Study on sodium-water reaction phenomena in steam generator of sodium-cooled fast reactor, 25; Evaluation of heat transfer coefficient for reaction jet in sodium-water reaction experiment, 1

Kurihara, Akikazu ; Umeda, Ryota ; Shimoyama, Kazuhito ; Abe, Yuta ; Kikuchi, Shin ; Ohshima, Hiroyuki

The authors have carried out the sodium-water experiment to acquire the data for heat transfer coefficient between reaction jet and tube, for the purpose of clarifying the overheating tube rupture phenomena under water leak accident in steam generator of sodium-cooled fast reactor.

Language	:	Japanese
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Meeting title	:	日本原子力学会2013年春の年会
Held date	:	2013/03
Location (city)	:	東大阪
Location (country)	:	日本
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Keywords	:	no keyword
Research Facility	:	高速炉安全性試験施設
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Registration No. : BB20123263
JAEA Abstracts No. :
Paper Submission No. :

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