00.8001.28 -
BRRC Letter Amendment Page 34 of 45 A.2 Sample MCNP Input File (BRR_rodlet_pg_bot.i)
BRR Rodlets Shielding C *** Cell Cards ***
C C===== Air Gaps and Thermal Shield 1
1
-0.0012 101 -102 19 -20 imp:p=l fill=2 2
$ radial gap (Pb shrinkage 1/16 " )
2 1
-0.0012 133 -132 3 -301 imp:p=l fill=22
$ top axial gap (Pb shrinkage 1/4 " )
3 1
-0.0012 201 -200 24 -25 imp:p=l fill=22
$ air gap thermal shield 4
4
-7.94 201 -200 25 -26 imp:p=l fill =21
$ ss shell over thermal gap 5
1
-0.0012 309 -100 -306 imp:p=l fill=32
$ vertical drain hole 95 6
1
-0.0012
-307 308 -24 (-309 : 306) imp:p=l fill =32
$ horizontal drain hole 96 7
1
-0.0012
-135 137 37
-36 imp :p=l fill=l4
$ radial gap at lid 8
1
-0.0012 157 -150 (44 303) (-1:-302) imp:p=l fill=l4
$ Air below shield plug 9
1
-0.0012 (150 -141 40 -41) :
(141 -137 -41) imp :p=l fill=l4
$ Air above shield plug 10 1
-0. 0012 157 -141 -161 imp:p=l fill =l 3
$ Shield plug drain C
c===== Rebuilt cells 11 8
-11.35 (1555 -1431 161 -45) :
(160 -140 46 -43 161) imp:p=l fill=lO
$ Shield plug lead 12 4
- 7. 94
( (157 -150 (-44 : -303) 161) (-1555: 45)):
(150 -160 45 -40) :
(160 -141 43 -40) :
(140 -141 -43 161) imp :p=l fill=ll
$ Shield plug steel 13 4
-7.94 1431 -140 -46 imp :p=l fill =ll
$ Shield plug steel insert 14 4
-7.94 (157 -132 (1 302) - 3) :
(132 -150 302 -24) imp:p=l fill=12
$ Lower top steel 15 4
-7.94 (150 -135 41 -24)
(-138 :-35) (-37 : 36: -1 37) imp:p=l fill=l2
$ Corner top steel 16 4
-7.94 137 -135 -41 imp:p=l fill=ll
$ Upper top steel 17 8
-11. 35
( (103 -300) (-133 -301) 3 -19) :
(101 -102 3 -19) imp:p=l fill=20
$ Side wall lead 18 4
-7. 94 100 -157 1 - 3 imp:p=l fill=21
$ Inner side wall steel 19 4
-7. 94 103 -132 3 -20
( (300 -101): (301 102))
imp:p=l fill=21
$ Side wall steel wedges 20 4
-7. 94 103 -132 20 -24 imp:p=l fill=21
$ Outer side wall steel 21 8
-11. 35 125 -106 -33 (-27 :-114) imp:p=l fill=30
$ Bottom lead 22 4
- 7.94 114 -100 -24 (27 : 106) (-103 :-3)
(-309 : 100: 306)
(-308 : 24:307) imp:p=l fill=31
$ Upper bottom steel 23 4
-7. 94 127 -114 -24 (126:-35) (-125 : 33) imp:p=l fill=31
$ Lower bottom steel C
24 0
-1 100 -157 fill=l (19.82 0 -0. 1426) imp:p=l
$ insert basket 25 0
((351.l:351.2:350.1 : 350.2:50) -999) :
(201 -200 26 -50) imp :p=l
$ Outer air 26 0
999 imp:p=O 27 0
(24: 135 : (138 35))
(200 350. 3 -50) : -350 imp :p=l
$ Uppper impact limiter 28 0
(24: -127: (-126 35))
(351.3 -201 -50):-351 imp:p=l
$ Lower impact limiter C
C ----- Universe 1 : Source Sphere 100 0
-400 imp:p=l u=l 101 1 -0.0012 400 imp :p=l u=l C - - --- Universe 10 : Top Lead Splitting Layers 1003 8 -11. 35
-1003 imp:p=2.42E+Ol u=lO 1004 8 -11. 35
-1004 1003 imp:p=6.74E+Ol u=lO 1005 8 -11. 35
-1005 1004 imp:p=l. 34E+02 u=lO 1006 8 -11. 35
-1006 1005 imp:p=2. 54E+02 u=lO 1007 8 -11.35
-1007 1006 imp : p=4. 74E+02 u=lO 1008 8 -11.35
-1008 1007 imp : p=8. 72E+02 u=lO 1009 8 -11. 35
-1009 1008 imp:p=l.58E+03 u=lO 1010 8 -11.35
-1010 1009 imp:p=2.87E+03 u=lO 1011 8 -11. 35
-1011 1010 imp : p=5.10E+03 u=lO 1012 8 -11. 35
-1012 1011 imp:p=8.88E+03 u=lO 1013 8 -11.35
-1013 1012 imp : p=l.54E+04 u=lO 1014 8 -11. 35
-1014 1013 imp:p=2.58E+04 u=lO
0 Orano Federal Services orano
Title:
BRR Fuel Rod Segment Shielding Analysis Doc.!Rev.: CALC-3020462-000 Project:
0191 O.OO.B001.28 -
1015 8 -11.35 1016 8 -11.35 1017 8 - 11. 35 1018 8 -11. 35 1019 8 -11. 35 1020 8 -11. 35 1021 8 - 11. 35 1022 8 -11.35 1023 8 -11. 35 1024 8 -11. 35 1025 8 -11. 35 1026 8 -11. 35 C
-1015 1014
-1016 1015
- 1017 1016
-1018 1017
-1019 1018
-1020 1019
-1021 1020
-1022 1021
-1023 1022
-1024 1023
