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) |
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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 | |
State | Published - Jan 1 2012 |
All Science Journal Classification (ASJC) codes
- General Engineering
- General Materials Science
- General Energy