摘要
对AP1000核电厂钢制安全壳的老化机理和影响进行分析,发现存在的潜在老化机理及效应包括:全面腐蚀、点蚀和缝隙腐蚀导致材料损失,循环载荷导致开裂及累计疲劳损伤等。针对钢制安全壳的设计特征和老化机理确定了在役检查规则和无损检测方案,对各类无损检测方法的有效性进行了评估。
Aging mechanisms and effects applicable to Steel containment vessel(SCV)in AP1000 nuclear power plant have been investigated.The potential Aging mechanisms and effects of SCV includes:loss of material due to general,pitting and crevice corrosion,cracking due to stress corrosion cracking or cyclic loading,cumulative fatigue damage,etc.According to AP1000 SCV design features and degradation mechanism,the in-service inspection rules and non-destructive examination has been determined.
出处
《无损探伤》
2016年第2期19-22,共4页
Nondestructive Testing Technology
关键词
钢制安全壳
老化机理
在役检查
无损检测
Steel Containment Vessel
Aging Mechanism
In-service Inspection
Non-destructive Examination