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EQ6 Calculations for Chemical Degradation of PWR LEU and PWR MOX Spent Fuel Waste Packages
EQ6 Calculations for Chemical Degradation of PWR LEU and PWR MOX Spent Fuel Waste Packages
OECD/NEA Burnup Credit Criticality Benchmark, Analysis of Phase II-B Results: Conceptual PWR Spent Fuel Transportation Cask
OECD/NEA Burnup Credit Criticality Benchmark, Analysis of Phase II-B Results: Conceptual PWR Spent Fuel Transportation Cask
Research Supporting Implementation of Burnup Credit in the Criticality Safety Assessment of Transport and Storage Casks
Research Supporting Implementation of Burnup Credit in the Criticality Safety Assessment of Transport and Storage Casks
Spent Fuel Project Office, ISG-8 - Limited Burnup Credit in the Criticality Safety Analyses of PWR Spent Fuel in Transport and Storage Casks
Spent Fuel Project Office, ISG-8 - Limited Burnup Credit in the Criticality Safety Analyses of PWR Spent Fuel in Transport and Storage Casks
Spent Fuel Project Office Interim Staff Guidance - 8
Spent Fuel Project Office, Interim Staff Guidance - 8, Revision 1, Burnup Credit in the Criticality Safety Analyses of PWR Spent Fuel in Transport and Storage Casks
Spent Fuel Project Office, Interim Staff Guidance - 8, Revision 1, Burnup Credit in the Criticality Safety Analyses of PWR Spent Fuel in Transport and Storage Casks
Spent Fuel Project Office, Interim Staff Guidance - 8, Revision 1
Issues for Effective Implementation of Burnup Credit
Issues for Effective Implementation of Burnup Credit
In the United States, burnup credit has been used in the criticality safety evaluation for storage pools at
pressurized water reactors (PWRs) and considerable work has been performed to lay the foundation for use of
burnup credit in dry storage and transport cask applications and permanent disposal applications. Many of the
technical issues related to the basic physics phenomena and parameters of importance are similar in each of these
applications. However, the nuclear fuel cycle in the United States has never been fully integrated and the
Regulatory Status of Burnup Credit for Spent-Fuel Storage and Transport Casks
Regulatory Status of Burnup Credit for Spent-Fuel Storage and Transport Casks
Spent Fuel Project Office, Interim Staff Guidance - 8, Revision 2, Burnup Credit in the Criticality Safety Analyses of PWR Spent Fuel in Transport and Storage Casks
Spent Fuel Project Office, Interim Staff Guidance - 8, Revision 2, Burnup Credit in the Criticality Safety Analyses of PWR Spent Fuel in Transport and Storage Casks
Spent Fuel Project Office, Interim Staff Guidance - 8, Revision 2 - Burnup Credit in the Criticality Safety Analyses of PWR Spent Fuel in Transport
and Storage Casks
Isotopic Generation and Verification of the PWR Application Model
Isotopic Generation and Verification of the PWR Application Model
The objective of this calculation is to establish an isotopic database to represent commercial spent nuclear fuel (CSNF) from pressurized water reactors (PWRs) in criticality analyses performed for the proposed Monitored Geologic Repository at Yucca Mountain, Nevada. Confirmation of the conservatism with respect to criticality in the isotopic concentration values represented by this isotopic database is performed as described in Section 3.5.3.1.2 of the Disposal Criticality Analysis Methodology Topical Report (YMP 2000).
Criticality Consequence Calculation Involving Intact PWR MOX SNF in a Degraded 21 PWR Assembly Waste Package
Criticality Consequence Calculation Involving Intact PWR MOX SNF in a Degraded 21 PWR Assembly Waste Package
The purpose of this calculation is to evaluate the transient behavior and consequences of a worst- case criticality event involving intact pressurized water reactor (PWR) mixed-oxide (MOX) spent nuclear fuel (SNF) in a degraded basket configuration inside a 21 PWR waste package (WP). This calculation will provide information necessary for demonstrating that the consequences of a worst-case criticality event involving intact PWR MOX SNF are insignificant in their effect on the overall radioisotopic inventory and on the integrity of the repository.
PWR Axial Burnup Profile Analysis
PWR Axial Burnup Profile Analysis
The purpose of this activity is to develop a representative “limiting” axial burnup profile for pressurized water reactors (PWRs), which would encompass the isotopic axial variations caused by different assembly irradiation histories, and produce conservative isotopics with respect to criticality. The effect that the low burnup regions near the ends of spent fuel have on system reactivity is termed the “end-effect”. This calculation will quantify the end-effects associated with Pressurized Water Reactor (PWR) fuel assemblies emplaced in a hypothetical 21 PWR waste package.
