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

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

doi:10.1007/978-3-030-04639-2_94

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

2 Scopus citations

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	Minerals, Metals and Materials Series
Publisher	Springer International Publishing
Pages	1417-1430
Number of pages	14
ISBN (Print)	9783030046385, 9783030046392, 9783319515403, 9783319651354, 9783319728520, 9783319950211
DOIs	https://doi.org/10.1007/978-3-030-04639-2_94
State	Published - 2019
Event	18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors 2019 - Boston, United States Duration: Aug 18 2019 → Aug 22 2019

Publication series

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

Conference

Conference	18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors 2019
Country/Territory	United States
City	Boston
Period	08/18/19 → 08/22/19

Funding

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	DE-AC05-00OR22725

Keywords

Digital image correlation
EBSD
FeCrAl alloys
Laser-beam welding

Access to Document

10.1007/978-3-030-04639-2_94

Cite this

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title = "Mechanical behavior and structure of advanced Fe-Cr-Al alloy weldments",

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.",

keywords = "Digital image correlation, EBSD, FeCrAl alloys, Laser-beam welding",

author = "Gussev, {M. N.} and Field, {K. G.} and E. Cakmak and Y. Yamamoto",

note = "Publisher Copyright: {\textcopyright} 2019, The Minerals, Metals & Materials Society.; 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors 2019 ; Conference date: 18-08-2019 Through 22-08-2019",

year = "2019",

doi = "10.1007/978-3-030-04639-2_94",

language = "English",

isbn = "9783030046385",

series = "Minerals, Metals and Materials Series",

publisher = "Springer International Publishing",

pages = "1417--1430",

booktitle = "Minerals, Metals and Materials Series",

}

Gussev, MN, Field, KG, Cakmak, E & Yamamoto, Y 2019, Mechanical behavior and structure of advanced Fe-Cr-Al alloy weldments. in Minerals, Metals and Materials Series. Minerals, Metals and Materials Series, Springer International Publishing, pp. 1417-1430, 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors 2019, Boston, United States, 08/18/19. https://doi.org/10.1007/978-3-030-04639-2_94

TY - GEN

T1 - Mechanical behavior and structure of advanced Fe-Cr-Al alloy weldments

AU - Gussev, M. N.

AU - Field, K. G.

AU - Cakmak, E.

AU - Yamamoto, Y.

PY - 2019

Y1 - 2019

N2 - 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.

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

KW - EBSD

KW - FeCrAl alloys

KW - Laser-beam welding

UR - http://www.scopus.com/inward/record.url?scp=85064063988&partnerID=8YFLogxK

U2 - 10.1007/978-3-030-04639-2_94

DO - 10.1007/978-3-030-04639-2_94

M3 - Conference contribution

AN - SCOPUS:85064063988

SN - 9783030046385

SN - 9783030046392

SN - 9783319515403

SN - 9783319651354

SN - 9783319728520

SN - 9783319950211

T3 - Minerals, Metals and Materials Series

SP - 1417

EP - 1430

BT - Minerals, Metals and Materials Series

PB - Springer International Publishing

T2 - 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors 2019

Y2 - 18 August 2019 through 22 August 2019

ER -

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

Abstract

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Keywords

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