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Study on application of CHF models on reactor pressure vessel lower head for severe accident condition

  • Xi'an Jiaotong University
  • Nuclear Power Institute of China

科研成果: 期刊稿件文章同行评审

3 引用 (Scopus)

摘要

According to the in-vessel retention (IVR) mitigation and the heat transfer characteristics, two theoretical models for predicting the critical heat flux (CHF), the interfacial lift-off theoretical model and the theoretical model considering the hydrodynamic behavior of the vapor-liquid interface of a bubble, are modified, respectively, and a general CHF model is developed to analyze the lower head CHF. The results indicate that the CHF model could well predict the experimental data on large scale curved surface.

源语言英语
页(从-至)46-50
页数5
期刊Hedongli Gongcheng/Nuclear Power Engineering
33
6
出版状态已出版 - 12月 2012

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