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Mechanical Behavior and Structure of Advanced Fe-Cr-Al Alloy Weldments

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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

FeCrAl alloys are promising for developing accident tolerant nuclear fuel claddings. These alloys showed good environmental compatibility and oxidation resistance in elevated-temperature water and steam, as well as low radiation-induced swelling. However, FeCrAl alloys may suffer from several degradation mechanisms, one of which may be a susceptibility to cracking during welding. Here, a set of advanced modified FeCrAl alloys were designed and produced by varying Al-content and employing additions of Nb and TiC. Strength, ductility, and deformation hardening behavior of the advanced FeCrAl alloys and their weldments are discussed.

This manuscript has been authored by UT-Battelle, LLC, under Contract No. DE-AC0500OR22725 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 nonexclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this manuscript, or allow others to do so, for the 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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Acknowledgements

This research was sponsored by the U.S. Department of Energy, Office of Nuclear Energy, for the Nuclear Energy Enabling Technologies (NEET) program for the Reactor Materials effort. This report was authored by UT-Battelle, LLC under Contract No. DE-AC05-00OR22725 with the U.S. Department of Energy. Authors would like to thank Dr. L. Tan (ORNL) for fruitful discussion of the results and S. Crawford (ORNL) for valuable help in manuscript preparation.

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Authors and Affiliations

  1. Oak Ridge National Laboratory, One Bethel Valley Road MS-6151, P.O. Box 2008, Oak Ridge, TN, 37831, USA

    M. N. Gussev, K. G. Field, E. Cakmak & Y. Yamamoto

Authors
  1. M. N. Gussev
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  2. K. G. Field
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  3. E. Cakmak
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  4. Y. Yamamoto
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Corresponding author

Correspondence to M. N. Gussev .

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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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Gussev, M.N., Field, K.G., Cakmak, E., Yamamoto, Y. (2019). Mechanical Behavior and Structure of Advanced Fe-Cr-Al Alloy Weldments. 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_94

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