Boisson, Marylou
and Legras, Laurent and Andrieu, Eric and Laffont, Lydia
Role of irradiation and irradiation defects on the oxidation first stages of a 316L austenitic stainless steel.
(2019)
Corrosion Science, 161. 108194. ISSN 0010-938X
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(Document in English)
PDF (Author's version) - Requires a PDF viewer such as GSview, Xpdf or Adobe Acrobat Reader 9MB |
Official URL: https://doi.org/10.1016/j.corsci.2019.108194
Abstract
The role of irradiation and irradiation defects on the oxidation first stages of 316 L alloy was investigated. A sample with both a proton pre-irradiated and an unirradiated area was exposed to a simulated PWR environment during 24 hours. Irradiation defects and Radiation Induced Segregation at grain boundary and on irradiation defects were characterized and quantified and their effect on the oxidation was evaluated. Irradiation affects the morphology, thickness and chemistry of the oxide layers formed. It enhances the oxidation kinetic and induces the formation of an inner oxide richer in chromium. Defects induced by irradiation act as preferential nucleation sites.
| Item Type: | Article |
|---|---|
| HAL Id: | hal-02364908 |
| Audience (journal): | International peer-reviewed journal |
| Uncontrolled Keywords: | |
| Institution: | French research institutions > Centre National de la Recherche Scientifique - CNRS (FRANCE) Other partners > EDF (FRANCE) Université de Toulouse > Institut National Polytechnique de Toulouse - Toulouse INP (FRANCE) Université de Toulouse > Université Toulouse III - Paul Sabatier - UT3 (FRANCE) |
| Laboratory name: | |
| Statistics: | download |
| Deposited On: | 15 Nov 2019 10:02 |
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