DOI QR코드

DOI QR Code

ON THE DEVELOPMENT OF A DISTILLATION PROCESS FOR THE ELECTROMETALLURGICAL TREATMENT OF IRRADIATED SPENT NUCLEAR FUEL

  • 발행 : 2008.04.30

초록

As part of the spent fuel treatment program at the Idaho National Laboratory, a vacuum distillation process is being employed for the recovery of actinide products following an electrorefining process. Separation of the actinide products from a molten salt electrolyte and cadmium is achieved by a batch operation called cathode processing. A cathode processor has been designed and developed to efficiently remove the process chemicals and consolidate the actinide products for further processing. This paper describes the fundamentals of cathode processing, the evolution of the equipment design, the operation and efficiency of the equipment, and recent developments at the cathode processor. In addition, challenges encountered during the processing of irradiated spent nuclear fuel in the cathode processor will be discussed.

키워드

참고문헌

  1. R.W. Benedict and H.F. McFarlane, 'EBR-II Spent Fuel Demonstration Project Status,' Radwaste, 5, 23 (1998)
  2. B.R. Westphal and R.D. Mariani, 'Uranium Processing during the Treatment of Sodium-Bonded Spent Nuclear Fuel,' JOM, 52 (9), 21 (2000)
  3. K.C. Marsden, C. Knight, K.J. Bateman, B.R. Westphal, and R.P. Lind, 'Process and Equipment Qualification of the Ceramic and Metal Waste Forms for Spent Fuel Treatment,' Proc. Global 2005, Tsukuba, Japan, Oct. 9-13, 2005
  4. H.F. McFarlane, K.M. Goff, T.J. Battisti, B.R. Westphal, and R.D. Mariani, 'Options for the Disposition of Uranium Recovered from Electrometallurgical Treatment of Sodium - Bonded Spent Nuclear Fuel,' ANL-NT-109, Argonne National Laboratory (1999)
  5. D. Vaden, B.R. Westphal, S.X. Li, and T.A. Johnson, 'Engineering Scale Liquid Cadmium Cathode Experiments,' Nucl. Tech., 162 (2008)
  6. S.X. Li, T.A. Johnson, B.R. Westphal, K.M. Goff, and R.W. Benedict, 'Electrorefining Experience for Pyrochemical Processing of Spent EBR-II Driver Fuel,' Proc. Global 2005, Tsukuba, Japan, Oct. 9-13, 2005
  7. S.X. Li, D. Vaden, R.W. Benedict, T.A. Johnson, B.R. Westphal, and G.L. Fredrickson, 'Integrated Efficiency Test for Pyrochemical Fuel Cycles,' Proc. Global 2007, Boise, ID, Sept. 9-13, 2007
  8. B.R. Westphal, J.C. Price, D. Vaden, and R.W. Benedict, 'Engineering-Scale Distillation of Cadmium for Actinide Recovery,' J. Alloys Comp., 444, 561 (2007) https://doi.org/10.1016/j.jallcom.2007.02.072
  9. A. Roine, HSC Chemistry 5.0 Thermochemical Database, Outokumpu Research Oy, Finland (2002)
  10. J.F. Lenc, W.E. Miller, G.J. Bernstein, A.L. Chandler, R.C. Paul, and E.F. Johnston, 'Retorting Unit for Recovery of Uranium from Zinc-Magnesium Solutions,' ANL-7503, Argonne National Laboratory (1969)
  11. C.E. Stevenson, The EBR-II Fuel Cycle Story, p. 85, ANS, La Grange Park, IL (1987)
  12. A.R. Brunsvold, P.D. Roach, and B.R. Westphal, 'Design and Development of a Cathode Processor for Electrometallurgical Treatment of Spent Nuclear Fuel,' Proc. of ICONE 8, Baltimore, MD, April 2-6, 2000
  13. B.R. Westphal, D.V. Laug, A.R. Brunsvold, and P.D. Roach, 'Initial Cathode Processing Experiences and Results for the Treatment of Spent Fuel,' Proc. of DOE Spent Nucl. Fuel & Fissile Mtl. Mgt., Reno, NV, June 16-20, 1996
  14. B.R. Westphal, D. Vaden, J.R. Liaw, and J.R. Krsul, 'Initial Results for Uranium Product from EBR-II Spent Fuel Treatment,' Trans. Amer. Nucl. Soc., 76, 74 (1997)
  15. B.R. Westphal, A.R. Brunsvold, P.D. Roach, K.C. Marsden, B.A. Jensen, and D.V. Laug, 'Development of Cathode Processor and Casting Furnace Operating Conditions,' ANL-NT-110, Argonne National Laboratory (1999)
  16. A.R. Brunsvold, J.L. Krazinski, P.D. Roach, and C.W. Grandy, 'Design and Development of Improvements for Increased Performance of the Cathode Processor,' Proc. of ICONE 9, Nice, France, April 8-12, 2001
  17. B.R. Westphal, D.Vaden, T.Q. Hua, J.L. Willit, and D.V. Laug, 'Recent Developments at the Cathode Processor for Spent Fuel Treatment,' Proc. of DOE Spent Nucl. Fuel & Fissile Mtl. Mgt., Charleston, SC, Sept. 17-20, 2002
  18. B.R. Westphal, J.R. Krsul, and D.W. Maddison, 'Molten Salt Separation from Uranium During the Processing of Spent Nuclear Fuel,' Proc. Light Metals 2002, Seattle, WA, Feb. 17-21, 2002
  19. E. Stumpp, 'The Intercalation of Metal Chlorides and Bromides into Graphite,' Mtl. Science Eng., 31, 53 (1977) https://doi.org/10.1016/0025-5416(77)90011-8
  20. H.J. Emeleus and A.G. Sharpe, Advances in Inorganic Chemistry and Radiochemistry, V. 23, p. 300, Academic Press Inc., New York (1980)
  21. C.W. Solbrig, B.R. Westphal, and R.W. Benedict, 'Thermal Performance of the Cathode Processor: Determination of the Most Important Parameter,' ANL-NT-174, Argonne National Laboratory (2001)
  22. B.R. Westphal, D. Vaden, L.W. Scott, S.R. Sherman, T.Q. Hua, and J.R. Krsul, 'Investigation of Plutonium in Uranium Products during Spent Fuel Treatment,' Plutonium Futures- The Science, Albuquerque, NM, July 6-10, 2003
  23. D.E. McKenzie, W.L. Elsdon, and J.W. Fletcher, 'The Extraction of Plutonium from Neutron-Irradiated Uranium by Uranium Trichloride and by Magnesium Chloride,' Can. J. Chem., 36, 1233 (1958) https://doi.org/10.1139/v58-180
  24. N.R. Chellew and R.K. Steunenberg, 'Extraction of Plutonium from Uranium-Plutonium Alloy with Uranium Trichloride,' Nucl. Appl., 3, 142 (1967) https://doi.org/10.13182/NT67-A27868
  25. S.M. McDeavitt and G.W. Billings, 'The Development of Stable Ceramic Materials for the Containment of Molten Zirconium and Uranium Alloys,' Proc. TMS-Reactive Metals, San Antonio, TX, Feb. 15-19, 1998
  26. G.W. Billings, 'Refractory Crucibles and Molds for Containing Reactive Molten Metals and Salts,' U.S. Patent 6604941, 2003

