Corrosion of Zirconium Alloys

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

doi:10.1016/B978-0-12-803581-8.11708-4

Corrosion of Zirconium Alloys

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

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

15 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 language	English (US)
Title of host publication	Comprehensive Nuclear Materials
Subtitle of host publication	Second Edition
Publisher	Elsevier
Pages	64-95
Number of pages	32
ISBN (Electronic)	9780081028650
ISBN (Print)	9780081028667
DOIs	https://doi.org/10.1016/B978-0-12-803581-8.11708-4
State	Published - Jul 22 2020

All Science Journal Classification (ASJC) codes

General Physics and Astronomy

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10.1016/B978-0-12-803581-8.11708-4

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AU - Allen, Todd R.

AU - Konings, Rudy J.M.

AU - Motta, Arthur T.

AU - Couet, Adrien

PY - 2020/7/22

Y1 - 2020/7/22

N2 - 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.

AB - 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.

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M3 - Chapter

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SN - 9780081028667

SP - 64

EP - 95

BT - Comprehensive Nuclear Materials

PB - Elsevier

ER -

Corrosion of Zirconium Alloys

Abstract

All Science Journal Classification (ASJC) codes

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