The U.S. Department of Energy could use Alloy 22 as the waste package outer container material for long-term disposal of high-level nuclear waste at the potential Yucca Mountain repository. In the repository emplacement drift the waste packages may be exposed to stress levels and chemical environments that could induce stress corrosion cracking. In this paper, a criterion for stress corrosion cracking is defined. Conditions that can promote stress corrosion cracking of mill-annealed Alloy 22 are identified by analyzing the corrosion potential model as well as possible environmental chemistries arising from seepage water in the emplacement drift. In addition, an abstracted model for stress corrosion cracking of mill-annealed Alloy 22 has been developed using slow strain rate test data. The proposed model accounts for certain chemical species, temperature, pH, and stress corrosion cracking potential. Cyclic potentiodynamic polarization tests in solutions containing chloride, bicarbonate, and carbonate ions were performed to demonstrate a plausible correlation between peak anodic potential and stress corrosion cracking potential.

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