Influence of chemical disorder on energy dissipation and defect evolution in advanced alloys

Zhang, Yongfeng; Jin, Ke; Xue, Haizhou; Lu, Chenyang; Olsen, Raina J.; Béland, Laurent Karim; Ullah, Mohammad W.; Zhao, Shijun; Bei, Hongbin; Aidhy, Dilpuneet S.; Samolyuk, German D.; Wang, Lumin; Caro, M.; Caro, A.; Stocks, G. M.; Larson, B. C.; Robertson, I. M.; Correa, Alfredo A.; Weber, William J.

doi:10.1557/jmr.2016.269

Cited by 126 publications

(80 citation statements)

References 53 publications

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“…The temperature dependence of microstructure evolution under ion irradiations at elevated temperatures has been performed in FeNiMnCr 0.66 to 10 dpa at 400-700 • C (Kumar et al, 2016), and in NiCoFeCrAl 0.1 to 31 dpa at 250-650 • C FIGURE 6 | (a) Ion channeling spectra of several Ni-containing FCC SP-CSAs irradiated with 1.5 MeV Ni ions to the fluence of 1 × 10 14 cm −2 , adapted from Zhang et al (2016). Reproduced with the permission of the copyright holder (Cambridge University Press).…”

Section: Response To the Irradiations At Elevated Temperaturesmentioning

confidence: 99%

Single-Phase Concentrated Solid-Solution Alloys: Bridging Intrinsic Transport Properties and Irradiation Resistance

Jin

Bei

2018

Front. Mater.

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Single-phase concentrated solid-solution alloys (SP-CSAs), including high entropy alloys (HEAs), are compositionally complex but structurally simple, and provide a playground of tailoring material properties through modifying their compositional complexity. The recent progress in understanding the compositional effects on the energy and mass transport properties in a series of face-centered-cubic SP-CSAs is the focus of this review. Relatively low electrical and thermal conductivities, as well as small separations between the interstitial and vacancy migration barriers have been generally observed, but largely depend on the alloying constituents. We further discuss the impact of such intrinsic transport properties on their irradiation response; the linkage to the delayed damage accumulation, slow defect aggregation, and suppressed irradiation induced swelling and segregation has been presented. We emphasize that the number of alloying elements may not be a critical factor on both transport properties and the defect behaviors under ion irradiations. The recent findings have stimulated novel concepts in the design of new radiation-tolerant materials, but further studies are demanded to enable predictive models that can quantitatively bridge the transport properties to the radiation damage.

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Section: Response To the Irradiations At Elevated Temperaturesmentioning

confidence: 99%

Single-Phase Concentrated Solid-Solution Alloys: Bridging Intrinsic Transport Properties and Irradiation Resistance

Jin

Bei

2018

Front. Mater.

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“…Historically, alloy development with desired performance focused on traditional alloys, where enhanced radiation resistance relied largely on unique microstructural heterogeneity to mitigate displacement damage 6 . In contrast to traditional alloys (containing one or two principle elements), SP-CSAs contain two to five or more elements at high concentration, sometimes at equal or near-equal concentration.…”

Section: Introductionmentioning

confidence: 99%

Effects of chemical alternation on damage accumulation in concentrated solid-solution alloys

Ullah

Xue

Velişa

et al. 2017

Sci Rep

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Single-phase concentrated solid-solution alloys (SP-CSAs) have recently gained unprecedented attention due to their promising properties. To understand effects of alloying elements on irradiation-induced defect production, recombination and evolution, an integrated study of ion irradiation, ion beam analysis and atomistic simulations are carried out on a unique set of model crystals with increasing chemical complexity, from pure Ni to Ni80Fe20, Ni50Fe50, and Ni80Cr20 binaries, and to a more complex Ni40Fe40Cr20 alloy. Both experimental and simulation results suggest that the binary and ternary alloys exhibit higher radiation resistance than elemental Ni. The modeling work predicts that Ni40Fe40Cr20 has the best radiation tolerance, with the number of surviving Frenkel pairs being factors of 2.0 and 1.4 lower than pure Ni and the 80:20 binary alloys, respectively. While the reduced defect mobility in SP-CSAs is identified as a general mechanism leading to slower growth of large defect clusters, the effect of specific alloying elements on suppression of damage accumulation is clearly demonstrated. This work suggests that concentrated solid-solution provides an effective way to enhance radiation tolerance by creating elemental alternation at the atomic level. The demonstrated chemical effects on defect dynamics may inspire new design principles of radiation-tolerant structural alloys for advanced energy systems.

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“…In low-dose ion-beam experiments, with ion energies of a few MeV, NiFe was shown to generate fewer microstructural defects than pure Ni, as measured by Rutherford backscattering (RBS) and TEM [3]. This is in agreement with MD simulations, that predict substantial (of the order of 50 %) reduction of Frenkel Pair yield of displacement cascades in NiFe, relative to Ni [3,4]. These experiments generated roughly 0.01 displacements per atom (dpa).…”

Section: Introductionmentioning

confidence: 99%

Differences in the accumulation of ion-beam damage in Ni and NiFe explained by atomistic simulations

Béland

Samolyuk

Stoller

2016

Journal of Alloys and Compounds

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Following low-dose irradiation with a 3 MeV beam of Au ions, i.e. less than one displacement per atom, a lower number of defects were experimentally observed in NiFe than in pure Ni. At higher doses, more damage is observed in NiFe than in pure Ni. Also, at these high doses, defect structures are observed deep in the material, far from the region where ions are implanted, more so in Ni than in NiFe. In this study, these experimental results are explained using atomistic modeling. Sequences of overlapping displacement cascades with intervening defect aging are simulated. Evidence is provided that nanosecond aging at 900K can be used as a surrogate for long-time, room-temperature aging. Then, using this procedure, it is shown that the low defect diffusivity of NiFe leads to less aggregation and recombination events between each displacement cascade in a given volume than in Ni. Variations in the local defect chemistry in NiFe produces a broad spectrum of defect formation energy, leading to the trapping of defects at energetically favorable sites: this explains the low defect diffusivity. Also, this low diffusivity explains why, at high dose, defects in NiFe do not propagate as deeply in the material than in pure Ni.

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Influence of chemical disorder on energy dissipation and defect evolution in advanced alloys

Abstract: Abstract

Cited by 126 publications

References 53 publications

Single-Phase Concentrated Solid-Solution Alloys: Bridging Intrinsic Transport Properties and Irradiation Resistance

Single-Phase Concentrated Solid-Solution Alloys: Bridging Intrinsic Transport Properties and Irradiation Resistance

Effects of chemical alternation on damage accumulation in concentrated solid-solution alloys

Differences in the accumulation of ion-beam damage in Ni and NiFe explained by atomistic simulations

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