A Visualization test for fragmentation behavior of molten stainless steel discharged into a sodium pool

Emura, Yuki; Isozaki, Mikio; Matsuba, Kenichi ; Kamiyama, Kenji

In core-disruptive accidents of sodium-cooled fast reactors, molten-core materials are discharged into a lower part of reactor vessel and are mixed with sodium there. In this study, molten stainless steel was poured into sodium and its behavior in the sodium was observed by a visualization system using X-ray.

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; 炉心崩壊事故; 溶融炉心物質再配置; 燃料-冷却材熱的相互作用; 原子炉容器内保持
Research Facility	:	高速炉安全性試験施設
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Article of JAEA R&D Review	:
Cooperating Institute	:	経済産業省

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Registration No. : BB20180520
JAEA Abstracts No. :
Paper Submission No. :

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