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| Naji, M. |
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| Mohamed, Tarek |
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| Ertürk, Emre |
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| Taccardi, Nicola |
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| Petrov, R. H. | Madrid |
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| Alshaaer, Mazen | Brussels |
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| Kočí, Jan | Prague |
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| Azam, Siraj |
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| Azevedo, Nuno Monteiro |
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| Landes, Michael |
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Nelson, Andrew
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Publications (6/6 displayed)
- 2024Methods for Testing Meniscal Repair Using a 3D-Printed Meniscuscitations
- 2023Exploiting NIR light mediated Surface-Initiated PhotoRAFT polymerization for orthogonal control polymer brushes and facile post-modification of complex architecture through opaque barrierscitations
- 20222′,3′-cAMP treatment mimics the stress molecular response in Arabidopsis thalianacitations
- 2019Next generation sequencing for clinical diagnostics: Five year experience of an academic laboratorycitations
- 2018Oxide Morphology of C26M at 300 - 600 °C
- 2016Probing the interfacial structure of bilayer plasma polymer films via neutron reflectometry
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Oxide Morphology of C26M at 300 - 600 °C
Abstract
Iron-chromium-aluminum (FeCrAl) alloys are of interest to the nuclear materials community due to their resistance to high temperature steam oxidation under accident conditions. The present work investigates oxide formation at temperatures relevant to light water reactor cladding operation following extended aging to assess growth kinetics, chemical composition, and microstructure of oxide formation on an Oak Ridge National Laboratory developed Fe-12Cr-6Al- 2Mo-0.2Si-0.03Y alloy (designated ‘C26M’). Aging treatments were performed for 100-2000 hours in stagnant air at 300, 400, 500, and 600 °C, respectively. Oxide growth behavior under the investigated conditions follows a logarithmic time dependence. When the oxidization temperature is 400 °C or below, the oxide is amorphous. At 500 °C, crystalline α-Al<sub>2</sub>O<sub>3</sub> oxide film develops and the correlated logarithmic rate constant decreases significantly, indicating enhanced oxidation resistance of the formed oxide film. In addition, Mo segregation at grain boundaries has been observed when the aging temperature exceeds 500 °C. The results of this study can be viewed as an upper bounding result for potential oxide coarsening on the cladding inner surface during reactor operation.