5.03 - Corrosion of Zirconium Alloys

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

doi:10.1016/B978-0-08-056033-5.00063-X

5.03 - Corrosion of Zirconium Alloys

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

Ken and Mary Alice Lindquist Department of Nuclear Engineering

Research output: Chapter in Book/Report/Conference proceeding › Chapter

182 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 language	English (US)
Title of host publication	Comprehensive Nuclear Materials
Subtitle of host publication	Volume 1-5
Publisher	Elsevier
Pages	49-68
Number of pages	20
Volume	1-5
ISBN (Electronic)	9780080560335
ISBN (Print)	9780080560274
DOIs	https://doi.org/10.1016/B978-0-08-056033-5.00063-X
State	Published - Jan 1 2012

All Science Journal Classification (ASJC) codes

General Engineering
General Materials Science
General Energy

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10.1016/B978-0-08-056033-5.00063-X

Cite this

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title = "5.03 - Corrosion of Zirconium Alloys",

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.",

author = "Allen, \{T. R.\} and Konings, \{R. J.M.\} and Motta, \{A. T.\}",

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T1 - 5.03 - Corrosion of Zirconium Alloys

AU - Allen, T. R.

AU - Konings, R. J.M.

AU - Motta, A. T.

PY - 2012/1/1

Y1 - 2012/1/1

N2 - 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.

AB - 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.

UR - https://www.scopus.com/pages/publications/84884740904

UR - https://www.scopus.com/pages/publications/84884740904#tab=citedBy

U2 - 10.1016/B978-0-08-056033-5.00063-X

DO - 10.1016/B978-0-08-056033-5.00063-X

M3 - Chapter

AN - SCOPUS:84884740904

SN - 9780080560274

VL - 1-5

SP - 49

EP - 68

BT - Comprehensive Nuclear Materials

PB - Elsevier

ER -

5.03 - Corrosion of Zirconium Alloys

Abstract

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