Localized Corrosion Behavior of Type 304SS with a Silica Layer Under Atmospheric Corrosion Environments
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.
- Research Organization:
- Yucca Mountain Project, Las Vegas, NV (United States)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- NA
- OSTI ID:
- 893925
- Report Number(s):
- NA; MOL.20060705.0068, DC# 47393; TRN: US0700074
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
36 MATERIALS SCIENCE
ALLOYS
CORROSION
CORROSION RESISTANT ALLOYS
DRYING
DUSTS
ELECTROLYTES
HIGH-LEVEL RADIOACTIVE WASTES
HUMIDITY
NUCLEAR FUELS
PARTICULATES
RADIOACTIVE WASTES
SILICA
WASTES
WATER
YUCCA MOUNTAIN