journal article·2022-07Open access

Phase stability, mechanical properties, and ion irradiation effects in face-centered cubic CrFeMnNi compositionally complex solid-solution alloys at high temperatures

Calvin Parkin, Michael Moorehead, Mohamed Elbakhshwan, Xuan Zhang, Pengyuan Xiu, Lingfeng He, Mukesh Bachhav, Kumar Sridharan, Adrien Couet

Abstract

Two CrFeMnNi face-centered cubic complex concentrated solid-solution alloys (CSA) have been evaluated for phase stability, mechanical properties, and radiation damage effects from heavy ions. Cr 18Fe 27Mn 27Ni 28 and Cr 15Fe 35Mn 15Ni 35 were predicted by thermodynamic calculations to phase separate and maintain a single phase at 700 °C, respectively. Aging experiments at this temperature confirmed varying degrees of precipitation of a body-centered cubic phase in both Cr 18Fe 27Mn 27Ni 28 and Cr 15Fe 35Mn 15Ni 35. The alloys showed promising strength in tensile deformation at room temperature, with yield strengths of 155 MPa and 151 MPa for Cr 18Fe 27Mn 27Ni 28 and Cr 15Fe 35Mn 15Ni 35, respectively. At 500 °C, the yield strength of Cr 18Fe 27Mn 27Ni 28 fell to 93 MPa, and to 100 MPa in Cr 15Fe 35Mn 15Ni 35. Unlike Cr 18Fe 27Mn 27Ni 28, Cr 15Fe 35Mn 15Ni 35 gained some ductility at 500 °C compared to room temperature. The two CSAs were irradiated to 75 dpa at 500 °C in the plateau region of the displacement curve using 3.7 MeV Ni 2+ ions, alongside model alloy 709 as a reference. Irradiation results produced similar densities and sizes of dislocations loops in the two CSAs compared to the reference. However, while large voids form in the plateau region of Cr 18Fe 27Mn 27Ni 28, small voids form just beyond the displacement peak of Cr 15Fe 35Mn 15Ni 35. Atom probe tomography and energy dispersive X-ray spectroscopy-equipped scanning transmission electron microscopes were used to characterize the alloys for changes in chemical distribution.
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Research context

OpenAlex topics: High Entropy Alloys Studies · Nuclear Materials and Properties · Fusion materials and technologies

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References (56)