-1025 1024 1025 BRRC Letter Amendment imp : p=4.30E+04 u=lO imp : p=7.32E+04 u=lO imp : p=l.72E+04 u=lO imp : p=4.98E+04 u=lO imp : p=l. 02E+05 u=lO imp :p=l.95E+05 u=lO imp :p=3.57E+05 u=lO i mp : p=6. 04E+05 u=lO i mp : p=9.84E+05 u=lO imp : p=l. 59E+06 u=lO imp : p=2.43E+06 u=lO imp :p=2.99E+06 u=lO c===== Universe 11: Top Steel Splitting Layers 1100 4 -7. 94
-1000 1101 4 -7. 94
-1001 1000 1102 4 -7.94
-1002 1001 1103 4 -7. 94
-1003 1002 1104 4 -7.94 1105 4 -7.94 1106 4 -7. 94 1107 4 -7. 94 1108 4 -7.94 1109 4 -7. 94 1110 4 -7.94 1111 4 -7.94 1112 4 -7. 94 1113 4 -7. 94 1114 4 -7. 94 1115 4 -7. 94 1116 4 -7.94 1117 4 -7. 94 1118 4 -7.94 1119 4 -7. 94 1120 4 -7. 94 1121 4 -7.94 1122 4 -7. 94 1123 4 -7.94 1124 4 -7. 94 1125 4 -7. 94 1126 4 -7. 94 1127 4 -7. 94 1128 4 - 7. 94 1129 4 - 7. 94 1130 4 -7. 94 1131 4 -7. 94 1132 4 -7. 94 1133 4 -7. 94 C
-1004 1003
-1005 1004
-1006 1005
-1007 1006
-1008 1007
-1009 1008
-1010 1009
-1011 1010
-1012 1011
-1013 1012
-1014 1013
-10 15 1014
-1016 1015
-1017 1016
-1018 1017
-1019 1018
-1020 1019
-1021 1020
-1022 1021
-1023 1022
-1024 1023
-1025 1024
-1026 1025
-1027 1026
- 1028 1027
-1029 1028
-1030 1029
-1031 1030
-1032 1031 1032 c===== Universe 12: Top Steel Corner 1200 4 -7. 94
- 1050 1201 4 - 7.94 1202 4 -7. 94 1203 4 -7. 94 1204 4 - 7.94 1205 4 - 7. 94 1206 4 -7. 94 1207 4 -7.94 1208 4 -7. 94 1209 4 -7.94 1210 4 -7. 94 1211 4 -7. 94 1212 4 -7. 94 1213 4 -7. 94 1214 4 -7.94 1215 4 -7. 94 1216 4 -7. 94 1217 4 -7. 94 1218 4 -7. 94
-1051 1050
-1052 1051
-1053 1052
-1054 1053
- 1055 1054
-1056 1055
-1057 1056
-1058 1057
-1059 1058
-1060 1059
-1061 1060
-1062 1061
-1063 1062
-1064 1063
-1065 1064
-1066 1065
-1067 1066
-1068 1067 imp : p=8.00E+OO u=ll imp:p=l.04E+Ol u=ll imp:p=l.65E+Ol u=ll imp : p=2. 42E+Ol u=ll imp:p=3. 24E+Ol u=ll imp:p=4.51E+Ol u=ll imp : p=6.44E+Ol u=ll imp:p=9.44E+Ol u=ll imp:p=l. 42E+02 u=ll imp : p=2.14E+02 u=ll imp:p=3.27E+02 u=ll imp:p=5.10E+02 u=ll imp:p=8.08E+02 u=ll imp:p=l. 18E+03 u=ll imp:p=7.09E+02 u=ll imp:p=7.11E+02 u=ll imp:p=7.56E+02 u=ll imp:p=8.96E+02 u=ll imp:p=l. 44E+03 u=ll imp :p=2. 18E+03 u=ll imp : p=3.09E+03 u=ll imp:p=4. 39E+03 u=ll imp :p=6. 21E+03 u=ll imp :p=8. 72E+03 u=ll imp : p=l.2 1E+04 u=ll imp : p=l. 70E+04 u=ll imp : p=2.38E+04 u=ll imp : p=3. 39E+04 u=ll imp:p=5.14E+04 u=ll imp : p=9. 12E+04 u=ll imp : p=l.34E+05 u=ll imp:p=2.04E+05 u=ll imp:p=3.11E+05 u=ll imp:p=4.98E+05 u=ll Splitting Layers imp:p=8.00E+OO u=l2 i mp:p=l.04E+Ol u=l2 imp:p=l. 65E+Ol u=l2 imp:p=2.42E+Ol u=l2 imp :p=3. 24E+Ol u= l 2 imp : p=4.51E+Ol u=l2 imp : p=6. 44E+Ol u=l2 imp :p=9. 44E+Ol u=l2 imp : p=l.42E+02 u=l2 imp : p=2.14E+02 u=l 2 imp:p=3. 27E+02 u=l2 imp : p=5.10E+02 u=l2 imp : p=8. 08E+02 u=l2 imp : p=l.18E+03 u=l2 imp : p=7.09E+02 u=l2 imp:p=7. 11E+02 u=l2 imp:p=7.56E+02 u=l2 imp:p=8.96E+02 u=l2 imp:p=l.44E+03 u=l2 Page 35 of 45
0 Orano Federal Services orano
Title:
BRR Fuel Rod Segment Shielding Analysis Doc.I Rev.: CALC-3020462-000 Project:
01910.00.8001.28 -
BRRC Letter Amendment 1219 4 -7. 94 1220 4 -7. 94 1221 4 -7.94 1222 4 -7. 94 1223 4 -7. 94 1224 4 -7. 94 1225 4 -7.94 1226 4 -7. 94 1227 4 -7. 94 1228 4 -7. 94 1229 4 -7. 94 1230 4 -7.94 1231 4 -7.94 1232 4 -7. 94 1233 4 -7.94 1234 4 -7.94 1235 4 -7.94 1236 4 -7. 94 1237 4 -7. 94 1238 4 -7. 94 C
-1069 1068
-1070 1069
- 1071 1070
-1072 1071
-1073 1072
- 1074 1073
- 1075 1074
-1076 1075
-1077 1076
-1078 1077
-1079 1078
-1080 1079
-1081 1080
- 1082 1081
-1083 1082
- 1084 1083
-1085 1084
-1086 1085
-1087 1086 1087 c===== Universe 13: Central 1300 1 -0.0012
-1000 1301 1 -0. 0012
-1001 1000 1302 1 -0.0012
-1002 1001 1303 1 -0.0012
-1003 1002 1304 1 -0. 0012 1305 1 -0. 0012 1306 1 -0. 0012 1307 1 -0. 0012 1308 1 -0. 0012 1309 1 -0. 0012 1310 1 -0. 0012 1311 1 -0.0012 1312 1 -0.0012 1313 1 -0. 0012 1314 1 -0. 0012 1315 1 -0.0012 1316 1 -0. 0012 1317 1 -0.0012 1318 1 -0. 0012 1319 1 -0. 0012 1320 1 -0. 0012 1321 1 -0. 0012 1322 1 -0.0012 1323 1 -0. 0012 1324 1 -0. 0012 1325 1 -0.0012 1326 1 -0. 0012 1327 1 -0. 0012 1328 1 -0.0012 C
