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An International Spent Nuclear Fuel Storage Facility -- Exploring a Russian Site as a Prototype: Proceedings of an International Workshop (2005)
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. "Opening Remarks." An International Spent Nuclear Fuel Storage Facility -- Exploring a Russian Site as a Prototype: Proceedings of an International Workshop. Washington, DC: The National Academies Press, 2005.

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An International Spent Nuclear Fuel Storage Facility: Exploring a Russian Site as a Prototype - Proceedings of an International Workshop

to start the process by collecting these materials in centralized, secure locations so that the risk they might pose to society can be minimized while ultimate solutions are developed, debated, and then implemented.

Our challenge for the next two days is to discuss the issues that must be resolved before we can be assured that the nuclear material now in temporary storage in many locations throughout the world has been placed in safe and secure storage. This is especially important for the smaller temporary sites where the cost per fuel unit of waste to ensure safety is very high because of the relatively small amounts of material involved. A centralized storage facility is certainly an attractive option for such material and that really is the focus of our workshop. We have invited speakers to cover the technical, policy, and legal issues of such a centralized facility. This is to be a workshop to illuminate the issues. No attempt will be made to resolve the issues, nor will an attempt be made to obtain a consensus. Our objective is to define what needs to be done as the next step in moving toward a solution—and identifying what might be some of the options for doing so. We will be successful if in the end we have provided elements and options for a solution that can be used by the decision makers in resolving the problem.

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Front Matter (R1-R12)
Opening Remarks (1-2)
Handling Spent Nuclear Fuel—International Experience -- IAEA Activities in Nuclear Spent Fuel Management (3-11)
Analysis of U.S. Experience with Spent Fuel (12-19)
Problems of Spent Nuclear Fuel Management and Storage Site Selection (20-29)
Feasibility of Transmutation of Radioactive Elements (30-49)
The High Level Waste Disposal Technology Development Program in Korea (50-58)
The Use of Sodium-Cooled Fast Reactors for Effectively Reprocessing Plutonium and Minor Actinides (59-72)
Site Selection for Spent Fuel Storage and Disposal of High Level Waste -- Site Selection for Spent Fuel Storage and Disposal of High Level Waste: Experience of European Countries (73-88)
The Private Fuel Limited Liability Company National Spent Fuel Site (89-95)
Experience of Japan (96-108)
The Current Status of Spent Nuclear Fuel in Korea (109-117)
Safe Transport of Spent Nuclear Fuel and High Level Waste: International Experience (118-127)
Ensuring Nuclear and Radiation Safety During the Transport of Radioactive Materials in Russia (128-142)
Problems in Establishing an International Repository for Spent Nuclear Fuel in Russia -- Creating an Infrastructure for Managing of Spent Nuclear Fuel (143-151)
Current Status of Government Regulation of Activities Associated with the Import of Spent Nuclear Fuel into the Russian Federation Return to the Russian Federation of Irradiated Fuel Assemblies from the Institute of Nuclear Physics of the Republic of Uzbekistan (152-158)
Return to the Russian Federation of Irradiated Fuel Assemblies from the Institute of Nuclear Physics of the Republic of Uzbekistan (159-162)
Investment and International Aspects of the Problem of Spent Nuclear Fuel Management (163-165)
Creation of an Underground Repository for Spent Nuclear Fuel near the City of Zheleznogorsk (Eastern Siberia) (166-176)
Conditions for the Creation of an International Spent Nuclear Fuel Repository near the Priargunsk Mining-Chemical Production Association (City of Krasnokamensk, Chita Oblast) (177-186)
Utilization of High-Level Waste -- Types of High-Level Radioactive Wastes Formed as a Result of Dry Methods of Spent Fuel Regeneration and Technologies for their Management (187-198)
Chemical Treatment of High Level Waste for Utilization (199-207)
Immobilization of High Level Waste: Analysis of Appropriate Synthetic Waste Forms (208-224)
The Management of High-Level Radioactive Wastes from the Mayak Production Association and Plans for the Creation of an Underground Laboratory (225-239)
Creation of Underground Laboratories at the Mining-Chemical Complex and at Mayak to Study the Suitability of Sites for Underground Isolation of Radioactive Wastes (240-247)
Concluding Observations--Milton Levenson (248-250)
Appendix A: Workshop Agenda (251-256)
Appendix B: Environmental Effects of Radiation in the Russian Federation (257-259)
Appendix C: Geochemistry of Actinides During the Long-Term Storage and Disposal of Spent Nuclear Fuel (260-290)