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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.
Stakeholder Involvement and Confidence in the Process of Decision-making for the Disposal of Spent Nuclear Fuel in Finland
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, 2nd Finnish National Report as referred to in Article 32 of the Convention
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, 2nd Finnish National Report as referred to in Article 32 of the Convention
Finland signed the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management on 2 October 1997 and deposited the tools of acceptance on 10 February 2000. The Convention entered into force on 18 June 2001. The major generators of radioactive waste in Finland are the two nuclear power plants, the Loviisa and Olkiluoto plants. The Loviisa plant has two PWR units, operated by Fortum Power and Heat Oy, and the Olkiluoto plant two BWR units, operated by Teollisuuden Voima Oy.
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, 4th Finnish National Report as referred to in Article 32 of the Convention
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, 4th Finnish National Report as referred to in Article 32 of the Convention
This is the Finnish National Report, in accordance with the provisions of the Article 32 of the Joint Convention, to the 4th Review Meeting of the Contracting Parties in May 2012. The aim of this report is to present the recent developments of waste management in Finland, to describe waste management facilities and practices in Finland and, for discussion and review among contracting parties, to describe how the obligations under the Convention are fulfilled in Finland.
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, 3rd Finnish National Report as referred to in Article 32 of the Convention
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, 3rd Finnish National Report as referred to in Article 32 of the Convention
The Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management was adopted on 29 September 1997 in the Vienna Diplomatic Conference. Finland signed the Convention on 2 October 1997 and deposited the tools of acceptance on 10 February 2000. The Convention entered into force on 18 June 2001. The fulfillment of the obligations of the Convention and the developments after the second Review Meeting are assessed in this report.
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, 3rd Finnish National Report as referred to in Article 32 of the Convention
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, 3rd Finnish National Report as referred to in Article 32 of the Convention
The Joint Convention on the Safety of Spent Fuel<br/>Management and on the Safety of Radioactive<br/>Waste Management was adopted on 29 September<br/>1997 in the Vienna Diplomatic Conference. Finland<br/>signed the Convention on 2 October 1997 and deposited<br/>the tools of acceptance on 10 February<br/>2000. The Convention entered into force on 18 June<br/>2001.<br/>The fulfilment of the obligations of the<br/>Convention and the developments after the second<br/>Review Meeting are assessed in this report.
Identifying remaining socio-technical challenges at the national level: Finland
Identifying remaining socio-technical challenges at the national level: Finland
This research report is part of the research programme International Socio-Technical Challenges for Implementing Geological Disposal (InSOTEC; see www.insotec.eu). The research programme is funded by the Seventh Framework Programme Theme [Fission-2010-1.1.2] [Research activities in support of implementation of geological disposal] (Grant agreement no: 269906).
Radioactive Waste Management and Decommissioning in Finland
Radioactive Waste Management and Decommissioning in Finland
OECD/NEA: Finland
OECD/NEA: Finland
Final Disposal of Spent Nuclear Fuel in Finnish Bedrock - Kivetty Site Report
Final Disposal of Spent Nuclear Fuel in Finnish Bedrock - Kivetty Site Report
Posiva Oy is studying the Finnish bedrock for the geological disposal of spent nuclear fuel. The study is based on the site selection research programme started originally in 1983. The programme is in accordance with the decision in principle by the Council of State in 1983 and aims at the selection of one site in 2000. Four sites, Hastholmen in Loviisa, Kivetty in Aanekoski, Olkiluoto in Eurajoki and Romuvaara in Kuhmo, have been studied in detail. This report summarises the results of the site investigations carried out at Kivetty.
Final Disposal of Spent Nuclear Fuel in Finnish Bedrock - Olkiluoto Site Report
Final Disposal of Spent Nuclear Fuel in Finnish Bedrock - Olkiluoto Site Report
Posiva Oy is studying the Finnish bedrock for the geological disposal of spent nuclear fuel. The study is based on the site selection research programme started originally in 1983. The programme is in accordance with the decision in principle by the Council of State in 1983 and aims at the selection of one site in 2000. Four sites, Hastholmen in Loviisa, Kivetty in Aanekoski, Olkiluoto in Eurajoki and Romuvaara in Kuhmo, have been studied in detail. This report summarises the results of the site investigations carried out at Olkiluoto.
Expansion of the Repository for Spent Nuclear Fuel: Environmental Impact Assessment Report
Expansion of the Repository for Spent Nuclear Fuel: Environmental Impact Assessment Report
Interim Summary Report of the Safety Case
Interim Summary Report of the Safety Case
The report outlines the current design and safety concept for the planned repository. It summarises the approach used to formulate scenarios for the evolution of the disposal system over time, describes these scenarios and presents the main models and computer codes used to analyse them. It also discusses compliance with Finnish regulatory requirements for long-term safety of a geological repository and gives the main evidence, arguments and analyses that lead to confidence, on the part of Posiva, in the long-term safety of the planned repository
Safety Case Plan
Safety Case Plan
Following the guidelines set forth by the Ministry of Trade and Industry (now Ministry of Employment and Economy) Posiva is preparing to submit the construction license application for a spent fuel repository by the end of the year 2012. The long-term safety section supporting the license application is based on a safety case, which, according to the internationally adopted definition, is a compilation of the evidence, analyses and arguments that quantify and substantiate the safety and the level of expert confidence in the safety of the planned repository.
Final Disposal of Spent Nuclear Fuel in Olkiluoto
Final Disposal of Spent Nuclear Fuel in Olkiluoto
Olkiluoto Site Description
Olkiluoto Site Description
This second version of the Olkiluoto Site Report, produced by the OMTF (Olkiluoto Modelling Task Force), updates the Olkiluoto Site Report 2004 (Posiva 2005) with the data and knowledge obtained up to December 2005.<br/>The main product of the modelling has been to develop a descriptive model of the site (the Site Descriptive Model), i.e. a model describing the geometry, properties of the bedrock and the water and the associated interacting processes and mechanisms.