-1004 1003
-1005 1004
-1006 1005
-1007 1006
-1008 1007
-1009 1008
-1010 1009
-1011 1010
-1012 1011
-10 13 1012
-1014 1013
- 1015 1014
-1016 1015
-10 17 1016
- 1018 1017
-1019 1018
-1020 1019
-1021 1020
-1022 1021
-1023 1022
-1024 1023
-1025 1024
-1026 1025
-1027 1026 1027 imp:p=2.1 8E+03 u=12 imp:p=3. 09E+03 u=12 imp : p=4. 39E+03 u=12 imp:p=6.21E+03 u=12 imp:p=8.72E+03 u=12 imp :p=l. 21E+04 u=l2 imp : p=l.70E+04 u=l2 imp : p=2. 38E+04 u=12 imp : p=3. 39E+04 u=l2 imp : p=5. 14E+04 u=12 imp : p=7.79E+04 u=12 imp :p=l.15E+05 u=l2 imp : p=l.70E+05 u=l2 imp : p=2. 41E+05 u=12 imp : p=3. 57E+05 u=12 imp :p=5. 26E+05 u=l2 imp : p=8. 40E+05 u=12 imp : p=l.50E+06 u=12 imp:p=l.50E+06 u=12 imp : p=l.50E+06 u=l2 Drain Air Splitting Layers imp : p=8.00E+OO u=13 imp:p=l.04E+Ol u=l3 imp:p=l.65E+Ol u=13 i mp : p=2. 42E+Ol u=13 imp:p=6. 74E+Ol u=l3 imp:p=l. 34E+02 u=l3 imp:p=2. 54E+02 u=13 imp:p=4.74E+02 u=13 imp:p=8.72E+02 u=13 imp:p=l.58E+03 u=13 imp : p=2.87E+03 u=l3 imp : p=5. 10E+03 u=13 imp : p=8.88E+03 u=l3 imp : p=l.54E+04 u=l3 imp :p=2.58E+04 u=l3 imp : p=4. 30E+04 u=l3 imp : p=7.32E+04 u=l3 imp : p=l.72E+04 u=l3 imp : p=4. 98E+04 u=13 imp : p=l. 02E+05 u=13 imp : p=l.95E+05 u=13 imp:p=3.57E+05 u=13 imp : p=6.04E+05 u=13 imp : p=9. 84E+05 u=13 imp : p=l.59E+06 u=13 imp : p=2.43E+06 u=13 imp : p=2.99E+06 u=l3 imp:p=3.39E+04 u=13 imp:p=5. 14E+04 u=13 c===== Universe 14: Shield Plug Side Air 1400 1 -0. 0012
-1000 Splitting Layers imp :p=8. 00E+OO u=1 4 imp : p=l.04E+Ol u=l4 imp :p=l. 65E+Ol u=l4 imp : p=2. 42E+Ol u=l4 i mp : p=3. 24E+Ol u=l4 imp : p=4.51E+Ol u=l4 imp : p=6. 44E+Ol u=14 imp:p=9. 44E+Ol u=l4 imp : p=l. 42E+02 u=14 imp : p=2.14E+02 u=l4 imp : p=3. 27E+02 u=l4 imp : p=S. 10E+02 u=l4 imp : p=8. 08E+02 u=l4 imp : p=l. 18E+03 u=l4 imp:p=7.09E+02 u=l4 imp : p=7. 11E+02 u=l4 1401 1 -0. 0012
-1001 1000 1402 1 -0.0 012 1403 1 - 0. 0012 1404 1 -0.0012 1405 1 -0. 0012 1406 1 -0.0012 1407 1 -0. 0012 1408 1 -0. 0012 1409 1 -0. 0012 1410 1 -0. 0012 1411 1 -0. 0012 1412 1 -0. 0012 1413 1 -0. 00 12 1414 1 -0. 0012 1415 1 -0. 0012
-1002 1001
- 1003 1002
- 1004 1003
-1005 1004
-1006 1005
-1007 1006
-1008 1007
-1009 1008
-1010 1009
-1011 1010
-1012 1011
-1013 1012
-1014 1013
-1015 1014 Page 36 of 45
L 0
Orano Federal Services orano
Title:
BRR Fuel Rod Segment Shielding Analysis Doc./Rev.: CALC-3020462-000 Project:
01910.00.8001.28 -
BRRC Letter Amendment 1416 1 -0. 0012 1417 1 -0.0012 1418 1 -0.0012 1419 1 -0.0012 1420 1 -0.0012 1421 1 -0. 0012 1422 1 - 0. 0012 1423 1 - 0.0012 1424 1 - 0.0012 1425 1 -0. 0012 1426 1 -0. 0012 1427 1 -0. 0012 1428 1 -0. 0012 1429 1 -0.0012 1430 1 - 0. 00 12 1431 1 - 0. 0012 1432 1 -0.0012 1433 1 -0.0012 C
-1016 1015
-1017 1016
-1018 1017
-1019 1018
-1020 1019
-1021 1020
- 1022 102 1
- 1023 1022
-10 24 1023
-1025 1024
- 1026 1025
-1027 1026
-1028 1027
-1029 1028
-1030 1029
-1031 1030
-1032 1031 1032 c===== Universe 20 : Side Lead Splitting 2002 8 -11.35
- 2002 2001 2003 8 -11.35
-2003 2002 2004 8 - 11. 35
-2004 2003 2005 8 -11.35
-2005 2004 2006 8 -11.35
- 2006 2005 2007 8 -11.35
-2007 2006 2008 8 - 11.35
-2008 2007 2009 8 -11. 35
- 2009 2008 2010 8 -11.35 2011 8 - 11. 35 2012 8 - 11. 35 2013 8 -11. 35 2014 8 -11. 35 20 15 8 - 11. 35 2016 8 - 11. 35 2017 8 -11. 35 2018 8 -11. 35 2019 8 - 11. 35 2020 8 - 11. 35 2021 8 -11. 35 2022 8 -11.35 2023 8 -11. 35 C
- 20 10 2009
-2011 2010
-2012 2011
- 2013 2012
- 20 14 2013
-2015 2014
-2016 2015
- 2017 2016
- 2018 2017
-2019 2018
- 2020 2019
- 202 1 2020
- 2022 2021
-2023 2022 c===== Universe 21 : Side Steel Splitting 2100 4 -7.94
