2020 Fall Meeting

Presentation information

Oral presentation

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

[3K03-08] Sodium-Cooled Fast Reactors 1

Fri. Sep 18, 2020 2:45 PM - 4:25 PM Room K (Zoom room 11)

Chair:SUNGHYON JANG(Univ. of Tokyo)

3:15 PM - 3:30 PM

[3K05] Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors

(21)Density and Surface Tension of 2.5mass%B4C-SS Eutectic Molten Material

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

Keywords:Sodium-cooled fast reactor, Boron carbide, Stainless steel, Density, Surface tension, Liquidus temperature

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 density and surface tension of 2.5mass%B4C-SS melt have been measured using the ultrahigh-temperature thermophysical property measurement system (PROSPECT).