Gas-phase molybdenum-99 separation from uranium dioxide by fluoride volatility using nitrogen trifluoride
- Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
- Flibe Energy, Richland, WA (United States)
Production of the important 99mTc medical isotope parent, molybdenum-99 (99Mo), via the fissioning of high- and low-enriched uranium (HEU/LEU) targets followed by target dissolution in acid and solution-phase purification of 99Mo 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 99Mo 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 UO2. The results indicate that volatile [99Mo]Mo can be captured downstream of the reacted solid mixture on a column bed (trap) of alumina; the majority of the captured [99Mo]Mo can be subsequently eluted from the alumina trap with a few milliliters of water. >1.0 × 105 single pass decontamination of U and the collected [99Mo]Mo product is demonstrated. This simple thermo-fluorination technique has the potential to provide a rapid methodology for routine 99Mo production.
- Research Organization:
- Pacific Northwest National Laboratory (PNNL), Richland, WA (United States)
- Sponsoring Organization:
- USDOE
- Grant/Contract Number:
- AC05-76RL01830
- OSTI ID:
- 1599144
- Report Number(s):
- PNNL-SA-148868
- Journal Information:
- RSC Advances, Journal Name: RSC Advances Journal Issue: 6 Vol. 10; ISSN 2046-2069; ISSN RSCACL
- Publisher:
- Royal Society of ChemistryCopyright Statement
- Country of Publication:
- United States
- Language:
- English
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