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Application of Sensitivity/Uncertainty Methods to Burnup Credit Criticality Validation

Application of Sensitivity/Uncertainty Methods to Burnup Credit Criticality Validation

Author(s)
Mueller, D. E. ,
Wagner, J. C.
Publication Date
The responsible use of calculational methods in nuclear criticality safety includes a determination of bias and bias uncertainty that may exist between the calculated results and reality. Such biases exist due to approximations used to model the real world, uncertainties in nuclear data, and approximations associated with the calculational method (e.g., Monte Carlo method). The bias and bias uncertainty are typically determined by using the modeling approximations, nuclear data, and calculational method to model well-known, usually critical, systems.
burnup credit criticality analysis iaea-tecdoc-1547 iaea sensitivity analysis

U.S. Regulatory Recommendations for Actinide-Only Burnup Credit in Transport and Storage Casks

U.S. Regulatory Recommendations for Actinide-Only Burnup Credit in Transport and Storage Casks

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

In July 1999, the U.S. Nuclear Regulatory Commission (NRC) Spent Fuel Project Office
(SFPO) issued Interim Staff Guidance 8 Revision 1 (ISG8R1) to provide recommendations for the use
of burnup credit in storage and transport of pressurized-water reactor (PWR) spent fuel. Subsequent to
the issuance of ISG8R1, the NRC Office of Regulatory Research (RES) has directed an effort to
investigate the technical basis for extending the criteria and recommendations of ISG8R1 to allow

burnup credit criticality analysis iaea-tecdoc-1547 iaea regulations

A Coordinated U.S. Program to Address Full Burnup Credit in Transport and Storage Casks

A Coordinated U.S. Program to Address Full Burnup Credit in Transport and Storage Casks

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

The benefits of burnup credit and the technical issues associated with utilizing burnup credit in spent
nuclear fuel (SNF) casks have been studied in the United States for almost two decades. The issuance of the
U.S. Nuclear Regulatory Commission (NRC) staff guidance for actinide-only burnup credit in 2002 was a
significant step toward providing a regulatory framework for using burnup credit in transport casks. However,
adherence to the current regulatory guidance (e.g., limit credit to actinides) enables only about 30% of the existing

burnup credit criticality analysis iaea-tecdoc-1547 iaea general

Advances in Applications of Burnup Credit to Enhance Spent Fuel Transportation, Storage, Reprocessing and Disposition-Proceedings of a Technical Meeting held in London, 29 August-2 September 2006

Advances in Applications of Burnup Credit to Enhance Spent Fuel Transportation, Storage, Reprocessing and Disposition-Proceedings of a Technical Meeting held in London, 29 August-2 September 2006

Publication Date

This publication records the proceedings of a technical meeting organized by the IAEA and
held in London 29 August–2 September 2005 with sixty participants from 18 countries. As
indicated in the title, the objective of this meeting was to provide a forum for exchange of
technical information on spent fuel burnup credit applications and thereby compile state-ofthe-
art information on technical advances related to spent fuel transportation, storage,
reprocessing and disposition.

burnup credit criticality analysis iaea-tecdoc-1547 proceedings london 2005

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Brazilian National Report

SED Publication Type

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Brazilian National Report

Author
Comissiio Nacional de Energia Nuclear (CNEN) ,
Industrias Nucleares Brasileiras (INB) ,
Eletrobras Termonuclear SA. (ELETRONUCLEAR) ,
Instituto Brasileiro do Meio Ambiente e dos Recursos Naturais Renovaveis (IBAMA) ,
Centro de Tecnologico da Marinha em Siio Paulo (CTMSP) ,
Ministirio da Ciencia e Tecnologia (MCT) ,
Ministirio de Relacoes Exteriores (MRE)
Publication Date

On 29 September 1997 the Join Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management was open for signature at the headquarters of the International Atomic Energy Agency in Vienna. Brazil signed the Convention on October 11th, 1997 and ratified it by the Legislative Decree n. 1.019 of November 14th, 2005. Brazil deposited the instrument of ratification with the Depositary on 17 February 2006. The Convention objectives are to achieve and maintain a high level of nuclear safety worldwide in spent fuel and radioactive waste management.

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

National Report of Brazill 2011 for the 4th Review Meeting of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management

SED Publication Type

National Report of Brazill 2011 for the 4th Review Meeting of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management

Author
Comissão Nacional de Energia Nuclear (CNEN) ,
Indústrias Nucleares do Brasil S.A. (INB) ,
Eletrobrás Termonuclear - Eletronuclear S.A. (ETN) ,
Instituto Brasileiro do Meio Ambiente e dos Recursos Naturais Renováveis (IBAMA) ,
Centro Tecnológico da Marinha em São Paulo (CTMSP) ,
Ministério da Ciência e Tecnologia (MCT) ,
Ministério de Relações Exteriores (MRE)
Publication Date

On 29 September 1997, the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management was open for signature at the headquarters of the International Atomic Energy Agency in Vienna. Brazil signed the Convention on October 11th, 1997 and ratified it by the Legislative Decree 1019 of November 14th, 2005. Brazil deposited the instrument of ratification with the Depositary on 17 February 2006.

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