The effect of injected interstitials on void formation in self-ion irradiated nickel containing concentrated solid solution alloys

Yang, Tonghai; Lu, Chenyang; Jin, Ke; Crespillo, Miguel L.; Zhang, Yongfeng; Bei, Hongbin; Wang, Lumin

doi:10.1016/j.jnucmat.2017.02.026

Cited by 53 publications

(24 citation statements)

References 35 publications

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“…The trend has been reported to be real even when the suppression of voiding by injected interstitials is accounted for [ 87 ], and follows trends reported from the 1970s onwards in Ni-Cu alloys [ 89 , 90 , 91 , 92 ]. Some have found little evidence of void formation under conditions where they would typically be expected in conventional alloys [ 67 , 78 , 93 , 94 ], although most others have seen voiding, but at a suppressed level [ 75 , 80 , 86 , 87 , 88 , 95 ]. For instance, significant void swelling has been observed in CrFeCoNi, but only at high damage doses, 86–250 dpa.…”

Section: The Potential Suitability Of Heas—irradiation Resistant?supporting

confidence: 72%

Section: The Potential Suitability Of Heas—irradiation Resistant?mentioning

confidence: 99%

“…A number of studies have measured the irradiation void swelling in concentrated alloys, including HEAs, to be significantly lower than in pure metals, often by over an order of magnitude for the same damage level [ 3 , 52 , 85 , 86 , 87 , 88 ]. The trend has been reported to be real even when the suppression of voiding by injected interstitials is accounted for [ 87 ], and follows trends reported from the 1970s onwards in Ni-Cu alloys [ 89 , 90 , 91 , 92 ]. Some have found little evidence of void formation under conditions where they would typically be expected in conventional alloys [ 67 , 78 , 93 , 94 ], although most others have seen voiding, but at a suppressed level [ 75 , 80 , 86 , 87 , 88 , 95 ].…”

Section: The Potential Suitability Of Heas—irradiation Resistant?mentioning

confidence: 99%

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High-Entropy Alloys for Advanced Nuclear Applications

Pickering

Carruthers

Barron

et al. 2021

Entropy

195

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The expanded compositional freedom afforded by high-entropy alloys (HEAs) represents a unique opportunity for the design of alloys for advanced nuclear applications, in particular for applications where current engineering alloys fall short. This review assesses the work done to date in the field of HEAs for nuclear applications, provides critical insight into the conclusions drawn, and highlights possibilities and challenges for future study. It is found that our understanding of the irradiation responses of HEAs remains in its infancy, and much work is needed in order for our knowledge of any single HEA system to match our understanding of conventional alloys such as austenitic steels. A number of studies have suggested that HEAs possess ‘special’ irradiation damage resistance, although some of the proposed mechanisms, such as those based on sluggish diffusion and lattice distortion, remain somewhat unconvincing (certainly in terms of being universally applicable to all HEAs). Nevertheless, there may be some mechanisms and effects that are uniquely different in HEAs when compared to more conventional alloys, such as the effect that their poor thermal conductivities have on the displacement cascade. Furthermore, the opportunity to tune the compositions of HEAs over a large range to optimise particular irradiation responses could be very powerful, even if the design process remains challenging.

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Section: The Potential Suitability Of Heas—irradiation Resistant?supporting

confidence: 72%

Section: The Potential Suitability Of Heas—irradiation Resistant?mentioning

confidence: 99%

Section: The Potential Suitability Of Heas—irradiation Resistant?mentioning

confidence: 99%

See 1 more Smart Citation

High-Entropy Alloys for Advanced Nuclear Applications

Pickering

Carruthers

Barron

et al. 2021

Entropy

195

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“…Bright-field TEM imaging of dislocation loops were taken in a two-beam condition (g = [200]) using JEOL 3011. To minimize the artificial effects from surface sinks and injected interstitials 46 , the region of 700±100 nm with a damage dose of 50±5 dpa-calculated by SRIM 08 41 was chosen for the statistic study of loop distribution.…”

Section: Discussionmentioning

confidence: 99%

Local lattice distortion in high-entropy alloys

Song

Tian

et al. 2017

Phys. Rev. Materials

203

123

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The atomic-level tunability that results from alloying multiple transition metals with d electrons in concentrated solid solution alloys (CSAs), including high-entropy alloys (HEAs), has produced remarkable properties for advanced energy applications, in particular, damage resistance in high-radiation environments. The key to understanding CSAs' radiation performance is quantitatively characterizing their complex local physical and chemical environments. In this study, the local structure of a FeCoNiCrPd HEA is quantitatively analyzed with X-ray total scattering and extended X-ray absorption fine

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“…In addition to the overall swelling values, the void formation has been observed under cross-sectional TEM observation Yang et al, 2017). Two qualitatively different types of depth distributions have been observed among these materials.…”

Section: Response To the Irradiations At Elevated Temperaturesmentioning

confidence: 96%

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

Jin

Bei

2018

Front. Mater.

Self Cite

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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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The effect of injected interstitials on void formation in self-ion irradiated nickel containing concentrated solid solution alloys

Cited by 53 publications

References 35 publications

High-Entropy Alloys for Advanced Nuclear Applications

High-Entropy Alloys for Advanced Nuclear Applications

Local lattice distortion in high-entropy alloys

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

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