低干度流动沸腾临界热流密度预测模型  

Critical Heat Flux Prediction Model for Low Quality Flow Boiling

作　　者：潘杰[1] 杨冬[2] 肖荣鸽[1] 邓志安[1] 

机构地区：[1]西安石油大学石油工程学院,西安710065 [2]西安交通大学动力工程多相流国家重点实验室,西安710049

出　　处：《核动力工程》2013年第4期58-63,共6页Nuclear Power Engineering

基　　金：西安石油大学博士科研启动基金项目(2011BS029);"十一五"国家科技支撑计划项目(2006BAA03B02-03)联合资助

摘　　要：基于近壁面气泡拥塞理论,针对高压力、低流速两相流动沸腾传热,建立适用于低蒸汽干度条件下的临界热流密度(CHF)预测模型。模型通过质量守恒方程进行气泡层与主流区域的极限流量传递计算,并采用能够考虑浮升力影响的气泡脱离直径计算公式以及一些现有的气泡脱离点、湍流速度分布和截面含气率等经验公式作为求解模型的本构方程。根据试验数据拟合得到气泡层临界含气率计算公式。模型的计算结果与试验数据吻合良好,在高压力、低流速条件下具有较高的预测精度。Based on the near wall bubble crowding mode, aimed at the two-phase flow boiling heat transfer at high pressure and low flow rate conditions, a critical heat flux prediction model for low vapor quality region was developed in this paper. The limiting transverse mass flux crossing the interface of the bubbly layer and core was determined from a momentum balance in the model. A formula for detached bubble diameter considering buoyancy and some existing correlations for bubble detachment point, turbulent velocity profile and void fraction were applied in the model, and the critical void fraction of wall bubbly layer were presented based on the experimental data. A good agreement is achieved between the results and experimental data, which implies that the CHF model is accurate at high pressure and low flow rate.

关 键 词：低干度 流动沸腾 传热恶化 临界热流密度 数学模型 

分 类 号：TL33[核科学技术—核技术及应用]