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 |
| 卷 | 33 |
| 期 | 6 |
| 出版状态 | 已出版 - 12月 2012 |
学术指纹
探究 'Study on application of CHF models on reactor pressure vessel lower head for severe accident condition' 的科研主题。它们共同构成独一无二的学术指纹。引用此
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