Diffusion-mediated chemical concentration variation and void evolution in ion-irradiated NiCoFeCr high-entropy alloy

Fan, Zhe; Zhong, Weicheng; Jin, Ke; Bei, Hongbin; Osetsky, Yuri N.; Zhang, Yanwen

doi:10.1557/s43578-020-00071-8

Diffusion-mediated chemical concentration variation and void evolution in ion-irradiated NiCoFeCr high-entropy alloy

Journal Article · Thu Feb 04 00:00:00 EST 2021 · Journal of Materials Research

DOI:https://doi.org/10.1557/s43578-020-00071-8· OSTI ID:1787316

^[1]; Zhong, Weicheng ^[1]; Jin, Ke ^[1]; Bei, Hongbin ^[1]; Osetsky, Yuri N. ^[1]; Zhang, Yanwen ^[2]

Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Materials Science and Technology Division
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Materials Science and Technology Division; Univ. of Tennessee, Knoxville, TN (United States). Dept. of Materials Science and Engineering

High-entropy alloys (HEAs) are proposed as potential structural materials for advanced nuclear systems, but little is known about the response of matrix chemistry in HEAs upon irradiation. Here, we reveal a substantial change of matrix chemical concentration as a function of irradiation damage (depth) in equiatomic NiCoFeCr HEA irradiated by 3 MeV Ni ions. After ion irradiation, the matrix contains more Fe/Cr in depth shallower than ~900–1000 nm but more Ni/Co from ~900–1000 nm to the end of the ion-damaged region due to the preferential diffusion of vacancies through Fe/Cr. Preferential diffusion also facilitates migration of vacancies from high radiation damage region to low radiation damage region, leading to no void formation below ~900–1000 nm and void formation around the end of the ion-damaged region at a fluence of 5 × 10¹⁶ cm^–2 (~123 dpa, displacements per atom, peak dose under full cascade mode). As voids grow significantly at an increased fluence (8 × 10¹⁶ cm^–2, 196 dpa), the matrix concentration does not change dramatically due to new voids formed below ~900–1000 nm.

View Accepted Manuscript (DOE)

Research Organization:: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

Sponsoring Organization:: USDOE Office of Science (SC), Basic Energy Sciences (BES)

Grant/Contract Number:: AC05-00OR22725

OSTI ID:: 1787316

Journal Information:: Journal of Materials Research, Journal Name: Journal of Materials Research Journal Issue: 1 Vol. 36; ISSN 0884-2914

Publisher:: Materials Research SocietyCopyright Statement

Country of Publication:: United States

Language:: English

References (59)

