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Understanding the Choices The Future Management of Canada’s Used Nuclear Fuel
Understanding the Choices The Future Management of Canada’s Used Nuclear Fuel
Understanding the Choices is the NWMO’s second discussion document, an important milestone in a three-year study (2002-2005) designed to recommend to the Government of Canada an approach to managing Canada’s used nuclear fuel for the long term. The report begins with an examination of the values and priorities of Canadians, and how the NWMO has used this understanding to build a framework to assess and compare management approaches.
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.
Public Values and Stakeholder Involvement - A New Framework for Performance Assessment
Public Values and Stakeholder Involvement - A New Framework for Performance Assessment
The objective of the RISCOM II project is to share the knowledge of the context of radioactive waste management in various European countries and to see to what extent it is possible to apply more widely the RISCOM Model (Andersson et al., 1998) in order to improve the acceptability of radioactive waste management. Thus, the project aims to promote the development of processes involving transparency, as well as means involving greater participation of the public.
Review of initiatives addressing socio-technical challenges of RWM & geological disposal in international programmes
Review of initiatives addressing socio-technical challenges of RWM & geological disposal in international programmes
Reflecting on the Implementing Geological Disposal Technology Platform as a knowledge network and potential scenarios for stakeholder involvement
Reflecting on the Implementing Geological Disposal Technology Platform as a knowledge network and potential scenarios for stakeholder involvement
This report was prepared in the context of Work Package 3 of the InSOTEC project. The overall objective of this work package (WP) is to take a closer look at arenas where socio-technical combinations on radioactive waste management (RWM) are formed. The attempt is to illustrate the interconnections between the sources of different types of information and knowledge development with the various stakeholders having access to that information.
Slides - Lessons Learned from US Nuclear Waste Repository Programs
Slides - Lessons Learned from US Nuclear Waste Repository Programs
Presented to the Blue Ribbon Commission on America's Nuclear Future Subcommittee on Disposal
Second Review Meeting, Joint Convention on the Safety of Spent Fuel Management on the Safety of Radioactive Waste Management, Answers to the Questions of Contracting Parties on the National Report submitted by Luxembourg
Second Review Meeting, Joint Convention on the Safety of Spent Fuel Management on the Safety of Radioactive Waste Management, Answers to the Questions of Contracting Parties on the National Report submitted by Luxembourg
Second Review Meeting, Joint Convention on the Safety of Spent Fuel Management on the Safety of Radioactive Waste Management, Answers to the Questions of Contracting Parties on the National Report submitted by Luxembourg
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 First 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 First 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 First National Report
CHARACTERIZATION OF CRYSTALLINE ROCKS IN THE LAKE SUPERIOR REGION, USA: IMPLICATIONS FOR NUCLEAR WASTE ISOLATION
CHARACTERIZATION OF CRYSTALLINE ROCKS IN THE LAKE SUPERIOR REGION, USA: IMPLICATIONS FOR NUCLEAR WASTE ISOLATION
The Lake Superior region (Wisconsin, the Upper Peninsula of Michigan, and Minnesota) contains 41 Precambrian crystalline (medium- to coarse-grained igneous and high-grade mstamorphic) rock complexes comprising 64 individual but related rock bodies with known surface exposures. Each complex has a map area greater than 78 km2. About 54% of the rock complexes have areas of up to 500 km2, 15% fall between 500 km2 and 1000 km2, 19% lie between 1000 km2 and 2500 km2, and 12% are over 2500 km2. Crystalline rocks of the region vary widely in composition, but they are predominantly granitic.
Options for Developing Public and Stakeholder Engagement for the Storage and Management of Spent Nuclear Fuel (SNF) and High Level Waste (HLW) in the United States
Options for Developing Public and Stakeholder Engagement for the Storage and Management of Spent Nuclear Fuel (SNF) and High Level Waste (HLW) in the United States
This report puts forth a number of options and recommendations for how to engage stakeholders and other members of the public in the storage and management of spent nuclear fuel and high level waste in the United States. The options are generated from a scientific review of existing publications proposing criteria for assessing past efforts to engage publics and stakeholders in decision-making about risky technologies.
