Abstract
The V-7.2Cr-14.5Ti, V-9.2Cr-4.9Ti, V-9.9Cr-9.2Ti, V-13.5Cr-5.2Ti, V-4.1Cr-4.3Ti, Vanstar-7, V-4.6Ti, V-17.7Ti, V-10.0Ti, V-3.1Ti-(0.5-1.0)Si, and V-2.5Ti-1.0Si alloys were evaluated for use as structural material in fusion reactors. The alloys were evaluated on the basis of their unirradiated and neutron-irradiated yield strength; swelling resistance; ductile-brittle transition temperature; resistance to hydrogen, helium, and irradiation embrittlement; and compatibility with a lithium reactor coolant. On the basis of these evaluations, alloys of V-(0–7)Cr-(5–10)Ti-(0–1)Si are recommended for more intensive evaluation for use as structural material in fusion reactors.
Published Version
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 call