Skip to main navigation Skip to search Skip to main content

Model development for oxidation and degradation behavior of accident tolerant Cr coating on Zr alloy cladding under high temperature steam atmosphere

  • Shihao Wu
  • , Dong Wang
  • , Yapei Zhang
  • , Koji Okamoto
  • , Marco Pellegrini
  • , Wenxi Tian
  • , Suizheng Qiu
  • , G. H. Su
  • Xi'an Jiaotong University
  • The University of Tokyo

Research output: Contribution to journalArticlepeer-review

41 Scopus citations

Abstract

The oxidation and degradation mechanisms of Cr coating on Zr alloy cladding under high temperature steam atmosphere are summarized. Six basic phenomena are considered for model development, including: oxidation of Cr, growth of ZrCr2, formation of Zr(Cr) solid solution, outward diffusion of Zr, reduction of Cr2O3, and volatilization of Cr2O3. The mathematical analysis model is established and validated, demonstrating its good capacity to predict the increase and subsequent decrease in the thickness of Cr2O3 scale, as well as the thickness changes in other individual layers. The developed model is applied in the analysis of the structure evolution of Cr coating under steady state, transient heating conditions and postulated accident scenarios.

Original languageEnglish
Article number154836
JournalJournal of Nuclear Materials
Volume589
DOIs
StatePublished - Feb 2024

Keywords

  • Accident tolerant fuel
  • Coating degradation
  • Cr-coated Zr alloy
  • High temperature steam oxidation
  • Model development

Fingerprint

Dive into the research topics of 'Model development for oxidation and degradation behavior of accident tolerant Cr coating on Zr alloy cladding under high temperature steam atmosphere'. Together they form a unique fingerprint.

Cite this