⁹⁹Mo Separation from High-Concentration Irradiated Uranium Nitrate and Uranium Sulfate Solutions

We report separation data indicating that ⁹⁹Mo 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 ⁹⁹Mo is produced during fission of high concentrations of low enriched uranium sulfate solution fuel, it is feasible to both recover >90% of the ⁹⁹Mo for further purification and the uranium for recycle