严重事故条件下反应堆压力容器下封头CHF模型应用研究

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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

摘要: 根据堆芯熔融物滞留(IVR)措施与压力容器的传热特点,对界面脱离临界热流密度(CHF)分析理论模型和考虑单个汽泡汽-液界面动力学的CHF分析理论模型分别进行改进,建立综合的CHF预测模型以应用于压力容器下封头CHF分析。结果表明,本文的综合模型预测的下封头CHF结果与国际上一些大尺寸的弯曲表面实验结果基本一致。
- 临界热流密度 /
- 严重事故 /
- 堆芯熔融物滞留
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