Non-Destructive Examination of PWR Steam Generator Tube-Tube Plate Welds After Repairing Melting Damage

Yan Zhang, JianLei Zhang, Zhonghe Cheng
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引用次数: 1

Abstract

The tube-tube plate weld is the boundary weld that separates the primary and secondary circuits of the Pressurized Water Reactor (PWR) Steam Generator and is the weakest link of the Steam Generator. If the weld leaks, the media that may be contaminated by radiation in the primary circuit may flow into the secondary circuit, resulting in a nuclear leakage event. Therefore, the welding quality of the weld is directly related to the safety of the nuclear power site and requires special attention during the manufacturing process. The tube-tube plate weld of the PWR Steam Generator generally uses non-filled wire self-fusion welding technology. In addition to common welding defects such as pores, incomplete penetration, and cracks during the welding process, melting damage may sometimes occur due to improper operation. Since the melt loss repair involves both the tube plate surfacing layer and the tube-to-tube plate sealing weld, the repair process is much more complicated. There is little experience in the successful implementation of non-destructive inspection after melting damage repair. How to remove the defects? Which non-destructive examination methods should be selected in the repair process to ensure the defect removal effect? How to weld repair after the defect removal? Which nondestructive examination techniques should be selected during the repair process to ensure the repair effect? How to conduct final non-destructive testing after repair to confirm Rework quality? These are urgent issues. In this paper, by using tube-tube plate weld samples to carry out melting damage repair simulation experiments. After repairing, the penetration examination and the radiographic examination have been successfully implemented, and good results have been achieved.
压水堆蒸汽发生器管板焊缝熔损修复后的无损检测
管板焊缝是压水堆蒸汽发生器一次回路和二次回路之间的边界焊缝,是蒸汽发生器最薄弱的环节。如果焊缝发生泄漏,一次回路中可能被辐射污染的介质就会流入二次回路,造成核泄漏事件。因此,焊缝的焊接质量直接关系到核电现场的安全,在制造过程中需要特别注意。压水堆蒸汽发生器的管板焊缝一般采用无填充丝自熔焊接技术。焊接过程中除了常见的气孔、熔透不全、裂纹等焊接缺陷外,有时还会因操作不当而造成熔化损伤。由于熔损修复既涉及到管板堆焊层,又涉及到管板间密封焊缝,因此修复过程要复杂得多。熔损修复后的无损检测成功实施的经验很少。如何去除缺陷?在修复过程中应选择何种无损检测方法,以保证缺陷的去除效果?缺陷消除后如何进行焊缝修复?在修复过程中应选择哪些无损检测技术来保证修复效果?返修后如何进行最终无损检测以确认返工质量?这些都是紧迫的问题。本文通过利用管-管板焊缝试样进行熔毁损伤修复模拟实验。修复后成功进行了侵彻检查和x线检查,取得了良好的效果。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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