The localized corrosion susceptibility of Alloy 22, a candidate container material for the disposal of high-level nuclear waste in the proposed repository at Yucca Mountain, Nevada, was assessed in chloride containing solutions at temperatures ranging from 60 to 150C. Tests were conducted using the as-received material in the mill-annealed condition. In addition, the effects of fabrication processes were examined using both as-welded and thermally aged specimens. A comparison of the crevice corrosion repassivation potential and corrosion potential measured in separate tests suggests that fabrication processes and environmental conditions such as temperature and chemical composition of water contacting the waste packages (WPs) may influence the localized corrosion susceptibility of the Alloy 22 containers.
Keywords: Alloy 22, high-level waste, localized corrosion, welding