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http://dx.doi.org/10.5516/NET.2011.43.4.335

ELECTROCHEMICAL PROCESSING OF USED NUCLEAR FUEL  

Goff, K.M. (Idaho National Laboratory)
Wass, J.C. (Idaho National Laboratory)
Marsden, K.C. (Idaho National Laboratory)
Teske, G.M. (Idaho National Laboratory)
Publication Information
Nuclear Engineering and Technology / v.43, no.4, 2011 , pp. 335-342 More about this Journal
Abstract
As part of the Department of Energy's Fuel Cycle Research and Development Program an electrochemical technology employing molten salts is being developed for recycle of metallic fast reactor fuel and treatment of light water reactor oxide fuel to produce a feed for fast reactors. This technology has been deployed for treatment of used fuel from the Experimental Breeder Reactor II (EBR-II) in the Fuel Conditioning Facility, located at the Materials and Fuel Complex of Idaho National Laboratory. This process is based on dry (non-aqueous) technologies that have been developed and demonstrated since the 1960s. These technologies offer potential advantages compared to traditional aqueous separations including: compactness, resistance to radiation effects, criticality control benefits, compatibility with advanced fuel types, and ability to produce low purity products. This paper will summarize the status of electrochemical development and demonstration activities with used nuclear fuel, including preparation of associated high-level waste forms.
Keywords
Electrochemical; Pyrochemical; Pyroprocess; Electrometallurgical;
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  • Reference
1 U.S. Department of Energy, Office of Arms Control and Nonproliferation, "Nonproliferation Impacts Assessment for the Treatment and Management of Sodium-Bonded Spent Nuclear Fuel" (July 1999).
2 S. X. Li, T. A. Johnson, B. R. Westphal, K. M. Goff, and R. W. Benedict, "Electrorefining Experience for Pyrochemical Reprocessing of Spent EBR-II Fuel," Proceedings of GLOBAL 2005, Tsukuba, Japan, October, (2005).
3 S. X. Li, S. D. Herrmann, K. M. Goff, M. F. Simpson, and R. W. Benedict, "Actinide Recovery Experiments with Bench-Scale Liquid Cadmium Cathode in Real Fission Product-Laden Molten Salt," Nuclear Technology, Vol. 165, No. 2, p. 190 (2009).   DOI
4 D. Vaden, S. X. Li, B. R. Westphal, K. B. Davies, T. A. Johnson, and D. M. Pace, "Engineering Scale Liquid Cadmium Cathode Experiments," Nuclear Technology, Vol. 162, No. 2, pp. 124 (2008).
5 S. D. Hermann, S. X. Li, M. F. Simpson, S. Phongikaroon, "Electrolytic Reduction of Spent Nuclear Oxide Fuel as Part of an Integral Process to Separate and Recover Actinides from Fission Products," Separations Science and Technology, 41: 1965-1983, 2006.   DOI
6 U. S. Department of Energy, Office of Nuclear Energy, Science and Technology, "A Report to Congress on Electrometallurgical Treatment Waste Forms," (March 2001).
7 L. J. Koch, Experimental Breeder Reactor II: An Integrated Experimental Fast Reactor Nuclear Power Station (Argonne, IL: Argonne National Laboratory, 2004).
8 C. E. Stevenson. The EBR-II Fuel Cycle Story (La Grange Park, IL: American Nuclear Society, 1987).
9 National Research Council, "Electrometallurgical Techniques for DOE Spent Fuel Treatment: Final Report," National Academy Press, Washington, DC (2000).
10 U. S. Department of Energy, "Final Environmental Impact Statement for the Treatment and Management of Sodium Bonded Spent Nuclear Fuel," DOE/EIS-0306 (July 2000).
11 "Cost Study of Alternatives Presented in the Draft Environmental Impact Statement for the Treatment and Management of Sodium-bonded Spent Nuclear Fuel" (August 1999).
12 Benedict, Pigford, and Levi. Nuclear Chemical Engineering (New York: McGraw-Hill Book Company, 1981).