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

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• 作者：Gregory E. Dale ; Dale A. Dalmas ; Michael J. Gallegos ; Kevin R. Jackman ; Charles T. Kelsey ; IV ; Iain May ; Sean D. Reilly ; Gary M. Stange
• 刊名：Industrial & Engineering Chemistry Research
• 出版年：2012
• 出版时间：October 10, 2012
• 年：2012
• 卷：51
• 期：40
• 页码：13319-13322
• 全文大小：222K
• 年卷期：v.51,no.40(October 10, 2012)
• ISSN：1520-5045

文摘

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.