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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
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.
Improved Radiochemical Assay Analyses Using TRITON Depletion Sequences in SCALE
Improved Radiochemical Assay Analyses Using TRITON Depletion Sequences in SCALE
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
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
Internationalization of the Nuclear Fuel Cycle: Goals, Strategies, and Challenges
Internationalization of the Nuclear Fuel Cycle: Goals, Strategies, and Challenges
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
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
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
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
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
Presentation made at IAEA on the NFST Execution Strategy Analysis Capability
Presentation made at IAEA on the NFST Execution Strategy Analysis Capability
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.
Presentation made at IAEA on Interim Storage Facility Design Concepts
Presentation made at IAEA on Interim Storage Facility Design Concepts
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.
Presentation made at IAEA on Dry Storage System Aging Management
Presentation made at IAEA on Dry Storage System Aging Management
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.
Guidance on the Selection of PTA Tools: For Stakeholders involved in Radioactive Waste Governance WP1
Guidance on the Selection of PTA Tools: For Stakeholders involved in Radioactive Waste Governance WP1
This research on "e;Guidance on the selection of PTA tools for stakeholders involved in radioactive waste governance"e; was performed under the umbrella of COWAM2-'Work Package 1' (WP1). Through a dialogue on enhancing involvement at a local level, WP1 allows local stakeholders to examine the issues they face in building a democratic local governance process. WP1 also tests how Participatory Technology Assessment (PTA) methods can offer a consensual framework and a platform for deliberative co-decision among scientific and societal actors at the local level.
Tools for Local Stakeholders in Radioactive Waste Governance: Challenges and Benefits of Selected PTA Techniques WP1
Tools for Local Stakeholders in Radioactive Waste Governance: Challenges and Benefits of Selected PTA Techniques WP1
The investigation consists of three parts and shall provide an input to the – empirical – PTA-2 study to be undertaken by SCK•CEN (called “lens”):<br>A. Compilation of – selected – existing PTA methods and procedures identifying requisites, practices, benefits, and challenges to answer the key questions in the context of WP1 about a PTA “toolbox”: “What can you apply, when can you apply, and what is needed to apply?” The multi-dimensional context of a possible “PTA situation” is analysed; suitable and nonsuitable methods, techniques and procedures are discussed.<br>B.
Nuclear waste management from a local perspective: Reflections for a Better Governance Final Report
Nuclear waste management from a local perspective: Reflections for a Better Governance Final Report
During the 1990s, nuclear waste programmes in nearly every concerned country met many difficulties. Nuclear waste management was seen as a technical issue, and the local communities were only involved in the last stage of the decision-making process when almost all components of the decision were already fixed. The management of high level radioactive waste is now recognised as a complex decision-making process entailing technical, ethical, social, political and economic dimensions where no solution can be reached solely on the basis of technical considerations.