Microstructural stability and mechanical behavior of FeNiMnCr high entropy alloy under ion irradiation

Leonard, Keith J.; Bei, Hongbin; Zinkle, Steven J.; Kiran Kumar, N. A. P.; Li, C.

doi:10.1016/j.actamat.2016.05.007

Microstructural stability and mechanical behavior of FeNiMnCr high entropy alloy under ion irradiation

Journal Article · Fri May 13 00:00:00 EDT 2016 · Acta Materialia

DOI:https://doi.org/10.1016/j.actamat.2016.05.007· OSTI ID:1256811

Leonard, Keith J. ^[1]; Bei, Hongbin ^[1]; Zinkle, Steven J. ^[2]; Kiran Kumar, N. A. P. ^[1]; Li, C. ^[3]

Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Univ. of Tennessee, Knoxville, TN (United States)
Univ. of Tennessee, Knoxville, TN (United States)

In recent years, high entropy alloys (HEAs) have attracted significant attention due to their excellent mechanical properties and good corrosion resistance, making them potential candidates for high temperature fission and fusion structural applications. However there is very little known about their radiation resistance, particularly at elevated temperatures relevant for energy applications. In the present study, a single phase (face centered cubic) concentrated solid solution alloy of composition 27%Fe-28%Ni-27%Mn-18%Cr was irradiated with 3 or 5.8 MeV Ni ions at temperatures ranging from room temperature to 700 °C and midrange doses from 0.03 to 10 displacements per atom (dpa). Transmission electron microscopy (TEM), scanning transmission electron microscopy with energy dispersive x-ray spectrometry (STEM/EDS) and X-ray diffraction (XRD) were used to characterize the radiation defects and microstructural changes. Irradiation at higher temperatures showed evidence of relatively sluggish solute diffusion with limited solute depletion or enrichment at grain boundaries. The main microstructural feature at all temperatures was high-density small dislocation loops. Voids were not observed at any irradiation condition. Nano-indentation tests on specimens irradiated at room temperature showed a rapid increase in hardness ~35% and ~80% higher than the unirradiated value at 0.03 and 0.3 dpa midrange doses, respectively. The irradiation-induced hardening was less pronounced for 500 °C irradiations (<20% increase after 3 dpa). Overall, the examined HEA material exhibits superior radiation resistance compared to conventional single phase Fe-Cr-Ni austenitic alloys such as stainless steels. Furthermore, the present study provides insight on the fundamental irradiation behavior of a single phase HEA material over a broad range of irradiation temperatures.

View Accepted Manuscript (DOE)

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

Sponsoring Organization:: USDOE Office of Science (SC); USDOE Office of Science (SC), Fusion Energy Sciences (FES)

Grant/Contract Number:: AC05-00OR22725

OSTI ID:: 1256811

Alternate ID(s):: OSTI ID: 1326425

Journal Information:: Acta Materialia, Journal Name: Acta Materialia Journal Issue: C Vol. 113; ISSN 1359-6454

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

References (93)

