首页> 外文会议>ASME Pressure Vessels Piping Conference >THERMAL AGING ASSESSMENT AND MICROSTRUCTURAL INVESTIGATIONS OF ALLOY 52 DISSIMILAR METAL WELDS FOR NUCLEAR COMPONENTS
【24h】

THERMAL AGING ASSESSMENT AND MICROSTRUCTURAL INVESTIGATIONS OF ALLOY 52 DISSIMILAR METAL WELDS FOR NUCLEAR COMPONENTS

机译:合金成分的合金52异种金属焊缝的热时效评估和微观结构研究

获取原文

摘要

Dissimilar Metal Welds (DMW) are commonly found between the ferritic low alloy steel heavy section components and the austenitic stainless steel piping sections in nuclear power plants. In the EPR™ design which is the latest FRAMATOME Pressurized water reactor (PWR) these DMW involve a narrow gap technology with no buttering, and only one bead per layer of a nickel base alloy weld filler metal (Alloy 52). In order to assess the thermal aging performance of this relatively new narrow gap DMW design, a significant internal R&D program was launched some years ago. Several representative mock-ups were thoroughly characterized in the initial condition as well as in the thermal aged condition, up to 50,000 hours aging at 350°C. The characterisations were focused on the fusion line between the ferritic low alloy steel (LAS) and the nickel base alloy since a particular microstructure is present in this area, especially in the carbon depleted area of the Heat Affected Zone (HAZ) which is often regarded as the weak zone of the weld joint. Metallography, hardness, nanohardness, chemical analyses, and Atom Probe Tomography, as well as fracture toughness tests were carried out on different specimens in different thermal aging conditions. The results show that the fracture toughness behaviour in the ductile-brittle domain of the low alloy steel carbon depleted HAZ at the interface with the alloy 52 weld metal of the DMWs is excellent, even for a thermal ageing equivalent to 60 years at service temperature. This was found in spite of the carbon depleted zone of the HAZ, the variations of hardness, chemical composition, particularly the carbon gradients, and the thermal aging effect induced by phosphorous segregation at grain boundaries.
机译:核电厂中,铁素体低合金钢重截面部件与奥氏体不锈钢管道截面之间通常会发现异种金属焊缝(DMW)。在最新的FRAMATOME压水反应堆(PWR)的EPR™设计中,这些DMW涉及一种窄间隙技术,无黄油,每层镍基合金焊接填充金属(合金52)仅含一个焊缝。为了评估这种相对较新的窄间隙DMW设计的热老化性能,几年前启动了一项重要的内部研发计划。在初始条件和热老化条件下,在350°C时效高达50,000小时的老化条件下,已对几种具有代表性的模型进行了全面表征。这些特征集中于铁素体低合金钢(LAS)和镍基合金之间的熔合线,因为该区域存在特定的显微组织,特别是在热影响区(HAZ)的碳贫化区域,这通常被认为是作为焊接接头的薄弱区域。在不同的热老化条件下,对不同的样品进行了金相,硬度,纳米硬度,化学分析和原子探针断层扫描以及断裂韧性测试。结果表明,即使在使用温度下相当于60年的热时效,低合金钢碳贫化的热影响区在与DMW合金52焊缝金属的界面处的韧性-脆性区的断裂韧性行为也非常好。尽管存在热影响区的碳耗尽区域,硬度,化学成分(尤其是碳梯度)的变化以及由晶界处的磷偏析引起的热老化效应,但仍发现了这一点。

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