Development of seismic assessment method for FR core, 2; Seismic experiment of full scale single model of control rod

Yamamoto, Tomohiko ; Iwasaki, Akihisa*; Kawamura, Kazuki*; Matsubara, Shinichiro*; Ikarimoto, Iwao*; Harada, Hidenori*

A sophisticated analysis method has to be developed to study the seismic response of Fast Reactor (FR) core considering 3 dimensional group vibration of FR core components. This paper summarizes for result of vertical vibration experiment of full scale single model of control rod.

Language	:	Japanese
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Meeting title	:	日本原子力学会2017年秋の大会
Held date	:	2017/09
Location (city)	:	札幌
Location (country)	:	日本
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Keywords	:	高速炉; 炉心耐震
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Cooperating Institute	:	経済産業省

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Registration No. : BB20170876
JAEA Abstracts No. :
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