Show source-provided references
1. Single-phase concentrated solid-solution alloys: bridging intrinsic transport properties and irradiation resistance
2. A critical review of high entropy alloys and related concepts10.1016/j.actamat.2016.08.081 ↗
3. Characterization of microstructure and property evolution in advanced cladding and duct: materials exposed to high dose and elevated temperature10.1557/jmr.2015.99 ↗
4. Advanced materials for indian future nuclear energy systems
5. Thermally activated deformation and the rate controlling mechanism in CoCrFeMnNi high entropy alloy10.1016/j.msea.2016.11.078 ↗
6. Nanomechanical behavior of CoCrFeMnNi High-Entropy Alloy10.1007/s11837-015-1566-6 ↗
7. The influences of temperature and microstructure on the tensile properties of a CoCrFeMnNi high-entropy alloy10.1016/j.actamat.2013.06.018 ↗
8. Mechanical properties, microstructure and thermal stability of a nanocrystalline CoCrFeMnNi high-entropy alloy after severe plastic deformation10.1016/j.actamat.2015.06.025 ↗
9. The high temperature tensile and creep behaviors of high entropy superalloy10.1038/s41598-017-13026-7 ↗
10. Tensile properties of an AlCrCuNiFeCo high-entropy alloy in as-cast and wrought conditions10.1016/j.msea.2011.11.045 ↗
11. Microstructural stability and mechanical behavior of FeNiMnCr high entropy alloy under ion irradiation10.1016/j.actamat.2016.05.007 ↗
12. Local electronic effects and irradiation resistance in high-entropy alloys10.1007/s11837-015-1579-1 ↗
13. Phonon broadening in high entropy alloys
14. Influence of chemical disorder on energy dissipation and defect evolution in advanced alloys10.1557/jmr.2016.269 ↗
15. Frenkel defect recombination in Ni and Ni-containing concentrated solid-solution alloys10.1016/j.actamat.2019.04.060 ↗
16. Lattice thermal conductivity of multi-component alloys10.1016/j.jallcom.2015.06.035 ↗
17. The effect of alloying nickel with iron on the supersonic ballistic stage of high energy displacement cascades10.1016/j.actamat.2016.06.031 ↗
18. Sluggish diffusion in Co–Cr–Fe–Mn–Ni high-entropy alloys10.1016/j.actamat.2013.04.058 ↗
19. Effects of compositional complexity on the ion-irradiation induced swelling and hardening in Ni-containing equiatomic alloys10.1016/j.scriptamat.2016.03.030 ↗
20. Irradiation responses and defect behavior of single-phase concentrated solid solution alloys10.1557/jmr.2018.285 ↗
21. Enhancing radiation tolerance by controlling defect mobility and migration pathways in multicomponent single-phase alloys10.1038/ncomms13564 ↗
22. Radiation-induced segregation on defect clusters in single-phase concentrated solid-solution alloys10.1016/j.actamat.2017.01.019 ↗
23. Irradiation effects in high entropy alloys and 316H stainless steel at 300 °C10.1016/j.jnucmat.2018.08.031 ↗
24. Neutron irradiation response of a Co-free high entropy alloy10.1016/j.jnucmat.2019.151838 ↗
25. Materials for future nuclear energy systems10.1016/j.jnucmat.2019.151837 ↗
26. In situ microstructural evolution in face-centered and body-centered cubic complex concentrated solid-solution alloys under heavy ion irradiation10.1016/j.actamat.2020.07.066 ↗
27. Enhanced diffusion of Cr in 20Cr-25Ni type alloys under proton irradiation at 670°C10.1016/j.nme.2018.10.001 ↗
28. ASTM, Standard Practice for investigating the effects of neutron radiation damage using charged-particle irradiation. 2018.
29. Erratum to “On the use of SRIM for computing radiation damage exposure” [Nucl. Instrum. Methods Phys. Res. B 310 (2013) 75–80]10.1016/j.nimb.2019.08.015 ↗
30. Quick calculation of damage for ion irradiation: implementation in Iradina and comparisons to SRIM
31. On the use of SRIM for calculating vacancy production: quick calculation and full-cascade options10.1016/j.nimb.2021.06.018 ↗
32. Chemical environment and magnetic moment effects on point defect formations in CoCrNi-based concentrated solid-solution alloys10.1016/j.actamat.2020.01.044 ↗
33. An experimental investigation of extrapolation methods in the derivation of accurate unit-cell dimensions of crystals10.1088/0959-5309/57/3/302 ↗
34. Liu, X., et al., Radiation response of a Fe–20Cr–25Ni austenitic stainless steel under Fe2+ irradiation at 500°C. Materialia, 2020. 9.10.1016/j.mtla.2019.100542 ↗
35. Dose dependence of the microstructural evolution in neutron-irradiated austenitic stainless steel10.1016/0022-3115(93)90128-L ↗
36. Evolution of ion damage at 773K in Ni- containing concentrated solid-solution alloys10.1016/j.jnucmat.2018.01.015 ↗
37. 1.03- radiation-induced effects on microstructure
38. Yang, Y., et al., Irradiation microstructure of austenitic steels and cast steels irradiated in the BOR-60 Reactor at 320°C. Proceedings of the 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems — Water Reactors, 2012.10.1002/9781118456835.ch222 ↗
39. Dislocation loop evolution and radiation hardening in nickel-based concentrated solid solution alloys10.1016/j.jnucmat.2020.152247 ↗
40. Corrosion and thermal stability of CrMnFeNi high entropy alloy in molten FLiBe Salt10.1038/s41598-019-55653-2 ↗
41. High-throughput synthesis of Mo-Nb-Ta-W high-entropy alloys via additive manufacturing10.1016/j.matdes.2019.108358 ↗
42. High-throughput ion irradiation of additively manufactured compositionally complex alloys10.1016/j.jnucmat.2021.152782 ↗
43. Discovery of new materials using combinatorial synthesis and high-throughput characterization of thin-film materials libraries combined with computational methods10.1038/s41524-019-0205-0 ↗
44. About the reliability of CALPHAD predictions in multicomponent systems
45. Swelling resistance of advanced austenitic alloy A709 and its comparison with 316 stainless steel at high damage levels10.1016/j.jnucmat.2019.151818 ↗
46. Nickel-ion bombardment of annealed and cold-worked type 316 stainless steel10.1016/0022-3115(73)90029-9 ↗
47. Influence of irradiation temperature on void swelling in NiCoFeCrMn and NiCoFeCrPd10.1016/j.scriptamat.2018.08.021 ↗
48. From suppressed void growth to significant void swelling in NiCoFeCr complex concentrated solid-solution alloy10.1016/j.mtla.2020.100603 ↗
49. Diffusion-mediated chemical concentration variation and void evolution in ion-irradiated NiCoFeCr high-entropy alloy10.1557/s43578-020-00071-8 ↗
50. Stacking fault energy maps of Fe–Mn–Al–C–Si Steels: effect of temperature, grain size, and variations in compositions10.1115/1.4033632 ↗
51. Dislocation loop nucleation in irradiated metals10.1016/0001-6160(73)90002-3 ↗
52. Fluctuations in stacking fault energies improve irradiation tolerance of concentrated solid-solution alloys10.1016/j.jnucmat.2019.151886 ↗
53. Effect of stacking fault energy on damage microstructure in ion-irradiated CoCrFeNiMnx concentrated solid solution alloys10.1016/j.jnucmat.2020.152642 ↗
54. First principle study of magnetism and vacancy energetics in a near equimolar NiFeMnCr high entropy alloy10.1063/1.5086172 ↗
55. Effect of defect imbalance on void swelling distributions produced in pure iron irradiated with 3.5 MeV self-ions10.1016/j.jnucmat.2014.06.002 ↗
56. Swelling and Radiation-Induced Segregation in Austentic Alloys10.1016/j.jnucmat.2005.02.008 ↗