About this Abstract |
Meeting |
2025 TMS Annual Meeting & Exhibition
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Symposium
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Microstructural, Mechanical, and Chemical Behavior of Solid Nuclear Fuel and Fuel-Cladding Interface II
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Presentation Title |
F-18: Evolution of Sputtered Protective Bilayer Coatings Under LOCA Steam Exposure |
Author(s) |
Brock Nowak, Fei Long, Kevin Daub, Suraj Y Persaud, Zhongwen Yao |
On-Site Speaker (Planned) |
Brock Nowak |
Abstract Scope |
Chromium-coated zircaloy claddings are a near-term accident tolerant fuel (ATF) technology under development for enhanced oxidation resistance of fuel cladding in steam environments produced under loss of coolant (LOCA) and/or reactivity-initiated accidents (RIAs). Bilayer coatings fabricated via magnetron sputtering were applied to zircaloy-2 substrates with variation in (i) bias voltage (-45 V to -80 V), and (ii) base layer composition (pure Cr, CrN). Oxidation tests were performed in high-temperature steam at 1130 °C (atmospheric pressure) for 15-, 120-, and 240-minute durations. Evolution of the film microstructure, oxide scale, and coating/Zr interface were characterized using scanning electron microscopy (SEM), and x-ray diffraction (XRD). |
Proceedings Inclusion? |
Planned: |
Keywords |
Nuclear Materials, Thin Films and Interfaces, Surface Modification and Coatings |