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OECD/NEA Burnup Credit Criticality Benchmark, Analysis of Phase II-B Results: Conceptual PWR Spent Fuel Transportation Cask

OECD/NEA Burnup Credit Criticality Benchmark, Analysis of Phase II-B Results: Conceptual PWR Spent Fuel Transportation Cask

Author(s)
Nouri, A.
Publication Date
The OECD/NEA “Burn-up Credit Criticality Benchmark” working group has studied the effect of axial burn-up profile on the criticality of a realistic PWR spent fuel transport cask (Phase II-B). The final results of this benchmark are presented and analysed in this report. Nine basic cases and two additional accident configurations were considered with the following varying parameters: burn-up (0 GWd/t for fresh fuel, 30 and 50 GWd/t), fuel composition (actinides only and actinides with fifteen fission products), axial burn-up discretisation (1 or 9 zones).
criticality pwr fuel transport cask end effect source convergence burnup axial burnup profile

Research Supporting Implementation of Burnup Credit in the Criticality Safety Assessment of Transport and Storage Casks

Research Supporting Implementation of Burnup Credit in the Criticality Safety Assessment of Transport and Storage Casks

Author(s)
Parks, C. V. ,
Gauld, I. C. ,
Wagner, J. C. ,
Broadhead, B. L. ,
DeHart, M. D. ,
Ebert, D. D.
Publication Date
The Nuclear Regulatory Commission (NRC) Office of Regulatory Research (RES) has initiated a program to support effective implementation of burnup credit in the criticality safety assessment of transport and dry storage casks. The goal is to develop technical bases that can be used to provide criteria and guidance for use in licensing activities. The program is being conducted in a phased approach, with the initial focus on unresolved issues related to the use of actinide-only bumupcredit in transport and dry storage casks designed for spent fuel from pressurized-water reaciors (PWRs).
burnup credit transport cask storage cask criticality safety analysis

Spent Fuel Project Office, ISG-8 - Limited Burnup Credit in the Criticality Safety Analyses of PWR Spent Fuel in Transport and Storage Casks

Spent Fuel Project Office, ISG-8 - Limited Burnup Credit in the Criticality Safety Analyses of PWR Spent Fuel in Transport and Storage Casks

Author(s)
Spent Fuel Project Office, NRC
Publication Date

Spent Fuel Project Office Interim Staff Guidance - 8

pwr spent fuel transport cask storage cask criticality safety analysis isg-8 interim staff guidance limited burnup credit used fuel

Spent Fuel Project Office, Interim Staff Guidance - 8, Revision 1, Burnup Credit in the Criticality Safety Analyses of PWR Spent Fuel in Transport and Storage Casks

Spent Fuel Project Office, Interim Staff Guidance - 8, Revision 1, Burnup Credit in the Criticality Safety Analyses of PWR Spent Fuel in Transport and Storage Casks

Author(s)
Spent Fuel Project Office, NRC

Spent Fuel Project Office, Interim Staff Guidance - 8, Revision 1

burnup credit pwr spent fuel transport cask storage cask criticality safety analysis isg-8 interim staff guidance used fuel

Issues for Effective Implementation of Burnup Credit

Issues for Effective Implementation of Burnup Credit

Author(s)
Parks, C. V. ,
Wagner, J. C.
Publication Date

In the United States, burnup credit has been used in the criticality safety evaluation for storage pools at
pressurized water reactors (PWRs) and considerable work has been performed to lay the foundation for use of
burnup credit in dry storage and transport cask applications and permanent disposal applications. Many of the
technical issues related to the basic physics phenomena and parameters of importance are similar in each of these
applications. However, the nuclear fuel cycle in the United States has never been fully integrated and the

burnup credit pwr dry cask storage transport cask

Topical Report on Actinide-Only Burnup Credit for PWR Spent Nuclear Fuel Packages

Topical Report on Actinide-Only Burnup Credit for PWR Spent Nuclear Fuel Packages

Author(s)
DOE
Publication Date

A methodology for performing and applying nuclear criticality safety calculations, for PWR spent nuclear fuel (SNF) packages with actinide-only burnup credit, is described. The changes in the U-234, U-235, U-236, U-238, Pu-238, Pu-239, Pu-240, Pu-241, Pu-242, and Am-241 concentration with burnup are used in burnup credit criticality analyses. No credit for fission product neutron absorbers is taken. The methodology consists of five major steps. (1) Validate a computer code system to calculate isotopic concentrations of SNF created during burnup in the reactor core and subsequent decay.

criticality spent fuel fission products cross-section data safety code cooling time decay design multiplication factors neutron absorbers reactor cores nuclear fuel burnup nuclear fuel cycle benchmarks used fuel

Topical Report on Actinide-Only Burnup Credit for PWR Spent Nuclear Fuel Packages

Topical Report on Actinide-Only Burnup Credit for PWR Spent Nuclear Fuel Packages

Author(s)
Office of Civilian Radioactive Waste Management
Publication Date

A methodology for performing and applying nuclear criticality safety calculations, for PWR spent nuclear fuel (SNF) packages with actinide-only burnup credit, is described. The changes in the U-234, U-235, U-236, U-238, Pu-238, Pu-239, Pu-240, Pu-241, Pu-242, and Am-241 concentration with burnup are used in burnup credit criticality analyses. No credit for fission product neutron absorbers is taken. The methodology consists of five major steps. (1) Validate a computer code system to calculate isotopic concentrations of SNF created during burnup in the reactor core and subsequent decay.

criticality spent fuel fission products cross-section data benchmark safety code cooling time decay design multiplication factors neutron absorbers reactor cores nuclear fuel burnup nuclear fuel cycle used fuel

Spent Fuel Project Office, Interim Staff Guidance - 8, Revision 2, Burnup Credit in the Criticality Safety Analyses of PWR Spent Fuel in Transport and Storage Casks

Spent Fuel Project Office, Interim Staff Guidance - 8, Revision 2, Burnup Credit in the Criticality Safety Analyses of PWR Spent Fuel in Transport and Storage Casks

Author(s)
Spent Fuel Project Office, NRC
Publication Date

Spent Fuel Project Office, Interim Staff Guidance - 8, Revision 2 - Burnup Credit in the Criticality Safety Analyses of PWR Spent Fuel in Transport
and Storage Casks

burnup credit pwr spent fuel transport cask storage cask criticality safety analysis isg-8 interim staff guidance used fuel

Destructive Examination of 3-Cycle LWR Fuel Rods from Turkey Point Unit 3 for the CLIMAX-Spent Fuel Test

SED Publication Type

Destructive Examination of 3-Cycle LWR Fuel Rods from Turkey Point Unit 3 for the CLIMAX-Spent Fuel Test

Author
Atkin, S. D.
Publication Date

The destructive examination results of five light water reactor rods from the Turkey Point Unit 3 reactor are presented. The examinations included fission gas collection and analyses, burnup and hydrogen analyses, and a metallographic evaluation of the fuel, cladding, oxide, and hydrides. The rods exhibited a low fission gas release with all other results appearing representative for pressurized water reactor fuel rods with similar burnups (28 GWd/MTU) and operating histories.

spent fuel fission gas turkey point burnup used fuel
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