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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

Summary of National and International Radioactive Waste Management Programs 1979

SED Publication Type

Summary of National and International Radioactive Waste Management Programs 1979

Author
K. M. Harmon
Publication Date

Many nations and international agencies are working to develop improved technology and industrial capability for nuclear fuel cycle and waste management operations. The effort in some countries is limited to research in university laboratories on treating low-level waste from reactor plant operations.

doe waste management siting fuel cycle pnl-2941
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