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)

3:00 PM - 3:15 PM

[3K04] Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors

(20)Thermophysical Properties of 17ass%B4C-SS Eutectic Materials in the Solid State

*Toshihide Takai1, Tomohiro Furukawa1, Hidemasa Yamano1 (1. Japan Atomic Energy Agency)

Keywords:Fast reactor, Boron carbide, Stainless steel, Eutectic reaction, Thermophysical property

ナトリウム冷却高速炉の炉心損傷事故評価において、制御棒材(炭化ホウ素:B4C)と原子炉構造材(ステンレス鋼:SS)の共晶溶融反応及びその移行挙動を模擬するのに必要な物理モデル構築に資するため、B4C-SS共晶物の固相物性測定を行った結果について報告する。