Abstract
A study has been performed for a small molten salt power reactor operated with Th-U fuel cycle, and nuclear characteristics of the reactor are evaluated using latest codes and cross sections. Nuclear characteristics of the reactor core are analyzed by using SRAC95 (a standard reactor analysis code), with 30 group cross section data from JENDL3.2 (nuclear data file). Burn up characteristics of the reactor are estimated by using SRAC95 and ORIGEN2 (a code to calculate the build up and decay of radioactive materials), assuming that the fuel salt is reprocessed once in every 6 years, and graphite moderator are replaced in every 15 years. From the present study, the following results have been obtained. (1) Fuel conversion ratio of the reactor is about 0.92, and the reactor can be operated feeding only 8% fossile material of LWR case. (2) Build up of dissolvable fission products is low enough not to cause chemical problems or precipitation troubles, even after 40 years operation. (3) Regarding long-lived radioactive waste, this reaetor produces only 10% minor actinides amount of LWR case.
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