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.

中文翻译：

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用不同的生产方法在2兆瓦熔融盐反应堆中供应I-131。

在2兆瓦熔融盐中评估了四种I-131生产方法，包括辐照通道中的TeO ₂靶材和铀靶材的辐照，从燃料盐中分批提取的碘以及通过旁路回路系统在线提取固体碲的方法反应堆。后一种方法可以产生大量的I-131年产量（约155,000 Ci）。在I-131的年产量相同的情况下，后一种方法的放射性屏蔽需求比其他I-131生产方法小得多。