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)

3:00 PM - 3:15 PM

[2E11] Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors

(26)Density and Surface Tension of 15mass%B4C-SS Eutectic Molten Materials

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

Keywords:Sodium-cooled fast reactors, boron carbide, stainless steel, density, surface tension

We have been systematically conducting the thermophysical property measurements of the stainless steel–B4C eutectic material for developing a physical model for the eutectic melting reaction between control-rod material (boron carbide, B4C) and austenitic stainless steel (SS316L(SS)) for a core disruptive accident in sodium-cooled fast reactors. This paper reports the liquidus temperature, and the density and surface tension of the molten SS−15mass%B4C system.