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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

PWR Axial Burnup Profile Analysis

PWR Axial Burnup Profile Analysis

Author(s)
OCRWM
Publication Date

The purpose of this activity is to develop a representative “limiting” axial burnup profile for pressurized water reactors (PWRs), which would encompass the isotopic axial variations caused by different assembly irradiation histories, and produce conservative isotopics with respect to criticality. The effect that the low burnup regions near the ends of spent fuel have on system reactivity is termed the “end-effect”. This calculation will quantify the end-effects associated with Pressurized Water Reactor (PWR) fuel assemblies emplaced in a hypothetical 21 PWR waste package.

criticality commercial spent nuclear fuel end effect storage axial burnup profile isotopic concentrations 21 pwr waste package pwr snf cal-dsu-nu-000012

BWR Axial Profile

BWR Axial Profile

Author(s)
OCRWM
Publication Date

The purpose of this calculation is to develop axial profiles for estimating the axial variation in burnup of a boiling water reactor (BWR) assembly spent nuclear fuel (SNF) given the average burnup of an assembly. A discharged fuel assembly typically exhibits higher burnup in the center and lower burnup at the ends of the assembly. Criticality safety analyses taking credit for SNF burnup must account for axially varying burnup relative to calculations based on uniformly distributed assembly average burnup due to the under-burned tips.

criticality end effect axial burnup profile bwr snf cal-dsu-nu-000005

Radioactive Waste Management Programmes in OECD/NEA Member Countries: Czech Republic

SED Publication Type

Radioactive Waste Management Programmes in OECD/NEA Member Countries: Czech Republic

Author
Organization for Economic Cooperation and Development/Nuclear Energy Agency
Publication Date

A summary of the radioactive waste management programs in the Czech Republic, including information on nuclear energy; sources, types, and quantities of waste; radioactive waste management policies and programs; research and development; decommissioning and dismantling policies and projects; transport; competent authorities; and financing.

direct disposal deep geological disposal disposal of used nuclear fuel nuclear fuel storage spent nuclear fuel

Radioactive Waste Management Programmes in OECD/NEA Member Countries: Spain

SED Publication Type

Radioactive Waste Management Programmes in OECD/NEA Member Countries: Spain

Author
Organization for Economic Cooperation and Development/Nuclear Energy Agency
Publication Date

A summary of the radioactive waste management programs in Spain, including the national nuclear energy context; sources, types, and quantities of waste; radioactive waste management policies and programs; research and development; decommissioning and dismantling policies and projects; transport; authorities and implementing organizations; financing; and public information.

radioactive material transport deep geological disposal financing civilian radioactive waste management program spent fuel disposal disposal of used nuclear fuel spent nuclear fuel
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