Progress of a pool-type SFR conceptual design study in Japan

Kubo, Shigenobu ; Higurashi, Koichi*; Shibata, Akihiro*

This paper describes progress of pool-type next generation sodium-cooled fast reactor (SFR) design study in Japan. Safety design criteria and safety design guidelines for SFR developed in the frame of generation IV international forum are fully applied in the safety design. In order to eliminate complete loss of heat removal, decay heat removal facilities are enhanced and their performance is evaluated.

Language	:	English
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Meeting title	:	Joint IAEA-GIF Workshop on the Safety of Non-Water Cooled Reactors
Held date	:	2023/05
Location (city)	:	Vienna
Location (country)	:	Austria
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Keywords	:	no keyword
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Cooperating Institute	:	三菱FBRシステムズ

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Registration No. : BB20230233
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