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机构地区:[1]上海核工程研究设计院,上海200233 [2]上海核工程研究设计院,上海市核电工程重点实验室,上海200233
出 处:《核技术》2013年第4期126-130,共5页Nuclear Techniques
摘 要:通过对某核电厂承压设备在役检查发现缺陷后的处理计算,阐述了基于线弹性断裂力学机理的裂纹扩展的计算分析和评定方法,计算方法中考虑了缺陷深度和长度的耦合作用。并在此基础上,运用Visual C++语言,开发裂纹扩展计算程序。程序内全面考虑了反应堆冷却剂系统(RCS)一次侧设计瞬态、反应堆冷却剂系统二次侧设计瞬态的交变载荷及缺陷初始形状、方位分类等问题,适用范围广泛。本文的计算方法及评定方法为电厂管道在役检修和能否继续运行提供重要依据。Background: The crack will grow gradually under alternating load for a pressurized pipe, whereas the load is less than the fatigue strength limit. Purpose: Both calculation and evaluation methodology for a flawed pipe that have been detected during in-service inspection is elaborated here base on the Elastic Plastic Fracture Mechanics (EPFM) criteria. Methods: In the compute, the depth and length interaction of a flaw has been considered and a compute program is developed per Visual C++. Results: The fluctuating load of the Reactor Coolant System transients, the initial flaw shape, the initial flaw orientation are all accounted here. Conclusions: The calculation and evaluation methodology here is an important basis for continue working or not.
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