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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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. "Feasibility of Transmutation of Radioactive Elements." 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

for example, since it has been difficult in the United States to keep the transmutation program alive, work on such topics as minor actinide fuel forms has been hampered. At the same time Russia is independently pursuing similar investigations with limited funding.10 There is no better time than now to call for an international summit on separations and transmutation to share the research and development progress in countries actively pursuing this technology, gain a consensus on the important questions to be answered, and establish GIFTS to decide which international collaborations would be most meaningful.

FEASIBILITY OF TRANSMUTATION TECHNOLOGY

Saying that the transmutation of radioactive waste elements is feasible may be too strong a statement at the present time. A better statement would be that it seems plausible, and significantly more work is needed to further down-select competing technologies. The only way to move from plausibility to feasibility is to proceed along the lines of the U.S. AFCI Program through to the completion of Series Two/Phase II. Getting there will not be easy. There are many difficult problems that must be solved, and there is a need for a pooling of world resources through international collaborations. In the meantime there is the need for a close coordination between GIF and a GIFTS-type organization to ensure that GEN-IV and transmutation technologies are compatible by, for example, including a suitable fast reactor for burning the actinides in the fleet of future reactors. More work is needed on separations technologies, such as UREX/UREX+ and the complementary (or possibly superior) pyroprocessing techniques. On the physics front there is a critical need for such data as fast neutron cross-sections for plutonium and the minor actinides for input and checks on reactor simulation codes.

It is clear that if transmutation is to be realized, the effort will take over a decade of hard work. In the United States there is already a shortage of students pursuing nuclear engineering and radiochemistry. Although other countries may not be experiencing the same problem, as the United States produces a large fraction of the world’s researchers in these fields, it becomes a world problem. It is critical that appropriate attention and resources be focused to confront this problem head-on. There are many problems to be solved, but the future still seems bright for the possibility of a full commercial-scale demonstration of nuclear transmutation.

NOTES

1.  

U.S. Department of Energy. A Report to Congress: A Roadmap for Developing Accelerator Transmutation of Waste (ATW) Technology, DOE/RW-0519. Washington, D.C.: U.S. Department of Energy, Office of Civilian Radioactive Waste Management, October 1999.

2.  

There is a dose and groundwater concentration limit for the first 10,000 years.

3.  

B. Richter, D. Hoffman, S. Mtingwa, R. Omberg, and J. Rempe. Report of the Advanced

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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)