| About this Abstract |
| Meeting |
MS&T22: Materials Science & Technology
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| Symposium
|
Resisting Degradation from the Environment: A Symposium Honoring Carolyn M. Hansson’s Research and Pioneering Experiences as a Woman in STEM
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| Presentation Title |
Oxidation Behavior of Model FeCrAl Steel and APMT Alloy After Exposure in Steam |
| Author(s) |
Kinga A. Unocic, Kenneth Kane, Yukinori Yamamoto, Bruce A Pint |
| On-Site Speaker (Planned) |
Kinga A. Unocic |
| Abstract Scope |
Over past few years, number of research has been conducted to address accident tolerant fuel cladding for light water nuclear reactors. Alloys with lower Cr contents are desired for radiation damage resistance during the operation.Thus, a model wrought ferritic Fe-12Cr-6Al-2Mo-0.2Si-0.03Y (wt%) steel (C26M) alloy was studied. For comparison, a commercial Kanthal® APMT alloy (Fe-22Cr-5Al-3Mo-0.6Si-0.18Y) was also evaluated. Both alloys were exposed for a short-time (4 hours) in a) steam and b) air between 1200-1475°C temperature range. Characterization of the alumina scales using scanning transmission electron microscopy (STEM) found that the scale morphology formed in steam was affected by the alloy Y content, which segregated along scale grain boundaries at 1200°C. However, after 4 hours at 1475°C, the scale morphology was drastically different and reactive elements along grain boundaries were diminished. Further, differences in scale morphology in both alloys between air and steam will be discussed. |