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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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. "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." 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

intended for reprocessing spent fuel from VVER-1000 reactors, had become obsolete and no longer met modern requirements. The only unit of the RT-2 plant that was completed was the spent fuel storage facility, which had a planned capacity of 13,416 fuel assemblies from VVER-1000-type reactors (6000 metric tons of uranium by weight). At this time the facility has been filled to approximately 57 percent of its planned capacity.

In 2002 the above-mentioned enterprises received six special shipments of spent fuel from nuclear power plants in Ukraine and one from Bulgaria (specifically, Mayak received one shipment from the Rovno Nuclear Power Plant, while the Mining-Chemical Complex received one shipment each from the Khmelnitsky, Zaporozhye, and Rovno plants, two from the South Ukrainian Nuclear Power Plant, and one from the Kozloduy Nuclear Power Plant in Bulgaria). Last year Mayak received 27.4 metric tons. The total amount of spent nuclear fuel received by the existing storage facility at the Mining-Chemical Complex is 140 metric tons from the Ukrainian power plants and 41.5 metric tons from the one in Bulgaria. The following shipments are planned in 2003:

  • Mayak: one shipment from the Rovno plant and one from the Kozloduy plant

  • Mining-Chemical Complex: three shipments from the South Ukrainian plant, one from the Khmelnitsky plant, and one from Kozloduy

The way that the spent fuel is transported is important from the security standpoint. In shipping spent fuel from VVER-440 reactors, 16 TK-6 rail containers are used. Designed in 1973–1978, a period characterized by a lack of experience in such operations and of relevant regulatory documents, the TK-6 is a first-generation container. Its design does not make it completely secure. The TUK-6 transport cask used with this container is categorized as type B(M), which must be used with certain restrictions and constant monitoring by operators.

Spent fuel from VVER-1000 reactors has been transported since 1986, using TK-10 and TK-13 rail containers and TUK-10V and TUK-13V transport casks. The TUK-13/1V includes a vessel made of corrosion-resistant steel (container and documentation produced by the Izhorsk Plants Open Joint-Stock Company).

According to the rules of the International Atomic Energy Agency (IAEA), the TUK-13 transport casks are considered to be type B(U), and their design fully ensures the security of the spent fuel transported in them. In shipping spent fuel with this sort of packaging no special organizational or technical measures are required to monitor packaging and environmental parameters or to ensure that these parameters are maintained within permissible limits. The TUK-10V transport cask is analogous in design to the TUK-13; however, its capacity is 50 percent lower (6 spent fuel rods as opposed to 12 with the TUK-13), and its body is made of 20-mark carbon steel, just like the body of the TK-6 container.

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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)