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

Yamano, Hidemasa ; Futagami, Satoshi ; Shibata, Akihiro*

This study examined the application of safety design criteria (SDC) and safety design guideline (SDG) developed in the Generation-IV international forum on the active reactor shutdown system (RSS) to sodium-cooled fast reactors (SFRs) recently designed in Japan.

Language	:	English
Journal	:	Proceedings of Advanced Reactor Safety (ARS 2024)
Volume	:
Number	:
Pages	:	p.151 - 160
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; Reactor shutdown system
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Article of JAEA R&D Review	:
Cooperating Institute	:	経済産業省

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Registration No. : BB20231621
JAEA Abstracts No. : 52001103
Paper Submission No. : 28529

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