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Localized Corrosion Susceptibility of Alloy 22 as a Waste Package Container Material

Published online by Cambridge University Press:  21 March 2011

Gustavo A. Cragnolino
Affiliation:
Center for Nuclear Waste Regulatory Analyses, Southwest Research Institute 6220 Culebra Road San Antonio, TX 78238-5166, U.S.A.
Darrell S. Dunn
Affiliation:
Center for Nuclear Waste Regulatory Analyses, Southwest Research Institute 6220 Culebra Road San Antonio, TX 78238-5166, U.S.A.
Yi-Ming Pan
Affiliation:
Center for Nuclear Waste Regulatory Analyses, Southwest Research Institute 6220 Culebra Road San Antonio, TX 78238-5166, U.S.A.
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Abstract

Alloy 22 is the material preferred by the U.S. Department of Energy for the waste package outer container for geological disposal of high-level radioactive waste at the proposed repository site in Yucca Mountain, Nevada. The susceptibility of Alloy 22 to localized corrosion is an important consideration in the evaluation of the waste package behavior and the assessment of the overall performance of the proposed repository. The effects of the environment chemical composition and temperature on localized corrosion susceptibility were examined by measuring the repassivation potential for crevice corrosion in chloride-containing solutions at temperatures ranging from 80 to 150°C. The effect of potentially inhibiting anionic species, such as nitrate, was also determined. In addition to the mill annealed material, tests were conducted on both welded and thermally aged material to evaluate microstructural effects related to container fabrication processes. The resistance of Alloy 22 to localized corrosion decreased with increasing temperature and chloride concentration. Welding and thermal aging also decreased the localized corrosion resistance of the alloy.

Type
Research Article
Copyright
Copyright © Materials Research Society 2002

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