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Effect of Inhibiting Oxyanions on the Localized Corrosion Susceptibility of Waste Package Container Materials

Published online by Cambridge University Press:  17 March 2011

D.S. Dunn ,
L. Yang ,
C. Wu  and
G.A. Cragnolino
D.S. Dunn
Affiliation:
ddunn@swri.orgCenter for Nuclear Waste Regulatory Analyses (CNWRA) Southwest Research Institute 6220 Culebra Road, San Antonio, TX 78238-5166, USA
L. Yang
Affiliation:
ddunn@swri.orgCenter for Nuclear Waste Regulatory Analyses (CNWRA) Southwest Research Institute 6220 Culebra Road, San Antonio, TX 78238-5166, USA
C. Wu
Affiliation:
ddunn@swri.orgCenter for Nuclear Waste Regulatory Analyses (CNWRA) Southwest Research Institute 6220 Culebra Road, San Antonio, TX 78238-5166, USA
G.A. Cragnolino
Affiliation:
ddunn@swri.orgCenter for Nuclear Waste Regulatory Analyses (CNWRA) Southwest Research Institute 6220 Culebra Road, San Antonio, TX 78238-5166, USA
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Abstract

The DOE is currently preparing a license application for the permanent disposal of high level radioactive waste at Yucca Mountain, Nevada. The proposed design of waste packages for the disposal of high level radioactive waste consists of an outer container made of Alloy 22, a corrosionresistant Ni-Cr-Mo-W alloy, surrounding an inner container made of Type 316 nuclear grade stainless steel. Under conditions where passivity is maintained, the uniform corrosion rate of Alloy 22 is slow and long waste package lifetimes are projected. However, the initiation of localized corrosion such as pitting or crevice corrosion may decrease waste package lifetimes. In this study the crevice corrosion susceptibility of Alloy22 was determined in chloride solutions with additions of oxyanions that are present in the groundwater at the potential repository site. When present in sufficient concentrations relative to chloride, nitrate, carbonate, bicarbonate, and sulfate inhibited pitting and crevice corrosion of Alloy 22.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 824: Symposium CC – Scientific Basis for Nuclear Waste Management XXVIII , 2004 , CC1.7
Copyright
Copyright © Materials Research Society 2004

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