Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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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)
  • Received : 2011.08.14
  • Published : 2011.08.31
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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

References

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