Geological Problems in Radioactive Waste Isolation Second Worldwide Review Part 2 Ch 10 - 17
Geological Problems in Radioactive Waste Isolation Second Worldwide Review Part 2 Ch 10 - 17
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.
Disposal and Storage of Spent Nuclear Fuel--Finding the Right Balance, A report to Congress and the Secretary of Energy
Disposal and Storage of Spent Nuclear Fuel--Finding the Right Balance, A report to Congress and the Secretary of Energy
The Nuclear Waste Policy Act of 1982, as amended, established a statutory basis<br/>for managing the nation’s civilian (or commercially produced) spent nuclear<br/>fuel. The law established a process for siting, developing, licensing, and constructing<br/>an underground repository for the permanent disposal of that waste.<br/>Utilities were given the primary responsibility for storing spent fuel until it is<br/>accepted by the federal government for disposal at a repository, which originally<br/>was expected to begin operating in 1998.
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.
Geological Problems in Radioactive Waste Isolation Second Worldwide Review Part 3 Ch 18 -27
Geological Problems in Radioactive Waste Isolation Second Worldwide Review Part 3 Ch 18 -27
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.
The U.S. Environmental Protection Agency’s Public Health and Safety Standards for Yucca Mountain, Nevada (40 CFR Part 197) - 9072
The U.S. Environmental Protection Agency’s Public Health and Safety Standards for Yucca Mountain, Nevada (40 CFR Part 197) - 9072
In 2001, as directed by the Energy Policy Act of 1992, the U.S. Environmental Protection Agency (EPA) issued public health and environmental radiation protection standards for the proposed repository at Yucca Mountain, Nevada. Several parties sued the Agency on a myriad of aspects of the rule. The Court ruled in EPA’s favor in all aspects of the case but one, and returned the standards to the Agency in 2004. In 2005, EPA proposed amendments to the standards. Following public hearings and a public review period, the final amendments were issued in September 2008.
Exploration of Crystalline Rocks for Nuclear Waste Repositories: Some Strategies for Area Characterization - UNITED STATES DEPARTMENT OF INTERIOR GEOLOGICAL SURVEY
Exploration of Crystalline Rocks for Nuclear Waste Repositories: Some Strategies for Area Characterization - UNITED STATES DEPARTMENT OF INTERIOR GEOLOGICAL SURVEY
A general strategy for the exploration of crystalline rock masses in the<br/>eastern United States for the identification of potential sites for high-level<br/>radioactive waste repositories has been generated by consideration of the<br/>Department of Energy (DOE) Siting Guidelines, available information on these<br/>crystalline rocks, and the capabilities and limitations of various exploration<br/>methods.
Review of MRWS White paper
Review of MRWS White paper
This paper is a first consideration of the MRWS White Paper on the framework for geological disposal. It is based primarily on discussions in Working Group D on July 21 2008 but also draws on CoRWM’s informal comments on the draft White Paper, on CoRWM’s recommendations as reported in 2006 and on an overview of the responses to the consultation that preceded the White Paper. There have been few opportunities, as yet, to discuss the White Paper through the CoRWM PSE process.
Articles of the Planning Act N¡. 2006-739 of 28 June 2006 Concerning the Sustainable Management of Radioactive Materials and Waste modifying the Environmental Code.
Articles of the Planning Act N¡. 2006-739 of 28 June 2006 Concerning the Sustainable Management of Radioactive Materials and Waste modifying the Environmental Code.
Frances Planning Act for Radioactive Materials and Waste
Final 40 CFR 19: Environmental Radiation Protection Standards for Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes
Final 40 CFR 19: Environmental Radiation Protection Standards for Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes
Final 40 CFR 40 Ruling on Environmental Radiation Protection Standards for Management and Disposal of Spent Nuclear Fuel , High-Level and Transuranic Radioactive Wastes
History of Repository Regulations
History of Repository Regulations
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