2021 Annual Meeting

Presentation information

Oral presentation

III. Fission Energy Engineering » 302-1 Advanced Reactor System

[1C07-11] Development of Advanced Reactor

Wed. Mar 17, 2021 2:45 PM - 4:10 PM Room C (Zoom room 3)

Chair: Akihiro Uchibori (JAEA)

3:30 PM - 3:45 PM

[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.