-2000 2101 4 - 7.94 2102 4 -7.94 2111 4 -7. 94 2112 4 -7.94 2113 4 -7. 94 2114 4 -7.94 2115 4 -7. 94 2116 4 -7.94 2117 4 - 7. 94 2118 4 - 7. 94 2119 4 -7.94 2120 4 -7.94 2121 4 -7.94 2122 4 - 7. 94 2123 4 - 7.94 2124 4 - 7. 94 2125 4 - 7. 94 2126 4 -7. 94 2127 4 - 7.94 2128 4 - 7. 94 C
-2001 2000
- 2002 2001
- 20 11 2010
-2012 2011
-2013 2012
- 20 14 2013
-2015 2014
-2016 2015
- 20 17 2016
-2018 2017
-2019 2018
-2020 2019
-202 1 2020
-2022 2021
- 2023 2022
- 202 4 2023
-2025 2024
-2026 2025
- 2027 2026 2027 imp:p=7.56E+02 u=l4 imp:p=8. 96E+02 u=l4 imp:p=l.44E+03 u=l4 imp:p=2. 18E+03 u=l4 imp :p=3.09E+03 u= l 4 imp :p=4. 39E+03 u=l4 imp : p=6. 21E+03 u=l4 imp :p=8. 72E+03 u=l4 imp:p=l. 21E+04 u=l4 imp:p=l.70E+04 u=l4 imp :p=2. 38E+04 u=l4 imp:p=3.39E+04 u=l4 imp:p=5. 14E+04 u=l4 imp:p=2. 41E+05 u=l4 imp : p=3. 57E+05 u=l4 imp : p=5.26E+05 u=l4 imp : p=8.40E+05 u=l4 imp : p=l. 50E+06 u=l4 Layers imp :p=2. 75E+OO u=20 i mp :p=3. 70E+ OO u=20 imp :p=8. 60E+OO u=20 imp :p=l.73E+Ol u=20 imp:p=3. 38E+Ol u=20 i mp :p=6. 55E+Ol u=20 imp :p=l.27E+02 u=20 imp:p=2. 42E+02 u=20 imp:p=4. 65E+02 u=20 imp:p=8. 83E+02 u=20 imp:p=l.68E+03 u=20 imp:p=3. 20E+03 u=20 imp:p=6. 05E+03 u=20 i mp:p=l. 15E+04 u=20 imp:p=2. 15E+04 u=20 imp:p=4. 03E+04 u=20 imp:p=7. 78E+04 u=20 imp : p=l. 47E+05 u=20 i mp : p=2. 75E+05 u=20 imp:p=5. 15E+05 u=20 imp:p=9.78E+05 u=20 imp :p=l. 84E+06 u=20 Layers imp : p=l. OOE+OO u=21 imp : p=l. 34E+OO u=21 imp : p=2.01E+OO u=21 imp : p=8. 83E+02 u=21 imp : p=l. 36E+03 u=21 imp : p=2. 14E+03 u=21 imp : p=l. 70E+03 u=21 imp : p=3. 20E+03 u=21 imp : p=5. 80E+03 u=21 i mp : p=l. 10E+04 u=21 imp : p=2. 01E+04 u=21 imp : p=3.65E+04 u=21 imp:p=6. 50E+04 u=21 imp : p=l.18E+05 u=21 imp : p=2. 14E+05 u=21 imp:p=l.84E+06 u=21 imp : p=2. 18E+06 u=21 imp:p=2. 80E+06 u=21 imp:p=3.78E+06 u=21 imp:p=5.45E+06 u=21 imp : p=7.93E+06 u=21 c===== Universe 22 : Side Air Splitting Layers 2202 1 - 0.0012
-2002 2001 imp : p=2. 75E+OO u=2 2 2203 1 -0.0012
-2003 2002 imp:p=l.89E+OO u=22 Page 37 of 45
Q Orano Federal Services orano
Title:
BRR Fuel Rod Segment Shielding Analysis Doc./Rev.: CALC-3020462-000 Project:
0191 O.OO.B001.28 -
BRRC Letter Amendment Page 38 of 45 2204 1 -0. 0012
-2004 2003 imp : p=2. 28E+OO u=22 2205 1 -0.0012
-2005 2004 imp:p=3.50E+OO u=22 2206 1 -0. 0012
-2006 2005 imp : p=4.88E+OO u=22 2207 1 -0.0012
-2007 2006 imp:p=6.40E+OO u=22 2208 1 -0. 0012
-2008 2007 imp : p=8.33E+OO u=22 2209 1 -0. 0012
- 2009 2008 imp : p=l.08E+Ol u=22 2210 1 -0.0012
- 2010 2009 imp : p=l.23E+Ol u=22 2211 1 -0. 0012
-2011 2010 imp:p=l. 44E+Ol u=22 2212 1 -0. 0012
-2012 2011 imp : p=2.49E+Ol u=22 2213 1 -0.0012
-2013 2012 imp:p=4.13E+Ol u=22 2214 1 -0. 0012
-20 14 2013 i mp : p=2.78E+02 u=22 2223 1 -0. 0012
-2023 2022 imp : p=l. 8 4E+O 6 u=22 2228 1 -0.0012 2027 imp : p=7.93E+06 u=22 C
C===== Universe 30: Bottom Lead Splitting Layers 3003 8 -11. 35 3003 imp :p=2.19E+Ol u=30 3004 8 -11.35
-3003 3004 imp:p=5. 27E+Ol u=30 3005 8 -11. 35
-3004 3005 imp : p=l.01E+02 u=30 3006 8 -11.35
-3005 3006 imp:p=l.86E+02 u=30 3007 8 -11.35
-3006 3007 imp : p=3. 24E+02 u=30 3008 8 -11. 35
-3007 3008 imp:p=5.35E+02 u=30 3009 8 -11. 35
-3008 3009 imp :p=9.01E+02 u=30 3010 8 -11. 35
-3009 3010 imp : p=l.44E+03 u=30 3011 8 -11. 35
-3010 3011 imp:p=2. 26E+03 u=30 3012 8 -11. 35
-3011 3012 imp:p=2.26E+03 u=30 3013 8 -11. 35
-3012 3013 imp:p=5.71E+03 u=30 3014 8 -11. 35
-3013 3014 imp :p=l. 19E+04 u=30 3015 8 -11. 35
-3014 3015 imp : p=2.34E+04 u=30 3016 8 -11. 35
- 3015 3016 imp : p=4.50E+04 u=30 3017 8 -11.35
- 3016 3017 imp : p=8.51E+04 u=30 3018 8 -11. 35
-3017 3018 imp : p=l. 60E+05 u=30 3019 8 -11. 35
-3018 3019 imp : p=2.99E+05 u=30 3020 8 -11.35
-3019 3020 imp : p=5.57E+05 u=30 3021 8 -11.35
-3020 3021 imp : p=l.03E+06 u=30 3022 8 -11. 35
-3021 imp:p=l.80E+06 u=30 C
