作者: Steven D. Herrmann , Michael F. Simpson , Shelly X. Li
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摘要: A series of tests were performed to demonstrate the electrolytic reduction spent light water reactor fuel at bench-scale in a hot cell Idaho National Laboratory Materials and Fuels Complex (formerly Argonne - West). The process involves conversion oxide metal by means, which would then enable subsequent separation recovery actinides via existing electrometallurgical technologies, i.e., electrorefining. Four runs bench scale using ~500 ml molten LiCl -- 1 wt% Li2O electrolyte 650 oC. In each run, ~50 g crushed was loaded into permeable stainless steel basket immersed as cathode. spiral wound platinum wire anode. When controlled electric current conducted through anode cathode, reduced oxygen gas evolved Salt samples extracted before after run analyzed for fission product constituents. baskets following sectioned sampled, revealing an extent uranium excess 98%.