核电站凝汽器单列运行安全性评价方法研究

Study on Safety Evaluation of Condenser Half Train Operation in Nuclear Power Plant

国内核电站凝汽器发生多起钛管断裂事件,分析显示支撑板跨距偏大是主要原因之一。对美国热交换学会(HEI)凝汽器标准的跨距计算方法适用范围进行探讨,指出核电厂凝汽器在冬季半列等特殊运行工况下热力参数超过标准的适用要求,并提出凝汽器多工况下跨距的修正计算算法。核电厂凝汽器跨距的设计可采用该修正算法,并结合支撑板实际合理的安装情况,综合选取较为保守的方案。结合凝汽器传热学模型和流体弹性激振模型,建立了某核电站凝汽器全年不同海水温度下的单列运行电功率指导图。

Many titanium tubes fracture events have occurred in nuclear power condensers. The root cause analysis shows that the large spacing design of support plate is one of the important reasons. By comparing different spacing calculation methods, the application scope of American Heat Exchange Institute(HEI) condenser standard is discussed, and points out that the thermal parameters of condenser in nuclear power plant exceed the applicable requirements of standard under special operating conditions. It is suggested that design of condenser spacing in nuclear power plant should adopt the correction algorithm under various working conditions, and comprehensively select a more conservative scheme in combination with actual and reasonable installation of support plate. Combined with the condenser thermodynamics and fluid elastic excitation model, the condenser half train operation power guide diagram of the nuclear power plant under different seawater temperatures throughout the year is established.