沸腾传热数值模拟方法及多管耦合应用特性研究  

Numerical Simulation Method of Boiling Heat Transfer and Its Application Characteristics under Multi-tube Coupled Heat Transfer

作　　者：张振国 谭思超[1] 李小畅[2] 刘思超 冯艺 黄玉健 田瑞峰[1] Zhang Zhenguo;Tan Sichao;Li Xiaochang;Liu Sichao;Feng Yi;Huang Yujian;Tian Ruifeng(College of Nuclear Science and Technology,Harbin Engineering University,Harbin,150001,China;College of Aerospace and Civil Engineering,Harbin Engineering University,Harbin,150001,China)

机构地区：[1]哈尔滨工程大学核科学与技术学院,哈尔滨150001 [2]哈尔滨工程大学航天与建筑工程学院,哈尔滨150001

出　　处：《核动力工程》2024年第2期130-138,共9页Nuclear Power Engineering

基　　金：国家自然科学基金(U22B2093,11805044)。

摘　　要：针对直流蒸汽发生器(OTSG)中全流型沸腾传热及一、二次侧耦合换热等复杂物理现象,计算流体动力学(CFD)数值分析普遍面临计算难度大、计算效率低及不确定性大等问题。基于欧拉两流体多相流模型与临界热流密度(CHF)壁面沸腾模型,建立了管内全流型流动沸腾传热数值分析模型,并验证了模型的有效性。基于所验证的模型,开展了数值模型在多管耦合传热下的应用特性研究,明确了该数值模拟方法在多管耦合下的可靠性,并对温度与相分布计算结果对相间作用力模型的敏感性进行了数值分析。研究结果表明:基于欧拉两流体多相流模型与CHF壁面沸腾模型,能够较准确地预测管内水介质由过冷到过热的全流型流动沸腾传热过程,计算的“干涸”点位置及壁面峰值温度与实验值符合较好,最大误差小于10%;基于欧拉两流体多相流模型与CHF壁面沸腾模型的数值方法对多管耦合工况有较好的适用性,计算的二次侧温度与实验结果吻合良好;两相间曳力对壁面温度及空泡份额的计算结果有较明显的影响,但非曳力对壁面温度的影响较小,因此对于大规模工程应用计算,可在分析中不考虑部分相间非曳力的影响。本文研究结果可为OSTG的三维精细化数值分析的模型选择提供有益参考。Aiming at the problems of high difficulty in simulation,low computational efficiency,and large uncertainties when applying the method of computational fluid dynamics(CFD)to the analysis of coupled heat transfer on primary and secondary sides and full-regime flow boiling heat transfer in once-through steam generator(OTSG),based on the Eulerian two-fluid multiphase model and the critical heat flux density(CHF)wall boiling model,a numerical analysis model of the full-regime flow boiling heat transfer in the tube is established,and the effectiveness of the model is verified.Based on the verified model,the application characteristics of the numerical model under multi-tube coupling heat transfer are studied,the reliability of the numerical simulation method under multi-tube coupling is clarified,and the sensitivity of the calculation results of temperature and phase distribution to the interphase force model is numerically analyzed.The results show that based on Euler's two-fluid multiphase flow model and CHF wall boiling model,the full-regime flow boiling heat transfer process of water in the tube from supercooling to overheating can be predicted accurately.The location of dry-out point and the peak temperature of the wall are in good agreement with the experimental values,with a maximum error of less than 10%.The numerical method based on Euler two-fluid multiphase flow model and CHF wall boiling model has good applicability to multi-tube coupling conditions,and the calculated secondary side temperature is in good agreement with the experimental results.The interphase drag force has obvious influence on the calculation results of wall temperature and cavitation share,but the nondrag force has little influence on wall temperature.Therefore,for large-scale engineering application calculation,the influence of some interphase non-drag forces may not be considered in the analysis.The results of this paper can provide useful reference for the model selection of OSTG's threedimensional refined numerical analysis.

关 键 词：直流蒸汽发生器(OSTG) 欧拉两流体多相流模型 流动沸腾 耦合换热 数值模拟 

分 类 号：TL334[核科学技术—核技术及应用] O368[理学—流体力学]