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)

2:45 PM - 3:00 PM

[3K03] Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors

(19)Project Overview and Progress until 2019

*Hidemasa Yamano Yamano1, Toshihide Takai1, Shin Kikuchi1, Yuki Emura1, Hideo Higashi2, Hiroyuki Fukuyama2, Tsuyoshi Nishi3, Hiromichi Ohta3, Koji Morita4, Kinya Nakamura5 (1. JAEA, 2. Tohoku Univ., 3. Ibaraki Univ., 4. Kyushu Univ., 5. CRIEPI)

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

It is necessary to simulate a eutectic melting reaction and relocation behavior of boron carbide (B4C) as a control rod material and stainless steel (SS) during a core disruptive accident in an advanced sodium-cooled fast reactor designed in Japan. On that account, a new project has been started to conduct eutectic melting experiments, thermophysical property measurement of the eutectic melt, and physical model development for the eutectic melting reaction. The eutectic experiments involve the visualization experiments, eutectic reaction rate experiments and material analyses. The thermophysical properties are measured in the range of liquid and solid states. The physical model is developed for a severe accident computer code based on the measured data of the eutectic reaction rate and the physical properties. This paper describes the project overview and progress until JFY2019.