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Localized Corrosion Behavior of Type 304SS with a Silica Layer Under Atmospheric Corrosion Environments
Author(s) -
Eiji Tada,
G. S. Frankel
Publication year - 2006
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/893925
Subject(s) - corrosion , radioactive waste , materials science , dispose pattern , layer (electronics) , galvanic cell , high level waste , spent nuclear fuel , electrolyte , environmental science , alloy , relative humidity , metallurgy , waste management , composite material , chemistry , engineering , electrode , physics , thermodynamics
The U.S. Department of Energy (DOE) has proposed a potential repository for spent nuclear fuel and high-level radioactive waste at the Yucca Mountain site in Nevada. [I] The temperature could be high on the waste packages, and it is possible that dripping water or humidity could interact with rock dust particulate to form a thin electrolyte layer with concentrated ionic species. Under these conditions, it is possible that highly corrosion-resistant alloys (CRAs) used as packages to dispose the nuclear waste could suffer localized corrosion. Therefore, to better understand long-term corrosion performance of CRAs in the repository, it is important to investigate localized corrosion under a simulated repository environment. We measured open circuit potential (OCP) and galvanic current (i{sub g}) for silica-coated Type 304SS during drying of salt solutions under controlled RH environments to clarify the effect of silica layer as a dust layer simulant on localized corrosion under atmospheric environments. Type 304SS was used as a relatively susceptible model CRA instead of the much more corrosion resistant alloys, such as Alloy 22, that are being considered as, waste package materials

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