Development of estimation technology for availability of measure for failure of containment vessel in sodium cooled fast reactor, 3; Corium/sodium-concrete interaction behavior

Kawaguchi, Munemichi ; Uno, Masayoshi*; Konishi, Kensuke ; Yamamoto, Ikuo*; Miyahara, Shinya*

We started a project on "Development of Estimation Technology for Availability of Measure for Failure of Containment Vessel in Sodium Cooled Fast Reactor" as a program for R&D for nuclear system, development of basic technology for safety. We planed to develop an evaluation method based on experiments of hydrogen generation and concrete ablation in sodium-concrete reaction. This report shows the plan and a part of the sodium test.

Language	:	Japanese
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Meeting title	:	日本原子力学会2015年春の年会
Held date	:	2015/03
Location (city)	:	日立
Location (country)	:	日本
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DOI for research data	:	Link to research data related to this paper/report.
Keywords	:	高速炉; シビアアクシデント; ナトリウム-コンクリート反応; 移行挙動; 反応停止機構
Research Facility	:	FBRサイクル研修施設
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Article of JAEA R&D Review	:
Cooperating Institute	:	福井大学

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Registration No. : BB20143072
JAEA Abstracts No. :
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