Article ID | Journal | Published Year | Pages | File Type |
---|---|---|---|---|
5440002 | Corrosion Science | 2017 | 11 Pages |
Abstract
This study considered a methodology to reflect the effect on material properties by neutron irradiation onto the FRI model of the crack growth rate (CGR) of stress corrosion cracking developed at Tohoku University. Yield strength and strain hardening exponent were evaluated by a tensile test for irradiated stainless steels, and the relationship between mechanical property and strain to fracture of the oxide film was derived. Effect of the radiation-induced segregation on CGR was also discussed. The experimental tendencies for the CGR to increase with dose and almost saturate above 3Â dpa were well replicated by the model calculations.
Keywords
Related Topics
Physical Sciences and Engineering
Materials Science
Ceramics and Composites
Authors
Masato Koshiishi, Tsuneyuki Hashimoto, Ryoji Obata,