Improved irradiation resistance of accident-tolerant high-strength FeCrAl alloys with heterogeneous structures
Abstract
In this work, post–neutron irradiation examination is performed on advanced accident-tolerant fuel (ATF) cladding iron-chromium-aluminum (FeCrAl) alloys with ~10–13at. % Cr, ~10–12 at. % Al, ~1 at. % Mo, and minor alloying elements including Y irradiated to a damage level of 7 displacements per atom (dpa) at irradiation temperatures of 267–282 °C. A compositional dependency of the Cr and Al content is observed on the ratio of sessile and glissile dislocation loops, where the density of a$$\langle$$100$$\rangle$$ type loops is somewhat higher than the a/2$$\langle$$111$$\rangle$$ type loops. The α' precipitate number density is inversely correlated to the starting Cr concentration of the alloys of interest. The irradiation to a higher dose of 7 dpa results in a higher density of dislocation loops and α' precipitates for the same alloys at a lower irradiation dose, such as 1.8 dpa. In this work, the effect of α' precipitates on the dislocation loop density is discussed, and the presence of α' appears to inhibit the nucleation of loops. Compared with first-generation FeCrAl alloys, these advanced alloys with heterogeneous structure exhibit a lower Cr concentration in α' precipitation at the same dose level; they act as weaker obstacles deviating from the primary hardening contribution from the mature α'. Hence, the overall irradiation-induced hardening decreases; our alloys show improved radiation resistance because of their stronger sink strengths. The results presented in this paper could provide insights for the design and optimization of ATF cladding materials for future fission and space applications.
- Authors:
-
[1];
[1];
[1];
[1];
[1];
[4];
[1]
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
- Oregon State Univ., Corvallis, OR (United States)
- Univ. of Michigan, Ann Arbor, MI (United States)
- Publication Date:
- Research Org.:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Org.:
- USDOE Office of Nuclear Energy (NE), Nuclear Fuel Cycle and Supply Chain. Advanced Fuel Campaign; USDOE Office of Science (SC), Basic Energy Sciences (BES)
- OSTI Identifier:
- 1886513
- Grant/Contract Number:
- AC05-00OR22725
- Resource Type:
- Accepted Manuscript
- Journal Name:
- Acta Materialia
- Additional Journal Information:
- Journal Volume: 231; Journal Issue: June; Journal ID: ISSN 1359-6454
- Publisher:
- Elsevier
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 36 MATERIALS SCIENCE; Dislocation loops; Irradiation; Precipitation; Ferritic steels; Accident tolerant
Citation Formats
Mao, Keyou S., Massey, Caleb P., Yamamoto, Yukinori, Unocic, Kinga A., Gussev, Maxim N., Zhang, Dalong, Briggs, Samuel A., Karakoc, Omer, Nelson, Andrew T., Field, Kevin G., and Edmondson, Philip D. Improved irradiation resistance of accident-tolerant high-strength FeCrAl alloys with heterogeneous structures. United States: N. p., 2022.
Web. doi:10.1016/j.actamat.2022.117843.
Mao, Keyou S., Massey, Caleb P., Yamamoto, Yukinori, Unocic, Kinga A., Gussev, Maxim N., Zhang, Dalong, Briggs, Samuel A., Karakoc, Omer, Nelson, Andrew T., Field, Kevin G., & Edmondson, Philip D. Improved irradiation resistance of accident-tolerant high-strength FeCrAl alloys with heterogeneous structures. United States. https://doi.org/10.1016/j.actamat.2022.117843
Mao, Keyou S., Massey, Caleb P., Yamamoto, Yukinori, Unocic, Kinga A., Gussev, Maxim N., Zhang, Dalong, Briggs, Samuel A., Karakoc, Omer, Nelson, Andrew T., Field, Kevin G., and Edmondson, Philip D. Sat .
"Improved irradiation resistance of accident-tolerant high-strength FeCrAl alloys with heterogeneous structures". United States. https://doi.org/10.1016/j.actamat.2022.117843. https://www.osti.gov/servlets/purl/1886513.
