Corrosion of Zirconium Alloys

T. R. Allen, R. J.M. Konings, Arthur Thompson Motta

Research output: Chapter in Book/Report/Conference proceedingChapter

78 Citations (Scopus)

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
PublisherElsevier Ltd
Pages49-68
Number of pages20
Volume5
ISBN (Print)9780080560335
DOIs
StatePublished - Dec 1 2012

Fingerprint

Zirconium alloys
Water cooled reactors
Corrosion
Oxidation
Hydrogen embrittlement

All Science Journal Classification (ASJC) codes

  • Energy(all)

Cite this

Allen, T. R., Konings, R. J. M., & Motta, A. T. (2012). Corrosion of Zirconium Alloys. In Comprehensive Nuclear Materials (Vol. 5, pp. 49-68). Elsevier Ltd. https://doi.org/10.1016/B978-0-08-056033-5.00063-X
Allen, T. R. ; Konings, R. J.M. ; Motta, Arthur Thompson. / Corrosion of Zirconium Alloys. Comprehensive Nuclear Materials. Vol. 5 Elsevier Ltd, 2012. pp. 49-68
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Allen, TR, Konings, RJM & Motta, AT 2012, Corrosion of Zirconium Alloys. in Comprehensive Nuclear Materials. vol. 5, Elsevier Ltd, pp. 49-68. https://doi.org/10.1016/B978-0-08-056033-5.00063-X

Corrosion of Zirconium Alloys. / Allen, T. R.; Konings, R. J.M.; Motta, Arthur Thompson.

Comprehensive Nuclear Materials. Vol. 5 Elsevier Ltd, 2012. p. 49-68.

Research output: Chapter in Book/Report/Conference proceedingChapter

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Allen TR, Konings RJM, Motta AT. Corrosion of Zirconium Alloys. In Comprehensive Nuclear Materials. Vol. 5. Elsevier Ltd. 2012. p. 49-68 https://doi.org/10.1016/B978-0-08-056033-5.00063-X