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The Properties of Zeolite A in Molten LiCl Waste

[+] Author Affiliations
J. G. Kim, J. H. Lee, G. I. Park, S. H. Lee, J. H. Kim

Korea Atomic Energy Research Institute, Daejeon, South Korea

Paper No. ICEM2003-4720, pp. 1327-1331; 5 pages
  • ASME 2003 9th International Conference on Radioactive Waste Management and Environmental Remediation
  • 9th ASME International Conference on Radioactive Waste Management and Environmental Remediation: Volumes 1, 2, and 3
  • Oxford, England, September 21–25, 2003
  • Conference Sponsors: Nuclear Engineering Division and Environmental Engineering Division
  • ISBN: 0-7918-3732-7 | eISBN: 0-7918-3731-9
  • Copyright © 2003 by ASME


An advanced spent fuel management process based on the Li reduction of oxide spent fuel to a metallic form, under development at Korea Atomic Energy Research Institute (KAERI), will generate a LiCl waste. To develop an immobilization process of the LiCl waste salt using zeolite A, the behavior of zeolite A in molten LiCl salt with CsCl and SrCl2 has been investigated at 923 K. All the types of zeolite A’s have been transformed into zeolite Li-A after contact with molten LiCl salt. The sodalite phase has also been formed for the high LiCl/zeolite ratio, and this sodalite formation has been enhanced by an addition of CsCl or SrCl2 . These results seem to be caused by the high temperature and Li concentration during the occlusion step. Ion-exchange properties of Cs and Sr at 923 K were very similar to those of the LiCl-KCl eutectic salt at 725 K: an uptake of Cs reached an equilibrium state very rapidly and kept constant, while that of Sr reached a maximum and decreased slightly.

Copyright © 2003 by ASME



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