[2F_PL] Evaluation of Critical Heat Flux of Nuclear Reactor, Present and Future

[2F_PL03] Current Evalution Method of CHF in Light Water Reactor

Subchannel Analysis

*Yuki Narushima¹ (1. Hitachi)

To integrate knowledge related to critical heat flux (CHF) of nuclear fuel for the mechanistic evaluation of CHF, research committee for mechanistic evaluation of critical heat flux for nuclear reactors was established with the cooperation of the thermal-hydraulics, the computational science and engineering divisions. In this session, outline of this committee, current evaluation methods of CHF and current status related to mechanistic evaluation methods for CHF will be introduced by young researchers.