• Williamson, M.A. (Argonne National Laboratory) ;
  • Willit, J.L. (Argonne National Laboratory)
  • Received : 2011.07.28
  • Published : 2011.08.31


Two conceptual flowsheets were developed for recycling used nuclear fuel. One flowsheet was developed for recycling used oxide nuclear fuel from light water reactors while the other was developed for recycling used metal fuel from fast spectrum reactors. Both flowsheets were developed from a set of design principles including efficient actinide recovery, nonproliferation, waste minimization and commercial viability. Process chemistry is discussed for each unit operation in the flowsheet.


  1. C.E. Stevenson, "The EBR II Fuel Cycle Story," American Nuclear Society, LaGrange Park, IL USA (1987).
  2. R.K. Steunenberg, R.D. Pierce and L. Burris, "Pyrometallurgical and Pyrochemical Fuel Processing," Progress in Nuclear Energy Series III, Process Chemistry, 461 (1969).
  3. C.E. Till, Y.I. Chang and W.H. Hannum, "The Integral Fast Reactor - An Overview," Progress in Nuclear Energy, 31, 1-2, 3 (1997)
  4. National Research Council, "Electrometallurgical Techniques for DOE Spent Fuel Treatment: Final Report," National Academy Press, Washington, DC (2000).
  5. K. Gourishankar, L. Redey and M.A. Williamson, "Electrochemical Reduction of Metal Oxides in Molten Salts," Light Metals 2002, TMS, 1075 (2002).
  6. L.A. Barnes and M.A. Williamson, "Developments in Electrolytic Reduction: Effect of Rare Earth Oxides," 2008 International Pyroprocessing Research Conference, Jeju Island, Republic of Korea, August 2008.
  7. A.F. LaPlace, J. Lacquement, J.L. Willit, R.A. Finch, G.A. Fletcher and M.A. Williamson, "Electrodeposition of Uranium and Transuranics (Pu) on Solid Cathodes," Nuclear Technology, Vol. 163, 366 (2008).

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