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Japan’s Spent Fuel and Plutonium Management Challenges
Japan’s Spent Fuel and Plutonium Management Challenges
Japan’s spent fuel management and fuel cycle programs are now at a critical stage. Its first commercial-scale reprocessing plant, at Rokkasho Village, will soon start full-scale operation.
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.
Locating a radioactive waste repository in the ring of fire
Locating a radioactive waste repository in the ring of fire
The scientific, technical, and sociopolitical challenges of finding a secure site for a geological repository for radioactive wastes have created a long and stony path for many countries. Japan carried out many years of research and development before taking its first steps in site selection.
H12: Project to Establish the Scientific and Technical Basis for HLW Disposal in Japan Project Overview Report
H12: Project to Establish the Scientific and Technical Basis for HLW Disposal in Japan Project Overview Report
As outlined in the overall program for high-level waste (HLW) management in Japan, defined by the Atomic Energy Commission (AEC), HWL separated from spent nuclear fuel during reprocessing will be immobilized in a glass matrix and stored for a period of 30 to 50 years to allow cooling; it will then be disposed of in a stable deep geological formation.
Evaluating Site Suitability for a HLW Repository
Evaluating Site Suitability for a HLW Repository
The primary objective of government policy, and of NUMO in implementing this policy, is to
ensure that a repository for Japan’s high-level radioactive waste is located so as to provide
secure isolation of the waste and adequate safety for present and future generations. This
means that the site has to be chosen carefully, taking full account of all its characteristics. In
order to address these characteristics in an orderly and structured manner, we have established
H12: Project to Establish the Scientific and Technical Basis for HLW Disposal in Japan Supplementary Report Background of Geologic Disposal
H12: Project to Establish the Scientific and Technical Basis for HLW Disposal in Japan Supplementary Report Background of Geologic Disposal
Radioactive waste is produced from a wide range of human activities. The wastes arising from the nuclear fuel cycle occur as a wide range of materials and in many different physical and chemical forms, contaminated with varying activities of radionuclides. Their common feature is the potential hazard associated with their radioactivity and the need to manage them in such a way as to protect the human environment. The safe disposal of radioactive waste is a key reequirement of the nuclear industry worldwide.
The NUMO Structured Approach to HLW Disposal in Japan
The NUMO Structured Approach to HLW Disposal in Japan
The constraints set by the Japanese HLW disposal programme – particularly associated with
the decision to initiate siting by an open call for volunteers to host a geological repository –
pose particular challenges for repository project management. In order to maintain the
flexibility required to respond to the conditions found at volunteer sites, NUMO has not
published reference designs or site characterisation plans, as is normal for programmes
progressing by site nomination. Instead, we have developed a methodology – the NUMO
Dry Cask Storage of Nuclear Spent Fuel
Dry Cask Storage of Nuclear Spent Fuel
Cost Estimate for an Away-From-Reactor Generic Interim Storage Facility (GISF) for Spent Nuclear Fuel
Cost Estimate for an Away-From-Reactor Generic Interim Storage Facility (GISF) for Spent Nuclear Fuel
As nuclear power plants began to run out of storage capacity in spent nuclear fuel (SNF) storage pools, many nuclear operating companies added higher density pool storage racks to increase pool capacity. Most nuclear power plant storage pools have been re-racked one or more times. As many spent fuel storage pools were re-racked to the maximum extent possible, nuclear operating companies began to employ interim dry storage technologies to store SNF in certified casks and canister-based systems outside of the storage pool in independent spent fuel storage installations (ISFSIs).
Technical Bases for Extended Dry Storage of Spent Nuclear Fuel
Technical Bases for Extended Dry Storage of Spent Nuclear Fuel
Independent spent fuel storage installations (ISFSIs) are currently licensed for 20 years. However, delays in developing permanent spent fuel disposal capability require continued ISFSI storage beyond the 20-year term. This report provides a technical basis for demonstrating the feasibility of extended spent fuel storage in ISFSIs.
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.
slides - ISFSI Pad Design Issues
slides - ISFSI Pad Design Issues
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
slides - ISFSI Security Rulemaking Update
slides - ISFSI Security Rulemaking Update
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
slides - ISFSI Security Rulemaking Update
slides - ISFSI Security Rulemaking Update
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
Yankee Atomic Electric Company vs The United States, November 14, 2013
Yankee Atomic Electric Company vs The United States, November 14, 2013
Spent Nuclear Fuel Litigation - Court of Federal Claims decision in Maine Yankee II, Conn Yankee II and Yankee Atomic II
slides - Prairie Island ISFSI License Renewal and High Burn Up Fuel Contention
slides - Prairie Island ISFSI License Renewal and High Burn Up Fuel Contention
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
THERMAL PERFORMANCE SENSITIVITY STUDIES IN SUPPORT OF MATERIAL MODELING FOR EXTENDED STORAGE OF USED NUCLEAR FUEL
THERMAL PERFORMANCE SENSITIVITY STUDIES IN SUPPORT OF MATERIAL MODELING FOR EXTENDED STORAGE OF USED NUCLEAR FUEL
The work reported here is an investigation of the sensitivity of component temperatures in a specific storage system, including fuel cladding temperatures, in response to modeling assumptions that differ from design-basis, including age-related changes that could degrade the thermal behavior of the system. Preliminary evaluations of representative horizontal and vertical storage systems at design basis conditions provides general insight into the expected behavior of storage systems over extended periods of time.
DECOMMISSIONING COST ANALYSIS for the CLINTON POWER STATION
DECOMMISSIONING COST ANALYSIS for the CLINTON POWER STATION
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Crystal River Unit 3 -- UPDATED IRRADIATED FUEL MANAGEMENT PROGRAM- 10 CFR 50.54(bb) and SITE-SPECIFIC DECOMMISSIONING COST ESTIMATE FOR THE CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT
Crystal River Unit 3 -- UPDATED IRRADIATED FUEL MANAGEMENT PROGRAM- 10 CFR 50.54(bb) and SITE-SPECIFIC DECOMMISSIONING COST ESTIMATE FOR THE CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT
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Kewaunee Power Station -- Post-Shutdown Decommissioning Activities Report
Kewaunee Power Station -- Post-Shutdown Decommissioning Activities Report
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ORDER GRANTING APPLICATIONS TO REDUCE RATES UNDER WHOLESALE POWER CONTRACTS
ORDER GRANTING APPLICATIONS TO REDUCE RATES UNDER WHOLESALE POWER CONTRACTS
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Radioactive Waste Repositories and Host Regions: Envisaging the Future Together
Radioactive Waste Repositories and Host Regions: Envisaging the Future Together
SITING PROCESS FOR HLW REPOSITORY IN JAPAN
SITING PROCESS FOR HLW REPOSITORY IN JAPAN
In the year 2000, the geological disposal program for high-level radioactive waste in Japan moved from the phase of generic research and development (R&D) into the phase of implementation. Following legislation entitled the “Specified Radioactive Waste Final Disposal Act”, the Nuclear Waste Management Organization of Japan (NUMO) was established as the implementing organization.