c===== Universe 31: Bottom Steel Splitting Layers 3100 4 -7.94 3000 imp:p=8 u=31 3101 4 -7.94
-3000 3001 imp:p=l.lOE+Ol u=31 3102 4 -7. 94
-3001 3002 imp:p=l.55E+Ol u=31 3103 4 -7. 94
-3002 3003 imp : p=2.19E+Ol u=31 3104 4 -7. 94
-3003 3014
-3050 i mp :p=2.19E+Ol u=31 3105 4 -7.94
-3003 3014 3050 -3051 imp : p=2. 19E+Ol u=31 3106 4 -7.94
-3003 3014 3051 -3052 imp : p=2. 76E+Ol u=31 3107 4 -7.94
-3003 3014 3052 -3053 imp:p=3.80E+Ol u=31 3108 4 -7.94
-3003 3014 3053 -3054 imp : p=5.19E+Ol u=31 3109 4 -7.94
-3003 3014 3054 -3055 imp:p=7.24E+Ol u=31 3110 4 -7.94
-3003 3014 3055 -3056 imp:p=l.02E+02 u=31 3111 4 -7.94
-3003 3014 3056 -3057 imp:p=l. 44E+02 u=31 3112 4 -7.94
-3003 3014 3057 -3058 imp:p=2. 23E+02 u=31 3113 4 -7.94
-3003 3014 3058 -3059 imp :p=4.18E+02 u=31 3114 4 -7.94
- 3003 3014 3059 -3060 imp : p=l.15E+03 u=31 3115 4 -7.94
-3003 3014 3060 -3061 imp : p=5. 31E+03 u=31 3116 4 -7. 94
-3003 3014 3061 -3062 imp : p=2. 48E+04 u=31 3117 4 -7.94
-3003 3014 3062 -3063 imp : p=6.93E+04 u=31 3118 4 -7.94
- 3003 3014 3063 -3064 imp : p=l. 35E+05 u=31 3119 4 -7.94
-3003 3014 3064 -3065 imp : p=2.18E+05 u=31 3120 4 -7.94
-3003 3014 3065 -3066 imp : p=4. 18E+05 u=31 3121 4 -7.94
-3003 3014 3066 -3067 imp:p=4.76E+06 u=31 3122 4 -7.94
- 3003 3014 3067 -3068 imp:p=2.38E+07 u=31 3123 4 -7. 94
-3003 3014 3068 imp :p=2.86E+07 u=31 3124 4 -7.94
-3014 3015 imp :p=4. 18E+05 u=31 3125 4 -7.94
-3015 3016 imp :p=5. 39E+05 u=31 3126 4 -7.94
-3016 3017 imp:p=8. 37E+05 u=31 3127 4 -7.94
-3017 3018 imp : p=l.48E+06 u=31 3128 4 -7.94
-3018 3019 imp:p=2. 88E+06 u=31 3129 4 -7.94
-3019 3020 imp : p=5.35E+06 u=31 3130 4 -7. 94
-3020 3021 imp :p=l. 19E+07 u=31 3131 4 -7. 94
-3021 3022 imp : p=l. 19E+07 u=31
Q Orano Federal Services orano
Title:
BRR Fuel Rod Segment Shielding Analysis Doc./Rev.: CALC-3020462-000 Project:
01910.00.8001.28 -
BRRC Letter Amendment Page 39 of 45 3132 4 -7. 94
-3022 3023 imp : p=l. 19E+07 u=31 3133 4 - 7. 94
-3023 3024 i mp : p=l.54E+07 u=31 3134 4 - 7. 94
-3024 i mp : p=2. 15E+07 u=31 C
c===== Universe 32: Bottom Air Splitting Layers 3200 1 - 0. 00 12 3000 imp:p=8 u=32 3201 1 - 0. 0012
-3000 3001 i mp: p=l. l OE+O l u=32 3202 1 - 0. 0012
- 3001 3002 i mp : p=l. 55E+Ol u=32 3203 1 - 0.0012
-3002 3003 imp : p=2. 19E+Ol u=32 3204 1 - 0. 0012
-3003 3014
-3050 i mp : p=2.19E+Ol u=32 3205 1 - 0.0012
-3003 3014 3050 - 3051 i mp :p=2.19E+Ol u=32 3206 1 -0. 0012
-3003 3014 3051 - 3052 imp : p=2. 76E+Ol u=32 3207 1 - 0.0012
-3003 3014 3052 -3053 imp:p=3. 80E+Ol u=32 3208 1 - 0. 0012
-3003 301 4 3053 -3054 i mp:p=5. 19E+Ol u=32 3209 1 -0. 0012
-3003 3014 3054 - 3055 imp:p=7. 2 4E+Ol u=32 3210 1 - 0. 0012
-3003 3014 3055 -3056 imp : p=l.02E+02 u=32 3211 1 - 0. 0012
-3003 3014 3056 -3057 imp:p=l.44E+02 u=32 32 12 1 -0. 00 12
-3003 301 4 3057 -3058 imp: p =2. 23E+02 u=32 3213 1 - 0. 00 12
-3003 301 4 3058 - 3059 i mp:p=4. 18E+02 u=32 3214 1 - 0. 0012
-3003 3014 3059 - 3060 imp:p=l.15E+03 u=32 3215 1 - 0. 0012
-3003 3014 3060 -3061 imp : p=5.31E+03 u=32 32 16 1 - 0. 0012
-3003 3014 3061 - 3062 imp:p=2. 48E+04 u=32 3217 1 - 0. 0012
-3003 3014 3062 -3063 imp : p=6.93E+0 4 u=32 C *** Surface Cards ***
C ***** cylindrical ca sk surfaces C
1 CZ 20.32
$ cask i nner surface cavity wall radius 3
CZ 22. 86
$ outside inner shell radius 19 CZ 43. 02125
$ outer gamma shield (Pb shrinkage surface - 1/16 " )
20 CZ 43. 18
$ cask inner surface outer wall 24 CZ 48.26
$ cask outer surface outer wall 25 CZ 48.5267
$ air gap
( 0. 105 " )
26 CZ 48.7934
$ therma l shiel d outer surface 27 CZ 12. 3825
$ bottom l ead s heet cavity (small )
C 33 CZ 30. 099
$ bottom lead sheet cavity (large) 35 CZ 34. 6837
$ bot tom a nd top cask ss outer s urface 36 C Z 31.11 5
$ top cask inner cavity for c l osure lid 37 CZ 30.7975
