摘要
划伤过程使690合金局部产生严重变形区，背散射电子衍射及透射电镜观察发现，该区域初始晶粒出现细化．在330℃含铅碱溶液中的浸泡试验表明，划伤侧边出现沿机械孪晶界生长的应力腐蚀裂纹柬；在高温高纯水中持续浸泡发现，已有裂纹仍快速向基体延伸。材料表面或裂纹路径残留的微量铅仍促进应力腐蚀裂纹或裂纹柬的持续快速生长。研究结果为蒸汽发生器传热管的研发、制造安装、以及寿命管理等方面提供重要参考。
The stress corrosion EBSD, TEM and high-temperature cracking （SCC） behavior of scratched and high-pressure immersion tests. It Alloy 690 was studied by using was found that highly deformed zone was produced during scratching process. EBSD and TEM results show that original grains around the scratch groove are refined. SCC tests for scratched Alloy 690 were performed in lead-contaminated caustic solution and high purity water at high temperature in succession. The results show that a bundle of SCC cracks grew along mechanical twin boundaries and the cracks continuously extended in high purity water. A small amount of residual lead on surface of Alloy 690 or crack path could accelerate crack growth. This result of scratch-induced SCC will contribute to research and development, manufacture and installation, and lifetime management of steam generator tubes.
出处
《核电工程与技术》
2013年第1期13-17,共5页
Nuclear Power Engineering and Technology
