Journal article
New insight into crack formation during corrosion of zirconium-based metal-oxide systems
Abstract
Zirconium alloys are typically used in nuclear pressurized water reactors (PWR) as fuel cladding tubes due to their chemical stability and their mechanical strength at operating temperatures (≈300°C). However, the corrosion of Zr-based cladding tubes is one of the factors limiting the burn-off rate in PWRs. It is commonly accepted that the corrosion kinetics involves a periodic succession of growth where the oxide thickness varies parabolically …
Authors
Vermaak N; Parry G; Estevez R; Bréchet Y
Journal
Acta Materialia, Vol. 61, No. 12, pp. 4374–4383
Publisher
Elsevier
Publication Date
7 2013
DOI
10.1016/j.actamat.2013.04.009
ISSN
1359-6454