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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

Japan’s Spent Fuel and Plutonium Management Challenges

Japan’s Spent Fuel and Plutonium Management Challenges

Author(s)
Tatsujiro Suzuki ,
Tadahiro Katsuta
Publication Date

Japan’s spent fuel management and fuel cycle programs are now at a critical stage. Its first commercial-scale reprocessing plant, at Rokkasho Village, will soon start full-scale operation.

spent fuel reprocessing plutonium recycling japan blue ribbon commission used fuel

Locating a radioactive waste repository in the ring of fire

SED Publication Type

Locating a radioactive waste repository in the ring of fire

Author
Mick Apted ,
Kelvin Berryman ,
Neil Chapman ,
Mark Cloos ,
Chuck Connor ,
Kazumi Kitayama ,
Steve Sparks ,
Hiroyuki Tsuchi
Publication Date

The scientific, technical, and sociopolitical challenges of finding a secure site for a geological repository for radioactive wastes have created a long and stony path for many countries. Japan carried out many years of research and development before taking its first steps in site selection.

high level waste repository waste management japan siting

H12: Project to Establish the Scientific and Technical Basis for HLW Disposal in Japan Project Overview Report

SED Publication Type

H12: Project to Establish the Scientific and Technical Basis for HLW Disposal in Japan Project Overview Report

Author
Japan Nuclear Cycle Development Institute
Publication Date

As outlined in the overall program for high-level waste (HLW) management in Japan, defined by the Atomic Energy Commission (AEC), HWL separated from spent nuclear fuel during reprocessing will be immobilized in a glass matrix and stored for a period of 30 to 50 years to allow cooling; it will then be disposed of in a stable deep geological formation.

disposal high level waste repository japan siting regulations characterization

Evaluating Site Suitability for a HLW Repository

SED Publication Type

Evaluating Site Suitability for a HLW Repository

Author
Nuclear Waste Management Organization of Japan
Publication Date

The primary objective of government policy, and of NUMO in implementing this policy, is to
ensure that a repository for Japan’s high-level radioactive waste is located so as to provide
secure isolation of the waste and adequate safety for present and future generations. This
means that the site has to be chosen carefully, taking full account of all its characteristics. In
order to address these characteristics in an orderly and structured manner, we have established

disposal high level waste repository japan siting

H12: Project to Establish the Scientific and Technical Basis for HLW Disposal in Japan Supplementary Report Background of Geologic Disposal

SED Publication Type

H12: Project to Establish the Scientific and Technical Basis for HLW Disposal in Japan Supplementary Report Background of Geologic Disposal

Author
Japan Nuclear Cycle Development Institute
Publication Date

Radioactive waste is produced from a wide range of human activities. The wastes arising from the nuclear fuel cycle occur as a wide range of materials and in many different physical and chemical forms, contaminated with varying activities of radionuclides. Their common feature is the potential hazard associated with their radioactivity and the need to manage them in such a way as to protect the human environment. The safe disposal of radioactive waste is a key reequirement of the nuclear industry worldwide.

disposal high level waste spent fuel nuclear waste nuclear fuel cycle japan used fuel

The NUMO Structured Approach to HLW Disposal in Japan

SED Publication Type

The NUMO Structured Approach to HLW Disposal in Japan

Author
Nuclear Waste Management Organization of Japan
Publication Date

The constraints set by the Japanese HLW disposal programme – particularly associated with
the decision to initiate siting by an open call for volunteers to host a geological repository –
pose particular challenges for repository project management. In order to maintain the
flexibility required to respond to the conditions found at volunteer sites, NUMO has not
published reference designs or site characterisation plans, as is normal for programmes
progressing by site nomination. Instead, we have developed a methodology – the NUMO

disposal high level waste repository japan siting waste facilities

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

SITING PROCESS FOR HLW REPOSITORY IN JAPAN

SED Publication Type

SITING PROCESS FOR HLW REPOSITORY IN JAPAN

Author
Sumio Masuda ,
Kazumi Kitayama ,
Hiroyuki Umeki ,
Morimasa Naito ,
NUMA
Publication Date

In the year 2000, the geological disposal program for high-level radioactive waste in Japan moved from the phase of generic research and development (R&D) into the phase of implementation. Following legislation entitled the “Specified Radioactive Waste Final Disposal Act”, the Nuclear Waste Management Organization of Japan (NUMO) was established as the implementing organization.

high level waste repository japan siting

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, National Report of Japan for the Third Review Meeting

SED Publication Type

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, National Report of Japan for the Third Review Meeting

Author
Government of Japan
Publication Date

Nuclear facilities in Japan are as listed in the following table, the details of which are described in Section D.

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

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, National Report of Japan for the Fourth Review Meeting

SED Publication Type

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, National Report of Japan for the Fourth Review Meeting

Author
Government of Japan
Publication Date

Nuclear facilities in Japan are listed in Table A1-1, the details of which are described in Section D.<br/>The overview of spent fuel management and radioactive waste management and the current<br/>status of the preparation of radioactive waste disposal regulation system are shown in Table<br/>A1-2 and Table A1-3 respectively.

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

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, National Report of Japan for the Third Review Meeting - Annexes

SED Publication Type

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, National Report of Japan for the Third Review Meeting - Annexes

Author
Government of Japan
Publication Date

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, National Report of Japan for the Third Review Meeting - Annexes

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