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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

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Czech Republic National Report, Revision 2.3

SED Publication Type

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Czech Republic National Report, Revision 2.3

Author
Czech Republic
Publication Date

. On 25 March 1999 the Government of the Czech Republic approved the Joint Convention which came into effect in the Czech Republic on 18 June 2001. In agreement with the obligations resulting from its accession to the Joint Convention the Czech Republic has already drawn the second National Report for the purposes of Review Meetings of the Contracting Parties, which describes the system of spent fuel and radioactive waste management in the scope required by selected articles of the Joint Convention.

siting national report joint convention spent fuel management czech republic radioactive waste management

Czech Republic National Report under the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management

SED Publication Type

Czech Republic National Report under the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management

Author
Czech Republic
Publication Date

On 25 March 1999 the government of the Czech Republic approved the Joint Convention which came into effect in the Czech Republic on 18 June 2001. In agreement with the obligations resulting from its accession to the Joint Convention the Czech Republic has drawn already the fourth National Report for the purposes of review meetings of the contracting parties, which describes the system of spent fuel and radioactive waste management in the scope required by selected articles of the Joint Convention.

siting national report joint convention spent fuel management czech republic radioactive waste management

Identifying remaining socio-technical challenges at the national level: Czech Republic

SED Publication Type

Identifying remaining socio-technical challenges at the national level: Czech Republic

Author
Karel Svacina ,
Zdenek Konopasek
Publication Date

This report describes the history, recent developments and the current situation of the management of highly radioactive waste and spent nuclear fuel in the Czech Republic, with a particular focus on the development of geological disposal for this kind of waste. Special attention is given to the interplay of social and technical aspects of the process. The first chapter gives an overview of the state of affairs and sketches out the trajectories leading to it.

disposal public perception radioactive waste siting czech republic wp 1 ms 4

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

SED Publication Type

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

Author
Czech Republic
Publication Date

This report is the National Report submitted by the Czech Republic for the purposes of assessment meeting of the parties to the Joint Convention. Its objective is to describe the fulfillment status of obligations under the Joint Convention in the Czech Republic as on 31 December 2002. The outline of the National Report is based on recommendations approved at the preparatory meeting of the parties to the Joint Convention in December 2001 and contained in the „Guidelines regarding the form and structure of national reports (JC-SFRW/PREP/FINAL/DOCUMENT 3)“ of 13 December 2001.

siting national report joint convention spent fuel management czech republic radioactive waste management
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