2021 Fall Meeting

Presentation information

Oral presentation

IV. Nuclear Plant Technologies » 402-1 Nuclear Safety Engineering (Safety Design, Safety Assessment/Analysis, Management)

[2E10-14] Next Generation Reactor Safety 3

Thu. Sep 9, 2021 2:45 PM - 4:10 PM Room E

chair: Isamu Sato (TCU)

3:15 PM - 3:30 PM

[2E12] Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors

(27)Normal Spectral Emissivity, Heat Capacity and Thermal Conductivity of 15mass%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 normal spectral emissivity, heat capacity and thermal conductivity of the 15mass%B4C-SS melt have been measured using noncontact modulated laser calorimetry with the ultra-high-temperature thermophysical property measurement system (PROSPECT).