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.)

9:45 AM - 10:00 AM

[2G02] Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors

(12)Thermophysical Properties of 7mass%B4C-SS Eutectic Materials in the Solid State

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

Keywords:Sodium Cooled Fast Reactor, Boron Carbide, Stainless Steel, Eutectic Reaction, Thermophysical Property in the Solid Phase

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。