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.
- Nuclear Engineering Division and Environmental Engineering Division
The Properties of Zeolite A in Molten LiCl Waste
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Kim, JG, Lee, JH, Park, GI, Lee, SH, & Kim, JH. "The Properties of Zeolite A in Molten LiCl Waste." Proceedings of the 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. pp. 1327-1331. ASME. https://doi.org/10.1115/ICEM2003-4720
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