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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.
WP 2 Appendix 5 Participación Institucional De Los Municipios En El Proceso De Toma De Decisiones Para El Emplazamiento De Un Almacenamiento De Residuos Radiactivos
Aspects of Governance in the Practical Implementation of the Concept of Reversibility for Deep Geological Disposal
Aspects of Governance in the Practical Implementation of the Concept of Reversibility for Deep Geological Disposal
The European project COWAM in Practice (CIP) was aimed to lead for three years (2007-2009) a process of monitoring, analyzing and evaluating the governance linked with radioactive waste management. This project, in cooperation with a research group and stakeholders, was conducted in parallel in 5 European countries (Spain, France, United Kingdom, Romania, Slovenia).
D1-11 Prospective Case Study - Spain
D1-11 Prospective Case Study - Spain
WP 2 Appendix 4 Estudio Sociológico Sobre La A.M.A.C. Y El Hecho Nuclear En España
WP 2 Appendix 4 Estudio Sociológico Sobre La A.M.A.C. Y El Hecho Nuclear En España
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, First Spanish National Report
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, First Spanish National Report
The present document constitutes the First National Report of Spain, drawn up in order to meet the requirements of Article 32 of the Joint Convention on the safety of spent fuel management and on the safety of radioactive waste management, adopted in Vienna on 5th September 1997. This Convention, which was signed by Spain on 30th June 1998 and ratified on 11th May 1999, entered into force on 18th June 2001.
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Fourth Spanish National Report
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Fourth Spanish National Report
The present document constitutes the Fourth Spanish National Report, submitted in compliance with the requirements of article 32 of the Joint Convention on Safety in the Management of Spent Fuel and Safety in the Management of Radioactive Waste, done in Vienna on September 5th 1997. This report will be examined during the review meeting of the Contracting Parties contemplated in article 30 of this Convention, which will begin in May 2012.
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Second Spanish National Report
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Second Spanish National Report
The present document constitutes the Second Spanish National Report, issued in compliance with the requirements of article 32 of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management (hereinafter, Joint Convention), made in Vienna on September 5th 1997. This report will be examined during the Review Meeting between the Contracting Parties contemplated in article 30 of the Joint Convention, which is scheduled to start on May 15th 2006. The Ministry of Industry, Tourism and Trade (Span.
Identifying remaining socio-technical challenges at the national level: Spain
Identifying remaining socio-technical challenges at the national level: Spain
On 29 December 2009, the Spanish government launched a site selection process to host a centralised interim storage facility for spent fuel and high-level radioactive waste. It was an unprecedented call for voluntarism among Spanish municipalities to site a controversial facility. Two nuclear municipalities, amongst a total of thirteen municipalities from five different regions, presented their candidatures to host the facility in their territories. For two years the government did not make a decision.