Letter Sequence Other |
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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance...
- Supplement, Supplement, Supplement, Supplement
Results
Other: ML23058A279, ML23058A281, ML23058A284, ML23058A286, ML23058A287, ML23059A252, ML23067A441, ML23109A009, ML23115A080, ML23115A082, ML23115A086, ML23115A320, ML23160A084, ML23160A087, ML23310A163, ML23310A297, ML23310A299, ML23310A300, ML23310A301, ML23310A302, ML23310A303, ML23310A304, ML23310A305, ML23310A306, ML23331A675, ML23331A679, ML23331A681, ML23331A683, ML23331A684, ML23331A686, ML23331A688, ML23331A690, ML23331A692, ML23331A693, ML23331A695, ML23331A698, ML23331A700, ML23331A702, ML23331A897, ML23331A898, ML23331A899... further results
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MONTHYEARML23331A9071989-06-19019 June 1989
Decree No. 76/1989 Coll., Decree of the Czech Labour Safety Authority to Ensure the Safety of Technical Equipment in the Nuclear Power Industry (Cancelled: 7/27/2005)
Project stage: Other
ML23331A8971991-05-31031 May 1991
Decree No. 263/1991 Coll.Decree of the Czech Office of Labour Safety Amending and Supplementing Decree No. 76/1989 Coll. of the Czech Office of Labour Safety to Ensure the Safety of Technical Equipment in the Nuclear Power Industry (Cancell
Project stage: Other
ML23331A9041997-01-24024 January 1997
Act No. 18/1997 Coll., Peaceful Utilisation of Nuclear Energy and Ionising Radiation (the Atomic Act) and on Amendments and Alterations to Some Acts
Project stage: Other
ML23331A9011997-08-15015 August 1997
Regulation No. 214/1997 Sb., Quality Assurance in Activities Related to the Utilization of Nuclear Energy and in Radiation Practices and Laying Down Criteria for the Assignment and Categorization of Classified Equipment Into Safety Classes
Project stage: Other
ML23331A8991998-08-31031 August 1998
Regulation No. 106/1998 Sb., Nuclear Safety and Radiation Protection Assurance During Commissioning and Operation of Nuclear Facilities
Project stage: Other
ML23331A9001999-08-21021 August 1999
Regulation No. 195/1999 Sb., Requirements on Nuclear Installations for Assurance of Nuclear Safety, Radiation Protection and Emergency Preparedness
Project stage: Other
ML23331A8982002-06-13013 June 2002
Decree No. 317/2002, on type-approval of Packagings for Shipment, Storage and Disposal of Nuclear Materials and Radioactive Substances, on type-approval of Ionizing Radiation Sources and Shipment of Nuclear Materials and Specified Radioacti
Project stage: Other
ML23331A9022002-06-13013 June 2002
Regulation No. 307/2002 Coll., Radiation Protection
Project stage: Other
ML23310A3032002-06-13013 June 2002
Decree No. 317/2016, on type-approval of Packagings for Shipment, Storage and Disposal of Nuclear Materials and Radioactive Substances..., State Officer for Nuclear Safety, June 13, 2002, Czech Republic (Model No. SKODA Package Revalidation
Project stage: Other
ML23331A6922004-03-31031 March 2004
Appendix 4, Ujv Report Z-1172, MCP Calculation of Cask Criticality for Atabor Internals of Thickness 4 Mm, March 2004
Project stage: Other
ML23331A6932004-05-0101 May 2004
Appendix 4, Ujv Report: Z-1172-Amendment 1, a SKODA MCNP Calculation of Cask Criticality for Atabor Internals of Thickness 4 Mm, Amendment 1, May 2004
