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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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. "Immobilization of High Level Waste: Analysis of Appropriate Synthetic Waste Forms." 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

The highest actinide concentrations are characteristic of ferrites, while the lowest are observed in silicon- and aluminum-containing garnets.

Based on data that has been collected it has been concluded that it is possible to use pyrochlore matrices to incorporate the actinide and actinide-zirconium-rare earth fractions of high-level radioactive wastes. A phase with a garnet structure represents a more universal matrix. This material may be used for immobilizing both actinide and actinide-zirconium-rare earth fractions and actinide wastes with a more complex composition containing high levels of corrosion products (Al, Ga, Fe, Cr, Ni, Mn, Co). A biphase garnet-spinel association is a promising matrix for such wastes. Research on the radiation resistance and chemical stability of samples of garnet matrices under the influence of heated waters is a top priority for further study.

ACKNOWLEDGMENTS

The author is grateful to A. G. Ptashkin (Radon Research and Production Association, Moscow) and M. I. Lapina, A. V. Mokhov, and A. V. Sivtsov (IGEM) for their help in synthesizing and studying samples. This research was carried out with the partial financial support of the U.S. Department of Energy (project RC0-20002-SC14).

NOTES

1.  

R. H. Flowers, L. E. J. Roberts, and B. J. Tymons. Characteristics and quantities of radioactive wastes. Philosophical Transactions of the Royal Society A319(1986):5–16.

2.  

A. E. Ringwood. Disposal of high-level nuclear wastes: a geological perspective. (Hallimond Lecture 1983). Mineralogical Magazine 49(1985):159–176.

3.  

W. Lutze and R. Ewing, eds. Radioactive Waste Forms for the Future. New York: Elsevier Science Publishers, 1988.

4.  

L. L. Hench, D. E. Clark, and J. Campbell. High-level waste immobilization forms. Nuclear and Chemical Waste Management 5(1984):149–173.

5.  

A. A. Vashman, A. S. Polyakov, eds. Phosphate glasses with radioactive wastes. Moscow: Central Scientific Research Institute of Atomic Information, 1997.

6.  

H. Matzke and J. van Geel. Incorporation of Pu and other actinides in borosilicate glass and in waste ceramics. In Disposal of Weapon Plutonium, eds. E. R. Merz and C. E. Walter. Dordrecht: Kluwer, 1996 pp. 93–105. See also N. P. Laverov, B. I. Omelyanenko, S. V. Yudintsev, B. I. Nikonov, I. A. Sobolev, and S. V. Stefanovsky. Mineralogy and geochemistry of immobilization matrices for high-level radioactive wastes. Geology of Ore Deposits 39(3)(1997):211–228.

7.  

National Research Council. Glass as a Waste Form and Vitrification Tool: Summary of an International Workshop. Washington, D.C.: National Academy Press, 1996.

8.  

Nuclear Energy Agency. Actinide and fission product partitioning and transmutation: status and assessment report. Proceedings of the V International Information Exchange Meeting. Paris: Nuclear Energy Agency (EUR 18898 EN), 1999.

9.  

G. S. Sombret. Waste forms for conditioning high-level radioactive solutions. In The Geological Disposal of High Level Radioactive Wastes, ed. D. G. Brookins. Athens: Theophrastus Publishers, 1987, pp. 69–160.

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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)