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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

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

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

The Partnership Approach to Siting and Developing Radioactive Waste Management Facilities

SED Publication Type

The Partnership Approach to Siting and Developing Radioactive Waste Management Facilities

Author
NEA
Publication Date

History shows that the search for sites for radioactive waste management facilities has been marred by conflicts and delays. Affected communities have often objected that their concerns and interests were not addressed. In response, institutions have progressively turned away from the traditional “decide, announce and defend” model, and are learning to “engage, interact and co-operate”. This shift has fostered the emergence of partnerships between the proponent of the facility and the potential host community, as shown in a recent NEA study.

public perception nea waste management siting community interaction
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