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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

科研成果: 期刊稿件文献综述同行评审

21 引用 (Scopus)

摘要

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.

源语言英语
期刊论文编号1381818
期刊Frontiers in Materials
11
DOI
出版状态已出版 - 2024

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