Corrosion of Zirconium Alloys

Todd R. Allen, Rudy J.M. Konings, Arthur T. Motta, Adrien Couet

Research output: Chapter in Book/Report/Conference proceedingChapter

7 Scopus citations

Abstract

When zirconium alloys are used in water-cooled reactors, they are subjected to waterside corrosion. As a result, an oxide thickness forms at the interface and hydrogen is being picked up by the substrate. The emphasis of this article is on uniform oxidation and hydrogen embrittlement and how environmental factors such as irradiation may affect them. The coupled processes of oxidation and hydriding are described comprehensively in terms of their underlying mechanisms. Results from experiments and models highlighting these mechanisms are also reported.

Original languageEnglish (US)
Title of host publicationComprehensive Nuclear Materials
Subtitle of host publicationSecond Edition
PublisherElsevier
Pages64-95
Number of pages32
ISBN (Electronic)9780081028650
ISBN (Print)9780081028667
DOIs
StatePublished - Jul 22 2020

All Science Journal Classification (ASJC) codes

  • General Physics and Astronomy

Cite this