Nanostructured High-Entropy Alloys with Multiple Principal Elements: Novel Alloy Design Concepts and Outcomes Yeh, J.-W.; Chen, S.-K.; Lin, S.-J. Advanced Engineering Materials, Vol. 6, Issue 5, p. 299-303 https://doi.org/10.1002/adem.200300567	journal	May 2004
Wear resistance and high-temperature compression strength of Fcc CuCoNiCrAl0.5Fe alloy with boron addition Hsu, Chin-You; Yeh, Jien-Wei; Chen, Swe-Kai Metallurgical and Materials Transactions A, Vol. 35, Issue 5 https://doi.org/10.1007/s11661-004-0254-x	journal	May 2004
Formation of simple crystal structures in Cu-Co-Ni-Cr-Al-Fe-Ti-V alloys with multiprincipal metallic elements Yeh, Jien-Wei; Lin, Su-Jien; Chin, Tsung-Shune Metallurgical and Materials Transactions A, Vol. 35, Issue 8 https://doi.org/10.1007/s11661-006-0234-4	journal	August 2004
Irradiation Resistance in Al x CoCrFeNi High Entropy Alloys Xia, S. Q.; Yang, X.; Yang, T. F. JOM, Vol. 67, Issue 10 https://doi.org/10.1007/s11837-015-1568-4	journal	August 2015
Local Electronic Effects and Irradiation Resistance in High-Entropy Alloys Egami, T.; Ojha, M.; Khorgolkhuu, O. JOM, Vol. 67, Issue 10 https://doi.org/10.1007/s11837-015-1579-1	journal	August 2015
Beyond Atomic Sizes and Hume-Rothery Rules: Understanding and Predicting High-Entropy Alloys Troparevsky, M. Claudia; Morris, James R.; Daene, Markus JOM, Vol. 67, Issue 10 https://doi.org/10.1007/s11837-015-1594-2	journal	September 2015
Effect of fast-neutron irradiation on mechanical properties of stainless steels: AISI types 304, 316 and 347 Higgy, H. R.; Hammad, F. H. Journal of Nuclear Materials, Vol. 55, Issue 2 https://doi.org/10.1016/0022-3115(75)90151-8	journal	February 1975
Void formation in solution-treated aisi 316 and 321 stainless steels under 46.5 mev ni6+ irradiation Hudson, J. A. Journal of Nuclear Materials, Vol. 60, Issue 1 https://doi.org/10.1016/0022-3115(76)90121-5	journal	April 1976
Void-swelling in irons and ferritic steels Little, E. A.; Stow, D. A. Journal of Nuclear Materials, Vol. 87, Issue 1 https://doi.org/10.1016/0022-3115(79)90123-5	journal	November 1979
Interstitial loop nucleation and growth in solution-treated type 316 stainless steel irradiated to low doses with 22 MeV C2+ and 46.5 MeV Ni6+ ions Williams, T. M. Journal of Nuclear Materials, Vol. 79, Issue 1 https://doi.org/10.1016/0022-3115(79)90431-8	journal	January 1979
A theory of radiation-induced segregation in concentrated alloys Wiedersich, H.; Okamoto, P. R.; Lam, N. Q. Journal of Nuclear Materials, Vol. 83, Issue 1 https://doi.org/10.1016/0022-3115(79)90596-8	journal	August 1979
The effect of soluble carbon on void swelling and low dose dislocation structures in type 316 austenitic stainless steel irradiated with 46.5 MeV Ni6+ ions Williams, T. M. Journal of Nuclear Materials, Vol. 88, Issue 2-3 https://doi.org/10.1016/0022-3115(80)90277-9	journal	February 1980
The effect of irradiation and post-irradiation annealing on the yield stress and microstructure of vanadium-carbon alloys Takahashi, H.; Ohnuki, S.; Takeyama, T. Journal of Nuclear Materials, Vol. 96, Issue 3 https://doi.org/10.1016/0022-3115(81)90567-5	journal	February 1981
Void swelling and segregation of solute in ion-irradiated ferritic steels Ohnuki, Soumei; Takahashi, Heishichiro; Takeyama, Taro Journal of Nuclear Materials, Vol. 104 https://doi.org/10.1016/0022-3115(82)90751-6	journal	January 1981
Impact of the injected interstitial on the correlation of charged particle and neutron-induced radiation damage Garner, F. A. Journal of Nuclear Materials, Vol. 117 https://doi.org/10.1016/0022-3115(83)90023-5	journal	July 1983
Suppression of void nucleation by injected interstitials during heavy ion bombardment Plumton, D. L.; Wolfer, W. G. Journal of Nuclear Materials, Vol. 120, Issue 2-3 https://doi.org/10.1016/0022-3115(84)90062-X	journal	April 1984
Void swelling and radiation-induced phase transformation in high purity Fe-Ni-Cr alloys Stubbins, James F. Journal of Nuclear Materials, Vol. 141-143 https://doi.org/10.1016/0022-3115(86)90085-1	journal	November 1986
Radiation-induced segregation in HT-9 martensitic steel Clausing, R. E.; Heatherly, L.; Faulkner, R. G. Journal of Nuclear Materials, Vol. 141-143 https://doi.org/10.1016/0022-3115(86)90128-5	journal	November 1986
