Mechanical behavior and structure of advanced Fe-Cr-Al alloy weldments

M. N. Gussev; K. G. Field; E. Cakmak; Y. Yamamoto

doi:10.1007/978-3-319-68454-3_18

Mechanical behavior and structure of advanced Fe-Cr-Al alloy weldments

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

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

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.

Original language	English
Title of host publication	Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors
Editors	Michael Wright, Denise Paraventi, John H. Jackson
Publisher	Springer International Publishing
Pages	201-214
Number of pages	14
ISBN (Print)	9783319684536
DOIs	https://doi.org/10.1007/978-3-319-68454-3_18
State	Published - 2018
Event	18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, 2017 - Portland, United States Duration: Aug 13 2017 → Aug 17 2017

Publication series

Name	Minerals, Metals and Materials Series
Volume	Part F11
ISSN (Print)	2367-1181
ISSN (Electronic)	2367-1696

Conference

Conference	18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, 2017
Country/Territory	United States
City	Portland
Period	08/13/17 → 08/17/17

Funding

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). 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.

Funders	Funder number
U.S. Department of Energy
Office of Nuclear Energy
Nuclear Energy Enabling Technologies	DE-AC05-00OR22725

Keywords

Digital image correlation
EBSD
FeCrAl alloys
Laser-beam welding

Access to Document

10.1007/978-3-319-68454-3_18

Cite this

Gussev, M. N., Field, K. G., Cakmak, E., & Yamamoto, Y. (2018). Mechanical behavior and structure of advanced Fe-Cr-Al alloy weldments. In M. Wright, D. Paraventi, & J. H. Jackson (Eds.), Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors (pp. 201-214). (Minerals, Metals and Materials Series; Vol. Part F11). Springer International Publishing. https://doi.org/10.1007/978-3-319-68454-3_18

Gussev, M. N. ; Field, K. G. ; Cakmak, E. et al. / Mechanical behavior and structure of advanced Fe-Cr-Al alloy weldments. Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors. editor / Michael Wright ; Denise Paraventi ; John H. Jackson. Springer International Publishing, 2018. pp. 201-214 (Minerals, Metals and Materials Series).

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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.",

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Gussev, MN, Field, KG, Cakmak, E & Yamamoto, Y 2018, Mechanical behavior and structure of advanced Fe-Cr-Al alloy weldments. in M Wright, D Paraventi & JH Jackson (eds), Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors. Minerals, Metals and Materials Series, vol. Part F11, Springer International Publishing, pp. 201-214, 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, 2017, Portland, United States, 08/13/17. https://doi.org/10.1007/978-3-319-68454-3_18

Mechanical behavior and structure of advanced Fe-Cr-Al alloy weldments. / Gussev, M. N.; Field, K. G.; Cakmak, E. et al.
Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors. ed. / Michael Wright; Denise Paraventi; John H. Jackson. Springer International Publishing, 2018. p. 201-214 (Minerals, Metals and Materials Series; Vol. Part F11).

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

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AB - 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.

KW - Digital image correlation

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Gussev MN, Field KG, Cakmak E , Yamamoto Y. Mechanical behavior and structure of advanced Fe-Cr-Al alloy weldments. In Wright M, Paraventi D, Jackson JH, editors, Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors. Springer International Publishing. 2018. p. 201-214. (Minerals, Metals and Materials Series). doi: 10.1007/978-3-319-68454-3_18

Mechanical behavior and structure of advanced Fe-Cr-Al alloy weldments

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