Analysis of Weld Overlay Residual Stress for Dissimilar Metal Welds in Qinshan Nuclear Power Plant
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摘要: 核电厂一回路系统设备的接管嘴与管道的焊缝结构广泛应用合金81/182,该类焊缝为异种金属焊(DMW),DMW焊缝对一次侧水应力腐蚀(PWSCC)较为敏感,运行过程中易发生裂纹泄漏等问题。堆焊修复方法在国外核电处理该类问题得到广泛应用。本文基于秦山一期核电厂稳压器喷雾管接管嘴尺寸,建立轴对称有限元模型,采用生死单元模拟焊接过程的瞬态热输入,研究了结构在堆焊修复过程中温度场的变化分布特性,将计算得到的结构热分布历程作为热载荷,进而获得了堆焊修复过程中结构残余应力的变化特性,结果表明堆焊修复完成后,DMW焊缝区域内壁的残余应力能够起到控制PWSCC的作用。Abstract: Alloy 82/182 were used extensively in PWR primary coolant system as the DMW weld structure for the pipe nozzle and pipelines. The dissimilar metal welds(DMW) easily appears cracking due to the stress corrosion and fatigue after long operation. Based on the service data from foreign nuclear powers, the primary water stress corrosion(PWSCC) is the major factor for cracking, which is sensitive to the stress of pipe inside surface. The structural weld overlay repair is an appropriate way to repair the operating nuclear reactor piping according to the international experiences. Based on the nozzle of Qingshan nuclear power phase I, the axis symmetric FE model was set up to simulate the welding procedures and obtain the thermal field and residual stress field at the area of DMW weld by ANSYS finite element analysis software. The residual stress analysis indicated that PWSCC will be prevented by the resulted inside surface stresses after weld overlay.
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Key words:
- Qinshan nuclear plant /
- Axial symmetrical /
- Residual stress /
- Overlay weld repair
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