$ closure lid radius C
40 CZ
- 22. 1361
$ s hie l d p l ug - ss outer radius(upper cylindrical r e gion) 41 CZ 22. 3901
$ shield p l ug cavity 43 CZ 21.1836
$ shield plug-ss inner radius (upper c;,ylindrical region) 44 CZ 20. 066
$ shield plug - ss outer radius (lower cylindrical r egion) 45 CZ 18. 796
$ s h ield plug - ss i nner radius (lower cylindrical r egion) 46 CZ 3. 81 ss bar at center of shield plug C
50 CZ 99.06
$ outer radius of impact limiter, 78 " OD per 3000219-002 C
C tally surfaces C
C 51 CZ 800
$ problem radial delimiter C
C **** Horizontal planes C
100 pz
-0.6426 bottom of cask inner cavity 101 pz 4. 445 horizontal surface for lateral gamma shield 102 pz 139. 7 horizontal surface at top of lateral gamma s hield +3 "
103 pz
-5. 08 hor i zontal surface at bottom of lateral gamma shield C
106 pz
-3. 7338 bottom cask interface of ss -
s h rinkage gap 114 pz
-12.7 bottom cask -
Pb split 125 pz
-23. 3426 bottom cask -
lower Pb surface 126 pz
-1 4. 9352 bottom cask - ss outer surface (shoulder) 127 pz
-25. 8826 bottom cas k -
SS outer surf ace C
132 pz 149. 225 horizontal surface at top of lateral Pb shield cavity 133 pz 146.2278 top surface of lateral Pb shield after drop (1.12 " )
Q Orano Federal Services orano
Title:
BRR Fuel Rod Segment Shielding Analysis Doc.I Rev.: CALC-3020462-000 Project:
0191 O.OO.B001.28 -
BRRC Letter Amendment 135 pz 170.0276 top surface of closure lid 137 pz 164. 9476 seating surface for top lid 138 pz 159. 0802 C
140 pz 163. 3728 shield plug Pb top surface 141 pz 164. 6428 shield plug top surface 1431 pz 160. 6296 surface for SS rod (surface 141-1.5 " )
150 pz 151.7396 shield plug Pb split surface - modified 1555 pz 139. 0396 bottom plug steel 157 pz 136. 4996 bottom s urface of s hield plug -modified 160 pz 153. 0096 upper SS s urface at seating ring - new 161 10 CZ 1. 04648 pipe in shie l d plug C
C sur faces for IL C
200 pz 135. 9916 upper interface IL with thermal shield 201 pz 8. 1534 lower interface IL with thermal shield C 202 pz 223.8756 upper surface of top impact limiter C 203 pz
- 79.7306 bottom surface of bottom impact limiter C
C c various conical surfaces C
300 kz -36. 3601 1 1 301 kz 180. 5051 1 -1 302 kz -143.9353 0.00489 1 303 kz - 140. 2468 0. 00 489 1 C 304 kz - 220. 38 0. 00275 1 C 305 kz -122.0849 0. 00489 C
c bottom drain C
306 c/z 17. 145 0 0. 635 307 c/x 0
- 7. 5184 0. 635 308 px 15. 24 309 pz
-7. 94 C
999 sz 100 1000 C
$ tapered surface at bottom of lateral gamma shield tapered surface at top of lateral gamma shield
$ tapered s urface at cask top tapered cavit y
$ tapered s urface at s hield p lug (SS)
$ tapered surface at shield plug (gap) 1
$ tapered surface at shield plug (lead surface)
$ vertical cylinder for bottom drain
$ horizontal cylinder for bottom drain
$ start of horizontal bottom drain
$ depth of vertical drain c===== New Impact Limiter Surfaces 350 trc O O 185. 7756 0 0 38.1 99. 06 61. 595 351 trc O O - 41. 6306 0 0 -38. 1 99. 06 61.595 C
$ Upper impact limiter cone
$ Lower i mpact limiter cone 352 pz 198. 4756 $ Upper impact limiter cone tally segmenting surfaces 353 pz 211.1756 C
354 pz -54. 3306 $ Lower impact limiter cone tally segmenting surfaces 355 pz -67.0306 C
c===== Source Sphere 400 so 0. 5 $ 1 cm diameter source sphere c===== Top Splitting Layers c Vertical Layers 1000 pz 137 1001 pz 138 1002 pz 139 1003 pz 140 1004 pz 141 1005 pz 142 1006 pz 143 1007 pz 144 1008 pz 145 1009 pz 146 1010 pz 147 1011 pz 148 1012 pz 149 1013 pz 150 1014 pz 151 1015 pz 152 Page 40 of 45
0 Orano Federal Services orano
Title:
BRR Fuel Rod Segment Shielding Analysis Doc./Rev.: CALC-3020462-000 Project:
0191 O.OO.B001.28 -