Project stage: Other
ML23331A6792005-01-0808 January 2005
Appendix 2, Ae 11543/Dok, Rev. 2, Cover Page Only, SKODA Vpvr/M Safety Analysis Report, Cask Dynamic Behaviour SKODA Vpvr/M
Project stage: Other
ML23331A7002005-02-15015 February 2005
Appendix 5, Cover Page Only, PZJ-02-04, Vision 2, Quality Plan, Vpvr Cask / SKODA Vpvr/M Cask
Project stage: Other
ML23331A6752005-02-15015 February 2005
Appendix 1, Cover Page, Document No. Ae 11543/Dok, Rev. 2, Radiation Protection (Shielding Calculation), Safety Documentation of the Cask SKODA Vpvr/M
Project stage: Other
ML23331A6982005-08-0101 August 2005
Appendix 5, Ae 11543/Dok, Rev. 2, Cover Page Only, Safety Documentation of the Cask SKODA Vpvr/M, Q.A. - 1
Project stage: Other
ML23331A6972005-08-0101 August 2005
Appendix 4A, Cover Page, Ae 11543/Dok, Revision 2, Safety Documentation of the Cask SKODA Vpvr/M, Nuclear Safety (Subcriticality Calculation), Supplements 1 and 2)
Project stage: Supplement
ML23331A6952005-08-0101 August 2005
Appendix 4, Ujv Report: Z-1172- Amendment 2, SKODA MCNP Calculation of Cask Criticality for Atabor Internals of Thickness 4 Mm, Amendment 2
Project stage: Other
ML23331A6902005-08-0101 August 2005
Appendix 4, Cover Page Only, Ae 11543/Dok, Revision 2, Nuclear Safety Subcriticality Evaluation
Project stage: Other
ML23331A6842005-08-0101 August 2005
Appendix 3, Cover Page Only, Ae 11543/Dok, Rev. 2, Safety Analysis Report of SKODA Vpvr/M Cask, Decontamination Effect on Structural Materials
Project stage: Other
ML23331A6832005-08-0101 August 2005
Appendix 3, Ujv Report: Z-1336, Revision 2, Decontamination Effect on Structural Materials of the SKODA Vpvr/M Cask
Project stage: Other
ML23331A6812005-08-0101 August 2005
Appendix 2, Vz 04/01, Revision 3, Strength Analysis of SKODA Vpvr/M Cask for Spent Fuel Assemblies from Research Reactors Drop from the Height of 9 Meters
Project stage: Other
ML23331A6862006-07-0101 July 2006
Appendix 3, Újv Report: Z-1336, Revision 2, Decontamination Effect on Structural Materials of SKODA Vpvr/M Cask, July 2005
Project stage: Other
ML23331A6882006-08-0101 August 2006
Appendix 4, Ujv Report Z-1296, SKODA MCP Calculation of Cask Criticality for Atabor Internals of Thickness 4 Mm, Nuclear Research Institute, Division of Reactor Services, August 2005
Project stage: Other
ML23310A3022016-07-14014 July 2016
Act No. 263/201, Atomic Act, July 14, 2016, Czech Republic (Model No. SKODA Revalidation)
Project stage: Other
ML23310A3042016-10-17017 October 2016
Decree No. 358/2016, Requirements for Assurance of Quality and Technical Safety and Assessment and Verification of Conformity of Selected Equipment, October 17, 2016, Czech Republic (Model No. SKODA Revalidation)
Project stage: Other
ML23310A3062016-11-0707 November 2016
Decree 379/2016, Approval of Some Products in the Field of Peaceful Use of Nuclear Energy and Ionising Radiation and the Carriage of Radioactive or Fissile Material, November 7, 2016, Czech Republic (Model No. SKODA Revalidation)
Project stage: Other
ML23310A3052016-11-0707 November 2016
Decree No. 376/2016, Requirements for a Declaration Concerning the end-use of a dual-use Item in the Nuclear Area, November 7, 2016, Czech Republic (Model No. SKODA Revalidation)
