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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
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, Canada's Responses to Questions, April 2009
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Canada's Responses to Questions, April 2009
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Canada's Responses to Questions, April 2009
Canadian National Report for the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Third Report, October 2008
Canadian National Report for the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Third Report, October 2008
This report demonstrates how Canada continues to meet its obligations under the terms of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management. A collaboration by government, industry and the regulatory body, this document focuses specifically on the progress of long-term management initiatives for spent fuel and radioactive waste in Canada, revisions and updates to Canada’s Second National Report and comments and issues raised at the Second Review Meeting.
Regulatory Guide - Geological Considerations in Siting a Repository for Underground Disposal of High-level Radioactive Waste
Regulatory Guide - Geological Considerations in Siting a Repository for Underground Disposal of High-level Radioactive Waste
At the present time in Canada, high-level radioactive waste is accumulating in the form of irradiated, used fuel from research reactors and nuclear power generating stations. The used fuel bundles are kept in water-filled bays at each of the reactor sites. Because water is both a radiation barrier and an effective coolant, this system provides a safe means of storage. Used fuel is also safely stored above ground in dry concrete canisters in several Canadian locations.
Radioactive Waste Management and Decommissioning in Canada
Radioactive Waste Management and Decommissioning in Canada
OECD/NEA: Canada
OECD/NEA: Canada
Discussion Document# 1: Asking the Right Questions?
Discussion Document# 1: Asking the Right Questions?
Canadian National Report for the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Canadian National Report -- Final Report
Canadian National Report for the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Canadian National Report -- Final Report
This report demonstrates how Canada continues to meet its obligations under the terms of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management. A collaboration by government, industry and the regulatory body, this document focuses specifically on the progress of long-term management initiatives for spent fuel and radioactive waste in Canada, revisions and updates to Canada’s Third National Report and comments and issues raised at the Third Review Meeting.
Discussion Document# 2: Understanding the Choices
Discussion Document# 2: Understanding the Choices
Canadian Site Visit and Workshop - Summary and International Perspective
Canadian Site Visit and Workshop - Summary and International Perspective
INITIAL SCREENING FOR SITING A DEEP GEOLOGICAL REPOSITORY FOR CANADA'S USED NUCLEAR FUEL - Northern Village of Pinehouse, Saskatchewan
INITIAL SCREENING FOR SITING A DEEP GEOLOGICAL REPOSITORY FOR CANADA'S USED NUCLEAR FUEL - Northern Village of Pinehouse, Saskatchewan
On August 17, 2010, the Northern Village of Pinehouse, Saskatchewan and the Kineepik Métis Local expressed interest in learning more about the Nuclear Waste Management Organization (NWMO) site selection process to find an informed and willing community to host a deep geological repository for Canada’s used nuclear fuel (NWMO 2010). This report summarizes the findings of an initial screening, conducted by Golder Associates Ltd., to evaluate the potential suitability of the Pinehouse area against five screening criteria using readily available information.
JOINT CONVENTION ON THE SAFETY OF SPENT FUEL MANAGEMENT AND ON THE SAFETY OF RADIOACTIVE WASTE MANAGEMENT CANADA'S RESPONSES TO QUESTIONS
JOINT CONVENTION ON THE SAFETY OF SPENT FUEL MANAGEMENT AND ON THE SAFETY OF RADIOACTIVE WASTE MANAGEMENT CANADA'S RESPONSES TO QUESTIONS
Response to Questions Posted To Canada in 2006
Fourth Review Meeting of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Canada's Responses to Questions to its Fourth National Report
Fourth Review Meeting of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Canada's Responses to Questions to its Fourth National Report
Fourth Review Meeting of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Canada's Responses to Questions to its Fourth National Report
Moving Forward Together: Canada’s Plan for the Long-Term Management of Used Nuclear Fuel
Moving Forward Together: Canada’s Plan for the Long-Term Management of Used Nuclear Fuel
Canadian National Report for the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management -- Second Report
Canadian National Report for the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management -- Second Report
This is Canada's Second National Report and it demonstrates how Canada continues to meet its obligations under the terms of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management. The main aspect addressed in this report is the progress on initiatives for the long-term management of spent fuel and radioactive waste in Canada. This report also includes information on Canada's systematic monitoring programs and their implementation and addresses specific topics raised at the First Review Meeting.
INITIAL SCREENING FOR SITING A DEEP GEOLOGICAL REPOSITORY FOR CANADA'S USED NUCLEAR FUEL - English River First Nation, Saskatchewan
INITIAL SCREENING FOR SITING A DEEP GEOLOGICAL REPOSITORY FOR CANADA'S USED NUCLEAR FUEL - English River First Nation, Saskatchewan
On September 13, 2010, the English River First Nation expressed interest in learning more about the Nuclear Waste Management Organization (NWMO) site selection process to find an informed and willing community to host a deep geological repository for Canada’s used nuclear fuel (NWMO, 2010). This report summarizes the findings of an initial screening, conducted by Golder Associates Ltd., to evaluate the potential suitability of thirteen English River First Nation reserve areas against five screening criteria using readily available information.