High-Entropy Alloys Gao, Michael C.; Yeh, Jien-Wei; Liaw, Peter K. https://doi.org/10.1007/978-3-319-27013-5	book	January 2016
In Situ Studies on the Irradiation-Induced Twin Boundary-Defect Interactions in Cu Fan, C.; Li, Jin; Fan, Zhe Metallurgical and Materials Transactions A, Vol. 48, Issue 11 https://doi.org/10.1007/s11661-017-4293-5	journal	August 2017
The radiation damage tolerance of ultra-high strength nanolayered composites Misra, A.; Demkowicz, M. J.; Zhang, X. JOM, Vol. 59, Issue 9 https://doi.org/10.1007/s11837-007-0120-6	journal	September 2007
On the Room-Temperature Mechanical Properties of an Ion-Irradiated TiZrNbHfTa Refractory High Entropy Alloy Moschetti, Michael; Xu, Alan; Schuh, Benjamin JOM, Vol. 72, Issue 1 https://doi.org/10.1007/s11837-019-03861-6	journal	November 2019
Recent insights on the swelling and creep of irradiated austenitic alloys Garner, F. A. Journal of Nuclear Materials, Vol. 122, Issue 1-3 https://doi.org/10.1016/0022-3115(84)90641-X	journal	May 1984
Evolution of microstructure in face-centered cubic metals during irradiation Garner, F. A. Journal of Nuclear Materials, Vol. 205 https://doi.org/10.1016/0022-3115(93)90076-B	journal	October 1993
Efficiency of ab-initio total energy calculations for metals and semiconductors using a plane-wave basis set Kresse, G.; Furthmüller, J. Computational Materials Science, Vol. 6, Issue 1, p. 15-50 https://doi.org/10.1016/0927-0256(96)00008-0	journal	July 1996
Radiation-Induced Effects on Microstructure**Prepared for the Oak Ridge National Laboratory under Contract No. DE-AC05-000R22725 Zinkle, S. J. Comprehensive Nuclear Materials https://doi.org/10.1016/B978-0-08-056033-5.00003-3	book	February 2012
Radiation-induced segregation accompanied by grain boundary migration in austenitic stainless steel Watanabe, S.; Sakaguchi, N.; Hashimoto, N. Journal of Nuclear Materials, Vol. 232, Issue 2-3 https://doi.org/10.1016/S0022-3115(96)00433-3	journal	September 1996
On the mechanism of radiation-induced segregation in austenitic Fe–Cr–Ni alloys Allen, T. R.; Busby, J. T.; Was, G. S. Journal of Nuclear Materials, Vol. 255, Issue 1 https://doi.org/10.1016/S0022-3115(98)00010-5	journal	May 1998
Structural materials for fission & fusion energy Zinkle, Steven J.; Busby, Jeremy T. Materials Today, Vol. 12, Issue 11 https://doi.org/10.1016/S1369-7021(09)70294-9	journal	November 2009
Materials challenges for nuclear systems Allen, Todd; Busby, Jeremy; Meyer, Mitch Materials Today, Vol. 13, Issue 12 https://doi.org/10.1016/S1369-7021(10)70220-0	journal	December 2010
Microstructures and mechanical properties of a directionally solidified NiAl–Mo eutectic alloy Bei, H.; George, E. P. Acta Materialia, Vol. 53, Issue 1 https://doi.org/10.1016/j.actamat.2004.09.003	journal	January 2005
Materials challenges in nuclear energy Zinkle, S. J.; Was, G. S. Acta Materialia, Vol. 61, Issue 3 https://doi.org/10.1016/j.actamat.2012.11.004	journal	February 2013
Microstructural stability and mechanical behavior of FeNiMnCr high entropy alloy under ion irradiation Kumar, N. A. P. Kiran; Li, C.; Leonard, K. J. Acta Materialia, Vol. 113 https://doi.org/10.1016/j.actamat.2016.05.007	journal	July 2016
Specific features of defect and mass transport in concentrated fcc alloys Osetsky, Yuri N.; Béland, Laurent K.; Stoller, Roger E. Acta Materialia, Vol. 115 https://doi.org/10.1016/j.actamat.2016.06.018	journal	August 2016
Mechanisms of radiation-induced segregation in CrFeCoNi-based single-phase concentrated solid solution alloys He, Mo-Rigen; Wang, Shuai; Shi, Shi Acta Materialia, Vol. 126 https://doi.org/10.1016/j.actamat.2016.12.046	journal	March 2017
Radiation-induced segregation on defect clusters in single-phase concentrated solid-solution alloys Lu, Chenyang; Yang, Taini; Jin, Ke Acta Materialia, Vol. 127 https://doi.org/10.1016/j.actamat.2017.01.019	journal	April 2017
Preferential diffusion in concentrated solid solution alloys: NiFe, NiCo and NiCoCr Zhao, Shijun; Osetsky, Yuri; Zhang, Yanwen Acta Materialia, Vol. 128 https://doi.org/10.1016/j.actamat.2017.01.056	journal	April 2017
Bulk tracer diffusion in CoCrFeNi and CoCrFeMnNi high entropy alloys Vaidya, M.; Pradeep, K. G.; Murty, B. S. Acta Materialia, Vol. 146 https://doi.org/10.1016/j.actamat.2017.12.052	journal	March 2018
Helium irradiated cavity formation and defect energetics in Ni-based binary single-phase concentrated solid solution alloys Fan, Zhe; Zhao, Shijun; Jin, Ke Acta Materialia, Vol. 164 https://doi.org/10.1016/j.actamat.2018.10.040	journal	February 2019