Neutron irradiation of FeMn, FeCrMn and FeCrNi alloys and an explanation of their differences in swelling behavior Garner, F. A.; Brager, H. R.; Gelles, D. S. Journal of Nuclear Materials, Vol. 148, Issue 3 https://doi.org/10.1016/0022-3115(87)90023-7	journal	May 1987
Damage profiles in a stainless steel irradiated with Ar and N ions Shiraishi, K.; Fukai, K.; Yagi, E. Journal of Nuclear Materials, Vol. 179-181 https://doi.org/10.1016/0022-3115(91)90147-Y	journal	March 1991
A method for evaluating radiation-induced grain boundary segregation using ion-irradiated microcrystalline stainless alloys Bruemmer, S. M.; Merz, M. D.; Charlot, L. A. Journal of Nuclear Materials, Vol. 186, Issue 1 https://doi.org/10.1016/0022-3115(91)90346-9	journal	December 1991
Temperature dependence of the dislocation microstructure of PCA austenitic stainless steel irradiated in ORR spectrally-tailored experiments Maziasz, P. J. Journal of Nuclear Materials, Vol. 191-194 https://doi.org/10.1016/0022-3115(92)90563-Z	journal	September 1992
Elemental inhomogeneities developed in stainless steels by radiation-induced segregation Kenik, Edward A. Journal of Nuclear Materials, Vol. 205 https://doi.org/10.1016/0022-3115(93)90095-G	journal	October 1993
Defect accumulation in pure fcc metals in the transient regime: a review Singh, B. N.; Zinkle, S. J. Journal of Nuclear Materials, Vol. 206, Issue 2-3 https://doi.org/10.1016/0022-3115(93)90125-I	journal	November 1993
Dose dependence of the microstructural evolution in neutron-irradiated austenitic stainless steel Zinkle, S. J.; Maziasz, P. J.; Stoller, R. E. Journal of Nuclear Materials, Vol. 206, Issue 2-3 https://doi.org/10.1016/0022-3115(93)90128-L	journal	November 1993
The evolution of mechanical property change in irradiated austenitic stainless steels Lucas, G. E. Journal of Nuclear Materials, Vol. 206, Issue 2-3 https://doi.org/10.1016/0022-3115(93)90129-M	journal	November 1993
Dependence of radiation-induced segregation on dose, temperature and alloy composition in austenitic alloys Damcott, D. L.; Allen, T. R.; Was, G. S. Journal of Nuclear Materials, Vol. 225 https://doi.org/10.1016/0022-3115(94)00690-3	journal	August 1995
Sink effect of grain boundary on radiation-induced segregation in austenitic stainless steel Watanabe, S.; Takamatsu, Y.; Sakaguchi, N. Journal of Nuclear Materials, Vol. 283-287 https://doi.org/10.1016/S0022-3115(00)00204-X	journal	December 2000
Perspective of ODS alloys application in nuclear environments Ukai, Shigeharu; Fujiwara, Masayuki Journal of Nuclear Materials, Vol. 307-311, p. 749-757 https://doi.org/10.1016/S0022-3115(02)01043-7	journal	December 2002
Ferritic/martensitic steels – overview of recent results Klueh, R. L.; Gelles, D. S.; Jitsukawa, S. Journal of Nuclear Materials, Vol. 307-311 https://doi.org/10.1016/S0022-3115(02)01082-6	journal	December 2002
Microstructural evolution in FeCrNi alloy irradiated with Ni ion under varying temperature Xu, Q.; Watanabe, H.; Yoshida, N. Journal of Nuclear Materials, Vol. 233-237 https://doi.org/10.1016/S0022-3115(96)00118-3	journal	October 1996
The effect of alloy composition on radiation-induced segregation in FeCrNi alloys Allen, T. R.; Was, G. S.; Kenik, E. A. Journal of Nuclear Materials, Vol. 244, Issue 3 https://doi.org/10.1016/S0022-3115(96)00744-1	journal	April 1997
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
Research and development on vanadium alloys for fusion applications Zinkle, S. J.; Matsui, H.; Smith, D. L. Journal of Nuclear Materials, Vol. 258-263 https://doi.org/10.1016/S0022-3115(98)00269-4	journal	October 1998
Radiation-induced material changes and susceptibility to intergranular failure of light-water-reactor core internals Bruemmer, S. M.; Simonen, E. P.; Scott, P. M. Journal of Nuclear Materials, Vol. 274, Issue 3 https://doi.org/10.1016/S0022-3115(99)00075-6	journal	September 1999
Comparison of swelling and irradiation creep behavior of fcc-austenitic and bcc-ferritic/martensitic alloys at high neutron exposure Garner, F. A.; Toloczko, M. B.; Sencer, B. H. Journal of Nuclear Materials, Vol. 276, Issue 1-3 https://doi.org/10.1016/S0022-3115(99)00225-1	journal	January 2000
Indentation size effects in crystalline materials: A law for strain gradient plasticity Nix, William D.; Gao, Huajian Journal of the Mechanics and Physics of Solids, Vol. 46, Issue 3 https://doi.org/10.1016/S0022-5096(97)00086-0	journal	March 1998
