Abstract
A proton-irradiated SUS316 stainless steel was exposed to the simulated BWR NWC environment for 70 hours during a constant extension rate tensile test and the resulted oxide film was examined using transmission electron microscopy. The oxide film on both the unirradiated and irradiated parts of the sample consists of an outer layer of hematite particles and an inner layer of (Fe, Cr, Ni)3O4 spinel. Formation of hematite under BWR NWC condition is consistent with the predication by the potential-pH diagram. Both the outer layer and the inner layer of the oxide film show a strong dependence on grain orientation. Some grains exhibit an inner layer thickness of 40–100 nm while some others have barely any oxidation. Persistent damage induced by proton irradiation did not show a strong influence on the oxidation process as the thickness structure and compositions of the oxide film on both the unirradiated and irradiated parts of the sample were very similar.
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© 2011 TMS (The Minerals, Metals & Materials Society)
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Jiao, Z., Was, G. (2011). Oxidation of a Proton-Irradiated 316 Stainless Steel in Simulated BWR NWC Environment. In: Busby, J.T., Ilevbare, G., Andresen, P.L. (eds) Proceedings of the 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems — Water Reactors. Springer, Cham. https://doi.org/10.1007/978-3-319-48760-1_81
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DOI: https://doi.org/10.1007/978-3-319-48760-1_81
Publisher Name: Springer, Cham
Online ISBN: 978-3-319-48760-1
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