@article{osti_1886513,
title = {Improved irradiation resistance of accident-tolerant high-strength FeCrAl alloys with heterogeneous structures},
author = {Mao, Keyou S. and Massey, Caleb P. and Yamamoto, Yukinori and Unocic, Kinga A. and Gussev, Maxim N. and Zhang, Dalong and Briggs, Samuel A. and Karakoc, Omer and Nelson, Andrew T. and Field, Kevin G. and Edmondson, Philip D.},
abstractNote = {In this work, post–neutron irradiation examination is performed on advanced accident-tolerant fuel (ATF) cladding iron-chromium-aluminum (FeCrAl) alloys with ~10–13at. % Cr, ~10–12 at. % Al, ~1 at. % Mo, and minor alloying elements including Y irradiated to a damage level of 7 displacements per atom (dpa) at irradiation temperatures of 267–282 °C. A compositional dependency of the Cr and Al content is observed on the ratio of sessile and glissile dislocation loops, where the density of a$\langle$100$\rangle$ type loops is somewhat higher than the a/2$\langle$111$\rangle$ type loops. The α' precipitate number density is inversely correlated to the starting Cr concentration of the alloys of interest. The irradiation to a higher dose of 7 dpa results in a higher density of dislocation loops and α' precipitates for the same alloys at a lower irradiation dose, such as 1.8 dpa. In this work, the effect of α' precipitates on the dislocation loop density is discussed, and the presence of α' appears to inhibit the nucleation of loops. Compared with first-generation FeCrAl alloys, these advanced alloys with heterogeneous structure exhibit a lower Cr concentration in α' precipitation at the same dose level; they act as weaker obstacles deviating from the primary hardening contribution from the mature α'. Hence, the overall irradiation-induced hardening decreases; our alloys show improved radiation resistance because of their stronger sink strengths. The results presented in this paper could provide insights for the design and optimization of ATF cladding materials for future fission and space applications.},
doi = {10.1016/j.actamat.2022.117843},
journal = {Acta Materialia},
number = June,
volume = 231,
place = {United States},
year = {Sat Mar 19 00:00:00 EDT 2022},
month = {Sat Mar 19 00:00:00 EDT 2022}
}
Free Publicly Available Full Text
Publisher's Version of Record
Other availability
Search WorldCat to find libraries that may hold this journal
Save to My Library
You must Sign In or Create an Account in order to save documents to your library.
Works referenced in this record:
In-situ TEM observation of the evolution of dislocation loops and helium bubbles in a pre helium irradiated FeCrAl alloy during annealing
journal, November 2020
- Chen, Yang; Li, Yipeng; Ran, Guang
- Progress in Nuclear Energy, Vol. 129
Radiation damage in nanostructured materials
journal, July 2018
- Zhang, Xinghang; Hattar, Khalid; Chen, Youxing
- Progress in Materials Science, Vol. 96
Does irradiation enhance or inhibit strain bursts at the submicron scale?
journal, June 2017
- Cui, Yinan; Po, Giacomo; Ghoniem, Nasr
- Acta Materialia, Vol. 132
Materials challenges in nuclear energy
journal, February 2013
- Zinkle, S. J.; Was, G. S.
- Acta Materialia, Vol. 61, Issue 3
Efficient Annealing of Radiation Damage Near Grain Boundaries via Interstitial Emission
journal, March 2010
- Bai, X. M.; Voter, A. F.; Hoagland, R. G.
- Science, Vol. 327, Issue 5973
Associating GB characteristics with its sink efficiency in absorbing Frank loops in Cu
journal, February 2021
- Chen, J.; Dang, K.; Vo, H. T.
- Scripta Materialia, Vol. 192
The temperature dependence of heavy-ion damage in iron: A microstructural transition at elevated temperatures
journal, December 2010
- Yao, Z.; Jenkins, M. L.; Hernández-Mayoral, M.
- Philosophical Magazine, Vol. 90, Issue 35-36
The effect of Al on the 475°C embrittlement of Fe–Cr alloys
journal, June 2013
- Li, Wei; Lu, Song; Hu, Qing-Miao
- Computational Materials Science, Vol. 74
Effect of environment on the scale formed on oxide dispersion strengthened FeCrAl at 1050°C and 1100°C
journal, September 2012
- Unocic, K. A.; Essuman, E.; Dryepondt, S.
