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Response of the UK Government and the Department of the Environment, Northern Ireland to the Committee on Radioactive Waste management (CoRWM) Report on 'Geological Disposal of Higher Activity Radioactive Wastes'
Response of the UK Government and the Department of the Environment, Northern Ireland to the Committee on Radioactive Waste management (CoRWM) Report on 'Geological Disposal of Higher Activity Radioactive Wastes'
The primary task of the Committee on Radioactive Waste Management (CoRWM) is to provide independent scrutiny of the Government’s and Nuclear Decommissioning Authority’s proposal, plans and programmes to deliver geological disposal, together with robust interim storage, as the long-term<br/>management option for the UK’s higher activity wastes. In June 2007 the Scottish Executive announced a policy of near-surface, near-site long-term storage rather than geological disposal.
Report to Congress on the Demonstration of the Interim Storage of Spent Nuclear Fuel from Decommissioned Nuclear Power Reactor Sites
Report to Congress on the Demonstration of the Interim Storage of Spent Nuclear Fuel from Decommissioned Nuclear Power Reactor Sites
This report discusses the status of the commercial spent nuclear fuel (SNF) inventory in the United States, at both decommissioned and operating commercial nuclear power reactor sites; summarizes the contractual arrangement the government and utilities have under the Standard Contract for Disposal of Spent Nuclear Fuel and/or High-Level Radioactive Waste (10 CFR Part 961) (Standard Contract), related litigation, and the financial liabilities resulting from the Department’s delay in performance under these contracts; provides a history of interim storage policy as it relates to commercial SN
Advanced Fuel Cycle Cost Basis
Advanced Fuel Cycle Cost Basis
This report, commissioned by the U.S. Department of Energy (DOE), provides a comprehensive set of cost data supporting a cost analysis for the relative economic comparison of options for use in the Advanced Fuel Cycle Initiative (AFCI) Program. The report describes the AFCI cost basis development process, reference information on AFCI cost modules, a procedure for estimating fuel cycle costs, economic evaluation guidelines, and a discussion on the integration of cost data into economic computer models.
Spent Nuclear Fuel: Accumulating Quantities at Commercial Reactors Present Storage and Other Challenges
Spent Nuclear Fuel: Accumulating Quantities at Commercial Reactors Present Storage and Other Challenges
The amount of spent fuel stored on-site at commercial nuclear reactors will continue to accumulate—increasing by about 2,000 metric tons per year and likely more than doubling to about 140,000 metric tons—before it can be moved off-site, because storage or disposal facilities may take decades to develop. In examining centralized storage or permanent disposal options, GAO found that new facilities may take from 15 to 40 years before they are ready to begin accepting spent fuel. Once an off-site facility is available, it will take several more decades to ship spent fuel to that facility.
Evaluation of Burnup Credit for Accommodating PWR Spent Nuclear Fuel in High-capacity Cask Designs
Evaluation of Burnup Credit for Accommodating PWR Spent Nuclear Fuel in High-capacity Cask Designs
This paper presents an evaluation of the amount of burnup credit needed for high-density casks to
transport the current U.S. inventory of commercial spent nuclear fuel (SNF) assemblies. A prototypic
32-assembly cask and the current regulatory guidance were used as bases for this evaluation.
By comparing actual pressurized-water-reactor (PWR) discharge data (i.e., fuel burnup and initial
enrichment specifications for fuel assemblies discharged from U.S. PWRs) with actinide-only-based
Monitored Retrievable Storage Project Plan
Monitored Retrievable Storage Project Plan
The purpose of this document is to describe the Monitored Retrievable Storage (MRS) Project and to establish approved cost and schedule baselines against which overall progress and management effectiveness shall be measured. For the sake of brevity, this Project Plan will be referred to as the Plan throughout this document.
Fast Flux Test Facility (FFTF) Reactor Fuel Criticality Calculations
Fast Flux Test Facility (FFTF) Reactor Fuel Criticality Calculations
The purpose of these calculations is to characterize the criticality safety concerns for the storage of Fast Flux Test Facility (FFTF) nuclear fuel in a Department of Energy spent nuclear fuel (DOE SNF) canister in a co-disposal waste package. These results will be used to support the analysis that will be done to demonstrate concept viability related to use in the Monitored Geologic Repository (MGR) environment.
FEDERAL COMMITMENTS REGARDING USED FUEL AND HIGH-LEVEL WASTES
FEDERAL COMMITMENTS REGARDING USED FUEL AND HIGH-LEVEL WASTES
slides - Canister Confinement Integrity, Integrated Plan for Addressing Potential Chloride-Induced Stress Corrosion Cracking of Austenitic Stainless Steel Dry Cask Storage System Canisters
slides - Canister Confinement Integrity, Integrated Plan for Addressing Potential Chloride-Induced Stress Corrosion Cracking of Austenitic Stainless Steel Dry Cask Storage System Canisters
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
Waste Acceptance System Requirements Document, Revision 5, ICN 01
Waste Acceptance System Requirements Document, Revision 5, ICN 01
The purpose of this document is to establish waste acceptance technical requirements for the U.S. Department of Energy’s (DOE) Civilian Radioactive Waste Management System (CRWMS). These requirements and functions consist of two types: (a) internal CRWMS requirements derived from the Civilian Radioactive Waste Management System Requirements Document (CRD) (DOE 2007a) as illustrated in Figure 1, and (b) acceptance criteria imposed by the CRWMS on spent nuclear fuel (SNF) and high-level waste (HLW) delivered into the CRWMS.