Structural damage and phase stability of Al0.3CoCrFeNi high entropy alloy under high temperature ion irradiation Yang, Tengfei; Guo, Wei; Poplawsky, Jonathan D. Acta Materialia, Vol. 188 https://doi.org/10.1016/j.actamat.2020.01.060	journal	April 2020
Segregation of Ni at early stages of radiation damage in NiCoFeCr solid solution alloys Tuomisto, F.; Makkonen, I.; Heikinheimo, J. Acta Materialia, Vol. 196 https://doi.org/10.1016/j.actamat.2020.06.024	journal	September 2020
Chemically-biased diffusion and segregation impede void growth in irradiated Ni-Fe alloys Barashev, Alexander; Osetsky, Yuri; Bei, Hongbin Current Opinion in Solid State and Materials Science, Vol. 23, Issue 2 https://doi.org/10.1016/j.cossms.2018.12.001	journal	April 2019
Predicting damage production in monoatomic and multi-elemental targets using stopping and range of ions in matter code: Challenges and recommendations Weber, William J.; Zhang, Yanwen Current Opinion in Solid State and Materials Science, Vol. 23, Issue 4 https://doi.org/10.1016/j.cossms.2019.06.001	journal	August 2019
High He-ion irradiation resistance of CrMnFeCoNi high-entropy alloy revealed by comparison study with Ni and 304SS Yang, Lixin; Ge, Hualong; Zhang, Jian Journal of Materials Science & Technology, Vol. 35, Issue 3 https://doi.org/10.1016/j.jmst.2018.09.050	journal	March 2019
Structural materials challenges for advanced reactor systems Yvon, P.; Carré, F. Journal of Nuclear Materials, Vol. 385, Issue 2 https://doi.org/10.1016/j.jnucmat.2008.11.026	journal	March 2009
Assessment of radiation-induced segregation mechanisms in austenitic and ferritic–martensitic alloys Was, Gary S.; Wharry, Janelle P.; Frisbie, Brian Journal of Nuclear Materials, Vol. 411, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2011.01.031	journal	April 2011
Phase stability and microstructures of high entropy alloys ion irradiated to high doses Xia, Songqin; Gao, Michael C.; Yang, Tengfei Journal of Nuclear Materials, Vol. 480 https://doi.org/10.1016/j.jnucmat.2016.08.017	journal	November 2016
The effect of injected interstitials on void formation in self-ion irradiated nickel containing concentrated solid solution alloys Yang, Tai-ni; Lu, Chenyang; Jin, Ke Journal of Nuclear Materials, Vol. 488 https://doi.org/10.1016/j.jnucmat.2017.02.026	journal	May 2017
Temperature-dependent defect accumulation and evolution in Ni-irradiated NiFe concentrated solid-solution alloy Fan, Zhe; Velisa, Gihan; Jin, Ke Journal of Nuclear Materials, Vol. 519 https://doi.org/10.1016/j.jnucmat.2019.03.031	journal	June 2019
Diffusion controlled helium bubble formation resistance of FeCoNiCr high-entropy alloy in the half-melting temperature regime Chen, Da; Zhao, Shijun; Sun, Jianrong Journal of Nuclear Materials, Vol. 526 https://doi.org/10.1016/j.jnucmat.2019.151747	journal	December 2019
Phase stability of single phase Al0.12CrNiFeCo high entropy alloy upon irradiation Kombaiah, B.; Jin, K.; Bei, H. Materials & Design, Vol. 160 https://doi.org/10.1016/j.matdes.2018.11.006	journal	December 2018
Radiation damage tolerant nanomaterials Beyerlein, I. J.; Caro, A.; Demkowicz, M. J. Materials Today, Vol. 16, Issue 11 https://doi.org/10.1016/j.mattod.2013.10.019	journal	November 2013
Microstructural development in equiatomic multicomponent alloys Cantor, B.; Chang, I. T. H.; Knight, P. Materials Science and Engineering: A, Vol. 375-377 https://doi.org/10.1016/j.msea.2003.10.257	journal	July 2004
Evolution of local lattice distortion under irradiation in medium- and high-entropy alloys Tong, Y.; Velisa, G.; Zhao, S. Materialia, Vol. 2 https://doi.org/10.1016/j.mtla.2018.06.008	journal	October 2018
From suppressed void growth to significant void swelling in NiCoFeCr complex concentrated solid-solution alloy Fan, Zhe; Yang, Tai-ni; Kombaiah, Boopathy Materialia, Vol. 9 https://doi.org/10.1016/j.mtla.2020.100603	journal	March 2020
SRIM – The stopping and range of ions in matter (2010) Ziegler, James F.; Ziegler, M. D.; Biersack, J. P. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, Vol. 268, Issue 11-12 https://doi.org/10.1016/j.nimb.2010.02.091	journal	June 2010
New ion beam materials laboratory for materials modification and irradiation effects research Zhang, Y.; Crespillo, M. L.; Xue, H. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, Vol. 338 https://doi.org/10.1016/j.nimb.2014.07.028	journal	November 2014
Microstructures and properties of high-entropy alloys Zhang, Yong; Zuo, Ting Ting; Tang, Zhi Progress in Materials Science, Vol. 61 https://doi.org/10.1016/j.pmatsci.2013.10.001	journal	April 2014
