A. Udyawar, C. Tomes, Alexandria M. Carolan, S. Marlette, V ThomasL.Meikle, W. Bamford
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摘要

这一目标是通过IWB-2500和IWB-3700第11节所载的定期检查和操作工厂标准的要求来实现的。运行中的工厂疲劳问题可能是由运行条件或原始设计中未考虑的特定瞬变引起的。第11节附录L中提供的选项之一是通过使用缺陷容忍度分析。缺陷容忍度评价包括假设缺陷并预测其未来的增长,从而确定其服务期限,使其能够满足第11节的结构完整性要求。缺陷容忍方法的优点是不需要了解循环服务历史,跟踪未来的周期,或安装系统来监视瞬态和周期。裂纹容限评价考虑了适用管道的几何形状、材料、载荷、裂纹扩展机制(如疲劳裂纹扩展)以及检测检测能力。第11节附录L评估的目的是证明反应堆冷却剂管道系统继续保持其结构完整性,并确保工厂的安全运行。
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ASME Section XI Appendix L Flaw Tolerance Evaluation of Pressurized Water Reactor Piping Systems to Support Second License Renewal (80-Years Operation)
One of the goals of ASME Section XI is to ensure that systems and components remain in safe operation throughout the service life, which can include plant license extensions and renewals. This goal is maintained through requirements on periodic inspections and operating plant criteria as contained in Section XI IWB-2500 and IWB-3700, respectively. Operating plant fatigue concerns can be caused from operating conditions or specific transients not considered in the original design transients. ASME Section XI IWB-3740, Operating Plant Fatigue Assessments, provides guidance on analytical evaluation procedures that can be used when the calculated fatigue usage exceeds the fatigue usage limit defined in the original Construction Code. One of the options provided in Section XI Appendix L is through the use of a flaw tolerance analysis. The flaw tolerance evaluation involves postulation of a flaw and predicting its future growth, and thereby establishing the period of service for which it would remain acceptable to the structural integrity requirements of Section XI. The flaw tolerance approach has the advantage of not requiring knowledge of the cyclic service history, tracking future cycles, or installing systems to monitor transients and cycles. Furthermore, the flaw tolerance can also justify an inservice inspection period of 10 years, which would match a plant’s typical Section XI in-service inspection interval. The goal of this paper is to demonstrate a flaw tolerance evaluation based on ASME Section XI Appendix L for several auxiliary piping systems for a typical PWR (Pressurized Water Reactor) nuclear power plant. The flaw tolerance evaluation considers the applicable piping geometry, materials, loadings, crack growth mechanism, such as fatigue crack growth, and the inspection detection capabilities. The purpose of the Section XI Appendix L evaluation is to demonstrate that a reactor coolant piping system continues to maintain its structural integrity and ensures safe operation of the plant.
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