Supply of I-131 in a 2 MW molten salt reactor with different production methods.

Four I-131 production methods including irradiated TeO 2 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. • The I-131 production capability in a 2 MW Molten Salt Reactor with different methods is evaluated. • The annual production activity of I-131 for online extracted solid tellurium through the BPLS method is about 155,000 Ci. • The radioactivity shielding demand for the latter method is much smaller than the other I-131 production methods. [ABSTRACT FROM AUTHOR]