- Materials at High Temperatures, Vol. 29, Issue 3
Role of cavities on deformation-induced martensitic transformation pathways in a laser-welded, neutron irradiated austenitic stainless steel
journal, March 2020
- Mao, Keyou S.; Sun, Cheng; Shiau, Ching-Heng
- Scripta Materialia, Vol. 178
Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors
journal, December 2015
- Yamamoto, Y.; Pint, B. A.; Terrani, K. A.
- Journal of Nuclear Materials, Vol. 467
Grain orientation dependence of nanoindentation and deformation-induced martensitic phase transformation in neutron irradiated AISI 304L stainless steel
journal, March 2019
- Mao, Keyou S.; Sun, Cheng; Huang, Yina
- Materialia, Vol. 5
Small scale mechanical testing of irradiated materials
journal, April 2015
- Hosemann, P.; Shin, C.; Kiener, D.
- Journal of Materials Research, Vol. 30, Issue 9
Aspects of the observation of clusters in the 3-dimensional atom probe
journal, January 2007
- Cerezo, A.; Davin, L.
- Surface and Interface Analysis, Vol. 39, Issue 2-3
Influence of welding and neutron irradiation on dislocation loop formation and α′ precipitation in a FeCrAl alloy
journal, December 2019
- Zhang, Dalong; Briggs, Samuel A.; Edmondson, Philip D.
- Journal of Nuclear Materials, Vol. 527
Development of cladding oxidation analysis code [COAC] and application for early stage severe accident simulation of AP1000
journal, November 2015
- Mao, Keyou; Wang, Jun; Li, Longze
- Progress in Nuclear Energy, Vol. 85
High-Efficiency Three-Dimensional Visualization of Complex Microstructures via Multidimensional STEM Acquisition and Reconstruction
journal, March 2020
- Field, Kevin G.; Eftink, Benjamin P.; Parish, Chad M.
- Microscopy and Microanalysis, Vol. 26, Issue 2
Heavy-ion irradiations of Fe and Fe–Cr model alloys Part 2: Damage evolution in thin-foils at higher doses
journal, July 2008
- Hernández-Mayoral, M.; Yao, Z.; Jenkins, M. L.
- Philosophical Magazine, Vol. 88, Issue 21
Bringing nuclear materials discovery and qualification into the 21st century
journal, May 2020
- Aguiar, Jeffery A.; Jokisaari, Andrea M.; Kerr, Matthew
- Nature Communications, Vol. 11, Issue 1
Radiation resistance of oxide dispersion strengthened alloys: Perspectives from in situ observations and rate theory calculations
journal, April 2018
- Liu, Xiang; Miao, Yinbin; Li, Meimei
- Scripta Materialia, Vol. 148
The role of slow screw dislocations in controlling fast strain avalanche dynamics in body-centered cubic metals
journal, January 2020
- Cui, Yinan; Po, Giacomo; Srivastava, Pratyush
- International Journal of Plasticity, Vol. 124
Hardening of ODS ferritic steels under irradiation with high-energy heavy ions
journal, September 2017
- Ding, Z. N.; Zhang, C. H.; Yang, Y. T.
- Journal of Nuclear Materials, Vol. 493
Materials selection for nuclear applications: Challenges and opportunities
journal, January 2018
- Hosemann, P.; Frazer, D.; Fratoni, M.
- Scripta Materialia, Vol. 143
Advanced oxidation-resistant iron-based alloys for LWR fuel cladding
journal, May 2014
- Terrani, K. A.; Zinkle, S. J.; Snead, L. L.
- Journal of Nuclear Materials, Vol. 448, Issue 1-3
Effect of radiation damage and water radiolysis on corrosion of FeCrAl alloys in hydrogenated water
journal, May 2020
- Wang, Peng; Grdanovska, Slavica; Bartels, David M.
- Journal of Nuclear Materials, Vol. 533
Plasticity of irradiated materials at the nano and micro-scales
journal, April 2021
- Cui, Yinan; Ghoniem, Nasr; Po, Giacomo
- Journal of Nuclear Materials, Vol. 546
Applications of atom-probe tomography to the characterisation of solute behaviours
journal, July 2010
- Marquis, Emmanuelle A.; Hyde, Jonathan M.
