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Reuse Technology of LiCl Salt Waste Generated from Electrolytic Reduction Process of Spent Oxide Fuel  

Cho, Yung-Zun (Korea Atomic Energy Research Institute)
Jung, Jin-Seok (Korea Atomic Energy Research Institute)
Lee, Han-Soo (Korea Atomic Energy Research Institute)
Kim, In-Tae (Korea Atomic Energy Research Institute)
Publication Information
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT) / v.8, no.1, 2010 , pp. 57-63 More about this Journal
Abstract
Layer crystallization process was tested for the separation(or concentration) of cesium and strontium fission products in a LiCl waste salt generated from an electrolytic reduction process of a spent oxide fuel. In a crystallization process, impurities (CsCl and $SrCl_2$) are concentrated in a small fraction of the LiCl salt by the solubility difference between the melt phase and the crystal phase. Based on the phase diagram of LiCl-CsCl-$SrCl_2$ system, the separation possibility by using crystallization was determined and the molten salt temperature profile during layer crystallization operation was predicted by using mathematical calculation. In the layer crystallization process, the crystal growth rate strongly affects the crystal structure and therefore the separation efficiency. In the conditions of about 20-25 l/min cooling air flow rate and less than 0.2g/min/$cm^2$ crystal flux, the separation efficiency of both CsCl and $SrCl_2$ showed about 90% by the layer crystallization process, assuming a LiCl salt reuse rate of 90wt%.
Keywords
pyroprocessing; LiCl salt waste; reuse; Cs/Sr separation; layer crystallization;
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Times Cited By KSCI : 5  (Citation Analysis)
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