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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

OECD/NEA Burnup Credit Criticality Benchmarks Phase IIIB: Burnup Calculations of BWR Fuel Assemblies for Storage and Transport

OECD/NEA Burnup Credit Criticality Benchmarks Phase IIIB: Burnup Calculations of BWR Fuel Assemblies for Storage and Transport

Author(s)
Okuno, Hiroshi ,
Naito, Yoshitaka ,
Suyama, Kenya
Publication Date

The report describes the final results of the Phase IIIB Benchmark conducted by the
Expert Group on Burnup Credit Criticality Safety under the auspices of the Nuclear Energy
Agency (NEA) of the Organization for Economic Cooperation and Development (OECD).
The Benchmark was intended to compare the predictability of current computer code and
data library combinations for the atomic number densities of an irradiated BWR fuel
assembly model. The fuel assembly was irradiated under specific power of 25.6 MW/tHM

burnup credit criticality analysis nea jaeri nea/nsc/doc(2002)/2 composition calculations

Burn-up Credit Criticality Safety Benchmark - Phase VII, UO2 Fuel: Study of Spent Fuel Compositions for Long-term Disposal

Burn-up Credit Criticality Safety Benchmark - Phase VII, UO2 Fuel: Study of Spent Fuel Compositions for Long-term Disposal

Author(s)
Wagner, J. C. ,
Radulescu, G.
Publication Date
burnup credit spent fuel isbn 978-92-64-99172-9 nea no. 6998 criticality analysis spent fuel composition nea wpncs egbuc used fuel

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

Stakeholder Confidence in Radioactive Waste Management: An Annotated Glossary of Key Terms

Stakeholder Confidence in Radioactive Waste Management: An Annotated Glossary of Key Terms

Author(s)
OECD
Publication Date

The OECD Nuclear Energy Agency (NEA) Forum on Stakeholder Confidence (FSC) acts as a centre for informed exchange of knowledge and experience regarding stakeholder interaction and public participation in radioactive waste management. It promotes an open discussion among members and stakeholders, across institutional boundaries, and between technical and non-technical actors, in an atmosphere of trust and mutual respect. As such, the FSC is, first and foremost, a learning organisation.

public perception nea radioactive waste 6988 waste management stakeholders

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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