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Updated: Dec 22, 2025

Production of Synthetic Nuclear Melt Glass
Published on: January 4, 2016
Sustainable supply of 99Mo source in a 2 MW molten salt reactor using low-enriched uranium
Chenggang Yu1, Chunyan Zou2, Chen Wu2
1Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai, 201800, China; CAS Innovative Academy in TMSR Energy System, Chinese Academy of Sciences, Shanghai 201800, China.
Abstract:
The 99Mo production in a 2 MW molten salt reactor using liquid low-enriched uranium (LEU) fuel has been evaluated. The batch-wise extraction period of 99Mo is optimized to be one day corresponding to 9415 6-day Ci/week of the 99Mo production rate. The required amount of uranium is only 4.77 kg annually. The required chemically reprocessed amount of FPs is about 58.4 g annually, accounting for only 4.9% of the solid LEU target method under the identical production capacity of 99Mo.
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