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Steam Oxidation Behavior of FeCrAl Cladding

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Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors

Part of the book series: The Minerals, Metals & Materials Series ((MMMS))

Abstract

In order to better understand the high temperature steam oxidation behavior of FeCrAl alloys, this study addressed two topics. The first is continuing to evaluate the effect of alloy composition on performance of commercial and laboratory-made candidate FeCrAl alloys. For a few optimized compositions, this includes the performance of commercially-made tubing where it is clear that dropping the Cr content from 20% to 10–13% reduces the maximum operating temperature in steam by ~50 °C. The second addresses more realistic accident conditions. Model FeCrAl compositions that were exposed in ~300 °C water for 1 year were subsequently “ramp” tested in steam at 5 °C/min to 1500 °C to assess the effect of the Fe-rich oxide formed in water on the subsequent steam oxidation resistance. For Fe-18Cr-3Al+Y, the 1 year exposures in three different LWR water chemistries did not affect the ability to form alumina to 1500 °C. However, for marginal alloys Fe-13Cr-4Al and Fe-10Cr-5Al, some specimens began forming voluminous Fe-rich oxide at lower temperatures.

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Acknowledgements

The experimental work was conducted by M. Howell, T. Lowe and T. Jordan. S. S. Raiman 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.

Notice: This manuscript has been authored by UT-Battelle, LLC under Contract No. DE-AC05-00OR22725 with the U.S. Department of Energy. The United States Government retains and the publisher, by accepting the article for publication, acknowledges that the United States Government retains a non-exclusive, paid-up, irrevocable, world-wide license to publish or reproduce the published form of this manuscript, or allow others to do so, for United States Government purposes. The Department of Energy will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan (http://energy.gov/downloads/doe-public-access-plan).

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Authors and Affiliations

  1. Oak Ridge National Laboratory, P. O. Box 2008, Oak Ridge, TN, 37831-6156, USA

    B. A. Pint & K. A. Terrani

  2. GE Global Research, 1 Research Circle, Schenectady, NY, 12309, USA

    R. B. Rebak

Authors
  1. B. A. Pint
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  2. K. A. Terrani
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  3. R. B. Rebak
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Corresponding author

Correspondence to B. A. Pint .

Editor information

Editors and Affiliations

  1. Idaho National Laboratory, Idaho Falls, ID, USA

    John H. Jackson

  2. Naval Nuclear Laboratory, Pittsburgh, PA, USA

    Denise Paraventi

  3. Chalk River Laboratories, Canadian Nuclear Laboratories, Chalk River, ON, Canada

    Michael Wright

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© 2019 The Minerals, Metals & Materials Society

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Pint, B.A., Terrani, K.A., Rebak, R.B. (2019). Steam Oxidation Behavior of FeCrAl Cladding. In: Jackson, J., Paraventi, D., Wright, M. (eds) Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors. The Minerals, Metals & Materials Series. Springer, Cham. https://doi.org/10.1007/978-3-030-04639-2_96

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