Recycle of enriched Mo targets for economic production of 99Mo/99mTc medical isotope without use of enriched uranium
Journal Article
·
· Journal of Radioanalytical and Nuclear Chemistry
- Argonne National Lab. (ANL), Argonne, IL (United States)
A new recycle process for recovery of enriched 98Mo or 100Mo used for production of 99Mo/99mTc medical isotope was developed. In this process, Mo is precipitated from spent NorthStar Mo/Tc generator solution containing ~200 g/L Mo as K2MoO4 in 5 M KOH using acetic acid and then washed with nitric acid. High purification factors from potassium were achieved, and typical Mo recovery yields were ~95 %. In conclusion, the recycle process was performed with up to 260 g of Mo per batch and can be easily implemented for processing of up to 400 g of Mo.
- Research Organization:
- Argonne National Laboratory (ANL), Argonne, IL (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA)
- Grant/Contract Number:
- AC02-06CH11357
- OSTI ID:
- 1399098
- Journal Information:
- Journal of Radioanalytical and Nuclear Chemistry, Vol. 308, Issue 1; ISSN 0236-5731
- Publisher:
- SpringerCopyright Statement
- Country of Publication:
- United States
- Language:
- English
Cited by: 14 works
Citation information provided by
Web of Science
Web of Science
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