Developing a Recovery Column for Mo-99 from Highly Concentrated Uranyl Nitrate Solutions
- Argonne National Lab. (ANL), Argonne, IL (United States). Chemical and Fuel Cycle Technologies Div.
- Argonne National Lab. (ANL), Argonne, IL (United States). Strategic Security Sciences
- Argonne National Lab. (ANL), Argonne, IL (United States). Operations and Business Management
The feasibility of a highly concentrated uranyl nitrate target for 99Mo production and recovery was investigated with respect to three separate resins. Two resins were inorganic-based – titania and zirconia – and the other was organic-based utilizing Aliquot® 336 extraction chromatography. Results show that pH has a significant effect on select fission products such as Zr whereas Mo is reasonably well retained between pH 0 and 2. Temperature also appreciably affected the retention of Mo. Using a normal-phase titania resin (Sachtapore®), the sorption of Mo was investigated by varying acid and uranium concentrations. The stability of the resin was also studied as a function of acid concentration. Results from the batch studies were then input into the in-house Versatile Reaction Separation (VERSE) code in order to design and optimize a recovery column for 99Mo. The experimental and model results show that >99.9% of the 99Mo can be recovered in the presence of saturated uranyl nitrate solutions.
- Research Organization:
- Argonne National Lab. (ANL), Argonne, IL (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA) - Office of Defense Nuclear Nonproliferation - Office of Material Management and Minimization (NA-23)
- DOE Contract Number:
- AC02-06CH11357
- OSTI ID:
- 1570300
- Report Number(s):
- ANL/CFCT-19/19; 156461; TRN: US2000040
- Country of Publication:
- United States
- Language:
- English
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