Donghai Du , Tenghong Lin , Mi Wang , Miao Song , Hefei Huang , Gary S. Was
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引用次数: 0
Abstract
Oxidized grain boundaries (GBs) in Alloy 690 samples from both unirradiated and irradiated regions were systematically characterized following constant extension rate tensile testing in a simulated pressurized water reactor primary water environment. Comparative analysis revealed distinct degradation mechanisms: significant chromium depletion occurred at carbide-free GBs, while crack initiation predominated at carbide-decorated GBs in irradiated specimens. Notably, irradiated regions exhibited substantially higher strain localization at both GBs and carbide/matrix interfaces compared to unirradiated GBs. These observations demonstrate that irradiation enhances stress corrosion cracking susceptibility through two synergistic mechanisms: radiation-enhanced diffusion along GBs and intensified strain localization at carbide/matrix interfaces.
期刊介绍:
Corrosion occurrence and its practical control encompass a vast array of scientific knowledge. Corrosion Science endeavors to serve as the conduit for the exchange of ideas, developments, and research across all facets of this field, encompassing both metallic and non-metallic corrosion. The scope of this international journal is broad and inclusive. Published papers span from highly theoretical inquiries to essentially practical applications, covering diverse areas such as high-temperature oxidation, passivity, anodic oxidation, biochemical corrosion, stress corrosion cracking, and corrosion control mechanisms and methodologies.
This journal publishes original papers and critical reviews across the spectrum of pure and applied corrosion, material degradation, and surface science and engineering. It serves as a crucial link connecting metallurgists, materials scientists, and researchers investigating corrosion and degradation phenomena. Join us in advancing knowledge and understanding in the vital field of corrosion science.