5.03 - Corrosion of Zirconium Alloys

T. R. Allen, R. J.M. Konings, A. T. Motta

Research output: Chapter in Book/Report/Conference proceedingChapter

151 Scopus citations


When zirconium alloys are used in water-cooled reactors, they are subjected to waterside corrosion. The emphasis of this chapter is on uniform oxidation and hydrogen embrittlement. The twin processes of oxidation and hydriding are described comprehensively in terms of their underlying mechanisms.

Original languageEnglish (US)
Title of host publicationComprehensive Nuclear Materials
Subtitle of host publicationVolume 1-5
Number of pages20
ISBN (Electronic)9780080560335
ISBN (Print)9780080560274
StatePublished - Jan 1 2012

All Science Journal Classification (ASJC) codes

  • General Engineering
  • General Materials Science
  • General Energy


Dive into the research topics of '5.03 - Corrosion of Zirconium Alloys'. Together they form a unique fingerprint.

Cite this