Report on Radioactive Waste Ownership and Management of Long-Term Liabilities in EDRAM Member Countries
Report on Radioactive Waste Ownership and Management of Long-Term Liabilities in EDRAM Member Countries
This report has been prepared by an ad-hoc Working Group (WG) formed by ANDRA (France), NUMO (Japan), NAGRA (Switzerland) and ENRESA (Spain) in May 2003, after the EDRAM meeting held in Valencia to study the situation in the different EDRAM member countries regarding the treatment of radioactive waste ownership and management of long-term liabilities.
Program of Research and Development for Management and Disposal of Commercially Generated Radioactive Wastes: Record of Decision
Program of Research and Development for Management and Disposal of Commercially Generated Radioactive Wastes: Record of Decision
This Record of Decision has been prepared pursuant to the Regulations of
the council on Environmental Quality, 40 CFR Part 1805, on the selection of a
strategy for the disposal of commercially-generated radioactive wastes and the
supporting program of research and development.
The United States Department of Energy has decided to (1) adopt a strategy to
develop mined geologic repositories for disposal of commercially-generated
high-level and transuranic radioactive wastes (while continuing to examine
Republic of Hungary National Report, Second Report, prepared in the Framework on the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management
Republic of Hungary National Report, Second Report, prepared in the Framework on the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management
The Republic of Hungary was among the first to sign the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management (hereafter Convention), established under the auspices of the International Atomic Energy Agency, on 29 September 1997, and ratified it on 2 June 1998. The Convention was promulgated in Act LXXVI of 2001. In order to fulfill the obligations of Article 32 of the Convention the present National Report has been prepared and submitted.
Republic of Hungary National Report, Document prepared in the Framework on the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, First Report
Republic of Hungary National Report, Document prepared in the Framework on the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, First Report
The Republic of Hungary was among the first to sign the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management (hereafter Convention), established under the auspices of the International Atomic Energy Agency, on 29th September 1997, and ratified it on 2nd June 1998. The Convention was promulgated in Act LXXVI of 2001. In order to fulfil the obligations of Article 32 of the Convention the present National Report has been prepared and submitted.
Experience Gained From Programs to Manage High-Level Radioactive Waste and Spent Nuclear Fuel in the United States and Other Countries, A Report to Congress and the Secretary of Energy
Experience Gained From Programs to Manage High-Level Radioactive Waste and Spent Nuclear Fuel in the United States and Other Countries, A Report to Congress and the Secretary of Energy
This report explores how 13 nations are carrying out efforts to find a permanent solution for isolating and containing high-level radioactive waste (HLW) and spent nuclear fuel (SNF) generated within their borders Many forces shape how those efforts are designed and implemented Some of the forces are technical, including choices made about what reactor technology to adopt and about what nuclear fuel cycle to pursue.
UK Government and Devolved Administration Response to the Committee on Radioactive Waste Management (CoRWM) Report on 'Interim Storage of Higher Activity Wastes and the Management of Spent Fuels, Plutonium and Uranium'
UK Government and Devolved Administration Response to the Committee on Radioactive Waste Management (CoRWM) Report on 'Interim Storage of Higher Activity Wastes and the Management of Spent Fuels, Plutonium and Uranium'
The UK Government and the devolved administrations_ (for Scotland, Wales and Northern Ireland, from here on referred to as "The Government") statement of October 2006 made clear there will be strong independent scrutiny of the proposals, plans and programmes to deliver geological disposal of higher activity radioactive waste.
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
Moving Forward Together: Process for Selecting a Site for Canada’s Deep Geological Repository for Used Nuclear Fuel
Moving Forward Together: Process for Selecting a Site for Canada’s Deep Geological Repository for Used Nuclear Fuel
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
Geological Problems in Radioactive Waste Isolation Second Worldwide Review Part 1 Ch 1 - 9
Geological Problems in Radioactive Waste Isolation Second Worldwide Review Part 1 Ch 1 - 9
The first world wide review of the geological problems in radioactive waste isolation was published by Lawrence Berkeley National Laboratory in 1991. This review was a compilation of reports that had been submitted to a workshop held in conjunction with the 28th International Geological Congress that took place July 9-19,1989 in Washington, D.C.
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.
Republic of Hungary National Report, Third Report, prepared in the Framework on the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management
Republic of Hungary National Report, Third Report, prepared in the Framework on the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management
The Republic of Hungary was among the first to sign the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management (hereafter Convention), established under the auspices of the International Atomic Energy Agency, on 29 September 1997, and ratified it on 2 June 1998. The Convention was promulgated by Act LXXVI of 2001 [I.11].
Republic of Hungary National Report, Fourth Report, prepared within the Framework on the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management
Republic of Hungary National Report, Fourth Report, prepared within the Framework on the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management
The Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management (hereafter Convention) was promulgated by Act LXXVI of 2001 [I.11]. (Hereafter the references to legal instruments listed in Annex 4 are used by numbering in brackets.) In order to fulfill the obligations of Article 32 of the Convention the present National Report has been prepared and submitted.
Direct Radiation Dose Consequence Calculation for Category 1 and 2 Event Sequences
Direct Radiation Dose Consequence Calculation for Category 1 and 2 Event Sequences
Performance objectives for the geologic repository operations area through permanent closure in 10 CFR 63.111 identify compliance with regulatory dose limits for workers and members of the public as a design objective. The purpose of this design calculation is to determine direct radiation dose consequences for Category 1 and 2 event sequences. It does not include worker dose assessment for recovery operations following Category 1 event sequences.