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Understanding the high-temperature corrosion behavior of zirconium alloy as cladding tubes: a review

  • Yan Tang
  • , Jingjing Liao
  • , Di Yun
  • Nuclear Power Institute of China

Research output: Contribution to journalReview articlepeer-review

20 Scopus citations

Abstract

Operated under extreme conditions, corrosion occurs between zirconium alloy cladding tubes and the coolant in the primary loop of pressurized water reactors (PWRs), contributing to a reduction in the effective metallic material thickness. Therefore, understanding the corrosion behavior of zirconium alloy is vital to both raising the burnup of PWR and the improvement of safety properties of these reactors. During the past decades, extensive investigation was conducted with various conditions, such as changing corrosion temperatures and alloying elements, but contradiction persists and universal conclusion remain elusive. In the present work, a variety of research results that focused on corrosion kinetics, microstructural evolution, and the influence of alloying elements were integrated and summarized, so that a valuable reference can be provided to further research.

Original languageEnglish
Article number1381818
JournalFrontiers in Materials
Volume11
DOIs
StatePublished - 2024

Keywords

  • alloying element
  • corrosion
  • high temperaature oxidation
  • kinetic transition
  • zirconium alloy

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