Development of Mo recovery and concentration column processes for production of 99Mo from accelerator-driven irradiation of aqueous uranyl-sulfate solution

SEPARATION SCIENCE AND TECHNOLOGY(2020)

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摘要
Recovery and concentration columns were designed for separation of Mo from highly concentrated uranyl-sulfate solution. Molybdenum uptake on titania sorbent, from concentrated uranium solutions, is superior to alumina and enables use of low-enriched uranium (LEU, <20% U-235) for Mo-99 production. Compared to highly enriched uranium (HEU), LEU requires five times more uranium to produce the same amount of Mo. Isotherm parameters were examined for Mo, Te, and Tc. The VERSE (VErsatile Reaction SEparation) model was used to generate profiles for metal ion concentrations in the columns and determine the minimum column length required for 99.9% Mo capture. Column designs were verified with an irradiated uranyl sulfate solution in a pilot-scale process, where 1.4 Ci of Mo-99 was produced, recovered, and purified. Partitioning of fission products on titania columns is also presented.
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关键词
Mo-99,isotope production,radiochemical separations,chromatography,LEU
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