[1J05-09] Thermal Hydraulics of Sodium-Cooled Fast Reactors 1

[1J08] Development of fundamental numerical simulation system for integrated safety evaluation in various innovative sodium-cooled fast reactor

(4)Development of evaluation model for core melting

*Tohru Suzuki¹, Haruki Honda¹, Yu Takahashi¹, Ken-ichi Kawada² (1. Tokyo City Univ., 2. JAEA)

Keywords:sodium-cooled fast reactor, safety evaluation, phenomena identification, core melting

The progress on the identification of physical phenomena that are important for evaluating the steady behavior of fuel pins and the melting behavior during core disruption, and the construction of an analysis module based on them will be presented.