The effect of Zr on precipitation in oxide dispersion strengthened FeCrAl alloys
Abstract
Oxide dispersion strengthened (ODS) FeCrAl alloys are promising candidate materials for advanced nuclear reactor applications requiring high-temperature strength, corrosion resistance, and irradiation tolerance. As these alloys have increased in compositional complexity through attempts to use highly reactive elements such as Zr to refine particle sizes and optimize nanoprecipitate dispersion characteristics, much debate has ensued as to the effects of these alloying element additions on alloy properties. In an attempt to reconcile differences in nanoprecipitate distributions reported in the literature over the past decade, a detailed investigation of a recently developed ODS FeCrAl alloy with nominal composition Fe–10Cr-6.1Al-0.3Zr+0.3Y2O3 is presented here using a combination of atom probe tomography (APT), scanning/transmission electron microscopy (S/TEM), and computational thermodynamics modeling. It is illustrated that based on the amount of Zr available in the lattice, Zr competes with Al and Cr to form carbides and nitrides as opposed to oxygen-rich precipitates. This alloy system has a high number density (>1023 m-3) of ~2–4 nm diameter (Y,Al,O)-rich nanoprecipitates, but it is shown that due to the compositional spread and unknown partitioning of Al between the matrix and precipitates, significant challenges still exist for quantifying the exact compositions of these precipitates using APT. However, the noted compositionalmore »
- Authors:
-
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Max-Planck-Institut fur Eisenforschung, Dusseldorf (Germany)
- Publication Date:
- Research Org.:
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
- Sponsoring Org.:
- USDOE Office of Nuclear Energy (NE); USDOE Office of Science (SC), Fusion Energy Sciences (FES)
- OSTI Identifier:
- 1651407
- Alternate Identifier(s):
- OSTI ID: 1606064
- Grant/Contract Number:
- AC05-00OR22725
- Resource Type:
- Accepted Manuscript
- Journal Name:
- Journal of Nuclear Materials
- Additional Journal Information:
- Journal Volume: 533; Journal Issue: 1; Journal ID: ISSN 0022-3115
- Publisher:
- Elsevier
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 36 MATERIALS SCIENCE; atom probe tomography; oxide dispersion strengthened (ODS) alloy; precipitation; electron microscopy
Citation Formats
Massey, Caleb, Edmondson, Philip, Unocic, Kinga, Yang, Ying, Dryepondt, Sebastien N., Kini, Anoop, Gault, Baptiste, Terrani, Kurt, and Zinkle, Steven J. The effect of Zr on precipitation in oxide dispersion strengthened FeCrAl alloys. United States: N. p., 2020.
Web. doi:10.1016/j.jnucmat.2020.152105.
Massey, Caleb, Edmondson, Philip, Unocic, Kinga, Yang, Ying, Dryepondt, Sebastien N., Kini, Anoop, Gault, Baptiste, Terrani, Kurt, & Zinkle, Steven J. The effect of Zr on precipitation in oxide dispersion strengthened FeCrAl alloys. United States. https://doi.org/10.1016/j.jnucmat.2020.152105
Massey, Caleb, Edmondson, Philip, Unocic, Kinga, Yang, Ying, Dryepondt, Sebastien N., Kini, Anoop, Gault, Baptiste, Terrani, Kurt, and Zinkle, Steven J. Tue .
"The effect of Zr on precipitation in oxide dispersion strengthened FeCrAl alloys". United States. https://doi.org/10.1016/j.jnucmat.2020.152105. https://www.osti.gov/servlets/purl/1651407.
@article{osti_1651407,
title = {The effect of Zr on precipitation in oxide dispersion strengthened FeCrAl alloys},
author = {Massey, Caleb and Edmondson, Philip and Unocic, Kinga and Yang, Ying and Dryepondt, Sebastien N. and Kini, Anoop and Gault, Baptiste and Terrani, Kurt and Zinkle, Steven J.},
abstractNote = {Oxide dispersion strengthened (ODS) FeCrAl alloys are promising candidate materials for advanced nuclear reactor applications requiring high-temperature strength, corrosion resistance, and irradiation tolerance. As these alloys have increased in compositional complexity through attempts to use highly reactive elements such as Zr to refine particle sizes and optimize nanoprecipitate dispersion characteristics, much debate has ensued as to the effects of these alloying element additions on alloy properties. In an attempt to reconcile differences in nanoprecipitate distributions reported in the literature over the past decade, a detailed investigation of a recently developed ODS FeCrAl alloy with nominal composition Fe–10Cr-6.1Al-0.3Zr+0.3Y2O3 is presented here using a combination of atom probe tomography (APT), scanning/transmission electron microscopy (S/TEM), and computational thermodynamics modeling. It is illustrated that based on the amount of Zr available in the lattice, Zr competes with Al and Cr to form carbides and nitrides as opposed to oxygen-rich precipitates. This alloy system has a high number density (>1023 m-3) of ~2–4 nm diameter (Y,Al,O)-rich nanoprecipitates, but it is shown that due to the compositional spread and unknown partitioning of Al between the matrix and precipitates, significant challenges still exist for quantifying the exact compositions of these precipitates using APT. However, the noted compositional spread is supported by identified complex oxides yttrium aluminum monoclinic (YAM) and yttrium aluminum garnet (YAG) using S/TEM. As a result of these findings, researchers developing ODS FeCrAl with reactive element additions must pay careful attention to C and N impurities when optimizing reactive element additions.},
doi = {10.1016/j.jnucmat.2020.152105},
journal = {Journal of Nuclear Materials},
number = 1,
volume = 533,
place = {United States},
year = {Tue Mar 24 00:00:00 EDT 2020},
month = {Tue Mar 24 00:00:00 EDT 2020}
}
Web of Science
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