期刊文献+

钢制安全壳及其附件的在役检查和无损检测

Steel Containment Vessel and attachment In-service Inspection and Non-destructive Examination
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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.
作者 王震亚
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
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参考文献8

  • 1NRC Information Notice 2011- 15, Steel Containment Degradation and Associated License Renewal Aging Management Issues[-S~.
  • 2NRC Information Notice 2010- 12, Containment Liner CorrosionES~.
  • 3NRC Information Notice 1989- 79, Degraded Coatings and Corrosion of Steel Containment VesselsES~.
  • 4IAEA-- TECDOC-- 1025, Assessment and management of ageing of major nuclear power plant components im- portant to safety: Concrete containment buildingsES~.
  • 5NUREG 1801, Generic Aging Lessons I.earned (GALL) ReportES~.
  • 6ASME Boiler and Pressure Vessel Code Section XI 2018, Rules for In--Service Inspection of Nuclear Power Plant ComponentsES~.
  • 7EPRI Report 1000105, Experimental Validation of Con- crete Effects on Guided Waves in Plates[-S}.
  • 8Li J, Rose J L, L J. Guided Wave Inspection of Contain- ment Structures 2JJ. Materials Evaluation, 2001, 59 (6) : 783-787.

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