Project stage: Other
ML23310A3002016-12-0606 December 2016
Decree No. 408/2016, Management System Requirements, December 6, 2016, Czech Republic (Model No. SKODA Package Revalidation)
Project stage: Other
ML23310A3012016-12-14014 December 2016
Decree No. 422/2016, Implementing Decree, Radiation Protection and Security of a Radioactive Source, December 14, 2016, Czech Republic (Model No. SKODA Revalidation)
Project stage: Other
ML23331A9032017-07-11011 July 2017
Czech Republic Certificate of Competent Authority Identification No. CZ/048/B(U)-96, Revision 2, SKODA Vpvr/M
Project stage: Other
ML23331A7022017-07-11011 July 2017
Appendix 5, Pzj 02-04, Revision 2, Vpvr Cask, SKODA Vpvr/M Cask
Project stage: Other
ML23310A2992017-07-11011 July 2017
Resolution No. SUBJ/ORNV/12586/2017, Certificate No. CZ/048/B(U)F–96, State Office for Nuclear Safety, July 11, 2017, Czech Republic (Model No. SKODA Package Revalidation)
Project stage: Other
ML23310A2972017-09-26026 September 2017
Decree No. 329/2017, Implementing Decree, September 26, 2017, Czech Republic (Model No. SKODA Package Revalidation)
Project stage: Other
ML23115A0802019-08-16016 August 2019
U.S. Certificate of Competent Authority USA/0208/B(U)F-96, Revision 13 (Japanese Certificate J/61/B(U)F-96), Expired May 28.2022
Project stage: Other
ML23058A2862022-07-29029 July 2022
Part 1-Response, Acceptance Review, 2/23/23, Document No. 1 Japanese Certificate of the Competent Authority No. J/2043/B(U)F, Model No. JRF-90Y-950K (English Version) Issued on May 23, 2022
Project stage: Other
ML23006A1042023-01-0505 January 2023
Cover Letter from Richard Boyle (DOT) Requesting the Review and Revalidation of the Model No. JRF-90Y-950K
Project stage: Request
ML23160A0842023-01-0505 January 2023
Email Dated 1/5/23 from Rwboyle (DOT) to Arony (Edlow)-Incomplete Application, Information Request, Japanese Certificate of Competent Authority No. J/2043/B(U)F, Model No. JRF-90Y-950K
Project stage: Other
ML23006A0982023-01-0505 January 2023
Document No. 5 - Summary of Changes of the Safety Evaluation Report for the Model No. JRF-90Y-950K Nuclear Fuel Transport Package
Project stage: Request
ML23046A0402023-02-0202 February 2023
Revised Affidavit Dated 2/3/23, Revalidation Request for the Japanese Certificate of the Competent Authority No. J/2043/B(U)F, Model No. JRF-90Y-950K
Project stage: Request
2006-07-01
[Table View] |
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Category:Final Safety Analysis Report (FSAR)
MONTHYEARML23331A7022017-07-11011 July 2017
Appendix 5, Pzj 02-04, Revision 2, Vpvr Cask, SKODA Vpvr/M Cask
ML23331A6882006-08-0101 August 2006
Appendix 4, Ujv Report Z-1296, SKODA MCP Calculation of Cask Criticality for Atabor Internals of Thickness 4 Mm, Nuclear Research Institute, Division of Reactor Services, August 2005
ML23331A6862006-07-0101 July 2006
Appendix 3, Újv Report: Z-1336, Revision 2, Decontamination Effect on Structural Materials of SKODA Vpvr/M Cask, July 2005
ML23331A6902005-08-0101 August 2005
Appendix 4, Cover Page Only, Ae 11543/Dok, Revision 2, Nuclear Safety Subcriticality Evaluation
ML23331A6952005-08-0101 August 2005
Appendix 4, Ujv Report: Z-1172- Amendment 2, SKODA MCNP Calculation of Cask Criticality for Atabor Internals of Thickness 4 Mm, Amendment 2