Operating temperature windows for fusion reactor structural materials Zinkle, S. J.; Ghoniem, N. M. Fusion Engineering and Design, Vol. 51-52, p. 55-71 https://doi.org/10.1016/S0920-3796(00)00320-3	journal	November 2000
Recrystallisation of practical mechanically alloyed iron-base and nickel-base superalloys Bhadeshia, H. K. D. H. Materials Science and Engineering: A, Vol. 223, Issue 1-2 https://doi.org/10.1016/S0921-5093(96)10507-4	journal	February 1997
Effect of aging treatment on irradiation-induced segregation of high Mn-Cr steel Bae, D. S.; Lee, S. P.; Cho, Y. R. Transactions of Nonferrous Metals Society of China, Vol. 21 https://doi.org/10.1016/S1003-6326(11)61061-3	journal	March 2011
Irradiation Behavior in High Entropy Alloys Xia, Song-qin; Wang, Zhen; Yang, Teng-fei Journal of Iron and Steel Research International, Vol. 22, Issue 10 https://doi.org/10.1016/S1006-706X(15)30084-4	journal	October 2015
Thermodynamic analysis of the simple microstructure of AlCrFeNiCu high-entropy alloy with multi-principal elements Li, Anmin; Zhang, Xiyan Acta Metallurgica Sinica (English Letters), Vol. 22, Issue 3 https://doi.org/10.1016/S1006-7191(08)60092-7	journal	June 2009
On the origin of deformation microstructures in austenitic stainless steel: part I—microstructures Lee, E. H.; Byun, T. S.; Hunn, J. D. Acta Materialia, Vol. 49, Issue 16 https://doi.org/10.1016/S1359-6454(01)00193-8	journal	September 2001
Positron annihilation spectroscopy on binary Fe–Cr alloys and ferritic/martensitic steels after neutron irradiation Lambrecht, Marlies; Malerba, Lorenzo Acta Materialia, Vol. 59, Issue 17 https://doi.org/10.1016/j.actamat.2011.06.046	journal	October 2011
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
Relative effects of enthalpy and entropy on the phase stability of equiatomic high-entropy alloys Otto, F.; Yang, Y.; Bei, H. Acta Materialia, Vol. 61, Issue 7 https://doi.org/10.1016/j.actamat.2013.01.042	journal	April 2013
Sluggish diffusion in Co–Cr–Fe–Mn–Ni high-entropy alloys Tsai, K. -Y.; Tsai, M. -H.; Yeh, J. -W. Acta Materialia, Vol. 61, Issue 13 https://doi.org/10.1016/j.actamat.2013.04.058	journal	August 2013
Radiation-induced solute segregation in metallic alloys Ardell, Alan J.; Bellon, Pascal Current Opinion in Solid State and Materials Science, Vol. 20, Issue 3 https://doi.org/10.1016/j.cossms.2015.11.001	journal	June 2016
Advanced materials for fusion technology Zinkle, Steven J. Fusion Engineering and Design, Vol. 74, Issue 1-4 https://doi.org/10.1016/j.fusengdes.2005.08.008	journal	November 2005
MeV electron-irradiation-induced structural change in the bcc phase of Zr–Hf–Nb alloy with an approximately equiatomic ratio Nagase, Takeshi; Anada, Satoshi; Rack, Philip D. Intermetallics, Vol. 38 https://doi.org/10.1016/j.intermet.2013.02.009	journal	July 2013
In-situ TEM observation of structural changes in nano-crystalline CoCrCuFeNi multicomponent high-entropy alloy (HEA) under fast electron irradiation by high voltage electron microscopy (HVEM) Nagase, Takeshi; Rack, Philip D.; Noh, Joo Hyon Intermetallics, Vol. 59 https://doi.org/10.1016/j.intermet.2014.12.007	journal	April 2015
Deformation and annealing behaviors of high-entropy alloy Al0.5CoCrCuFeNi Tsai, Che-Wei; Chen, Yu-Liang; Tsai, Ming-Hung Journal of Alloys and Compounds, Vol. 486, Issue 1-2 https://doi.org/10.1016/j.jallcom.2009.06.182	journal	November 2009
Equilibrium phase of high-entropy FeCoNiCrCu0.5 alloy at elevated temperature Lin, Chun-Ming; Tsai, Hsien-Lung Journal of Alloys and Compounds, Vol. 489, Issue 1 https://doi.org/10.1016/j.jallcom.2009.09.041	journal	January 2010
Phases, microstructure and mechanical properties of AlxCoCrFeNi high-entropy alloys at elevated temperatures Wang, Woei-Ren; Wang, Wei-Lin; Yeh, Jien-Wei Journal of Alloys and Compounds, Vol. 589 https://doi.org/10.1016/j.jallcom.2013.11.084	journal	March 2014
The effect of oversized solute additions on the microstructure of 316SS irradiated with 5 MeV Ni++ ions or 3.2 MeV protons Gan, J.; Simonen, E. P.; Bruemmer, S. M. Journal of Nuclear Materials, Vol. 325, Issue 2-3 https://doi.org/10.1016/j.jnucmat.2003.11.002	journal	February 2004
Materials design data for reduced activation martensitic steel type EUROFER Tavassoli, A. -A. F.; Alamo, A.; Bedel, L. Journal of Nuclear Materials, Vol. 329-333 https://doi.org/10.1016/j.jnucmat.2004.04.020	journal	August 2004