- Materials Science and Engineering: R: Reports, Vol. 69, Issue 4-5
Modeling the microstructure–mechanical property relationship for a 12Cr–2W–V–Mo–Ni power plant steel
journal, November 2003
- Li, Q.
- Materials Science and Engineering A, Vol. 361, Issue 1-2
High temperature oxidation of fuel cladding candidate materials in steam–hydrogen environments
journal, September 2013
- Pint, B. A.; Terrani, K. A.; Brady, M. P.
- Journal of Nuclear Materials, Vol. 440, Issue 1-3
Deconvoluting the Effect of Chromium and Aluminum on the Radiation Response of Wrought FeCrAl Alloys After Low-Dose Neutron Irradiation
journal, June 2021
- Massey, Caleb P.; Zhang, Dalong; Briggs, Samuel A.
- Journal of Nuclear Materials, Vol. 549
Formulating the strength factor α for improved predictability of radiation hardening
journal, October 2015
- Tan, L.; Busby, J. T.
- Journal of Nuclear Materials, Vol. 465
Small-scale mechanical testing on nuclear materials: bridging the experimental length-scale gap
journal, January 2018
- Hosemann, Peter
- Scripta Materialia, Vol. 143
Accident tolerant fuel cladding development: Promise, status, and challenges
journal, April 2018
- Terrani, Kurt A.
- Journal of Nuclear Materials, Vol. 501
Hydrothermal corrosion of 2nd generation FeCrAl alloys for accident tolerant fuel cladding
journal, August 2020
- Raiman, Stephen S.; Field, Kevin G.; Rebak, Raul B.
- Journal of Nuclear Materials, Vol. 536
New Techniques for the Analysis of Fine-Scaled Clustering Phenomena within Atom Probe Tomography (APT) Data
journal, November 2007
- Stephenson, Leigh T.; Moody, Michael P.; Liddicoat, Peter V.
- Microscopy and Microanalysis, Vol. 13, Issue 6
Flux effects in precipitation under irradiation – Simulation of Fe-Cr alloys
journal, February 2019
- Ke, Jia-Hong; Reese, Elaina R.; Marquis, Emmanuelle A.
- Acta Materialia, Vol. 164
Study and assessment of (FeCrAl) and (SiC) as candidate materials for accident tolerant fuel cladding in LWRs
journal, February 2020
- Sagiroun, Mamoun I. A.; Xinrong, Cao; Ayoub, Anuor A. T.
- IOP Conference Series: Materials Science and Engineering, Vol. 758
Void Swelling in Metals and Alloys Under Irradiation: An Assessment of the Theory
journal, August 1978
- Mansur, L. K.
- Nuclear Technology, Vol. 40, Issue 1
A statistical method to detect ordering and phase separation by APFIM
journal, June 1998
- Thuvander, M.; Andrén, H. -O; Stiller, K.
- Ultramicroscopy, Vol. 73, Issue 1-4
Accident tolerant fuels for LWRs: A perspective
journal, May 2014
- Zinkle, S. J.; Terrani, K. A.; Gehin, J. C.
- Journal of Nuclear Materials, Vol. 448, Issue 1-3
The effect of radiation upon diffusion in metals
journal, February 1978
- Sizmann, Rudolf
- Journal of Nuclear Materials, Vol. 69-70
Understanding bubble and void nucleation in dual ion irradiated T91 steel using single parameter experiments
journal, October 2020
- Taller, Stephen; Was, Gary S.
- Acta Materialia, Vol. 198
Effect of Al and Cr Content on Air and Steam Oxidation of FeCrAl Alloys and Commercial APMT Alloy
journal, March 2017
- Unocic, Kinga A.; Yamamoto, Yukinori; Pint, Bruce A.
- Oxidation of Metals, Vol. 87, Issue 3-4
The development of cladding materials for the accident tolerant fuel system from the Materials Genome Initiative
journal, December 2017
- Liu, Zhen; Li, Yifan; Shi, Diwei
- Scripta Materialia, Vol. 141
Microstructure and mechanical properties of FeCrAl alloys under heavy ion irradiations
journal, May 2018
- Aydogan, E.; Weaver, J. S.; Maloy, S. A.
