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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
Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants: A Guidance Manual for Users of Standard Technical Specifications (NUREG-0133)
Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants: A Guidance Manual for Users of Standard Technical Specifications (NUREG-0133)
This guidance manual provides the NRC staff methodology for calculating parameters for limiting conditions of operation required in the radiological effluent Technical Specifications for light-water-cooled nuclear power plants. it provides guidance in using the model specifications reported in NUREG-0472 (Revision 1)*, and NUREG-0473 (Revision 1)*, applicable to operating PWR and BWR licensees, and users of the Standard Technical Specifications packages available for various vendor designs.
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
Topical Report on Actinide-Only Burnup Credit for PWR Spent Nuclear Fuel Packages
Topical Report on Actinide-Only Burnup Credit for PWR Spent Nuclear Fuel Packages
A methodology for performing and applying nuclear criticality safety calculations, for PWR spent nuclear fuel (SNF) packages with actinide-only burnup credit, is described. The changes in the U-234, U-235, U-236, U-238, Pu-238, Pu-239, Pu-240, Pu-241, Pu-242, and Am-241 concentration with burnup are used in burnup credit criticality analyses. No credit for fission product neutron absorbers is taken. The methodology consists of five major steps. (1) Validate a computer code system to calculate isotopic concentrations of SNF created during burnup in the reactor core and subsequent decay.
Topical Report on Actinide-Only Burnup Credit for PWR Spent Nuclear Fuel Packages
Topical Report on Actinide-Only Burnup Credit for PWR Spent Nuclear Fuel Packages
A methodology for performing and applying nuclear criticality safety calculations, for PWR spent nuclear fuel (SNF) packages with actinide-only burnup credit, is described. The changes in the U-234, U-235, U-236, U-238, Pu-238, Pu-239, Pu-240, Pu-241, Pu-242, and Am-241 concentration with burnup are used in burnup credit criticality analyses. No credit for fission product neutron absorbers is taken. The methodology consists of five major steps. (1) Validate a computer code system to calculate isotopic concentrations of SNF created during burnup in the reactor core and subsequent decay.
Partnering for Long-term Management of Radioactive Waste-Evolution and Current Practice in Thirteen Countries
Partnering for Long-term Management of Radioactive Waste-Evolution and Current Practice in Thirteen Countries
Preliminary Transportation, Aging and Disposal Canister System Performance Specification Requirements Rationale, Revision B
Preliminary Transportation, Aging and Disposal Canister System Performance Specification Requirements Rationale, Revision B
The purpose of this document is to provide the requirements rationale for the current version of the Preliminary Transportation, Aging and Disposal Canister System Performance Specification; WMO-TADCS-000001.
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
Radioactive Waste Repositories and Host Regions: Envisaging the Future Together
Radioactive Waste Repositories and Host Regions: Envisaging the Future Together
Destructive Examination of 3-Cycle LWR Fuel Rods from Turkey Point Unit 3 for the CLIMAX-Spent Fuel Test
Destructive Examination of 3-Cycle LWR Fuel Rods from Turkey Point Unit 3 for the CLIMAX-Spent Fuel Test
The destructive examination results of five light water reactor rods from the Turkey Point Unit 3 reactor are presented. The examinations included fission gas collection and analyses, burnup and hydrogen analyses, and a metallographic evaluation of the fuel, cladding, oxide, and hydrides. The rods exhibited a low fission gas release with all other results appearing representative for pressurized water reactor fuel rods with similar burnups (28 GWd/MTU) and operating histories.
Emergence of Collective Action and Environmental Networking in Relation to Radioactive Waste Management
Emergence of Collective Action and Environmental Networking in Relation to Radioactive Waste Management
This paper explores the relationship between the national environmental movement and nuclear technology in relation to a local emergent group. The historical development of nuclear technology in this country has followed a path leading to continued fear and mistrust of waste management by a portion of the population. At the forefront of opposition to nuclear technology are people and groups endorsing environmental values.
Everything You Ever Wanted to Know about Radioactive Waste Management
Everything You Ever Wanted to Know about Radioactive Waste Management
Explanation of Radioactivity and Radioactive waste
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.