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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

Second Review Meeting, Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, written questions submitted to Luxembourg

SED Publication Type

Second Review Meeting, Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, written questions submitted to Luxembourg

Author
Luxembourg
Publication Date

Second Review Meeting, Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, written questions submitted to Luxembourg

siting national report joint convention spent fuel management luxembourg radioactive waste management

Luxembourg, National Report on the measures taken by Luxembourg to fulfill the obligations laid down in the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, 2009

SED Publication Type

Luxembourg, National Report on the measures taken by Luxembourg to fulfill the obligations laid down in the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, 2009

Author
Luxembourg
Publication Date

Luxembourg has signed the Joint Convention on 1st October 1997 and is a Party thereof since 19 November 2001. The Convention entered into force on 21 June 2001. Luxembourg has no nuclear power plant, no other fuel-cycle facility, no research reactor and no other facility generating radioactive substances. Thus many requirements of the Joint Convention do not apply to Luxembourg. It further has no spent nuclear fuel and no high level radioactive waste on its territory.

siting national report joint convention spent fuel management luxembourg radioactive waste management

Luxembourg, National Report on the measures taken by Luxembourg to fulfill the obligations laid down in the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, 2006

SED Publication Type

Luxembourg, National Report on the measures taken by Luxembourg to fulfill the obligations laid down in the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, 2006

Author
Luxembourg
Publication Date

Luxembourg has signed the Joint Convention on 1st October 1997 and is a Party thereof since 19 November 2001. The Convention entered into force on 21 June 2001. Luxembourg has no nuclear power plant, no other fuel-cycle facility, no research reactor and no other facility generating radioactive substances. Thus many requirements of the Joint Convention do not apply to Luxembourg. It further has no spent nuclear fuel and no high level radioactive waste on its territory.

siting national report joint convention spent fuel management luxembourg radioactive waste management

Second Review Meeting, Joint Convention on the Safety of Spent Fuel Management on the Safety of Radioactive Waste Management, Answers to the Questions of Contracting Parties on the National Report submitted by Luxembourg

SED Publication Type

Second Review Meeting, Joint Convention on the Safety of Spent Fuel Management on the Safety of Radioactive Waste Management, Answers to the Questions of Contracting Parties on the National Report submitted by Luxembourg

Author
Luxembourg
Publication Date

Second Review Meeting, Joint Convention on the Safety of Spent Fuel Management on the Safety of Radioactive Waste Management, Answers to the Questions of Contracting Parties on the National Report submitted by Luxembourg

siting national report joint convention spent fuel management luxembourg radioactive waste management
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