ML23331A6812005-08-0101 August 2005
Appendix 2, Vz 04/01, Revision 3, Strength Analysis of SKODA Vpvr/M Cask for Spent Fuel Assemblies from Research Reactors Drop from the Height of 9 Meters
ML23331A6832005-08-0101 August 2005
Appendix 3, Ujv Report: Z-1336, Revision 2, Decontamination Effect on Structural Materials of the SKODA Vpvr/M Cask
ML23331A6842005-08-0101 August 2005
Appendix 3, Cover Page Only, Ae 11543/Dok, Rev. 2, Safety Analysis Report of SKODA Vpvr/M Cask, Decontamination Effect on Structural Materials
ML23331A6982005-08-0101 August 2005
Appendix 5, Ae 11543/Dok, Rev. 2, Cover Page Only, Safety Documentation of the Cask SKODA Vpvr/M, Q.A. - 1
ML23331A6972005-08-0101 August 2005
Appendix 4A, Cover Page, Ae 11543/Dok, Revision 2, Safety Documentation of the Cask SKODA Vpvr/M, Nuclear Safety (Subcriticality Calculation), Supplements 1 and 2)
ML23331A6752005-02-15015 February 2005
Appendix 1, Cover Page, Document No. Ae 11543/Dok, Rev. 2, Radiation Protection (Shielding Calculation), Safety Documentation of the Cask SKODA Vpvr/M
ML23331A7002005-02-15015 February 2005
Appendix 5, Cover Page Only, PZJ-02-04, Vision 2, Quality Plan, Vpvr Cask / SKODA Vpvr/M Cask
ML23331A6792005-01-0808 January 2005
Appendix 2, Ae 11543/Dok, Rev. 2, Cover Page Only, SKODA Vpvr/M Safety Analysis Report, Cask Dynamic Behaviour SKODA Vpvr/M
ML23331A6932004-05-0101 May 2004
Appendix 4, Ujv Report: Z-1172-Amendment 1, a SKODA MCNP Calculation of Cask Criticality for Atabor Internals of Thickness 4 Mm, Amendment 1, May 2004
ML23331A6922004-03-31031 March 2004
Appendix 4, Ujv Report Z-1172, MCP Calculation of Cask Criticality for Atabor Internals of Thickness 4 Mm, March 2004
2017-07-11
[Table view] |
Text
Ústav jaderného výzkumu ez a.s.
Divize reaktorových sluzeb
ÚJV Report: Z - 1172 - Amendment 1
MCNP Calculation of Cask Criticality for ATABOR Internals of Thickness 4 mm
- Amendment 1
Prepared by: Stanislav Flíbor
Department Manager: Ing. Milan Marek, CSc.
DRS Manager: Ing. Jan Kysela, CSc.
ez, May 2004
píloha 4Adod1-kritinost.doc
- 1. Fuel EK-10 with 10% enrichment of 235U in a square stainless steel sheath
1.1 Material composition of fuel
Used library of effective cross-Enrichment 10.00% sections 235U weight portion 7.67% 92235.60c 238U weight portion 69.01% 92238.60c Mg weight portion 13.00% 12000.60c O weight portion 10.32% 8016.60c
235U weight 128.80 g 238U weight 1159.20 g Mg weight 218.36 g O weight 173.35g
Total 1679.72g
Active part length 50 cm Fuel volume 307.8761 cm3
U density 4.1835 g.cm-3 Fuel density 5.4558 g.cm-3
U atomic density 1.0597E+22 at.cm-3 Fuel atomic density 4.9364E+22 at.cm-3
235U mol. weight 235.0439 g.mol-1 238U mol. weight 238.0508 g.mol-1 Mg mol. weight 24.3050 g.mol-1 O mol. weight 15.9994 g.mol-1
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Fig. 1: Model of a basic cell with fuel EK-10 10% in a square stainless steel sheath
Fig. 2: Cross section of a cask with fuel EK-10 10% in a square stainless steel sheath
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Fig. 3: Longitudinal section of a cask with fuel EK-10 10% in a square stainless steel sheath