Observation and analysis of defect cluster production and interactions with dislocations Zinkle, S. J.; Matsukawa, Y. Journal of Nuclear Materials, Vol. 329-333 https://doi.org/10.1016/j.jnucmat.2004.04.298	journal	August 2004
The relationship between hardness and yield stress in irradiated austenitic and ferritic steels Busby, Jeremy T.; Hash, Mark C.; Was, Gary S. Journal of Nuclear Materials, Vol. 336, Issue 2-3 https://doi.org/10.1016/j.jnucmat.2004.09.024	journal	February 2005
Oxide dispersion-strengthened steels: A comparison of some commercial and experimental alloys Klueh, R. L.; Shingledecker, J. P.; Swindeman, R. W. Journal of Nuclear Materials, Vol. 341, Issue 2-3 https://doi.org/10.1016/j.jnucmat.2005.01.017	journal	May 2005
Characteristics of microscopic strain localization in irradiated 316 stainless steels and pure vanadium Byun, T. S.; Hashimoto, N.; Farrell, K. Journal of Nuclear Materials, Vol. 349, Issue 3 https://doi.org/10.1016/j.jnucmat.2005.10.011	journal	March 2006
Effect of hafnium on radiation-induced inter-granular segregation in ferritic steel Lu, Z.; Faulkner, R. G.; Sakaguchi, N. Journal of Nuclear Materials, Vol. 351, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2006.02.026	journal	June 2006
Microstructural evolution of proton irradiated T91 Gupta, G.; Jiao, Z.; Ham, A. N. Journal of Nuclear Materials, Vol. 351, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2006.02.028	journal	June 2006
The synergistic influence of temperature and displacement rate on microstructural evolution of ion-irradiated Fe–15Cr–16Ni model austenitic alloy Okita, T.; Sato, T.; Sekimura, N. Journal of Nuclear Materials, Vol. 367-370 https://doi.org/10.1016/j.jnucmat.2007.03.061	journal	August 2007
Ferritic/martensitic steels for next-generation reactors Klueh, R. L.; Nelson, A. T. Journal of Nuclear Materials, Vol. 371, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2007.05.005	journal	September 2007
Dislocation loop evolution under ion irradiation in austenitic stainless steels Etienne, A.; Hernández-Mayoral, M.; Genevois, C. Journal of Nuclear Materials, Vol. 400, Issue 1 https://doi.org/10.1016/j.jnucmat.2010.02.009	journal	May 2010
Ab-initio based modeling of diffusion in dilute bcc Fe–Ni and Fe–Cr alloys and implications for radiation induced segregation Choudhury, S.; Barnard, L.; Tucker, J. D. Journal of Nuclear Materials, Vol. 411, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2010.12.231	journal	April 2011
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
Silicon carbide composites as fusion power reactor structural materials Snead, L. L.; Nozawa, T.; Ferraris, M. Journal of Nuclear Materials, Vol. 417, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2011.03.005	journal	October 2011
Modeling radiation induced segregation in Ni–Cr model alloys from first principles Barnard, L.; Tucker, J. D.; Choudhury, S. Journal of Nuclear Materials, Vol. 425, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2011.08.022	journal	June 2012
On the radiation-induced segregation: Contribution of interstitial mechanism in Fe–Cr alloys Pechenkin, V. A.; Molodtsov, V. L.; Ryabov, V. A. Journal of Nuclear Materials, Vol. 433, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2012.10.016	journal	February 2013
Present status of vanadium alloys for fusion applications Muroga, T.; Chen, J. M.; Chernov, V. M. Journal of Nuclear Materials, Vol. 455, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2014.06.025	journal	December 2014
TEM, XRD and nanoindentation characterization of Xenon ion irradiation damage in austenitic stainless steels Huang, H. F.; Li, J. J.; Li, D. H. Journal of Nuclear Materials, Vol. 454, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2014.07.033	journal	November 2014
On the superior hot hardness and softening resistance of AlCoCrxFeMo0.5Ni high-entropy alloys Hsu, Chin-You; Juan, Chien-Chang; Wang, Woei-Ren Materials Science and Engineering: A, Vol. 528, Issue 10-11 https://doi.org/10.1016/j.msea.2011.01.072	journal	April 2011
Microstructures and mechanical properties of compositionally complex Co-free FeNiMnCr18 FCC solid solution alloy Wu, Z.; Bei, H. Materials Science and Engineering: A, Vol. 640 https://doi.org/10.1016/j.msea.2015.05.097	journal	July 2015
Radiation-induced degradation of stainless steel light water reactor internals Kenik, Edward A.; Busby, Jeremy T. Materials Science and Engineering: R: Reports, Vol. 73, Issue 7-8 https://doi.org/10.1016/j.mser.2012.05.002	journal	July 2012
