Abstract
<100> textured Cr-coating was deposited on Zr-based nuclear fuel cladding and went through steam oxidation at 1200 °C. The formed Cr2O3 layer exhibited thickening-thinning transition characteristic accompanying undulation of the Cr/Cr2O3 interface with oxidation progress. Electron microscopy characterization revealed that the convex tips of Cr/Cr2O3 interface invariably linked to grain boundaries of residual Cr-coating, which channeled the outward diffusion of Zr atoms consequently reducing Cr2O3-grains into Cr-grains. The reduction reaction at the Cr/Cr2O3 interface accounts for the interface undulation and consumption of protective oxides. This study is expected to shed light on failure mechanism of protective oxides on ATF Cr-coatings.
Original language | English |
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Article number | 111099 |
Journal | Corrosion Science |
Volume | 217 |
DOIs | |
State | Published - Jun 2023 |
Keywords
- ATF cladding
- Cr-coating
- EBSD
- High temperature oxidation
- Interface
- Reduction