[3E10-15] Advanced Reactor Safety

3:15 PM - 3:30 PM JST(6:15 AM - 6:30 AM UTC)

[3E12] Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors(38) Melting behavior analysis of SUS316L containing 30mass%B4C using ultrahigh-temperature thermal analysis based on blackbody radiation

*Hideo Higashi¹, Makoto Ohtsuka¹, Masayoshi Adachi¹, Hiroyuki Fukuyama¹, Hidemasa Yamano² (1. Tohoku UniV., 2. JAEA)

Keywords:

Sodium-cooled fast reactor,Boron carbide,Stainless steel,Melting behavior,Thermal analysis

This is a basic study for building a thermophysical model to simulate the eutectic melting behavior of control rod materials in core disruptive accidents of sodium-cooled fast reactors. The melting behavior of the SUS316L containing 30mass%B₄C was studied using ultra-high-temperature thermal analysis based on blackbody radiation that has been developed in Fukuyama lab.