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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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. "The Use of Sodium-Cooled Fast Reactors for Effectively Reprocessing Plutonium and Minor Actinides." 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

power operations creates a significant environmental threat. Minor actinides may be reprocessed as a side function in fast oxide-fueled reactors. However, this method is not sufficiently effective. A more efficient method involves burning minor actinides in specialized cores using fuel that does not contain uranium-238. Including fast reactors with such cores in the nuclear power industry’s closed fuel cycle would make it possible to stabilize the accumulation of minor actinides. In such a system all actinides produced by the industry are also recycled by it, and only the portion of these materials that cannot be separated out through chemical reprocessing must be stored as wastes. Organizing such a system, however, requires major capital investments for the creation of a large number of external fuel cycle enterprises. Therefore, the burning of plutonium and minor actinides in the open fuel cycle is of interest.

This report considers various means of using sodium-cooled fast reactors for reprocessing plutonium and minor actinides produced in nuclear power industry operations.

THE CONCEPT OF FAST REACTORS AS ACTINIDE BURNERS

In analyzing the possible use of BN-type fast reactors1 to recycle wastes from the nuclear power industry, let us highlight two problems: reprocessing of plutonium and reprocessing of minor actinides.

Efficient recycling (burning) of plutonium can be carried out in mixed-oxide-fueled fast reactors with reduced internal breeding due to increased fuel enrichment, but the use of mixed oxide (MOX) fuel for these purposes is not the best option. From the standpoint of secondary plutonium output, it would make sense to consider fuel compositions without uranium-238, as this isotope is the source that produces both plutonium and other very environmentally harmful actinides. Fuel without uranium-238, with this isotope being replaced by some inert matrix, is of great interest in this regard. A number of technological laboratories in Russia, France, and Japan have been working recently to develop such a fuel. For example, a power reactor (fast or thermal) could burn approximately 750–850 kg/GW (el) of plutonium per year without producing any secondary plutonium. Burning plutonium in reactors using fuel without uranium-238 is much more efficient in comparison with using MOX fuel.

Another important problem involves the reprocessing of minor actinides. Plutonium may be used as an efficient fuel in thermal and fast reactors for electricity production purposes. Minor actinides cannot be used in thermal reactors for these purposes, and their continual accumulation as a result of nuclear power industry operations creates a significant environmental threat. Let us note once again that plutonium from spent fuel from thermal reactors contains about 7 percent minor actinides, an amount that increases over time as a result of the decay of plutonium-241 (T1/2 = 14.7 years) and its transformation into americium-

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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)