Thermal transient evaluation of pool-type SFR

Kato, Atsushi ; Onoda, Yuichi ; Miyagawa, Takayuki*; Endo, Junji*; Kubo, Koji*

JAEA is studying 600 MWe pool-type sodium-cooled fast reactor. This report presents thermal hydraulic study in a reactor vessel and structural intactness evaluation in case of station black out and reactor trip.

Language	:	Japanese
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Meeting title	:	日本原子力学会2020年秋の大会
Held date	:	2020/09
Location (city)	:	福岡(online)
Location (country)	:	日本
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Keywords	:	ナトリウム冷却炉; タンク型炉
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Cooperating Institute	:	経済産業省

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Registration No. : BB20200428
JAEA Abstracts No. :
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