产量(工程)
熔盐
铀
放射化学
碘
盐(化学)
辐照
碲
熔盐反应器
化学
材料科学
核工程
环境科学
核化学
物理
冶金
核物理学
工程类
物理化学
作者
Chenggang Yu,Xiaohe Wang,Chen Wu,Chunyan Zou,Jianhui Wu,Cai Xiang-Zhou,Jingen Chen
标识
DOI:10.1016/j.apradiso.2020.109350
摘要
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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