材料科学
晶间腐蚀
应力腐蚀开裂
晶界
冶金
合金
腐蚀
微观结构
辐照
压力(语言学)
奥氏体
奥氏体不锈钢
核物理学
语言学
物理
哲学
作者
Gary S. Was,Chi Bum Bahn,Jeremy T. Busby,Bai Cui,Diana Farkas,Maxim N. Gussev,Mathematician He,Justin Hesterberg,Zhijie Jiao,D.C. Johnson,Wenjun Kuang,Michael D McMurtrey,I.M. Robertson,Abdullah Sinjlawi,Miao Song,Kale J. Stephenson,Kai Sun,Srinivasan Swaminathan,M. Wang,E. West
标识
DOI:10.1016/j.pmatsci.2024.101255
摘要
Irradiation assisted stress-corrosion cracking (IASCC) is a form of intergranular stress corrosion cracking that occurs in irradiated austenitic alloys. It requires an irradiated microstructure along with high temperature water and stress. The process is ubiquitous in that it occurs in a wide range of austenitic alloys and water chemistries, but only when the alloy is irradiated. Despite evidence of this degradation mode that dates back to the 1960s, the mechanism by which it occurs has remained elusive. Here, using high resolution electron backscattering detection to analyze local stress-strain states, high resolution transmission electron microscopy to identify grain boundary phases at crack tips, and decoupling the roles of stress and grain boundary oxidation, we are able to unfold the complexities of the phenomenon to reveal the mechanism by which IASCC occurs. The significance of the findings impacts the mechanical integrity of core components of both current and advanced nuclear reactor designs worldwide.
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