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1.2 Results of calculations for the change of water density
Water density keff error Water density keff error
[g.cm-3] 2 [g.cm-3] 2 0.001161 0.1691 0.0008 0.5 0.3461 0.0024 0.025 0.1956 0.0011 0.525 0.3499 0.0025 0.05 0.2154 0.0013 0.55 0.3540 0.0023 0.075 0.2308 0.0014 0.575 0.3589 0.0025 0.1 0.2437 0.0015 0.6 0.3669 0.0027 0.125 0.2540 0.0016 0.625 0.3655 0.0027 0.15 0.2627 0.0016 0.65 0.3718 0.0024 0.175 0.2721 0.0016 0.675 0.3767 0.0028 0.2 0.2785 0.0018 0.7 0.3810 0.0027 0.225 0.2873 0.0018 0.725 0.3837 0.0026 0.25 0.2938 0.0020 0.75 0.3929 0.0029 0.275 0.3002 0.0018 0.775 0.3968 0.0027 0.3 0.3044 0.0019 0.8 0.3999 0.0026 0.325 0.3099 0.0021 0.825 0.4067 0.0027 0.35 0.3150 0.0022 0.85 0.4078 0.0030 0.375 0.3202 0.0021 0.875 0.4134 0.0030 0.4 0.3244 0.0022 0.9 0.4178 0.0030 0.425 0.3300 0.0022 0.925 0.4267 0.0029 0.45 0.3344 0.0023 0.95 0.4263 0.0030 0.475 0.3412 0.0023 0.975 0.4345 0.0031 0.998203 0.4338 0.0028
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1.3 Results of calculations for flooding a cask with water
Water level in a cask keff error
[cm] 2
-5.75 0.1684 0.0009 4.25 0.1791 0.0012 9.25 0.2036 0.0014 14.25 0.2583 0.0018 19.25 0.3054 0.0024 24.25 0.3434 0.0026 34.25 0.3899 0.0029 44.25 0.4200 0.0029 54.25 0.4311 0.0031 64.25 0.4360 0.0029 74.25 0.4367 0.0034 84.25 0.4353 0.0029 94.25 0.4343 0.0030
(zero water level corresponds to the cask bottom)
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1.4 Results of calculations for individual tolerances
keff error 2
Calculations for individual temperature states of a cask 95,3°C - option 1 acc. to Ae 10622/Dok Rev.1 0.4339 0.0024 132,4°C - option 2a acc. to Ae 10622/Dok Rev.1 0.4325 0.0023 103,6°C - option 2b acc. to Ae 10622/Dok Rev.1 0.4325 0.0023 88,4°C - option 3a acc. to Ae 10622/Dok Rev.1 0.4333 0.0025 103,9°C - option 3b acc. to Ae 10622/Dok Rev.1 0.4322 0.0024 232°C - option 4 acc. to Ae 10622/Dok Rev.1 0.4339 0.0023
Calculations for B concentrations in ATABOR 1,2 % 0.4338 0.0028 1,6% 0.4150 0.0023
Calculations for tolerances of ATABOR internals thickness 3,6 mm 0.4338 0.0028 4,0 mm 0.4283 0.0024
Calculations for tolerances of total U weight in fuel
-5% 0.4271 0.0025
+5% 0.4421 0.0025
Calculations for enrichment tolerances
-1% 0.4328 0.0024
+1 0.4321 0.0025
Calculations for specified tolerances of matrix contents 11.7 % portion of Mg 0.4316 0.0024 14.3 % portion of Mg 0.4320 0.0024
Calculations for displacement of elements inside the rack Cask resting on its side 0.4281 0.0022 Aggregation of elements 0.4271 0.0022
Calculations for tolerances of fuel active part length 48 cm 0.4374 0.0025 52 cm 0.4296 0.0025
7 / 10 píloha 4Adod1-kritinost.doc
1.5 Conclusion With respect to criticality the transport and stor age cask for spent fuel from research reactors for fuel EK-10 with 10 % enrichment of 235U in a square stainless steel sheath satisfies the requirement for subcriticality according to §7 of the SÚJB Decree No. 106/1998 Col.
keff = 0.460
The resulting value of keff was determined according to the formula indicated in Chapter 5.
This calculation is conservative with respect to the number of fuel rods in one sheath (calculated for the maximum possible number of rods).
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