- Journal of Nuclear Materials, Vol. 503
Experimental observations in support of the dynamic-segregation theory to explain the reactive-element effect
journal, February 1996
- Pint, B. A.
- Oxidation of Metals, Vol. 45, Issue 1-2
Microstructure and environmental resistance of low Cr ODS FeCrAl
journal, January 2015
- Unocic, K. A.; Hoelzer, D. T.; Pint, B. A.
- Materials at High Temperatures, Vol. 32, Issue 1-2
In Situ Micro-Pillar Compression to Examine Radiation-Induced Hardening Mechanisms of FeCrAl Alloys
journal, January 2021
- Cui, Yuchi; Aydogan, Eda; Gigax, Jonathan G.
- Acta Materialia, Vol. 202
An active learning high-throughput microstructure calibration framework for solving inverse structure–process problems in materials informatics
journal, August 2020
- Tran, Anh; Mitchell, John A.; Swiler, Laura P.
- Acta Materialia, Vol. 194
TEM characterization of dislocation loops in irradiated bcc Fe-based steels
journal, March 2013
- Yao, B.; Edwards, D. J.; Kurtz, R. J.
- Journal of Nuclear Materials, Vol. 434, Issue 1-3
Irradiation-enhanced α′ precipitation in model FeCrAl alloys
journal, April 2016
- Edmondson, P. D.; Briggs, S. A.
- Scripta Materialia, Vol. 116
Computer simulation of the bias factor in void swelling in metals
journal, September 1994
- Kuramoto, E.; Tsutsumi, T.
- Journal of Nuclear Materials, Vol. 212-215
TEM characterisation of heavy-ion irradiation damage in FeCr alloys
journal, April 2009
- Xu, S.; Yao, Z.; Jenkins, M. L.
- Journal of Nuclear Materials, Vol. 386-388
Effects of Laves phase particles on recovery and recrystallization behaviors of Nb-containing FeCrAl alloys
journal, February 2018
- Sun, Zhiqian; Edmondson, Philip D.; Yamamoto, Yukinori
- Acta Materialia, Vol. 144
A procedure for quantification of precipitate microstructures from three-dimensional atom probe data
journal, May 2003
- Vaumousse, D.; Cerezo, A.; Warren, P. J.
- Ultramicroscopy, Vol. 95
Ultra-efficient reconstruction of 3D microstructure and distribution of properties of random heterogeneous materials containing multiple phases
journal, February 2021
- Gao, Yi; Jiao, Yang; Liu, Yongming
- Acta Materialia, Vol. 204
Multiscale modeling of cruciform dwell tests with the uncertainty-quantified parametrically homogenized constitutive model
journal, November 2020
- Maloth, Thirupathi; Ozturk, Deniz; Hommer, Garrison M.
- Acta Materialia, Vol. 200
Effect of Cr Concentration on ½<111> to <100> Dislocation Loop Transformation in Fe-Cr alloys
journal, January 2021
- Zhang, Yaxuan; Xiao, Ziqi; Bai, Xian-Ming
- Journal of Nuclear Materials, Vol. 543
Work-hardening and work-softening of face-centred cubic metal crystals
journal, March 1957
- Seeger, A.; Diehl, J.; Mader, S.
- Philosophical Magazine, Vol. 2, Issue 15
Heavy-ion irradiations of Fe and Fe–Cr model alloys Part 1: Damage evolution in thin-foils at lower doses
journal, July 2008
- Yao, Z.; Hernández-Mayoral, M.; Jenkins, M. L.
- Philosophical Magazine, Vol. 88, Issue 21
Quantification of APT physical limitations on chemical composition of precipitates in Fe–Cr alloys
journal, August 2019
- Hatzoglou, Constantinos; Radiguet, Bertrand; Da Costa, Gerald
- Journal of Nuclear Materials, Vol. 522
Precipitation of α′ in neutron irradiated commercial FeCrAl alloys
journal, January 2018
- Field, Kevin G.; Littrell, Kenneth C.; Briggs, Samuel A.
