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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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. "Chemical Treatment of High Level Waste for Utilization." 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

management methods (transmutation and disposal), as well as for the existing practice of high-level waste management. In Russia at the Mayak radiochemical plant, the UE-35 industrial facility, which recovers cesium and strontium from high-level waste, has been in operation since 1996. The next stage is aimed at development and implementation of actinide separation technology from high-level waste. For this purpose the following four processes are being studied and tested: (1) processes based on chlorinated cobalt dicarbollide (ChCoDiC-process); (2) isoamyldialkyl-phosphine oxide (POR-process); (3) diphenyldibutyl-carbamoylphosphine oxide (modified TRUEX-process); and (4) a combination of ChCoDiC, carbamoylphosphine oxide (CMPO), and polyethylene glycol (PEG) (UNEX-process).

ADDITIONAL REFERENCES

Dzekun, E. G., A. S. Scobtsov, et al. Proceedings of Conference in Ozersk (Zav. Lab.) pp. 29–36. [in Russian]


Horowitz, E. P., and W. W. Schulz. 1998. Metal Ion Separation and Preconcentration: Progress and Opportunities, Chapter XX, eds. A. H. Bond, M. L. Dietz, and R. D. Rogers. Cary, N.C.: American Nuclear Society.


Kulyako, Yu. M., D. A. Malikov, T. I. Trofimov, and B. F. Myasoedov. 1996. Behavior of transplutonium and rare earth elements in acidic and alkaline solutions of potassium ferricyanide. Mendeleev Communications 5:173–174.


Myasoedov, B. F., M. K. Chmutova, A. Yu. Shadrin, V. N. Romanovskiy, I. V. Smirnov, V. A. Babain. 1993. Proceedings of the International Conference and Technology Exhibition on Future Nuclear Systems: Emerging Fuel Cycles and Waste Disposal Options, GLOBAL ‘93, September 12–17, 1993, Seattle, Washington 1:581–587.

NOTES

1.  

E. A. Filippov, E. G. Dzekun, A. K. Nardova, I. V. Mamakin, V. M. Gelis, and V. V. Milyutin. Application of crown-ethers and ferrocyanide-based inorganic material for caesium and strontium recovery. Proceedings of the Symposium on Waste Management, Tucson, Arizona, March 1–5, 1992, 2(1992):1021–1025.

2.  

Ibid.

3.  

E. G. Dzekun, A. S. Scobtsov, et al. Proceedings of Conference in Ozersk (Zav. Lab.). 1991. p. 29–36. [in Russian]

4.  

E. P. Horwitz and W. W. Schulz. Metal Ion Separation and Preconcentration: Progress and Opportunities, Chapter XX, eds. A. H. Bond, M. L. Dietz, and R. D. Rogers. Cary, N.C.: American Nuclear Society, 1998.

5.  

V. M. Esimantovskiy, B. Ya. Galkin, E. G. Dzekun, L. N. Lazarev, R. I. Lyubtsev, V. N. Romanovskiy, D. N. Sichikin. Proceedings of the Symposium on Waste Management, Tucson, Arizona, March 1–5, 1992, 1(1992):805–808. See also Horwitz and Schulz, 1998, ibid.

6.  

B. F. Myasoedov and M. K. Chmutova. Proceedings of the Third Japan-Russian Joint Symposium on Analytical Chemistry, Nagoya, Japan. November 5–9, 1986.

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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)