Application of the GIF safety design criteria and safety design guidelines on decay heat removal system to next generation sodium-cooled fast reactor in Japan

Yamano, Hidemasa ; Futagami, Satoshi ; Higurashi, Koichi*

This paper describes the application of safety design criteria (SDC) and safety design guideline (SDG) developed in the Generation-IV international forum on decay heat removal system (DHRS) enhancing reliability to sodium-cooled fast reactors (SFRs) recently designed in Japan.

Language	:	English
Journal	:	Proceedings of Advanced Reactor Safety (ARS 2024)
Volume	:
Number	:
Pages	:	p.121 - 130
Publication Year/Month	:	2024/08
Meeting title	:	2024 ANS Annual Conference; Advanced Reactor Safety (ARS)
Held date	:	2024/06
Location (city)	:	Las Vegas
Location (country)	:	U.S.A.
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DOI for research data	:	Link to research data related to this paper/report.
Keywords	:	Generation-IV, Sodium-cooled fast reactor; Safety design criteria; Safety design guideline; Decy heat removal system
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Article of JAEA R&D Review	:
Cooperating Institute	:	経済産業省

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Registration No. : BB20231620
JAEA Abstracts No. : 52001102
Paper Submission No. : 28528

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