- Scripta Materialia, Vol. 142
Microstructure-property relationship for AISI 304/308L stainless steel laser weldment
journal, April 2018
- Mao, Keyou; Wang, Hao; Wu, Yaqiao
- Materials Science and Engineering: A, Vol. 721
Application of a three-feature dispersed-barrier hardening model to neutron-irradiated Fe–Cr model alloys
journal, May 2014
- Bergner, F.; Pareige, C.; Hernández-Mayoral, M.
- Journal of Nuclear Materials, Vol. 448, Issue 1-3
Mechanical properties of neutron-irradiated model and commercial FeCrAl alloys
journal, June 2017
- Field, Kevin G.; Briggs, Samuel A.; Sridharan, Kumar
- Journal of Nuclear Materials, Vol. 489
A combined APT and SANS investigation of α′ phase precipitation in neutron-irradiated model FeCrAl alloys
journal, May 2017
- Briggs, Samuel A.; Edmondson, Philip D.; Littrell, Kenneth C.
- Acta Materialia, Vol. 129
Mapping of 475°C embrittlement in ferritic Fe–Cr–Al alloys
journal, November 2010
- Kobayashi, Satoru; Takasugi, Takayuki
- Scripta Materialia, Vol. 63, Issue 11
Ultra-fine-grained and gradient FeCrAl alloys with outstanding work hardening capability
journal, August 2021
- Sun, Tianyi; Shang, Zhongxia; Cho, Jaehun
- Acta Materialia, Vol. 215
Application of STEM characterization for investigating radiation effects in BCC Fe-based alloys
journal, April 2015
- Parish, Chad M.; Field, Kevin G.; Certain, Alicia G.
- Journal of Materials Research, Vol. 30, Issue 9
New insights into the mechanism of yttrium changing high-temperature oxide growth of Fe-13Cr–6Al–2Mo–0.5Nb alloy for fuel cladding
journal, August 2020
- Yang, Zhi; Pan, Jie; Wang, Zixie
- Corrosion Science, Vol. 172
Dislocation loop evolution during in-situ ion irradiation of model FeCrAl alloys
journal, September 2017
- Haley, Jack C.; Briggs, Samuel A.; Edmondson, Philip D.
- Acta Materialia, Vol. 136
Radiation tolerance of neutron-irradiated model Fe–Cr–Al alloys
journal, October 2015
- Field, Kevin G.; Hu, Xunxiang; Littrell, Kenneth C.
- Journal of Nuclear Materials, Vol. 465
The effect of Laves phase on heavy-ion radiation response of Nb-containing FeCrAl alloy for accident-tolerant fuel cladding
journal, May 2022
- Xu, Hang; Si, Shuyao; Li, Yipeng
- Fundamental Research, Vol. 2, Issue 3
Effect of laser welding on deformation mechanisms in irradiated austenitic stainless steel
journal, January 2020
- Mao, Keyou S.; Sun, Cheng; Liu, Xiang
- Journal of Nuclear Materials, Vol. 528
α′ precipitation in neutron-irradiated Fe–Cr alloys
journal, March 2014
- Bachhav, Mukesh; Robert Odette, G.; Marquis, Emmanuelle A.
- Scripta Materialia, Vol. 74
The development of a zirconium oxidation calculating program module for Module In-vessel Degraded Analysis Code MIDAC
journal, May 2014
- Wang, Jun; Tian, Wenxi; Fan, Yuqiao
- Progress in Nuclear Energy, Vol. 73
Temperature dependence of irradiation-induced creep in dilute nanostructured Cu–W alloys
journal, March 2012
- Tai, Kaiping; Averback, Robert S.; Bellon, Pascal
- Journal of Nuclear Materials, Vol. 422, Issue 1-3
The mechanism of radiation-induced segregation in ferritic–martensitic alloys
journal, February 2014
- Wharry, Janelle P.; Was, Gary S.
- Acta Materialia, Vol. 65
Optimization of Reactive-Element Additions to Improve Oxidation Performance of Alumina-Forming Alloys
journal, April 2003
- Pint, Bruce A.
- Journal of the American Ceramic Society, Vol. 86, Issue 4