首页> 外文会议>International conference on environmental degradation of materials in nuclear power systems-water reactors >Characterization of Materials Properties and Crack Propagation Mechanisms in Damaged Alloy 718 Leaf Springs Following Commercial Reactor Exposure
【24h】

Characterization of Materials Properties and Crack Propagation Mechanisms in Damaged Alloy 718 Leaf Springs Following Commercial Reactor Exposure

机译:商业反应器暴露后受损合金718叶片弹簧中材料特性及裂纹繁殖机制的特征

获取原文

摘要

In this work, damaged leaf spring arms were discovered during refuelling outages in a pressurized water reactor following operations to >45 MWd/mtU burn-up. Two LS assemblies were transferred to Oak Ridge National Laboratory for inspection and detailed characterization of their mechanical and microstructural properties. The irradiated material is evaluated and compared to archival samples. Post irradiation microstructural examination includes changes to precipitate phases, solute redistribution following in-service exposure, and the characterization of the cracked regions of the leaf spring materials. For irradiated samples, crack propagation routes are examined through detailed microscopy analysis (TEM, SEM-EBSD), including focused ion beam milling of sections near the crack tip locations for transmission electron microscopy. Statistics on cracked/non-cracked grain boundary types (twins, random low- and high-angle) is discussed. The role of grain boundary precipitation of the delta-Ni_3Nb phase on the material performance is also discussed.
机译:在这项工作中,在将加压水反应堆中的加油中的停电期间发现了损坏的叶子弹簧臂,在操作之后> 45 mWd / mTU烧伤。将两个LS组件转移到Oak Ridge National实验室进行检查,并详细表征其机械和微观结构性质。评估辐照材料并与归档样品进行比较。后辐射微结构检测包括沉淀阶段的变化,溶质在在役暴露后溶质再分配,以及叶子弹簧材料的裂纹区域的表征。对于辐照样品,通过详细的显微镜分析(TEM,SEM-EBSD)检查裂缝传播路线,包括剖面离子束铣削近透射电子显微镜的裂缝尖端位置附近的部分。讨论了裂纹/非破裂晶粒边界类型(双胞胎,随机低和高角度)的统计。还讨论了Delta-Ni_3NB相对材料性能的晶粒边界沉淀的作用。

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