[1D06-09] Fast Reactor Development

[1D07] Evaluation of burnup performance of transuranic elements by a small chloride molten salt fast reactor

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

Keywords:molten salt reactor, fast reactor, chloride, transuranic element, transmutation

A chloride molten salt reactor is thought useful to reduce transuranic elements (TRU) contained in accumulated LWR spent fuel since it has a hard neutron spectrum similar to that of a sodium fast reactor with oxide fuels.
On this account, the TRU burnup performance was evaluated using a small chloride molten salt fast reactor of 700 MWt. As a result, it has been confirmed that it has a capability of reducing about 70% of TRU when it is operated for 120 years continuously charging, a few liters a day, fuel salt composed of the compositions of 45 GWd/t PWR discharged fuel.