改进型低温供热堆二次侧非能动余热排出系统不稳定性分析  

Analyses on Flow Instability of Secondary-Side Passive Residual Heat Removal System for Advanced Nuclear Heating Reactor

作　　者：梁卫红 解衡[1] Liang Weihong;Xie Heng(Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing, 100084, China)

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：《核动力工程》2018年第2期14-19,共6页Nuclear Power Engineering

摘　　要：研究了改进型低温供热堆非能动余热排出系统不稳定性问题。采用RELAP5程序计算分析了非能动余热排出系统瞬态响应情况,余热排出系统冷凝管内由于压力与两相段长度不匹配出现冷凝两相流不稳定性。采用RELAP5程序数值计算所得冷凝流动稳定性边界与Bhatt公式理论分析结果符合良好。增大冷凝管入口节流,增加冷凝管流通面积、换热面积,可以避免冷凝流动不稳定性。An advanced nuclear heating reactor model is provided to study the flow instability of secondary-side passive residual heat removal system. The RELAP5 program is used to simulate the transient process of PRHRS after accident. The results show that the origin for the condensate flow instability is the mismatch of vapor pressure and two phase length in the condensate tube of PRHRS. The condensate flow stability boundary calculated numerically by RELAP5 is satisfied with Bhatt＇s theoretical formula analysis results. By increasing the condensate tube inlet throttling, flow area and heat transfer area. the condensate flow instability can be avoided.

关 键 词：改进型低温堆 余热排出系统 流动不稳定性 RELAP5 

分 类 号：TL333[核科学技术—核技术及应用]