垂直上升管内对流沸腾瞬态数值模拟及其两相流不稳定性预测  

Transient Numerical Simulation and Two-phase Flow Instability Prediction of Convective Boiling in Vertical Up-flow Tube

作　　者：马越[1] 李晓伟[1] 吴莘馨[1] 

机构地区：[1]清华大学核能与新能源技术研究院,北京100084

出　　处：《原子能科学技术》2013年第12期2249-2253,共5页Atomic Energy Science and Technology

基　　金：国家自然科学基金资助项目(51006061);国家科技重大专项资助项目(2008ZX06901)

摘　　要：核电站蒸汽发生器二次侧为两相对流沸腾换热过程,在设计过程中须保证其不发生两相流不稳定性。本工作采用时域法对垂直上升管内两相流不稳定性进行研究,建立了垂直上升直管内流动沸腾过程的一维模型,并编制计算程序。采用该程序模拟了流动沸腾过程气液两相流密度波的不稳定性,给出两相流波动过程瞬态参数分布,由此分析了密度波不稳定发生的机理,并分析了质量流速、系统压力、入口过冷度对不稳定的影响。结果表明,与已有实验及理论结果相比,瞬态参数计算结果与实验结果符合较好,可较好找到不同工况下直管内气液两相流发生不稳定的边界,结果优于Khabenski线算图方法。The secondary side of the nuclear power plant steam generator is working in a two-phase convective boiling process in which two-phase flow instability must be avoided in design. The time domain method was used to study the two-phase flow instability in a vertical up-flow tube. One-dimensional model was established and a numerical program was compiled. Two-phase flow density-wave instability was simulated, and transient parameter distribution in the tube during the dynamic process was presented. The program was also used to analyze the effects of mass velocity, system pressure, and inlet sub-cooling on flow instability. The result shows that the transient parameter distribution from the program agree well with the experimental results, and it can predict the instability boundary, which is more accurate than that of the usually used Khabenski nomographic method.

关 键 词：气液两相流 不稳定性 数值模拟 

分 类 号：TL333[核科学技术—核技术及应用]