[2D05-08] Molten Chloride Salt Reactor

11:00 AM - 11:15 AM JST(2:00 AM - 2:15 AM UTC)

[2D06] Feasibility Study of Integral Molten Chloride Salt Fast Reactor (V)(2) Applicability Evaluation of the Point Reactor Kinetics Equation to the Molten Salt Fast Reactor

*Yoshihisa Tahara¹, Chikako Ishizuka² (1. NAIS, 2. Science Tokyo)

Keywords:

Molten salt reactor,Fast reactor,Chloride salt,Kinetics parameter,Safety analysis

The result of the reactor safety analysis is largely affected by the delayed neutron kinetics parameters. For a molten salt fast reactor, a temperature distribution arises and simultaneously He bubbling for removing undissolved fission products brings forth a void distribution. The effect of these distributions on the delayed neutron parameters was, therefore, examined and it was found that there is almost no effect. Hence, in the safety analysis, the delayed neutron kinetics parameters calculated using the core average values of temperature and void rate may be used.