Evolution of Cr/Cr2O3 interface in Cr-coated zirconium alloy in high temperature steam

Yao Wang, Bo Chen, Xian Zong Wang, Mingju Chen, Shilei Li, Guanghai Bai, Jinshan Li, Weijia Gong

Research output: Contribution to journalArticlepeer-review

27 Scopus citations

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 languageEnglish
Article number111099
JournalCorrosion Science
Volume217
DOIs
StatePublished - Jun 2023

Keywords

  • ATF cladding
  • Cr-coating
  • EBSD
  • High temperature oxidation
  • Interface
  • Reduction

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