BRRC Letter Amendment Page 41 of 45 1016 pz 153 1017 pz 154 1018 pz 155 1019 pz 156 1020 pz 157 1021 pz 158 1022 pz 159 1023 pz 160 1024 pz 161 1025 pz 162 1026 pz 163 1027 pz 164 1028 pz 165 1029 pz 1 66 1030 pz 1 67 1031 pz 168 1032 pz 169 C
c Cone Layers 1050 kz 143. 5 10 -1 1051 kz 144. 5 10 -1 1052 kz 1 45. 5 10 - 1 1053 kz 1 46.5 10 -1 1054 kz 147.5 10 -1 1055 kz 148. 5 10 -1 1056 kz 14 9. 5 10 -1 1057 kz 150. 5 10 -1 1058 kz 151. 5 10 -1 1059 kz 152. 5 10 -1 1060 kz 153. 5 10 -1 1061 kz 154. 5 10 -1 1062 kz 155. 5 10 -1 1063 kz 156. 5 10 -1 1064 kz 157. 5 10 -1 1065 kz 158. 5 10 -1 1066 kz 159. 5 10 -1 1067 kz 160.5 10 -1 1068 kz 161. 5 10 -1 1069 kz 162. 5 10 - 1 1070 kz 163. 5 10 -1 1071 kz 164. 5 10 -1 1072 kz 1 65.5 10 -1 1073 kz 166. 5 10 -1 1074 kz 167. 5 10 -1 1075 kz 168. 5 10 -1 1076 kz 169. 5 10 -1 1077 kz 170.5 10 -1 1078 kz 171. 5 10 -1 1079 kz 172. 5 10 -1 1080 kz 173. 5 10 -1 1081 kz 174. 5 10 -1 1082 kz 175. 5 10 -1 1083 kz 176. 5 10 -1 1084 kz 177. 5 10 -1 1085 kz 178.5 10 - 1 1086 kz 179. 5 10 - 1 1087 kz 180. 5 10 -1 C
C===== Side Splitting Layers 2000 CZ 21 2001 CZ 22 2002 CZ 23 2003 CZ 24 2004 CZ 25 2005 CZ 26 2006 CZ 27 2007 CZ 28 2008 CZ 29 2009 CZ 30
0 Orano Federal Services orano
Title:
BRR Fuel Rod Segment Shielding Analysis Doc./Rev.: CALC-3020462-000 Project:
01910.00.8001.28 -
BRRC Letter Amendment Page 42 of 45 2010 CZ 31 2011 CZ 32 2012 CZ 33 2013 CZ 34 2014 CZ 35 2015 CZ 36 2016 CZ 37 2017 CZ 38 2018 CZ 39 2019 CZ 40 2020 CZ 41 2021 CZ 42 2022 CZ 43 202 3 CZ 44 2024 CZ 45 2025 CZ 46 2026 CZ 47 2027 CZ 48 C
C===== Bottom Splitting Layers c Vertical Layers 3000 pz -1. 5 3001 pz - 2. 5 3002 pz -3.5 3003 pz -4. 5 3004 pz -5.5 3005 pz - 6.5 3006 pz -7.5 3007 pz -8.5 3008 pz - 9. 5 3009 pz - 10.5 3010 pz -11.5 3011 pz - 12. 5 3012 pz -1 3. 5 3013 pz -14.5 3014 pz - 15.5 3015 pz -16.5 3016 pz -17. 5 3017 pz -1 8. 5 3018 pz -19.5 3019 pz -20. 5 3020 pz - 21. 5 3021 pz - 22.5 3022 pz - 23.5 3023 pz -24.5 3024 pz -25.5 C
c Cone Layers 3050 kz -10.5 10 1 3051 kz -11. 5 10 1 3052 kz -12. 5 10 1 3053 kz -13.5 10 1 3054 kz -14.5 10 1 3055 kz -15.5 10 1 3056 kz -1 6. 5 10 1 3057 kz -17.5 10 1 3058 kz - 18. 5 10 1 3059 kz -19.5 10 1 3060 kz - 20. 5 10 1 3061 kz - 21.5 10 1 3062 kz - 22. 5 10 1 3063 kz - 23. 5 10 1 3064 kz - 24. 5 10 1 3065 kz -25.5 10 1 3066 kz -26.5 10 1 3067 kz -27.5 10 1 3068 kz - 28. 5 10 1 c *** Data Cards***
0 Orano Federal Services orano
Title:
BRR Fuel Rod Segment Shielding Analysis Doc./Rev.: CALC-3020462-000 Project:
01910.00.8001.28 -
BRRC Letter Amendment C===== TRCL definitions
- trl 0 0 0 45 135 90 45 45 90 $ 45 cw
- tr2 0 0 -0.6426 22.5 112.5 90 67.5 22.5 90
- trlO 0 0 150.022 50 90 140 90 0 90 40 90 50 C
C ----- Materials C===============================================
C Dry Air c Density= 0.0012 g/cmA3 c Reference : SCALE 6.0 Standard Comp. Library C===============================================
ml 7014
-76. 508 8016
-23.4793 6000
-0.0 126 C===============================================
c Stainless Steel 304 c Density= 7.9 4 g/cmA3 c Reference : SCALE 6. 0 Standard Comp. Library C -=-============================================
m4 6012
-0.08 14000
-1. 0 15000
-0.045 24000
-19 25000
-2 26000
- 68. 375 28000
-9. 5 C===============================================
c Lead c Density= 11. 35 g/cmA3 c
Reference:
PNNL-15870 Rev. 1 C =-===-=========================================
m8 82000 1.0
$ lead C
c===== Source Definition sdef cel=dl pos=O O O rad=d2 par=p erg=d3 wgt=9. 1748E+12 C
sil L (100<24) spl D 1 C
si2 HO 0.5 sp2 D -21 1 C
c Energy distribution taken sp3 from SCALE 6. 2.1. model si3 H
D
- 1. OOE-02 0
4. 50E- 02 2. 5455E+12 1. 00E-01 7. 3578E+ll 2.0 0E- 01
- 1. 0866E+ll 8. 00E-01 4.8675E+l2 l.OOE+OO 7. 8785E+10 l.33E+OO 1. 3684E+ll l.66E+OO 1. 4272E+10 2.00E+OO
