Deconvoluting the Effect of Chromium and Aluminum on the Radiation Response of Wrought FeCrAl Alloys After Low-Dose Neutron Irradiation

Caleb P. Massey; Dalong Zhang; Samuel A. Briggs; Philip D. Edmondson; Yukinori Yamamoto; Maxim N. Gussev; Kevin G. Field

doi:10.1016/j.jnucmat.2021.152804

Deconvoluting the Effect of Chromium and Aluminum on the Radiation Response of Wrought FeCrAl Alloys After Low-Dose Neutron Irradiation

Caleb P. Massey, Dalong Zhang, Samuel A. Briggs, Philip D. Edmondson, Yukinori Yamamoto, Maxim N. Gussev, Kevin G. Field

Research output: Contribution to journal › Article › peer-review

16 Scopus citations

Abstract

FeCrAl alloys have been extensively investigated over the past decade as a candidate material for accident-tolerant fuel cladding in light water reactors. This work completes a first of its kind study where Al and Cr concentrations are varied systematically under neutron irradiation to elucidate the post irradiation microstructural and mechanical response as a direct result of alloying content. Neutron irradiations were performed on alloys with composition Fe-(10-13)Cr-(5-7)Al in wt.% at temperatures of 214, 357, and 557°C to a dose of ~1.8 dpa (displacements per atom). Dislocation loop sizes and dispersion characteristics did not show strong compositional dependence. However, there were noticeable effects of composition on the dispersion of Cr-rich α^′-precipitates, particularly a decrease in number density with increasing Al content or a decrease in Cr content. The present results confirm previous studies indicating the Cr concentration in these precipitates is lower than that expected in binary FeCr alloys and that Al can act as a destabilizing alloying element for the deleterious α^′-phase.

Original language	English
Article number	152804
Journal	Journal of Nuclear Materials
Volume	549
DOIs	https://doi.org/10.1016/j.jnucmat.2021.152804
State	Published - Jun 2021

Funding

This manuscript has been authored by UT-Battelle, LLC, under contract DE-AC05-00OR22725 with the US Department of Energy (DOE). The US government retains and the publisher, by accepting the article for publication, acknowledges that the US 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 US government purposes. DOE 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). The work presented in this paper was supported by the Advanced Fuels Campaign of the Fuel Cycle R&D program in the Office of Nuclear Energy, US Department of Energy under contract DE-AC05-00OR22725 with the US Department of Energy (DOE). A portion of this research was conducted at ORNL's Center for Nanophase Materials Sciences (CNMS), which is a DOE Office of Science User Facility. A portion of this work was funded by a Nuclear Science User Facilities Rapid Turnaround Experiment and was conducted at the Center for Advanced Energy Studies–Microscopy and Characterization Suite (CAES-MaCS).

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

Keywords

Accident Tolerant
Dislocation Hardening
FeCrAl
Phase Stability

Access to Document

10.1016/j.jnucmat.2021.152804

Cite this

@article{6dc57ce4bc6c4a48870ed60d02fb5087,

title = "Deconvoluting the Effect of Chromium and Aluminum on the Radiation Response of Wrought FeCrAl Alloys After Low-Dose Neutron Irradiation",

abstract = "FeCrAl alloys have been extensively investigated over the past decade as a candidate material for accident-tolerant fuel cladding in light water reactors. This work completes a first of its kind study where Al and Cr concentrations are varied systematically under neutron irradiation to elucidate the post irradiation microstructural and mechanical response as a direct result of alloying content. Neutron irradiations were performed on alloys with composition Fe-(10-13)Cr-(5-7)Al in wt.% at temperatures of 214, 357, and 557°C to a dose of ~1.8 dpa (displacements per atom). Dislocation loop sizes and dispersion characteristics did not show strong compositional dependence. However, there were noticeable effects of composition on the dispersion of Cr-rich α′-precipitates, particularly a decrease in number density with increasing Al content or a decrease in Cr content. The present results confirm previous studies indicating the Cr concentration in these precipitates is lower than that expected in binary FeCr alloys and that Al can act as a destabilizing alloying element for the deleterious α′-phase.",