Criticality Consequence Analysis Involving Intact PWR SNF in a Degraded 21 PWR Assembly Waste Package
Criticality Consequence Analysis Involving Intact PWR SNF in a Degraded 21 PWR Assembly Waste Package
The purpose of this analysis is to evaluate the transient behavior and consequences of a worst case criticality event involving intact pressurized water reactor (PWR) spent nuclear fuel (SNF) in a degraded basket configuration inside a 21 PWR assembly waste package (WP). The objective of this analysis is to demonstrate that the consequences of a worst case criticality event involving intact PWR SNF are insignificant in their effect on the overall radioisotopic inventory in a WP. An internal WP criticality is modeled in a manner analogous to transient phenomena in a nuclear reactor core.
PWR Axial Burnup Profile Analysis
PWR Axial Burnup Profile Analysis
The purpose of this activity is to develop a representative “limiting” axial burnup profile for pressurized water reactors (PWRs), which would encompass the isotopic axial variations caused by different assembly irradiation histories, and produce conservative isotopics with respect to
3rd WP Probabilistic Criticality Analysis: Methodology for Basket Degradation with Application to Commercial SNF
3rd WP Probabilistic Criticality Analysis: Methodology for Basket Degradation with Application to Commercial SNF
This analysis is prepared by the Mined Geologic Disposal System (MGDS) Waste Package Development (WPD) department to describe the latest version of the probabilistic criticality analysis methodology and its application to the entire commercial waste stream of commercial pressurized water reactor (PWR) spent nuclear fuel (SNF) expected to be emplaced in the repository. The purpose of this particular application is to evaluate the 21 assembly PWR absorber plate waste package (WP) with respect to degradedmode criticality performance.
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Austrian National Report
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Austrian National Report
This report provides - a detailed description of the Austrian policy and the usual practices concerning the management of spent fuel of the Austrian research reactors and the management of radioactive waste (see Section B); - a detailed description of the Austrian legal regime concerning the management of spent fuel of the Austrian research reactors and the management of radioactive waste (see Section E).
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Answers to Questions Posted by the Contracting Parties on the Argentina Second National Report
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Answers to Questions Posted by the Contracting Parties on the Argentina Second National Report
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Answers to Questions Posted by the Contracting Parties on the Argentina Second National Report
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Czech Republic National Report, Revision 2.3
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Czech Republic National Report, Revision 2.3
. 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.
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, USA National Report
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, USA National Report
The United States of America ratified the “Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management” (Joint Convention) on April 9, 2003. The Joint Convention establishes an international peer review process among Contracting Parties and provides incentives for nations to take appropriate steps to bring their nuclear activities into compliance with general safety standards and practices. This first Review Meeting of the Contracting Parties under the Joint Convention is scheduled to take place in November 2003 in Vienna, Austria.
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.
Second Meeting of the Contracting Parties to the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Kingdom of Belgium National Report
Second Meeting of the Contracting Parties to the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Kingdom of Belgium National Report
On 8 December 1997 Belgium has signed the Joint Convention. The Belgian legislator has expressed its consent with the obligations resulting from the Convention via the Law of 2 August 2002. The ratification was obtained on 5 September 2002. The Convention became effective on 4 December 2002, or 90 days after the Ratification Act had been deposited. Belgium belongs to the group of Contracting Parties having at least one operational nuclear generating unit on their territory.
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Denmark National Report
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Denmark National Report
Denmark signed the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management 29 September 1997, the day it opened for signature. The Convention was accepted 3 September 1999 by letter from the Foreign Ministry to the International Atomic Energy Agency (IAEA). Until further notice the Convention does not apply for the autonomous territories Greenland and the Faroe Islands, which both do not possess spent nuclear fuel or radioactive waste. The present report is the Danish National Report for the Second Review Meeting to the Convention.
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
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
Nuclear facilities in Japan are as listed in the following table, the details of which are described in Section D.
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Report of the Federal Republic of Germany for the Third Review Meeting in May 2009
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Report of the Federal Republic of Germany for the Third Review Meeting in May 2009
The Federal Government will continue to meet Germany’s existing international obligations, particularly with regard to fulfilment of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management. In submitting this report, Germany is demonstrating its compliance with the Joint Convention and how it ensures the safe operation of facilities for the management of spent fuel and radioactive waste, including the decommissioning of nu-clear installations.
Republic of Croatia, National Report on Implementation of the Obligations Under Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, 3rd Report
Republic of Croatia, National Report on Implementation of the Obligations Under Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, 3rd Report
The Republic of Croatia signed the “Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management” (Joint Convention) on 9 April 1998, and ratified it on 5 February 1999. The first National Report on implementation of the obligations under the Joint Convention was prepared at the beginning of 2003, and the Republic of Croatia participated at the Review Meeting later that year. The second National Report was prepared in 2005 also followed by an active participation at the Review Meeting in 2006.