피인용 문헌

  1. Development of a Ceramic-Lined Crucible for the Separation of Salt from Uranium vol.40, pp.12, 2009, https://doi.org/10.1007/s11661-009-9957-3
  2. Investigation of the evaporation of rare earth chlorides in a LiCl–KCl molten salt vol.287, pp.2, 2011, https://doi.org/10.1007/s10967-010-0807-y
  3. Development of Treatment Process for Anode Residue from Molten Salt Electrorefining of Spent Metallic Fast Reactor Fuel vol.181, pp.3, 2013, https://doi.org/10.13182/NT13-A15807
  4. Development of continuous ingot casting process for uranium dendrites in pyroprocess vol.295, pp.3, 2013, https://doi.org/10.1007/s10967-012-2093-3
  5. Effects of compression molding on meltability of uranium dendrites for ingot consolidation in a pyroprocess vol.300, pp.3, 2014, https://doi.org/10.1007/s10967-014-3012-6
  6. Stability of plasma-sprayed TiN and ZrN coatings on graphite for application to uranium-melting crucibles for pyroprocessing vol.310, pp.3, 2016, https://doi.org/10.1007/s10967-016-4947-6
  7. Evaluation of nanocrystalline hafnium nitride coating exposed to molten uranium pp.1743-2944, 2017, https://doi.org/10.1080/02670844.2017.1371457
  8. Composition and Pressure Estimation on Salt Distillation Process after Electrorefining for Spent Nuclear Fuel vol.807-809, pp.1662-8985, 2013, https://doi.org/10.4028/www.scientific.net/AMR.807-809.1277
  9. Uranium recovery with zinc distillation from a liquid zinc cathode for pyroprocessing vol.316, pp.2, 2018, https://doi.org/10.1007/s10967-018-5789-1