Study on core disruptive accidents of metal-fueled sodium-cooled fast reactors, 1; Project overview

Yamano, Hidemasa ; Fukano, Yoshitaka ; Matsuba, Kenichi ; Ogata, Takanari*; Ota, Hirokazu*; Oishi, Yuji*; Morita, Koji*; Yamada, Yumi*; Shimada, Sadae*; Yamazaki, Saishun*

A research project has been started to conduct basic thermophysical property measurement of melt properties and eutectic reaction rate, development of core disruptive accident analysis codes, material relocation experiments for code validation, reactor application analysis and scenario study in order to simulate the fuel-cladding eutectic reaction and relocation behavior during core disruptive accidents in metal-fueled sodium-cooled fast reactors in Japan. This paper describes the project overview.

Language	:	Japanese
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Meeting title	:	日本原子力学会2025年秋の大会
Held date	:	2025/09
Location (city)	:	北九州
Location (country)	:	日本
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Keywords	:	ナトリウム冷却炉; 炉心損傷事故; 金属燃料; 共晶反応; 物質再配置
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Cooperating Institute	:	経済産業省

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Registration No. : BB20250173
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