第36卷第5期 2016年10月
核科学与工程
Nuclear Science and Engineering
Vol.36
No.5 Oct.2016
蒸汽发生器二次侧两相流传热特性数值研究
刘乐，黄禹，徐良旺
（深圳中广核工程设计有限公司上海分公司，上海200241)
摘要：以AP1000核电站蒸汽发生器为原型，建立蒸汽发生器二次侧"平均通道”模型，利用计算流体动力学软件ANSYSCFX，基于相界面模型对燕汽发生器二次侧两相流流动和沸腾换热过程进行研究。结果表明：数值模拟计算方法能准确模拟蒸汽发生器二次侧汽液两相流沸胖和传热过程；满负荷运行时，流体由预热区经过泡核沸腾区过渡到稳定沸腾区，含汽率和传热系数沿流动方向逐渐增大，出口含汽率与该型号蒸汽发生器设计值符合较好，平均传热系数的模拟结果和Jens&Lottes经验关联式的预测值基本一致。
关键调：蒸汽发生器；CFX；汽液两相流；传热特性
中图分类号：TL333
文章标志码：A
文章编号：0258-0918(2016)05-0611-06
Numerical Study on heatTransferCharacteristicof two-phase
flowinSGSecondaryside LIU Le, HUANG Yu, XU Liang-wang
(China Nuclear Power Design Co. ,Ltd. (Shenzhen), Shanghai Branch, Shanghai 200241,China
Abstract:Taking the steam generator in AP1ooo Nuclear Power Plant as the prototype, the "Average channel" model of SG secondary side was built. Based on the two-phase interface model, the two-phase flow and heat transfer in SG secondary side were analyzed by software ANSYS CFX.The results show that,it can simulate the phenomenon of boiling and heat transfer in SG by numerical simulation accurately. At full load, the liquid was heated from preheating region to stable boiling region via nucleate boiling region, both vapor fraction and heat transfer coefficient increased gradually along the direction of the flow. the vapor quality fraction at the outlet was largely consistent with the design value, and the average value of heat transfer coefficient which was calculated in this paper was agree with the results of Jens&Lottes empirical correlation generally.
Key words: Steam generator; CFX; Steam liquid two-phase flow; Heat transfer characteristic 修回日期：2015-06-23
作者简介：刘乐（1987一），男，河南驻马店人，工程师，硕士，现从事核反应堆热工水力分析工作
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