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

Abstract

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
PublisherElsevier
Pages49-68
Number of pages20
Volume1-5
ISBN (Electronic)9780080560335
ISBN (Print)9780080560274
DOIs
StatePublished - Jan 1 2012

All Science Journal Classification (ASJC) codes

  • General Engineering
  • General Materials Science
  • General Energy

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