[2K10-13] Molten Salt Reactor

[2K12] Research and development of a small chloride molten salt fast reactor

(3) Burnup analysis and investigation of a continuous refueling method

*Haruka Hirano¹, Yoshihisa Tahara¹, Hiroyasu Mochizuki¹, Satoshi Chiba¹ (1. Tokyo Tech)

Keywords:molten salt reactor, fast reactor, chloride, burnup analysis, transmutation

Burnup analysis and investigation of a continuous refueling method for a small chloride molten salt fast reactor were conducted. The latest nuclear data library ENDF/B-VIII.0 and the continuous energy Monte Carlo code SERPENT-2 were used for burnup analysis. The TRU transmutation ratio of 56% was achieved after 10 years operation, and it has been found that this reactor core is effective in the reduction of TRU.