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

Autor:	Gregory E. Dale, Michael J. Gallegos, Sean D. Reilly, Kevin R. Jackman, Charles T. Kelsey, Gary M. Stange, Iain May, Dale Allen Dalmas
Rok vydání:	2012
Předmět:	Isotope General Chemical Engineering Radiochemistry chemistry.chemical_element General Chemistry Natural uranium Uranium Enriched uranium Industrial and Manufacturing Engineering Uranium sulfate chemistry.chemical_compound chemistry Uranyl nitrate Uranyl sulfate Sulfate Nuclear chemistry
Zdroj:	Industrial & Engineering Chemistry Research. 51:13319-13322
ISSN:	1520-5045 0888-5885
DOI:	10.1021/ie3008743
Popis:	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.
Databáze:	OpenAIRE
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