2019 Fall Meeting

Presentation information

Oral presentation

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

[2G01-05] Severe Accident of Sodium-Cooled Fast Reactor 1

Thu. Sep 12, 2019 9:30 AM - 10:50 AM Room G (Common Education Bildg. 2F C22)

Chair:Takaaki Sakai(Tokai Univ.)

9:30 AM - 9:45 AM

[2G01] Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors

(11)Project Overview and Progress by JFY 2018

*Hidemasa Yamano1, Toshihide Takai1, Tomohiro Furukawa1, Shin Kikuchi1, Yuki Emura1, Hideo Higashi2, Hiroyuki Fukuyama2, Tsuyoshi Nishi3, Xiaoxing Liu4, Kenya Nakamura5 (1. Japan Atomic Energy Agency, 2. Tohoku University, 3. Ibaraki University, 4. Kyushu University, 5. Central Research Institute of Electric Power Industry)

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

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 by JFY2018.