Abstract
Cr-coatings with distinct crystallographic fiber textures were deposited on zirconium nuclear fuel cladding material. The <100> textured Cr-coating demonstrated superior properties to the <110> and <111> textured ones after high temperature steam oxidation. Electron microscopy characterization revealed that improvement in oxidation resistance could be attributed to rapid growth of <100> Cr-coating grains which leads to reduced grain boundaries for oxygen diffusion and zirconia particle nucleation as well as the absence of transgranular nano-porosity arrays in the residual Cr-coating. This work demonstrates a novel mechanism of orientation-dependent Cr-coating corrosion, which is expected to guide optimized design of Cr-coated nuclear fuel cladding.
Original language | English |
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Article number | 110449 |
Journal | Corrosion Science |
Volume | 205 |
DOIs | |
State | Published - 15 Aug 2022 |
Keywords
- ATF cladding
- Cr-coating
- Fiber texture
- High temperature oxidation
- Nano-porosity
- SEM