Re-estimation of nuclear characteristics of a small molten salt power reactor

A study has been performed for a small molten salt power reactor operated w ith Th-U fuel cycle, and nuclear characteristics of the reactor are evaluat ed using latest codes and cross sections. Nuclear characteristics of the re actor core are analyzed by using SRAC95 ia standard reactor analysis code), with 30 group cross section data from JENDL3.2 (nuclear data file). Burn u p characteristics of the reactor are estimated by using SRAC95 and ORIGEN2 (a code to calculate the build up and decay of radioactive materials), assu ming 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 follo wing results have been obtained. (1) Fuel conversion ratio of the reactor is about 0.92, and the reactor can be operated feeding only 8% fissile material of LWR case. (2) Build up of dissolvable fission products is low enough not to cause che mical problems or precipitation troubles, even after 40 years operation. (3) Regarding long-lived radioactive waste, this reactor produces only 10% minor actinides amount of LWR case.