Abstract
As a future material for a fusion first wall, ferritic steels have come to appear more attractive than austenitic steels for their higher swelling resistance. To reduce the degradation in mechanical properties at elevated temperatures, which makes ferritic steels inferior to austenitic steels, the application of stable oxide as strengthening dispersoid has been proposed. In this work, Fe-14Cr-1Ti steel strengthened with 0.25% Y2O3 (MA957) was dual- and single-ion bombarded at High-fluence Irradiation Test (HIT) facility of the University of Tokyo to 150 dpa at 723 and 923 K. Dual-ion irradiation with 1 appm He/dpa produced only small cavities with average diameter less than 3 nm. In 15 appm He/dpa irradiated samples, small bubbles as well as clustered voids were formed, the latter sited in regions where the titanium content was higher than the matrix. The dislocation structure and dispersion was stable, especially under single-ion irradiation, while recovery was observed in dual-ion irradiated specimens.
Sign-in/Register to access full text options 
Talk to us
Join us for a 30 min session where you can share your feedback and ask us any queries you have
Schedule a callDisclaimer: All third-party content on this website/platform is and will remain the property of their respective owners and is provided on "as is" basis without any warranties, express or implied. Use of third-party content does not indicate any affiliation, sponsorship with or endorsement by them. Any references to third-party content is to identify the corresponding services and shall be considered fair use under The CopyrightLaw.
