Pyrochemical reprocessing for the treatment of used nuclear fuel is attractive because of the use of inorganic salts, specifically halide based molten salts.Alternatively, there has recently been interest in exploring molybdate melts containing sodium molybdate (Na2MoO4) and molybdenum oxide (MoO3) to achieve the desired separations of uranium dioxide (UO2) from fission products by crystallization. The separation is based on the difference in solubility of the fission product metal oxides compared to the uranium or transuranic oxides in the molybdate melt.The used nuclear fuel is dissolved in the molybdate melt at high temperatures. Upon cooling,the fission products remain soluble in the melt whereas uranium precipitates as uranium oxide or molybdate.  Small scale experiments using gram quantities of uranium have been performed to investigate and optimize purification of the UO2 from the fission products. Initial experimental data on partitioning of selected fission products between  the uranium product and melt will be reported.

Investigation of U behavior in molybdate melts for alternative pyrochemical reprocessing of spent nuclear fuel

246th National Meeting (2013)

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