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Updated: Dec 12, 2025

Production of Synthetic Nuclear Melt Glass
Published on: January 4, 2016
Supply of I-131 in a 2 MW molten salt reactor with different production methods
Chenggang Yu1, Xiaohe Wang1, Chen Wu2
1Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai, 201800, China; CAS Innovative Academies in TMSR Energy System, Chinese Academy of Sciences, Shanghai, 201800, China.
Abstract:
Four I-131 production methods including irradiated TeO2 target and uranium target in the irradiation channel, batch-wise extracted iodine from the fuel salt, and online extracted solid tellurium through the by-pass loop system have been assessed in a 2 MW molten salt reactor. The latter method can produce a large annual yield of I-131 (about 155,000 Ci). The radioactivity shielding demand of the latter method is much smaller than the other I-131 production methods under the identical annual yield of I-131.
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