Actions for Development of ODS FeCrAl for compatibility in fusion and fission energy applications [electronic resource].

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Development of ODS FeCrAl for compatibility in fusion and fission energy applications [electronic resource].

Published
Washington, D.C. : United States. Office of the Assistant Secretary for Nuclear Energy, 2014.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy
Physical Description
2,458-2,466 : digital, PDF file
Additional Creators
Oak Ridge National Laboratory, United States. Office of the Assistant Secretary for Nuclear Energy, United States. Department of Energy. Office of Science, and United States. Department of Energy. Office of Scientific and Technical Information
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Summary
In this paper, 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.
Report Numbers
E 1.99:1185657
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Note
Published through SciTech Connect.
11/15/2014.
JOM. Journal of the Minerals, Metals & Materials Society 66 12 ISSN 1047-4838 AM
Bruce A. Pint; Sebastien N. Dryepondt; Kinga A. Unocic; David T. Hoelzer.
Funding Information
AC05-00OR22725
View MARC record | catkey: 24470415