On the initial corrosion mechanism of zirconium alloy: Interaction of oxygen and water with Zircaloy at room temperature and 450 C evaluated by x-ray absorption spectroscopy and photoelectron spectroscopy
- Sietec GmbH, Berlin (Germany)
- Siemens AG, Erlangen (Germany)
The initial stages of zirconium oxide formation on Zircaloy after water (H{sub 2}O) and oxygen (O{sub 2}) exposures have been investigated in situ using photoelectron spectroscopy and X-ray-absorption spectroscopy. The reactivity of the zirconium alloy with O{sub 2} at room temperature is about 1,000 times higher than for H{sub 2}O. Up to 100 L (1 L = 1 Langmuir unit = 1 {center_dot} 10{sup {minus}6} mbar {center_dot} s) H{sub 2}O exposure, the reactivity of the zirconium alloy at 450 C is comparable to the room temperature reaction. At higher H{sub 2}O exposure, a sharp increase in the reaction rate for the high-temperature oxidation is observed. From the energy position of the Zr 3d photo emission line and their oxygen-induced chemical shifts, one can really follow the formation of the oxide films. Two different substoichiometric oxides were found during reaction with water. Suboxide (1) is located at the zirconium/zirconium-oxide interface. Subsequently, a Suboxide (2) is concluded from the chemical shift of the zirconium photoelectrons. After an oxide thickness of 2 nm, the stoichiometric ZrO{sub 2} phase is not yet developed.
- OSTI ID:
- 55676
- Report Number(s):
- CONF-930611-; ISBN 0-8031-2011-7; TRN: 95:012921
- Resource Relation:
- Conference: 10. international symposium on zirconium in the nuclear industry, Baltimore, MD (United States), 21-24 Jun 1993; Other Information: PBD: 1994; Related Information: Is Part Of Zirconium in the nuclear industry: Tenth international symposium. ASTM STP 1245; Garde, A.M.; Bradley, E.R. [eds.]; PB: 818 p.
- Country of Publication:
- United States
- Language:
- English
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