Study on eutectic melting behavior of control rod materials in core disruptive accidents of sodium-cooled fast reactors, 16; Immersion tests of B $_{4}$ C into molten stainless steel

Emura, Yuki; Kamiyama, Kenji ; Yamano, Hidemasa

In core disruptive accidents of sodium-cooled fast reactors, boron carbide used as the control material may melt into molten stainless steel and be widely transferred to the inside and outside of the core region. In this study, a series of tests was conducted to acquire the data regarding melting rate of boron carbide into molten stainless steel and its results were considered.

Language	:	Japanese
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Meeting title	:	日本原子力学会2019年秋の大会
Held date	:	2019/09
Location (city)	:	富山
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; 炭化ホウ素; ステンレス鋼; 共晶溶融反応
Research Facility	:	高速炉安全性試験施設
Press Release	:
Article of JAEA R&D Review	:
Cooperating Institute	:	経済産業省

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Registration No. : BB20190610
JAEA Abstracts No. :
Paper Submission No. :

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Study on eutectic melting behavior of control rod materials in core disruptive accidents of sodium-cooled fast reactors, 16; Immersion tests of BC into molten stainless steel

Study on eutectic melting behavior of control rod materials in core disruptive accidents of sodium-cooled fast reactors, 16; Immersion tests of B $_{4}$ C into molten stainless steel