Study on eutectic melting behavior of control rod materials in core disruptive accidents of sodium-cooled fast reactors, 10; Development of eutectic reaction model for use in reactor safety analysis code

Liu, X.*; Morita, Koji*; Yamano, Hidemasa

A physical model used in a fast reactor safety analysis code, SIMMER-III, was developed in order to simulate a eutectic melting reaction and relocation behavior of boron carbide (B $_{4}$ C) as a control rod material and stainless steel (SS) in core disruptive accidents of sodium-cooled fast reactors. In addition, basic applicability was confirmed with estimation for existing visualization experiments of eutectic melts.

Language	:	Japanese
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Meeting title	:	日本原子力学会2018年秋の大会
Held date	:	2018/09
Location (city)	:	岡山
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; 共晶溶融反応; 高速炉安全解析コード
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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. : BB20180900
JAEA Abstracts No. :
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