On the use of SRIM for computing radiation damage exposure Stoller, R. E.; Toloczko, M. B.; Was, G. S. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, Vol. 310 https://doi.org/10.1016/j.nimb.2013.05.008	journal	September 2013
Effects of helium and hydrogen on radiation-induced microstructural changes in austenitic stainless steel Jin, Hyung-Ha; Ko, Eunsol; Lim, Sangyeop Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, Vol. 359 https://doi.org/10.1016/j.nimb.2015.07.086	journal	September 2015
Comparison of radiation-induced segregation in ultrafine-grained and conventional 316 austenitic stainless steels Etienne, A.; Radiguet, B.; Cunningham, N. J. Ultramicroscopy, Vol. 111, Issue 6 https://doi.org/10.1016/j.ultramic.2010.12.026	journal	May 2011
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
Superior radiation-resistant nanoengineered austenitic 304L stainless steel for applications in extreme radiation environments Sun, C.; Zheng, S.; Wei, C. C. Scientific Reports, Vol. 5, Issue 1 https://doi.org/10.1038/srep07801	journal	January 2015
Solid solution alloys of AlCoCrFeNiTix with excellent room-temperature mechanical properties Zhou, Y. J.; Zhang, Y.; Wang, Y. L. Applied Physics Letters, Vol. 90, Issue 18 https://doi.org/10.1063/1.2734517	journal	April 2007
Radiation Induced Segregation at Grain Boundary in an Austenitic Stainless Steel under Ion Irradiation Shigenaka, Naoto; Ono, Shigeki; Isobe, Yusuke Journal of Nuclear Science and Technology, Vol. 33, Issue 6 https://doi.org/10.1080/18811248.1996.9731939	journal	June 1996
Segregation in irradiated alloys: The inverse Kirkendall effect and the effect of constitution on void swelling Marwick, A. D. Journal of Physics F: Metal Physics, Vol. 8, Issue 9 https://doi.org/10.1088/0305-4608/8/9/008	journal	September 1978
Interatomic potential for studying ageing under irradiation in stainless steels: the FeNiCr model alloy Bonny, G.; Castin, N.; Terentyev, D. Modelling and Simulation in Materials Science and Engineering, Vol. 21, Issue 8 https://doi.org/10.1088/0965-0393/21/8/085004	journal	October 2013
Defect and solute properties in dilute Fe-Cr-Ni austenitic alloys from first principles Klaver, T. P. C.; Hepburn, D. J.; Ackland, G. J. Physical Review B, Vol. 85, Issue 17 https://doi.org/10.1103/PhysRevB.85.174111	journal	May 2012
Measuring and Interpreting the Structure of Grain-Boundary Networks: Measuring and Interpreting the Structure of Grain-Boundary Networks Rohrer, Gregory S. Journal of the American Ceramic Society, Vol. 94, Issue 3 https://doi.org/10.1111/j.1551-2916.2011.04384.x	journal	February 2011
Strengthening Materials by Engineering Coherent Internal Boundaries at the Nanoscale Lu, K.; Lu, L.; Suresh, S. Science, Vol. 324, Issue 5925 https://doi.org/10.1126/science.1159610	journal	April 2009
Designing Radiation Resistance in Materials for Fusion Energy Zinkle, S. J.; Snead, L. L. Annual Review of Materials Research, Vol. 44, Issue 1 https://doi.org/10.1146/annurev-matsci-070813-113627	journal	July 2014
Recent Developments in Irradiation-Resistant Steels Odette, G. R.; Alinger, M. J.; Wirth, B. D. Annual Review of Materials Research, Vol. 38, Issue 1, p. 471-503 https://doi.org/10.1146/annurev.matsci.38.060407.130315	journal	August 2008
Radiation-Induced Swelling in an Austenitic Alloy: Observations and Interpretation of the Effects of Helium Packan, Nicolas H.; Farrell, Kenneth Nuclear Technology - Fusion, Vol. 3, Issue 3 https://doi.org/10.13182/FST83-A20863	journal	May 1983
An improved technique for determining hardness and elastic modulus using load and displacement sensing indentation experiments Oliver, W. C.; Pharr, G. M. Journal of Materials Research, Vol. 7, Issue 06, p. 1564-1583 https://doi.org/10.1557/JMR.1992.1564	journal	June 1992
Classification of Bulk Metallic Glasses by Atomic Size Difference, Heat of Mixing and Period of Constituent Elements and Its Application to Characterization of the Main Alloying Element Takeuchi, Akira; Inoue, Akihisa MATERIALS TRANSACTIONS, Vol. 46, Issue 12 https://doi.org/10.2320/matertrans.46.2817	journal	January 2005
Phase Instability and Void Formation in Neutron-Irradiated Fe–Cr–Mn–Ni Alloys Ohnuki, S.; Garner, F. A.; Takahashi, H. Materials Transactions, JIM, Vol. 34, Issue 11 https://doi.org/10.2320/matertrans1989.34.1031	journal	January 1993

