CFD simulation on critical heat flux of flow boiling in IVR-ERVC of a nuclear reactor
Nuclear Engineering and Design(2016)
摘要
•CFD simulation on CHF of boiling two-phase flow in ERVC is proposed.•CFD simulation result of CHF agrees well with that of experimental result.•The characteristics of boiling two-phase flow and boiling crisis are analyzed.
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关键词
K. Thermal hydraulics
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