Opportunities and limitations for ion beams in radiation effects studies: Bridging critical gaps between charged particle and neutron irradiations Zinkle, S. J.; Snead, L. L. Scripta Materialia, Vol. 143 https://doi.org/10.1016/j.scriptamat.2017.06.041	journal	January 2018
Effects of temperature on the irradiation responses of Al0.1CoCrFeNi high entropy alloy Yang, Tengfei; Xia, Songqin; Guo, Wei Scripta Materialia, Vol. 144 https://doi.org/10.1016/j.scriptamat.2017.09.025	journal	February 2018
Exploring radiation induced segregation mechanisms at grain boundaries in equiatomic CoCrFeNiMn high entropy alloy under heavy ion irradiation Barr, Christopher M.; Nathaniel, James E.; Unocic, Kinga A. Scripta Materialia, Vol. 156 https://doi.org/10.1016/j.scriptamat.2018.06.041	journal	November 2018
Influence of irradiation temperature on void swelling in NiCoFeCrMn and NiCoFeCrPd Yang, Tai-ni; Lu, Chenyang; Velisa, Gihan Scripta Materialia, Vol. 158 https://doi.org/10.1016/j.scriptamat.2018.08.021	journal	January 2019
Metastable high-entropy dual-phase alloys overcome the strength–ductility trade-off Li, Zhiming; Pradeep, Konda Gokuldoss; Deng, Yun Nature, Vol. 534, Issue 7606 https://doi.org/10.1038/nature17981	journal	May 2016
Enhancing radiation tolerance by controlling defect mobility and migration pathways in multicomponent single-phase alloys Lu, Chenyang; Niu, Liangliang; Chen, Nanjun Nature Communications, Vol. 7, Issue 1 https://doi.org/10.1038/ncomms13564	journal	December 2016
Deviation from high-entropy configurations in the atomic distributions of a multi-principal-element alloy Santodonato, Louis J.; Zhang, Yang; Feygenson, Mikhail Nature Communications, Vol. 6, Issue 1 https://doi.org/10.1038/ncomms6964	journal	January 2015
Influence of chemical disorder on energy dissipation and defect evolution in concentrated solid solution alloys Zhang, Yanwen; Stocks, G. Malcolm; Jin, Ke Nature Communications, Vol. 6, Issue 1 https://doi.org/10.1038/ncomms9736	journal	October 2015
Strengthening in multi-principal element alloys with local-chemical-order roughened dislocation pathways Li, Qing-Jie; Sheng, Howard; Ma, Evan Nature Communications, Vol. 10, Issue 1 https://doi.org/10.1038/s41467-019-11464-7	journal	August 2019
Tunable chemical complexity to control atomic diffusion in alloys Osetsky, Yuri; Barashev, Alexander V.; Béland, Laurent K. npj Computational Materials, Vol. 6, Issue 1 https://doi.org/10.1038/s41524-020-0306-9	journal	April 2020
Tuning element distribution, structure and properties by composition in high-entropy alloys Ding, Qingqing; Zhang, Yin; Chen, Xiao Nature, Vol. 574, Issue 7777 https://doi.org/10.1038/s41586-019-1617-1	journal	October 2019
Grain size threshold for enhanced irradiation resistance in nanocrystalline and ultrafine tungsten El-Atwani, O.; Hinks, J. A.; Greaves, G. Materials Research Letters, Vol. 5, Issue 5 https://doi.org/10.1080/21663831.2017.1292326	journal	February 2017
Local Structure and Short-Range Order in a NiCoCr Solid Solution Alloy Zhang, F. X.; Zhao, Shijun; Jin, Ke Physical Review Letters, Vol. 118, Issue 20 https://doi.org/10.1103/PhysRevLett.118.205501	journal	May 2017
Thermodynamics of vacancies and clusters in high-entropy alloys Wang, Zhijun; Liu, C. T.; Dou, Peng Physical Review Materials, Vol. 1, Issue 4 https://doi.org/10.1103/PhysRevMaterials.1.043601	journal	September 2017
Effect of d electrons on defect properties in equiatomic NiCoCr and NiCoFeCr concentrated solid solution alloys Zhao, Shijun; Egami, Takeshi; Stocks, G. Malcolm Physical Review Materials, Vol. 2, Issue 1 https://doi.org/10.1103/PhysRevMaterials.2.013602	journal	January 2018
Outstanding radiation resistance of tungsten-based high-entropy alloys El-Atwani, O.; Li, N.; Li, M. Science Advances, Vol. 5, Issue 3 https://doi.org/10.1126/sciadv.aav2002	journal	March 2019
A fracture-resistant high-entropy alloy for cryogenic applications Gludovatz, B.; Hohenwarter, A.; Catoor, D. Science, Vol. 345, Issue 6201 https://doi.org/10.1126/science.1254581	journal	September 2014
Quantitative X-ray microanalysis of thin specimens in the transmission electron microscope; a review Lorimer, G. W. Mineralogical Magazine, Vol. 51, Issue 359 https://doi.org/10.1180/minmag.1987.051.359.05	journal	March 1987
An in situ study on Kr ion–irradiated crystalline Cu/amorphous-CuNb nanolaminates Fan, Zhe; Fan, Cuncai; Li, Jin Journal of Materials Research, Vol. 34, Issue 13 https://doi.org/10.1557/jmr.2019.24	journal	March 2019

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