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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

Research Supporting Implementation of Burnup Credit in the Criticality Safety Assessment of Transport and Storage Casks

Research Supporting Implementation of Burnup Credit in the Criticality Safety Assessment of Transport and Storage Casks

Author(s)
Parks, C. V. ,
Gauld, I. C. ,
Wagner, J. C. ,
Broadhead, B. L. ,
DeHart, M. D. ,
Ebert, D. D.
Publication Date
The Nuclear Regulatory Commission (NRC) Office of Regulatory Research (RES) has initiated a program to support effective implementation of burnup credit in the criticality safety assessment of transport and dry storage casks. The goal is to develop technical bases that can be used to provide criteria and guidance for use in licensing activities. The program is being conducted in a phased approach, with the initial focus on unresolved issues related to the use of actinide-only bumupcredit in transport and dry storage casks designed for spent fuel from pressurized-water reaciors (PWRs).
burnup credit transport cask storage cask criticality safety analysis

Spent Fuel Project Office, ISG-8 - Limited Burnup Credit in the Criticality Safety Analyses of PWR Spent Fuel in Transport and Storage Casks

Spent Fuel Project Office, ISG-8 - Limited Burnup Credit in the Criticality Safety Analyses of PWR Spent Fuel in Transport and Storage Casks

Author(s)
Spent Fuel Project Office, NRC
Publication Date

Spent Fuel Project Office Interim Staff Guidance - 8

pwr spent fuel transport cask storage cask criticality safety analysis isg-8 interim staff guidance limited burnup credit used fuel

Spent Fuel Project Office, Interim Staff Guidance - 8, Revision 1, Burnup Credit in the Criticality Safety Analyses of PWR Spent Fuel in Transport and Storage Casks

Spent Fuel Project Office, Interim Staff Guidance - 8, Revision 1, Burnup Credit in the Criticality Safety Analyses of PWR Spent Fuel in Transport and Storage Casks

Author(s)
Spent Fuel Project Office, NRC

Spent Fuel Project Office, Interim Staff Guidance - 8, Revision 1

burnup credit pwr spent fuel transport cask storage cask criticality safety analysis isg-8 interim staff guidance used fuel

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

Issues for Effective Implementation of Burnup Credit

Issues for Effective Implementation of Burnup Credit

Author(s)
Parks, C. V. ,
Wagner, J. C.
Publication Date

In the United States, burnup credit has been used in the criticality safety evaluation for storage pools at
pressurized water reactors (PWRs) and considerable work has been performed to lay the foundation for use of
burnup credit in dry storage and transport cask applications and permanent disposal applications. Many of the
technical issues related to the basic physics phenomena and parameters of importance are similar in each of these
applications. However, the nuclear fuel cycle in the United States has never been fully integrated and the

burnup credit pwr dry cask storage transport cask

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

Spent Fuel Project Office, Interim Staff Guidance - 8, Revision 2, Burnup Credit in the Criticality Safety Analyses of PWR Spent Fuel in Transport and Storage Casks

Spent Fuel Project Office, Interim Staff Guidance - 8, Revision 2, Burnup Credit in the Criticality Safety Analyses of PWR Spent Fuel in Transport and Storage Casks

Author(s)
Spent Fuel Project Office, NRC
Publication Date

Spent Fuel Project Office, Interim Staff Guidance - 8, Revision 2 - Burnup Credit in the Criticality Safety Analyses of PWR Spent Fuel in Transport
and Storage Casks

burnup credit pwr spent fuel transport cask storage cask criticality safety analysis isg-8 interim staff guidance used fuel

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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