Development of next generation innovative reactors in Japan

Yamano, Hidemasa ; Morita, Koji*

The contents are Worldwide development of Sodium-cooled Fast Reactors (SFRs), Nuclear energy policy in Japan, Development of SFRs in Japan, Thermal-hydraulic and safety related Research and Development (Analysis code development, Core deformation analysis, 1D-CFD simulation Severe accident analysis, Sodium-water reaction analysis, and Experimental facilities).

Language	:	English
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Meeting title	:	13th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS13)
Held date	:	2024/11
Location (city)	:	Seoul
Location (country)	:	Korea
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Keywords	:	ナトリウム冷却高速炉; 炉心損傷事故; B $_{4}$ C
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Cooperating Institute	:	経済産業省資源エネルギー庁

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Registration No. : BB20241468
JAEA Abstracts No. :
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