Cited By (29)

Effects of chemical alternation on damage accumulation in concentrated solid-solution alloys Ullah, Mohammad W.; Xue, Haizhou; Velisa, Gihan Scientific Reports, Vol. 7, Issue 1 https://doi.org/10.1038/s41598-017-04541-8	journal	June 2017
Origin of radiation resistance in multi-principal element alloys Do, Hyeon-Seok; Lee, Byeong-Joo Scientific Reports, Vol. 8, Issue 1 https://doi.org/10.1038/s41598-018-34486-5	journal	October 2018
Proton Irradiation Effects on Hardness and the Volta Potential of Welding 308L Duplex Stainless Steel Jiang, Baolong; Peng, Qunjia; Jiao, Zhijie Micromachines, Vol. 10, Issue 1 https://doi.org/10.3390/mi10010011	journal	December 2018
Beating Thermal Coarsening in Nanoporous Materials via High‐Entropy Design Joo, Soo‐Hyun; Bae, Jae Wung; Park, Won‐Young Advanced Materials, Vol. 32, Issue 6 https://doi.org/10.1002/adma.201906160	journal	December 2019
Fabrication of ODS Austenitic Steels and CoCrFeNi High-Entropy Alloys by Spark Plasma Sintering for Nuclear Energy Applications Yan, Xueliang; Zhang, Xiang; Wang, Fei JOM, Vol. 71, Issue 8 https://doi.org/10.1007/s11837-019-03531-7	journal	May 2019
Thermal Stability and Mechanical Properties of Low-Activation Single-Phase Ti-V-Ta Medium Entropy Alloys Jia, Nannan; Li, Yunkai; Liu, Xuan JOM, Vol. 71, Issue 10 https://doi.org/10.1007/s11837-019-03713-3	journal	August 2019
High-Throughput Nanomechanical Screening of Phase-Specific and Temperature-Dependent Hardness in AlxFeCrNiMn High-Entropy Alloys Chen, Youxing; Hintsala, Eric; Li, Nan JOM, Vol. 71, Issue 10 https://doi.org/10.1007/s11837-019-03714-2	journal	August 2019
Effects of Al and Ti Additions on Irradiation Behavior of FeMnNiCr Multi-Principal-Element Alloy Hoffman, Andrew; He, Li; Luebbe, Matthew JOM, Vol. 72, Issue 1 https://doi.org/10.1007/s11837-019-03871-4	journal	October 2019
Science and technology in high-entropy alloys Zhang, Weiran; Liaw, Peter K.; Zhang, Yong Science China Materials, Vol. 61, Issue 1 https://doi.org/10.1007/s40843-017-9195-8	journal	January 2018
Precipitation behavior of AlxCoCrFeNi high entropy alloys under ion irradiation Yang, Tengfei; Xia, Songqin; Liu, Shi Scientific Reports, Vol. 6, Issue 1 https://doi.org/10.1038/srep32146	journal	August 2016
Study on the damping behaviour of eutectic high-entropy alloys with lamellar structures Lin, Li-Feng; Tsai, Che-Wei Philosophical Magazine Letters, Vol. 99, Issue 6 https://doi.org/10.1080/09500839.2019.1660819	journal	June 2019
Thermal stability of microstructures and mechanical properties in a Fe-based Fe-Cr-Mn-Cu-Mo multi-component alloy Zhong, Z. H.; Xu, Q.; Mori, K. Philosophical Magazine, Vol. 99, Issue 12 https://doi.org/10.1080/14786435.2019.1585588	journal	February 2019
Effects of pulsed laser surface treatments on microstructural characteristics and hardness of CrCoNi medium-entropy alloy Chai, Linjiang; Xiang, Kang; Xia, Jiying Philosophical Magazine, Vol. 99, Issue 24 https://doi.org/10.1080/14786435.2019.1649499	journal	August 2019
Effect of irradiation on microstructure and hardening of Cr–Fe–Ni–Mn high-entropy alloy and its strengthened version Voyevodin, V. N.; Karpov, S. A.; Tolstolutskaya, G. D. Philosophical Magazine, Vol. 100, Issue 7 https://doi.org/10.1080/14786435.2019.1704091	journal	December 2019
Delayed damage accumulation by athermal suppression of defect production in concentrated solid solution alloys Velişa, G.; Wendler, E.; Zhao, S. Materials Research Letters, Vol. 6, Issue 2 https://doi.org/10.1080/21663831.2017.1410863	journal	December 2017
Computational characterization of the structural and mechanical properties of Al x CoCrFeNiTi 1− x high entropy alloys Bao, Nanyun; Zuo, Jie; Du, Zhenyu Materials Research Express, Vol. 6, Issue 9 https://doi.org/10.1088/2053-1591/ab2b77	journal	July 2019
