Abstract
Oxide dispersion strengthened (ODS) FeCrAl alloys with 12–15% Cr are being evaluated for improved compatibility with Pb-Li for a fusion energy application and with high temperature steam for a more accident-tolerant light water reactor fuel cladding application. A 12% Cr content alloy showed low mass losses in static Pb-Li at 700°C, where a LiAlO2 surface oxide formed and inhibited dissolution into the liquid metal. All the evaluated compositions formed a protective scale in steam at 1200°C, which is not possible with ODS FeCr alloys. However, most of the compositions were not protective at 1400°C, which is a general and somewhat surprising problem with ODS FeCrAl alloys that is still being studied. More work is needed to optimize the alloy composition, microstructure and oxide dispersion, but initial promising tensile and creep results have been obtained with mixed oxide additions, i.e. Y2O3 with ZrO2, HfO2 or TiO2.
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Acknowledgements
The experimental work was conducted by M. Howell, M. Stephens, C. Stevens, J. Moser, D. Harper, T. Lowe, H. Longmire, J. Mayotte, T. Geer and T. Jordan. K.A. Terrani, P.F. Tortorelli and R.B. Rebak provided useful comments on the manuscript. This research was funded by the U.S. Department of Energy’s Office of Nuclear Energy, Advanced Fuel Campaign of the Fuel Cycle R&D program and by the Office of Fusion Energy Sciences, Fusion Energy Materials Program under a proposal written by Dr. Peng Dou while he was at ORNL.
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Pint, B.A., Dryepondt, S., Unocic, K.A. et al. Development of ODS FeCrAl for Compatibility in Fusion and Fission Energy Applications. JOM 66, 2458–2466 (2014). https://doi.org/10.1007/s11837-014-1200-z
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DOI: https://doi.org/10.1007/s11837-014-1200-z