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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.
BWR Axial Profile
BWR Axial Profile
The purpose of this calculation is to develop axial profiles for estimating the axial variation in burnup of a boiling water reactor (BWR) assembly spent nuclear fuel (SNF) given the average burnup of an assembly. A discharged fuel assembly typically exhibits higher burnup in the center and lower burnup at the ends of the assembly. Criticality safety analyses taking credit for SNF burnup must account for axially varying burnup relative to calculations based on uniformly distributed assembly average burnup due to the under-burned tips.
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
PWR Axial Profile Evaluation
PWR Axial Profile Evaluation
This calculation compares results from criticality evaluations for a 21-assembly pressurized water reactor (PWR) waste package based on 12 axial burnup profile representations for commercial spent nuclear fuel (SNF) assemblies. The burnup profiles encompass the axial variations caused by different fuel assembly irradiation histories in a commercial PWR, including end effects, and the concomitant effect on reactivity in the waste package. The bounding axial burnup profiles in Table T of reference 6.3 are used for this analysis.
Research to Support Expansion of U.S. Regulatory Position on Burnup Credit for Transport and Storage Casks
Research to Support Expansion of U.S. Regulatory Position on Burnup Credit for Transport and Storage Casks
In 1999, the United States Nuclear Regulatory Commission (U.S. NRC) initiated a research program
to support the development of technical bases and guidance that would facilitate the implementation of burnup
credit into licensing activities for transport and dry cask storage. This paper reviews the following major areas of
investigation: (1) specification of axial burnup profiles, (2) assumption on cooling time, (3) allowance for
assemblies with fixed and removable neutron absorbers, (4) the need for a burnup margin for fuel with initial
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.