Corrosion resistance mechanism of the passive films formed on as-cast FeCoCrNiMn high-entropy alloy Jinlong, Lv; Jin, Huijin Materials Research Express, Vol. 7, Issue 1 https://doi.org/10.1088/2053-1591/ab6c92	journal	January 2020
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
Breakthrough applications of high-entropy materials Yeh, Jien-Wei; Lin, Su-Jien Journal of Materials Research, Vol. 33, Issue 19 https://doi.org/10.1557/jmr.2018.283	journal	August 2018
Irradiation responses and defect behavior of single-phase concentrated solid solution alloys Yang, Tengfei; Li, Congyi; Zinkle, Steven J. Journal of Materials Research, Vol. 33, Issue 19 https://doi.org/10.1557/jmr.2018.285	journal	September 2018
Dissimilar welding of Al _0.1 CoCrFeNi high-entropy alloy and AISI304 stainless steel Sokkalingam, Rathinavelu; Muthupandi, Veerappan; Sivaprasad, Katakam Journal of Materials Research, Vol. 34, Issue 15 https://doi.org/10.1557/jmr.2019.186	journal	June 2019
Radiation stability of nanocrystalline single-phase multicomponent alloys Levo, Emil; Granberg, Fredric; Utt, Daniel Journal of Materials Research, Vol. 34, Issue 5 https://doi.org/10.1557/jmr.2019.19	journal	February 2019
Cold Gas Spraying of a High-Entropy CrFeNiMn Equiatomic Alloy Lehtonen, Joonas; Koivuluoto, Heli; Ge, Yanling Coatings, Vol. 10, Issue 1 https://doi.org/10.3390/coatings10010053	journal	January 2020
Evaluation of Radiation Response in CoCrFeCuNi High-Entropy Alloys Wang, Yang; Zhang, Kun; Feng, Yihui Entropy, Vol. 20, Issue 11 https://doi.org/10.3390/e20110835	journal	October 2018
A Novel Low-Activation VCrFeTaxWx (x = 0.1, 0.2, 0.3, 0.4, and 1) High-Entropy Alloys with Excellent Heat-Softening Resistance Zhang, Weiran; Liaw, Peter; Zhang, Yong Entropy, Vol. 20, Issue 12 https://doi.org/10.3390/e20120951	journal	December 2018
Configurational Entropy in Multicomponent Alloys: Matrix Formulation from Ab Initio Based Hamiltonian and Application to the FCC Cr-Fe-Mn-Ni System Fernández-Caballero, Antonio; Fedorov, Mark; Wróbel, Jan Entropy, Vol. 21, Issue 1 https://doi.org/10.3390/e21010068	journal	January 2019
Hot Deformation Behavior of As-Cast and Homogenized Al0.5CoCrFeNi High Entropy Alloys Zhang, Yu; Li, Jinshan; Wang, Jun Metals, Vol. 6, Issue 11 https://doi.org/10.3390/met6110277	journal	November 2016
Delayed damage accumulation by athermal suppression of defect production in concentrated solid solution alloys Velişa, G.; Wendler, E.; Zhao, S. Taylor & Francis https://doi.org/10.6084/m9.figshare.5711458	text	January 2017
Delayed damage accumulation by athermal suppression of defect production in concentrated solid solution alloys [Supplementary Data] Velişa, G.; Wendler, E.; Zhao, S. Figshare-Supplementary information for journal article at DOI: 10.1080/21663831.2017.1410863, 1 .docx file (2.08 MB) https://doi.org/10.6084/m9.figshare.5711458.v1	preprint	December 2017

Similar Records

The effects of carbon on the phase stability and mechanical properties of heat-treated FeNiMnCrAl high entropy alloys

Journal Article · Fri Jan 25 19:00:00 EST 2019 · Materials Science and Engineering. A, Structural Materials: Properties, Microstructure and Processing · OSTI ID:1593731

In situ microstructural evolution in face-centered and body-centered cubic complex concentrated solid-solution alloys under heavy ion irradiation

Journal Article · Fri Jul 31 20:00:00 EDT 2020 · Acta Materialia · OSTI ID:1776842

Related Subjects

36 MATERIALS SCIENCE
concentrated multi-component solid solution alloy
dislocation loops
high entropy alloy
irradiation defects
radiation-induced segregation

Microstructural stability and mechanical behavior of FeNiMnCr high entropy alloy under ion irradiation

Citation Formats

References (93)

Cited By (29)

Similar Records

Related Subjects