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Gas-phase molybdenum-99 separation from uranium dioxide by fluoride volatility using nitrogen trifluoride

Production of the important (99m)Tc medical isotope parent, molybdenum-99 ((99)Mo), via the fissioning of high- and low-enriched uranium (HEU/LEU) targets followed by target dissolution in acid and solution-phase purification of (99)Mo is time-consuming, generates quantities of corrosive radioactive...

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Detalles Bibliográficos
Autores principales: McNamara, Bruce K., O'Hara, Matthew J., Clark, Richard A., Morrison, Samuel S., Soderquist, Chuck Z., Scheele, Randall D.
Formato: Online Artículo Texto
Lenguaje:English
Publicado: The Royal Society of Chemistry 2020
Materias:
Acceso en línea:https://www.ncbi.nlm.nih.gov/pmc/articles/PMC9048791/
https://www.ncbi.nlm.nih.gov/pubmed/35497761
http://dx.doi.org/10.1039/c9ra10270a
Descripción
Sumario:Production of the important (99m)Tc medical isotope parent, molybdenum-99 ((99)Mo), via the fissioning of high- and low-enriched uranium (HEU/LEU) targets followed by target dissolution in acid and solution-phase purification of (99)Mo is time-consuming, generates quantities of corrosive radioactive waste, and can result in the release of an array of radionuclides to the atmosphere. An alternative (99)Mo purification method has been devised that has the potential to alleviate many of these issues. Herein, we demonstrate the feasibility of a rapid Mo/Tc gas-phase separation from UO(2). The results indicate that volatile [(99)Mo]Mo can be captured downstream of the reacted solid mixture on a column bed (trap) of alumina; the majority of the captured [(99)Mo]Mo can be subsequently eluted from the alumina trap with a few milliliters of water. >1.0 × 10(5) single pass decontamination of U and the collected [(99)Mo]Mo product is demonstrated. This simple thermo-fluorination technique has the potential to provide a rapid methodology for routine (99)Mo production.