[2G01-05] Severe Accident of Sodium-Cooled Fast Reactor 1

[2G04] Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors

(14)Emissivity, Heat Capacity and Thermal Conductivity of 7mass%B₄C-SS Eutectic Molten Material

*Hideo Higashi¹, Hiroyuki Fukuyama¹, Hidemasa Yamano² (1. Tohoku Univ, 2. JAEA)

Keywords:Sodium-cooled fast reactor, Boron carbide, Stainless steel, Emissivity, Heat capacity, Thermal conductivity

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 emissivity, heat capacity and thermal conductivity of the 7mass%B₄C-SS melt have been measured using noncontact modulated laser calorimetry with the ultra-high-temperature thermophysical property measurement system (PROSPECT).