keywords = "Accident Tolerant, Dislocation Hardening, FeCrAl, Phase Stability",

author = "Massey, {Caleb P.} and Dalong Zhang and Briggs, {Samuel A.} and Edmondson, {Philip D.} and Yukinori Yamamoto and Gussev, {Maxim N.} and Field, {Kevin G.}",

note = "Publisher Copyright: {\textcopyright} 2021 Elsevier B.V.",

year = "2021",

month = jun,

doi = "10.1016/j.jnucmat.2021.152804",

language = "English",

volume = "549",

journal = "Journal of Nuclear Materials",

issn = "0022-3115",

publisher = "Elsevier",

}

TY - JOUR

T1 - Deconvoluting the Effect of Chromium and Aluminum on the Radiation Response of Wrought FeCrAl Alloys After Low-Dose Neutron Irradiation

AU - Massey, Caleb P.

AU - Zhang, Dalong

AU - Briggs, Samuel A.

AU - Edmondson, Philip D.

AU - Yamamoto, Yukinori

AU - Gussev, Maxim N.

AU - Field, Kevin G.

PY - 2021/6

Y1 - 2021/6

N2 - FeCrAl alloys have been extensively investigated over the past decade as a candidate material for accident-tolerant fuel cladding in light water reactors. This work completes a first of its kind study where Al and Cr concentrations are varied systematically under neutron irradiation to elucidate the post irradiation microstructural and mechanical response as a direct result of alloying content. Neutron irradiations were performed on alloys with composition Fe-(10-13)Cr-(5-7)Al in wt.% at temperatures of 214, 357, and 557°C to a dose of ~1.8 dpa (displacements per atom). Dislocation loop sizes and dispersion characteristics did not show strong compositional dependence. However, there were noticeable effects of composition on the dispersion of Cr-rich α′-precipitates, particularly a decrease in number density with increasing Al content or a decrease in Cr content. The present results confirm previous studies indicating the Cr concentration in these precipitates is lower than that expected in binary FeCr alloys and that Al can act as a destabilizing alloying element for the deleterious α′-phase.

AB - FeCrAl alloys have been extensively investigated over the past decade as a candidate material for accident-tolerant fuel cladding in light water reactors. This work completes a first of its kind study where Al and Cr concentrations are varied systematically under neutron irradiation to elucidate the post irradiation microstructural and mechanical response as a direct result of alloying content. Neutron irradiations were performed on alloys with composition Fe-(10-13)Cr-(5-7)Al in wt.% at temperatures of 214, 357, and 557°C to a dose of ~1.8 dpa (displacements per atom). Dislocation loop sizes and dispersion characteristics did not show strong compositional dependence. However, there were noticeable effects of composition on the dispersion of Cr-rich α′-precipitates, particularly a decrease in number density with increasing Al content or a decrease in Cr content. The present results confirm previous studies indicating the Cr concentration in these precipitates is lower than that expected in binary FeCr alloys and that Al can act as a destabilizing alloying element for the deleterious α′-phase.

KW - Accident Tolerant

KW - Dislocation Hardening

KW - FeCrAl

KW - Phase Stability

UR - http://www.scopus.com/inward/record.url?scp=85101105661&partnerID=8YFLogxK

U2 - 10.1016/j.jnucmat.2021.152804

DO - 10.1016/j.jnucmat.2021.152804

M3 - Article

AN - SCOPUS:85101105661

SN - 0022-3115

VL - 549

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

M1 - 152804

ER -

Deconvoluting the Effect of Chromium and Aluminum on the Radiation Response of Wrought FeCrAl Alloys After Low-Dose Neutron Irradiation

Abstract

Funding

Keywords

Access to Document

Other files and links

Fingerprint

Cite this