核电站汽水管道流动加速腐蚀的影响因素分析及对策  

Cause Analysis on FAC Failures of Steam/Water Piping in Secondary Loop of PWR Power Plants and the Countermeasures

作　　者：张桂英[1] 顾宇[1] 邵杰[1] 

机构地区：[1]国核电力规划设计研究院,北京100094

出　　处：《动力工程学报》2012年第2期170-176,共7页Journal of Chinese Society of Power Engineering

摘　　要：针对20世纪80年代以来国际上压水堆核电站二回路发生的因流动加速腐蚀引起的管道破裂事故造成的经济损失和社会影响,介绍了因流动加速腐蚀引起的事故及其造成的影响,进行了有关流动加速腐蚀特征、形成机理和影响因素方面的研究,并针对可以人为控制的因素提出了预防措施和对策,为压水堆核电站设计和运行人员提供因流动加速腐蚀对核安全造成的危害加以预防提供参考.Targeting at the pipe rupture accidents occurring all over the world in the pressurized water reactor（PWR） secondary loop induced by flow accelerated corrosion（FAC） since 1980s,which have led to economic losses and social impact,experimental studies are carried out to analyze the FAC corrosion behavior,formation mechanism and influencing factors,etc.after which preventive measures and strategies are proposed to deal with the FAC resulted from manual mishandling.This may serve as a reference for design and operation of pressurized water reactor（PWR） power plant in the prevention of FAC failures.

关 键 词：压水堆核电站 常规岛 二回路 汽水管道 流动加速腐蚀 

分 类 号：TM623.91[电气工程—电力系统及自动化]