Experiment and Numerical Simulation Study on CCFL Characteristic of Hot Leg Section under Loss of Coolant Accident

This study aims to investigate the characteristics of counter current flow limitation (CCFL) in the hot leg section of a nuclear reactor under a small break loss of coolant accident (SBLOCA) scenario, thereby enhancing the safety of thermal equipment in nuclear power plants. CCFL, a phenomenon that...

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Autor principal:	LIU Yang1, 2, SUN Wan1, 2, CHEN Huafa3, WAN Jie1, 2, LIANG Ren3, PAN Liangming1, 2
Format:	Artigo
Idioma:	Inglês
Publicat:	Editorial Board of Atomic Energy Science and Technology 2025-11-01
Col·lecció:	Yuanzineng kexue jishu
Matèries:	nuclear reactor safety counter current flow limitation numerical simulation small break loss of coolant accident
Accés en línia:	https://yznkxjs.xml-journal.net/article/doi/10.7538/yzk.2024.youxian.0924
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