[1C07-11] Development of Advanced Reactor

[1C10] A study of molten salt fast reactor with sustainable properties

*Koshi Mitachi¹ (1. Beyond energy research & development association)

Keywords:molten salt reactor, fast reactor, chloride salt, trans uranium elements, burnup calculation

Burnup charasteristics of a molten salt fast reactor (MSFR) was studied to utilize trans uranium elements (TRU) and depleted uranium effectively. The fuel salt used is a mixed salt of NaCl, CaCl₂, UCl₃ and TRUCl₃. This fuel salt is expected to have solidification temperature of about 530C and TRU solubility of about 30mol%. MSFR can reach a fuel conversion ratio of 1.0 after about 20 years of operation supplying ²³⁸U and TRU. After that, MSFR will continue to operate on ²³⁸U supply. Using the amount of depleted uranium in Japan, it may be possible to supply a lot of electricity for a long period. These burnup characteristics of MSFR were analyzed by SRAC2006 with SRACLIB-JDL40.