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Corrosion Processes Affecting the Performance of Alloy 22 as a High-Level Radioactive Waste Container Material

Published online by Cambridge University Press:  21 March 2011

G.A. Cragnolino
Affiliation:
Center for Nuclear Waste Regulatory Analyses (CNWRA), Southwest Research Institute 6220 Culebra Road, San Antonio, TX, 78238-5166, USA Email: gcragno@swri.edu
D.S. Dunn
Affiliation:
Center for Nuclear Waste Regulatory Analyses (CNWRA), Southwest Research Institute 6220 Culebra Road, San Antonio, TX, 78238-5166, USA Email: gcragno@swri.edu
Y.-M. Pan
Affiliation:
Center for Nuclear Waste Regulatory Analyses (CNWRA), Southwest Research Institute 6220 Culebra Road, San Antonio, TX, 78238-5166, USA Email: gcragno@swri.edu
O. Pensado
Affiliation:
Center for Nuclear Waste Regulatory Analyses (CNWRA), Southwest Research Institute 6220 Culebra Road, San Antonio, TX, 78238-5166, USA Email: gcragno@swri.edu
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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 site in Yucca Mountain, Nevada. Alloy 22 is considered to be extremely resistant to various modes of aqueous corrosion over broad ranges of temperature, pH, and concentration of anionic and oxidizing species. Uniform corrosion under passive dissolution conditions, localized corrosion in the form of crevice corrosion, and stress corrosion cracking are discussed on the basis of experimental results obtained with mill annealed, thermally treated, and welded specimens using electrochemical techniques. The approach developed for long-term performance prediction, including the use of empirically derived parameters for assessing localized corrosion and the modeling of the passive dissolution behavior, is described.

Type
Research Article
Copyright
Copyright © Materials Research Society 2001

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References

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