Investigation on residual stress in dissimilar steel weld for nuclear steam generators

ZHANG Junbao; GE Keke; XU Lianyong

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Investigation on residual stress in dissimilar steel weld for nuclear steam generators

Thermal Power Generation Issue 2, (2017)

更新时间：2025-09-28

- Investigation on residual stress in dissimilar steel weld for nuclear steam generators
- 作者机构：
  
  1. 上海核工程研究设计院,上海,200233
  2. 天津大学材料科学与工程学院,天津,300072
- 作者简介：
- 基金信息：
- DOI：
  CLC： TG404
- Published Online：01 March 2017，
  
  Published：2017
- 稿件说明：
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ZHANG Junbao, GE Keke, XU Lianyong. Investigation on residual stress in dissimilar steel weld for nuclear steam generators[J]. Thermal Power Generation, 2017, (2).
DOI：

ZHANG Junbao, GE Keke, XU Lianyong. Investigation on residual stress in dissimilar steel weld for nuclear steam generators[J]. Thermal Power Generation, 2017, (2). DOI：

摘要

为更好地预测核电站蒸汽发生器安全端异种钢焊接接头的残余应力状态

保障设备的安全运行

采用有限元分析软件

在充分考虑材料的热物理性能和力学性能的前提下

完成了核电站蒸汽发生器水室下封头的冷却剂出口低合金钢接管SA508和不锈钢安全端CF8A的异种钢焊接接头的应力场计算；采用盲孔法测量对接管内外壁的残余应力

并与模拟值进行比较。结果表明:轴向残余应力的实测值与模拟值吻合度较高

同时也证明了模拟方法的准确性；从试样的整体残余应力分布状态可知

轴向和周向残余高应力区主要分布在内外壁两侧隔离堆焊层及热影响区(HAZ)

此处属于发生应力腐蚀开裂的危险位置。

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