Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors, 1; Project Overview

Yamano, Hidemasa ; Takai, Toshihide ; Furukawa, Tomohiro ; Emura, Yuki; Kurata, Masaki ; Higashi, Hideo*; Fukuyama, Hiroyuki*; Nishi, Tsuyoshi*; Ota, Hiromichi*; Liu, X.*; Morita, Koji*; Furuya, Masahiro*

A research project has been started for thermophysical property evaluation of eutectic melt composed of B $_{4}$ C as control rod material and stainless steel (SS), eutectic reaction experiments, material analysis, physical modelling of eutectic reaction and reactor application analyses in order to simulate the B $_{4}$ C-SS eutectic melting and relocation behaviors in core disruptive accident of sodium-cooled fast reactor. This paper reports the project overview and the first year (JFY 2016) outcomes.

Language	:	Japanese
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Meeting title	:	日本原子力学会2017年秋の大会
Held date	:	2017/09
Location (city)	:	札幌
Location (country)	:	日本
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Keywords	:	ナトリウム冷却高速炉; 炉心損傷事故; B $_{4}$ C
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Cooperating Institute	:	経済産業省資源エネルギー庁

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Registration No. : BB20170346
JAEA Abstracts No. :
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