Study on Application of CHF Models on Reactor Pressure Vessel Lower Head for Severe Accident Condition

YU Hongxing; SU Guanghui; GUAN Zhonghua; HUANG Daishun

Mar. 2025

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YU Hongxing, SU Guanghui, GUAN Zhonghua, HUANG Daishun. Study on Application of CHF Models on Reactor Pressure Vessel Lower Head for Severe Accident Condition[J]. Nuclear Power Engineering, 2012, 33(6): 46-50.

Citation:

YU Hongxing, SU Guanghui, GUAN Zhonghua, HUANG Daishun. Study on Application of CHF Models on Reactor Pressure Vessel Lower Head for Severe Accident Condition[J]. Nuclear Power Engineering, 2012, 33(6): 46-50.

Citation:

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Study on Application of CHF Models on Reactor Pressure Vessel Lower Head for Severe Accident Condition

1. Department of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an, 710049, China;
2. Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610041, China

Received Date: 2012-05-09
Rev Recd Date: 2012-10-15

Available Online: 2025-03-08

Abstract

Abstract

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.
- Critical heat flux,
- Severe accident,
- In-vessel retention