2019 Fall Meeting

Presentation information

Oral presentation

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

[2G06-09] Severe Accident of Sodium-Cooled Fast Reactor 2

Thu. Sep 12, 2019 10:50 AM - 11:55 AM Room G (Common Education Bildg. 2F C22)

Chair:Daisuke Ito(Kyoto Univ.)

10:50 AM - 11:05 AM

[2G06] Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors

(16)Immersion Tests of B4C into Molten Stainless Steel

*Yuki Emura1, Kenji Kamiyama1, Hidemasa Yamano1 (1. JAEA)

Keywords:Sodium-cooled fast reactor, Core disruptive accident, Boron carbide, Stainless steel, Eutectic melting reaction

In core disruptive accidents of sodium-cooled fast reactors, boron carbide used as the control material may melt into molten stainless steel and be widely transferred to the inside and outside of the core region. In this study, a series of tests was conducted to acquire the data regarding melting rate of boron carbide into molten stainless steel and its results were considered.