CFD simulation on critical heat flux of flow boiling in IVR-ERVC of a nuclear reactor

Xiang Zhang,Teng Hu,Deqi Chen,Yunke Zhong,Hong Gao

Nuclear Engineering and Design（2016）

引用 19|浏览5

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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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K. Thermal hydraulics

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