首页> 外文会议>International conference on nuclear engineering;ICONE5 >RESIDUAL STRESS EVALUATION FOR J-WELDED JOINTS OF REACTOR PRESSURE VESSEL HEAD PENETRATIONS
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RESIDUAL STRESS EVALUATION FOR J-WELDED JOINTS OF REACTOR PRESSURE VESSEL HEAD PENETRATIONS

机译:反应堆压力容器头部侵彻J焊接接头的残余应力评估

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Welding residual stress analysis was conducted for J-welded joints of peripheral head penetrations to verify the reliability of PWR reactor pressure vessels. In the process of this analysis, 3-D thermo-elasto-plastic analysis by FEM was used. Welding process was simplified to one-pass weld. Welding temperature at the inside surface of a pipe was measured for mock-ups, and the residual stress was measured using the strain gauge method. The measured values of the peak temperature and the transient temperature in the process of cooling down almost corresponded to the analytical results. Those of the residual stress were also nearly equal to them. By these correspondences between the analyses and the measurements, the reliability of the simplified analysis was confirmed. The peak temperature appeared near the middle point between the root and toe of the weld and showed at the downhill side of the penetration weld. On the uphill side of the welds, high tensile residual stress at the inside surface of a pipe appeared under the toe. On the downhill side of the welds, however, it appeared under the root. There was a small difference between the peak residual stress at the uphill side and that at the downhill side. Additionally, the residual stress after hydrostatic test condition and that in operated condition were continuously analyzed by using the residual stress after welding. Welding residual stress became lower level after the high internal pressure of hydrostatic test though it appeared higher level after welding. In operating condition after hydrostatic test condition, the value of the residual stress went up to near that after welding. Based onthese results, both the level and trend of the residual stress for J-welded joints of reactor pressure vessel head penetrations were discussed.
机译:对外围头部穿刺的J型焊接接头进行了焊接残余应力分析,以验证压水堆反应堆压力容器的可靠性。在此分析过程中,使用了FEM进行的3-D热弹塑性分析。焊接过程简化为单程焊接。测量管内表面的焊接温度以进行模型化,并使用应变仪方法测量残余应力。冷却过程中峰值温度和过渡温度的测量值几乎与分析结果相对应。那些残余应力也几乎等于它们。通过分析和测量之间的这些对应关系,可以确认简化分析的可靠性。峰值温度出现在焊缝根部和趾部之间的中点附近,并出现在穿透焊缝的下坡侧。在焊缝的上坡侧,在脚趾下方出现了管道内表面的高拉伸残余应力。但是,在焊缝的下坡侧,它出现在根部下方。在上坡侧和下坡侧的峰值残余应力之间存在很小的差异。另外,通过使用焊接后的残余应力来连续地分析静水压试验条件之后的残余应力和在操作条件下的残余应力。静水压力高后,焊接残余应力降低,尽管焊接后应力升高。在水压试验条件之后的工作条件下,残余应力的值上升到接近焊接后的值。基于这些结果,讨论了反应堆压力容器头部贯入的J型焊接接头的残余应力水平和趋势。

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  • 会议地点 Nice(FR);Nice(FR)
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    Mitsubishi Heavy Industries Ltd. Takasago Research & Development Center 2-1-1 Shinhama Arai-cho Takasago 676 JAPAN;

    Kobe Shipyard & Machinery Works Mitsubishi Heavy Industries Ltd. 1-1 Wadasaki-cho 1-chome Hyogo-ku Kobe 652 JAPAN;

    The Kansai Electric Power Co. Inc. 3-3-22 Nakanoshima Kita-ku Osaka 530-70 JAPAN;

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