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作 者:汪宇[1] 陈志辉[1] 郝承明[1] 孙燕[1] 黄伟[1]
机构地区:[1]中国核动力研究设计院反应堆系统设计技术重点实验室,成都610213
出 处:《核动力工程》2016年第1期86-90,共5页Nuclear Power Engineering
摘 要:以模块化小型压水堆(ACP100)非能动余热排出系统为对象,建立系统进口管段一维传热模型,研究进口管段传热特性及系统泄漏瞬态,一维模型计算结果与三维模型基本吻合。分析结果表明,温度计测点设置在进口管高点下游的0.3 m外可以避免热源的影响;通过温度可以监测和量化泄漏率,泄漏率越高,测点最高温度就越大;当泄漏率高于8×10^(-4) m^3/h时,可以忽略泄漏过程中轴向传热的影响。Heat transfer model of inlet tube is established for Small PWR (ACP100) passive residual heat removal system. The heat transfer mechanism for the leakage of inlet line and passive residual system is researched. The results show that the temperature instrument located more than 0.3 m below the inlet line high point is evaluated sufficient to avoid the effect of the source. It is effective to detect and quantify the leaks by temperature monitor. Increasing the leak rate, the maximum temperature measured by the instrument tends to increase. For the leakage above 8× 10-4 m3/h, the effect of axial heat flux can be disregarded without affecting significantly the calculation.
分 类 号:TL33[核科学技术—核技术及应用]
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