DOI QR코드

DOI QR Code

DEVELOPMENT OF ELECTROREFINER WASTE SALT DISPOSAL PROCESS FOR THE EBR- II SPENT FUEL TREATMENT PROJECT

  • Published : 2008.04.30

Abstract

The results of process development for the blending of waste salt from the electrorefining of spent fuel with zeolite-A are presented. This blending is a key step in the ceramic waste process being used for treatment of EBR-II spent fuel and is accomplished using a high-temperature v-blender. A labscale system was used with non-radioactive surrogate salts to determine optimal particle size distributions and time at temperature. An engineering-scale system was then installed in the Hot Fuel Examination Facility hot cell and used to demonstrate blending of actual electrorefiner salt with zeolite. In those tests, it was shown that the results are still favorable with actinide-loaded salt and that batch size of this v-blender could be increased to a level consistent with efficient production operations for EBR-II spent fuel treatment. One technical challenge that remains for this technology is to mitigate the problem of material retention in the v-blender due to formation of caked patches of salt/zeolite on the inner v-blender walls.

Keywords

References

  1. 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
  2. M.F. Simpson, T.S. Yoo, R.W. Benedict, S. Phongikaroon, S. Frank, P. Sachdev, K. Hartman, 'Strategic Minimization of High Level Waste From Pyroprocessing of Spent Nuclear Fuel;' Proceedings of Global 2007, Boise, September 2007
  3. M.A. Lewis, D.F. Fischer, and C.D. Murphy, 'Densification of Salt-Occluded Zeolite A Powders to a Leach-Resistant Monolith,' Mater. Res. Soc. Symp. Proc. 333: 277 (1994)
  4. J.P. Ackerman, T.R. Johnson, L.S.H. Chow, E.L. Carls, W.H. Hannum, J.J. Laidler, 'Treatment of Wastes in the IFR Fuel Cycle,' Prog. in Nuc. Energy 31, p.141 (1997) https://doi.org/10.1016/0149-1970(96)00008-X
  5. L.J. Simpson and D.J. Wronkiewicz, 'Evaluation of Standard Durability Tests Towards the Qualification Process for the Glass-Zeolite Ceramic Waste Form,' Scientific Basis for Nuclear Waste Management XX, Vol.465, Ed. W.Gray and K. Knecht, p. 441 (1997)
  6. M.F. Simpson, K.M. Goff, S.G. Johnson, K.J. Bateman, T.J. Battisti, K.L. Toews, S.M. Frank, T.L. Moschetti, and T.P. O'Holleran, 'A Description of the Ceramic Waste Form Production Process from the Demonstration Phase of the Electrometallurgical Treatment of EBR-II Spent Fuel,' Nuclear Technology, vol.134, pp. 263-277 (2001) https://doi.org/10.13182/NT01-A3200
  7. M.C. Hash, C. Pereira, V.N. Zyryanov, M.A. Lewis, G.L. Burns, J.J. Smith, J.P. Thalacker, and J.P. Ackerman, 'Preparation Techniques for Ceramic Waste Form Powder,' in Environmental Issues and Waste Management Technologies in the Ceramic and Nuclear Industries III, eds., David K. Peeler and James C. Marra, American Ceramic Society, pp. 399-407 (1998)
  8. M.F. Simpson and T.J. Battisti, 'Adsorption of Eutectic LiCl-KCl into Zeolite 4A using a Mechanically Fluidized Vacuum System,' Industrial and Engineering Chemistry Research, vol. 38, n.6, p.2469 (June 1999) https://doi.org/10.1021/ie980635v
  9. C. Pereira, 'Production of Sodalite Waste Forms by Addition of Glass,' Ceram. Trans. 61: 389-407 (1997)
  10. K. J. Bateman and D.D. Capson, 'A Finite Element Analysis for a Ceramic Waste Form,' Proceedings of IMECE 2003, International Mechanical Engineering Congress and Exposition, Washington, D.C., November 16-21, 2003
  11. S. Priebe and K. Bateman, 'The Ceramic Waste Form Process at the Idaho National Laboratory,' Nuclear Technology, in press, 2008

Cited by

  1. Investigation of Fission Product Transport into Zeolite-A for Pyroprocessing Waste Minimization vol.181, pp.2, 2013, https://doi.org/10.13182/NT13-A15788
  2. Purification of LiCl–KCl eutectic waste salt containing rare earth chlorides delivered from the pyrochemical process of used nuclear fuel using a reactive distillation process vol.307, pp.2, 2016, https://doi.org/10.1007/s10967-015-4231-1
  3. Evaluation of the Electroextractions of Ce and Nd from LiCl-KCl Molten Salt Using Liquid Ga Electrode vol.164, pp.4, 2017, https://doi.org/10.1149/2.0511704jes
  4. at 500°C for Electrorefining Contaminated Zircaloy-4 Cladding vol.161, pp.3, 2014, https://doi.org/10.1149/2.046403jes
  5. Effect of Heat Treatment on Microstructure and Fracture Behavior of STS304-Zr Alloys for Metal Waste Forms vol.28, pp.3, 2018, https://doi.org/10.3740/MRSK.2018.28.3.174