- 2. 7277E+08 2.50E+OO 2.5469E+07 3. 00E+OO 2.4 912E+06 4. 00E+OO 6. 1175E+05 5.00E+OO l. 7670E+05 6.50E+OO 7. 2039E+04 8.00E+ OO l.4042E+04
- 1. OOE+Ol 3. 0158E+o3 2.00E+Ol 2.2075E+02 C
c===== Dose Tallies c ansi/ans - 6.1. 1-1977 flux-to-dose, photons (mrem/hr)/(p/cm**2/s)
Page 43 of 45
0 Orano Federal Services orano
Title:
BRR Fuel Rod Segment Shielding Analysis Doc./Rev.: CALC-3020462-000 Project:
01910.00.8001.28 -
BRRC Letter Amendment deO 0.01 0. 03 0. 05 0.07 0.10 0.15 0.20 0. 25 0. 35 0.40 0. 45 0.50 0. 55
- 0. 60 0.65 0.70
- 1. 00
- 1. 40
- 1. 80 2.20 2.60 2. 80 3.25 3.7 5 4.75 5.00 5.25 5.75 6.25 6.75 7.50 9.0 0 13.0 15. 0 dfO 3.96-3 5.82-4 2. 90-4 2. 58-4 2.83-4 3. 79-4 5.01-4 6. 31-4 8.78-4 9. 85-4 1. 08-3 1. 17-3 1. 27-3 1.36-3 1. 44-3 1.52-3 1. 98-3 2. 51-3 2. 99-3 3. 42-3 3. 82-3 4.01-3 4.41-3 4.83 - 3 5. 60-3 5. 80-3 6. 01 - 3 6. 37-3 6. 74-3 7.11-3 7.66-3 8.77-3 1.18-2 1.33-2 fc4 NCT Trailer Side Sur face Mesh (4 ft from cask centerline) f mesh4 :p geom=cyl origin=O O -79.7306 axs=O O 1 vec=0.866 -0.5 0 imesh=121.92 122.92 iints=l 1 jmesh=303.6062 jints=30 kmesh=l kints=6 C
fc14 NCT Top Surface Mesh (measured from IL top) fmesh14 :p geom=cyl origin=O O 223.8756 axs=O O 1 vec=0. 866 -0.5 0 imesh=61. 595 iints=6 jmesh=l jints=l kmesh=l kints=6 C
fc24 NCT Bottom Surface Mesh (measured from IL bottom) fmesh24:p geom=cyl origin=O O -80. 7306 axs=O O 1 vec=0. 866 -0.5 0 imesh=61.595 iints=6 jmesh=l jints=l kmesh=l kints=6 C
fc104 NCT Tr ail er Side 2m Mesh fmesh104 :p geom=cyl origin=O 0 -79.7 306 axs=O O 1 vec=0.866 -0. 5 0 iints=l 1 C
imesh=32 1. 92 322. 92 jmesh=303.6062 kmesh=l jints=30 ki nts=6 fc204 HAC Side lm Mesh (Measured from cask side) fmesh204:p geom=cyl origin=O O - 25. 8826 axs=O O 1 vec=0. 866 - 0.5 0 imesh=l48.7934 149. 7934 iints=l 1 jmesh=l95. 9102 jints=20 kmesh=l kints=6 C
fc214 HAC Top lm Mesh (Measured from cask top) fmesh214:p geom=cyl origin=O O 270. 0276 axs=O O 1 vec=0. 866 -0.5 0 imesh=99. 06 iints=lO C
jmesh=l kmesh=l jints=l kints=6 fc224 HAC Bottom lm Mesh (Measured from cas k bottom) fmesh224 :p geom=cyl origin=O O -125.8826 axs=O O 1 vec=0. 866 -0.5 0 imesh=99.06 iints=lO jmesh=l jints=l kmesh=l kints=6 C
fc394 Occupied Location Dose (25 ft from cask centerl ine) fmesh394 :p geom=cyl origin=O O -25.8826 axs=O O 1 vec=0. 866 -0.5 0 C
imesh=762 772 iints=l 1 jmesh=195.9102 jints=l kmesh=l kints=6 fc504 NCT Cask Side Surface Mesh (between impact limiters) fmesh504:p geom=cyl origin=O O 8.1534 axs=O O 1 vec=0. 866 - 0. 5 0 imesh=48. 7934 49. 7934 iints=l 1 jmesh=127.8382 jints=13 kmesh=l kints=6 C
fc514 NCT Impact Limiter Side Surface Mesh fmesh514 : p geom=cyl origin=O O -4 1. 6306 axs=O O 1 vec=0. 866 -0.5 0 imesh=99.06 100. 06 iints=l 1 jmesh=49.784 177. 6222 227. 4062 jints=5 1 5 kmesh=l kints=6 0.30 0. 80 4.25
- 11. 0 7. 59-4 1. 68-3 5.23-3 1.03-2 Page 44 of 45
0 Orano Federal Services orano
Title:
BRR Fuel Rod Segment Shielding Analysis Doc./Rev.: CALC-3020462-000 Project:
0191 O.OO.B001.28 -
BRRC Letter Amendment C
fc524 NCT Impact Limiter ' Underside ' Surface Mesh fmesh524 : p geom=cyl origin=O O 8. 1534 axs=O O 1 vec=0.866 -0. 5 0 imesh=48. 7934 99.06 iints=l 5 jmesh=l 126. 8382 127.8382 jints=l 1 1 kmesh=l kints=6 C
c Surface area of a conical frustum (TRC macrobody, rl > r2) excluding top and bottom is :
c A= pi*(rl+r2)
- sqrt[(rl-r2)A2+hA2]
26969 cmA2 fc32 Upper Surface (Cone) f32 : p 350. 1 fs32 - 352 - 353 sd32 8990 8990 8990 fc42 Lower Surface (Cone) f42 : p 351.1 fs42 354 355 sd42 8990 8990 8990 C
c fc444 DEBUG TALLY c fmesh444 : p geom=xyz origin=- 100 - 100 - 85 c
imesh=lOO iints=75 c
jmesh=lOO jints=75 c
kmesh=310 kints=l55 C
c Run Options mode p prdmp J J 1 2 ctme 29040 rand gen=2 stride=152917123
$ Use larger per iod and stride print 120 Page 45 of 45