首页> 外文会议>ASME Pressure Vessels and Piping Conference >A52M/SA52 DISSIMILAR METAL RPV REPAIR WELD: EXPERIMENTAL EVALUATION AND POST-WELD CHARACTERIZATIONS
【24h】

A52M/SA52 DISSIMILAR METAL RPV REPAIR WELD: EXPERIMENTAL EVALUATION AND POST-WELD CHARACTERIZATIONS

机译:A52M / SA52异种金属RPV修复焊接:实验评估和焊接后特征

获取原文

摘要

Aging management of the existing fleet of nuclear power plants is becoming an increasingly important topic, especially as many units are approaching their design lifetimes or are entering long-term operation. As these plants continue to age, there is an increased probability for the need of repairs due to extended exposure to a harsh environment. It is paramount that qualified and validated solutions are readily available. A repair method for a postulated through cladding crack into the low alloy steel of a nuclear power plant's reactor pressure vessel has been investigated in this study. This paper is part of larger study that evaluates the current possibilities of such repair welds. The present paper documents the weld-trials and method selection. A parallel paper describes numerical simulations and optimization of weld parameters. The presented weld-trial represents a case where a postulated crack has been excavated and repaired using a nickel base Alloy 52M filler metal by gas metal arc welding-cold metal transfer with a robotic arm. A SA235 structural steel has been used as a base material in this weld-trial. No pre-heating or post-weld heat treatment will be applied, as it would be nearly impossible to apply these treatments in a reactor pressure vessel repair situation. While Alloy 52M presents good material properties, in terms of resistance to environmentally assisted degradation mechanisms, such as primary water stress corrosion cracking, it is notoriously difficult to weld. Some difficulties and challenges during welding include a sluggish weld puddle, formation of titanium and/or aluminium oxides and its susceptibility to lack of fusion defects and weld metal cracking, such as ductility dip cracking and solidification cracking. Moreover, gas metal arc welding-cold metal transfer is not traditionally used in the nuclear industry. Nonetheless, it presents some interesting advantages, specifically concerning heat input requirements and automation possibilities, as compared to traditional welding methods. The mechanical properties, in terms of indentation hardness, and microstructure of a weld-trial sample have been evaluated in this study. The fusion boundary and heat affected zone were the main areas of focus when evaluating the mechanical and microstructural properties. Detailed microstructural characterization using electron backscatter diffraction and nanoindentation were performed across the weld interface. Based on these results, the gas metal arc welding cold metal transfer is seen as a potential high-quality weld method for reactor pressure vessel repair cases.
机译:现有核电站现有舰队的老化管理正在成为一个越来越重要的话题,特别是随着许多单位正在接近其设计寿命或正在进行长期运行。随着这些植物持续到年龄,由于延长暴露于恶劣环境,需要增加维修的概率。这是最重要的,合格和验证的解决方案很容易获得。本研究研究了通过覆层裂纹的修复方法,通过包层裂纹进入核电厂反应器压力容器的低合金钢。本文是较大研究的一部分,可评估这种修复焊缝的当前可能性。本文记录了焊接试验和方法选择。平行纸张介绍了焊接参数的数值模拟和优化。所提出的焊接试验代表了通过用机器人臂的气体金属电弧焊接冷金属转移使用镍基合金52M填充金属挖掘和修复假设裂缝和修复的情况。 SA235结构钢已被用作该焊接试验中的基材。没有预热或焊后热处理将应用,因为在反应器压力容器修复情况下几乎不可能应用这些处理。虽然合金52M呈现出良好的材料特性,但在对环境辅助降解机制的抵抗方面,例如初级水胁迫腐蚀裂缝,难以焊接难以焊接。焊接期间的一些困难和挑战包括缓慢的焊接水坑,钛和/或氧化铝的形成及其对缺乏融合缺陷和焊接金属裂缝的敏感性,例如延展性浸渍裂解和凝固裂解。此外,核工业传统上不使用气体金属弧焊冷金属转移。尽管如此,与传统焊接方法相比,它呈现出一些有趣的优势,特别是关于热量输入要求和自动化可能性。在本研究中已经评估了焊接试验样品的压痕硬度和微观结构的机械性能。融合边界和热影响区域是评估机械和微观结构性质时的主要焦点。使用电子反向散射衍射和纳米狭窄的详细微观结构表征在焊接界面上进行。基于这些结果,气体金属电弧焊接冷金属转移被视为电抗器压力容器修复壳体的潜在高质量焊接方法。

著录项

相似文献

  • 外文文献
  • 中文文献
  • 专利
获取原文

客服邮箱:kefu@zhangqiaokeyan.com

京公网安备:11010802029741号 ICP备案号:京ICP备15016152号-6 六维联合信息科技 (北京) 有限公司©版权所有
  • 客服微信

  • 服务号