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We report separation data indicating that 99 Mo can be separated from a vast excess of either uranyl sulfate or uranyl nitrate in irradiated dilute acid solutions. These results suggest that, if medical isotope 99 Mo is produced during fission of high concentrations of low enriched uranium sulfate solution fuel, it is feasible to both recover >90% of the 99 Mo for further purification and the uranium for recycle.
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Dale et al. (2012) studied this question.
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