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Early-stage diffusion and oxidation behavior of Cr-Nb coated Zr alloy accident tolerant fuel cladding materials at 1200°C–1500°C

  • Xi'an Jiaotong University
  • CAS - Lanzhou Institute of Chemical Physics
  • Tomsk Polytechnic University
  • Shanghai Nuclear Engineering Research and Design Institute

Research output: Contribution to journalArticlepeer-review

10 Scopus citations

Abstract

Although the Cr-coated Zr alloys are considered as the most promising accident tolerant fuel cladding materials in recent years, the Cr-Zr interdiffusion problem is a major obstacle for the widely used of the Cr coating. In this study, Cr-Nb coated Zr alloy samples were prepared by magnetron sputtering. The Nb layer was designed as a barrier layer to retard the Cr-Zr interdiffusion. By using a fast-in and fast-out equipment, short time annealing was conducted in argon environment to study the coating evolution in high temperature environment. Results show that the Nb coating can retard the inward diffusion of Cr because of the low diffusion coefficient of Cr in the Nb layer. However, the complete miscibility between Nb and Zr lead to the fast consumption of the Nb coating. After 10 min annealing at 1200 °C, the 2.5 μm Nb coating disappeared, and a Cr-Zr-Nb mixed phase formed between the residual Cr coating and Zr substrate. The early-stage microstructure evolution of the sample was analyzed, and the barrier effect of the Nb coating was summarized.

Original languageEnglish
Article number155257
JournalJournal of Nuclear Materials
Volume599
DOIs
StatePublished - Oct 2024

Keywords

  • Accident tolerant fuel
  • Cr coating
  • Interdiffusion
  • Nb interlayer
  • Oxidation

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