Fiber texture-dependent oxidation behaviour of Cr-coated zirconium alloy in high temperature steam

Yao Wang, Luhua Wang, Lunlin Shang, Guanghai Bai, Jinshan Li, Fei Xue, Weijia Gong

Research output: Contribution to journalArticlepeer-review

32 Scopus citations

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 languageEnglish
Article number110449
JournalCorrosion Science
Volume205
DOIs
StatePublished - 15 Aug 2022

Keywords

  • ATF cladding
  • Cr-coating
  • Fiber texture
  • High temperature oxidation
  • Nano-porosity
  • SEM

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