National Academy of Sciences | 150 Year Anniversary

Questions? Call 800-624-6242

| Items in cart [0]

The National Academies Press

PAPERBACK
price:$62.00
add to cart

Rights & Permissions

topleft topright

An International Spent Nuclear Fuel Storage Facility -- Exploring a Russian Site as a Prototype: Proceedings of an International Workshop (2005)
Development, Security, and Cooperation (DSC)

Citation Manager

. "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.

Please select a format:

BibTeX EndNote RefMan


Page
224
bottomleft bottomright

The following HTML text is provided to enhance online readability. Many aspects of typography translate only awkwardly to HTML. Please use the page image as the authoritative form to ensure accuracy.


An International Spent Nuclear Fuel Storage Facility: Exploring a Russian Site as a Prototype - Proceedings of an International Workshop

26.  

G. Menzer. Die kristallstruktur der granate. Zeitschrift für Kristallographie 69(1928): 300–396. See also S. Geller. Crystal chemistry of the garnets. Zeitschrift für Kristallographie. 125(1967):1–47.

27.  

Geller, op. cit. See also B. V. Mill and G. Ronniger. Unusual coordination numbers for ions in the structure of garnet. Crystallography 18(1)(1973):126–132.

28.  

G. A. Novak and G. V. Gibbs. The crystal chemistry of the silicate garnets. American Mineralogist 56(5–6)(1971):791–825.

29.  

H. Nishizawa and M. Koizumi. Synthesis and infrared spectra of Ca3Mn2Si3O12 and Cd3B2 Si3O12 (B: Al, Ga, Cr, V, Fe, Mn) garnets. American Mineralogist 60(1–2)(1975):84–87. See also B. A. Fursenko. Synthesis of new chromium-containing garnets under high temperatures. Reports of the USSR Academy of Sciences 250(4)(1980):945–949.

30.  

A. L. Gentile and R. Roy. Isomorphism and crystalline solubility in the garnet family. American Mineralogist 45(5–6)(1960):701–711.

31.  

S. Geller and C. E. Miller. Silicate garnet—yttrium-iron garnet solid solution. American Mineralogist 44(11–12)(1959):1115–1120.

32.  

N. A. Toropov, V. L. Barzakovsky, V. V. Lapin, and N. N. Kurtseva. Diagrams of the status of silicate systems. In Dual Systems (1st ed.). Leningrad: Nauka Publishers, 1969.

33.  

J. Ito and C. Frondel.Synthesis of zirconium and titanium garnets. American Mineralogist 52(5–6)(1967):773–781.

34.  

V. I. Vlasov, O. L. Kedrovsky, A. S. Nikiforov, et al. Management of liquid radioactive wastes under the closed nuclear fuel cycle concept. Vienna: IAEA, 1987, M-294/3, pp. 109–116.

35.  

T. V. Smelova, N. V. Krylova, S. V. Yudintsev, and B. S. Nikonov. A silicate matrix for actinides. Reports of the Russian Academy of Sciences 374(2)(2000):242–246.

36.  

B. E. Burakov, Ye. B. Anderson, M. V. Zamoryanskaya, and M. A. Petrova. Synthesis and study of 239Pu-doped gadolinium-aluminum garnet. Proceedings of the Symposium on the Scientific Basis of Nuclear Waste Management XXIII 608(2000):419–422.

37.  

Burakov et al., op. cit.

38.  

S. V. Yudintsev, M. I. Lapina, A. G. Ptashkin, T. S. Iodintseva, S. Utsunomiya, L. M. Wang, and R. C. Ewing. Uranium accommodation into garnet host (Isomprphic capacity and radiation stability of the garnet structured actinide host). Proceedings of the Material Research Society Symposium 713(2002):JJ11.28.1–4.

39.  

Ito and Frondel, op. cit.

Page
224
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)