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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

Presentation made at IAEA on A Unified Spent Nuclear Fuel (SNF) Database and Analysis System

Presentation made at IAEA on A Unified Spent Nuclear Fuel (SNF) Database and Analysis System

Author(s)
Scaglione
Publication Date

Presentation made at International Conference on The Management of Spent Nuclear Fuel from Nuclear Power Reactors, An Integrated approach to the Back-End of the Fuel Cycle (IAEA-CN-226). The purpose of the conference was to highlight the importance of an integrated long-term approach to the management of spent fuel from nuclear power reactors.

iaea snf unified database

Assessment of Benefits for Extended Burnup Credit in Transporting PWR Spent Nuclear Fuel in the USA

Assessment of Benefits for Extended Burnup Credit in Transporting PWR Spent Nuclear Fuel in the USA

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

This paper presents an assessment of the benefits for extended burnup credit in transporting
pressurized-water-reactor (PWR) spent nuclear fuel (SNF) in the United States. A prototypic 32-
assembly cask and the current regulatory guidance were used as bases for this assessment. By
comparing recently released PWR discharge data with actinide-only-based loading curves, this
evaluation shows that additional negative reactivity (through either increased credit for fuel burnup or

burnup credit criticality analysis iaea general

Internationalization of the Nuclear Fuel Cycle: Goals, Strategies, and Challenges

Internationalization of the Nuclear Fuel Cycle: Goals, Strategies, and Challenges

Author(s)
National Academy of Sciences
Publication Date

Following the proposals for nuclear fuel assurance of International Atomic Energy
Agency (IAEA) Director General Mohamed ElBaradei, former Russian President Vladimir V.
Putin, and U.S. President George W. Bush, joint committees of the Russian Academy of
Sciences (RAS) and the U.S. National Academies (NAS) were formed to address these and other
fuel assurance concepts and their links to nonproliferation goals. The joint committees also
addressed many technology issues relating to the fuel assurance concepts. This report provides

iaea nuclear fuel cycle gnep blue ribbon commission nonproliferation global nuclear energy partnership

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

Presentation made at IAEA on the NFST Execution Strategy Analysis Capability

Presentation made at IAEA on the NFST Execution Strategy Analysis Capability

Author(s)
Ralph Stoll ,
Mark Nutt ,
Natalia Saraeva ,
Alan Keizur ,
Alyssa Neir
Publication Date

Presentation made at International Conference on The Management of Spent Nuclear Fuel from Nuclear Power Reactors, An Integrated approach to the Back-End of the Fuel Cycle (IAEA-CN-226). The purpose of the conference was to highlight the importance of an integrated long-term approach to the management of spent fuel from nuclear power reactors.

iaea execution strategy analysis

Presentation made at IAEA on Interim Storage Facility Design Concepts

Presentation made at IAEA on Interim Storage Facility Design Concepts

Author(s)
Joe Carter
Publication Date

Presentation made at International Conference on The Management of Spent Nuclear Fuel from Nuclear Power Reactors, An Integrated approach to the Back-End of the Fuel Cycle (IAEA-CN-226). The purpose of the conference was to highlight the importance of an integrated long-term approach to the management of spent fuel from nuclear power reactors.

iaea design concepts interim storage facility

Presentation made at IAEA on Dry Storage System Aging Management

Presentation made at IAEA on Dry Storage System Aging Management

Author(s)
Yung Liu
Publication Date

Presentation made at International Conference on The Management of Spent Nuclear Fuel from Nuclear Power Reactors, An Integrated approach to the Back-End of the Fuel Cycle (IAEA-CN-226). The purpose of the conference was to highlight the importance of an integrated long-term approach to the management of spent fuel from nuclear power reactors.

dry cask storage iaea aging management

Second Meeting of the Contracting Parties to the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Kingdom of Belgium National Report

SED Publication Type

Second Meeting of the Contracting Parties to the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Kingdom of Belgium National Report

Author
Federal Agency for Nuclear Control on behalf of Belgium. Contributions were also made by ONDRAF/NIRAS, Electrabel, Association Vinçotte Nuclear and the SCK•CEN
Publication Date

On 8 December 1997 Belgium has signed the Joint Convention. The Belgian legislator has expressed its consent with the obligations resulting from the Convention via the Law of 2 August 2002. The ratification was obtained on 5 September 2002. The Convention became effective on 4 December 2002, or 90 days after the Ratification Act had been deposited. Belgium belongs to the group of Contracting Parties having at least one operational nuclear generating unit on their territory.

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

Kingdom of Belgium, Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Second Review Meeting (May 2006), Answers to the Questions of Contracting Parties on the National Report submitted by Belgium

SED Publication Type

Kingdom of Belgium, Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Second Review Meeting (May 2006), Answers to the Questions of Contracting Parties on the National Report submitted by Belgium

Author
Federal Agency for Nuclear Control on behalf of Belgium. Contributions were also made by ONDRAF/NIRAS, Electrabel, Association Vinçotte Nuclear and the SCK•CEN
Publication Date

Kingdom of Belgium, Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Second Review Meeting (May 2006), Answers to the Questions of Contracting Parties on the National Report submitted by Belgium

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

Kingdom of Belgium Fourth Meeting of the Contracting Parties to the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management National Report

SED Publication Type

Kingdom of Belgium Fourth Meeting of the Contracting Parties to the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management National Report

Author
Kingdom of Belgium
Publication Date

On 8 December 1997 Belgium signed the Joint Convention. The Belgian legislator has expressed its consent with the obligations resulting from the Convention by the Law of 2 August 2002. The ratification followed on 5 September 2002. The Convention became effective on 4 December 2002, i.e. 90 days following ratification. Belgium belongs to the group of Contracting Parties having at least one operational nuclear power plant on their territory.

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

Technical overview of the SAFIR 2 report: Safety Assessment and Feasibility Interim Report 2

SED Publication Type

Technical overview of the SAFIR 2 report: Safety Assessment and Feasibility Interim Report 2

Author
Belgium ,
ONDRAF/NIRAS
Publication Date

This document is the technical overview of the SAFIR 2 report that synthesises all of the technical and scientific knowledge available at the end of the second phase (1990–2000) of the ONDRAF/NIRAS programme of methodological research and development on the final disposal of category B and C waste in a poorly-indurated clay formation. The SAFIR 2 report will be handed over by ONDRAF/NIRAS to its supervisory Minister at the beginning of 2002, after publication approval by its Board of Directors.

disposal repository siting belgium

Identifying remaining socio-technical challenges at the national level: Belgium

SED Publication Type

Identifying remaining socio-technical challenges at the national level: Belgium

Author
Jantine Schroder ,
Anne Bergmans
Publication Date

This report is part of the research project International Socio-Technical Challenges for Implementing Geological Disposal: InSOTEC (see www.insotec.eu), funded by the European Commission under the Seventh Framework Programme.<br/>This report is a contribution to Work Package 1 of the project, which aims to identify the most significant socio-technical challenges related to geological disposal of radioactive waste. To achieve this objective, a comparative analysis of 14 national programmes will be performed.

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