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)

2:45 PM - 3:00 PM

[2E10] Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors

(25)Project Overview and Progress until 2020

*Hidemasa Yamano1, Toshihide Takai1, Yuki Emura1, Hideo Higashi2, Hiroyuki Fukuyama2, Tsuyoshi Nishi3, Koji Morita4, Kinya Nakamura5, Hirofumi Fukai6, Marco Pellegrini7 (1. JAEA, 2. Tohoku Univ., 3. Ibaraki Univ., 4. Kyushu Univ., 5. CRIEPI, 6. Waseda Univ., 7. UTokyo)

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

A research project has been conducting thermophysical property measurement of a eutectic melt, eutectic melting experiments and material analysis, physical model development for the eutectic melting reaction, and reactor application analysis in order to simulate the eutectic melting reaction and relocation behavior of boron carbide as a control rod material and stainless steel during a core disruptive accident in an advanced sodium-cooled fast reactor designed in Japan. This paper describes the project overview and progress until JFY2020.