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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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. "Return to the Russian Federation of Irradiated Fuel Assemblies from the Institute of Nuclear Physics of the Republic of Uzbekistan." 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

disposal of research SNF from 41 states in facilities of U.S. design in the United States.

The program’s major goal is the reduction of HEU quantities contained in SNF assemblies at research reactor sites, as well as advocating that the reactors be converted to use low-enriched fuel. From the U.S. perspective the issue of nuclear proliferation risk reduction in the area of research reactor fuel cannot be resolved completely without the involvement of Russia, the second largest world supplier of corresponding facilities, technologies, and fuel.

In 1999 Techsnabexport (a company authorized by the government of the Russian Federation to conduct foreign deals related to the management of spent nuclear fuel from foreign nuclear reactors) began several rounds of negotiations with the operators of foreign research reactors. Preliminary consultations have revealed a keen interest by a number of foreign states to begin regular shipments of their spent research nuclear fuel to Russia. However, in view of the limited budgets (or in some cases, the complete lack of funds) of the research reactor operators to finance SNF operations, large-scale fuel shipments hardly seem possible without the assistance of sponsors, such as the IAEA, the United States, EUROATOM, and private funders.

The United States has expressed its readiness to provide financial assistance to countries returning their fuel to Russia, on the condition that the HEU gradually be converted to that with enrichment of less than 20 percent U-235. At the same time, during trilateral meetings among the IAEA, Russia, and the United State, possibilities were discussed for the return of the spent nuclear research fuel to the Russian Federation.

In 2001, as a result of IAEA-Russia-U.S. technical missions to research reactor sites in Uzbekistan, Ukraine, and Yugoslavia, Uzbekistan was selected to be the first state from which the return of the spent fuel assemblies would be executed. The complex political situation in Central Asia and the maximum technical and organizational preparedness for the Uzbekistan export operation were factors in this decision.

SPENT NUCLEAR FUEL FROM THE RESEARCH REACTOR AT THE INSTITUTE OF NUCLEAR PHYSICS OF THE UZBEKISTAN ACADEMY OF SCIENCES

The Uzbekistan Academy of Sciences, Institute of Nuclear Physics was founded in 1956. It is one of the largest scientific institutes in Asia, currently carrying out fundamental and applied research in nuclear and elementary particle physics, solid body physics, radiochemistry, biology, element analysis, and many other areas.

Initially the power of the VVR-SM reactor, which was put into operation in September 1959, was 2 Mwt. In the Soviet era the reactor was used for both

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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)