Effects of 14 MeV nickel ion irradiation on nickel-copper alloys observed in cross-section

Wang, L.M.; Dodd, R.A.; Kulcinski, G.L.

doi:10.1016/0022-3115(88)90504-1

Cited by 12 publications

(5 citation statements)

References 12 publications

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“…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?supporting

confidence: 63%

“…The complexities of void nucleation and growth in concentrated alloys have been illustrated by investigations of void distribution through the depths of irradiated layers. Voids in pure Ni and some binaries have been found to be significantly larger and more evenly-distributed through the irradiated depth than those in higher-order alloys, which have tended to show fewer smaller voids [ 3 , 80 , 85 , 86 , 87 , 91 ]. The size, density and distribution have been found to be dependent on composition, with an apparent effect of the atomic size difference between the atoms present [ 75 , 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: 63%

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

confidence: 99%

High-Entropy Alloys for Advanced Nuclear Applications

Pickering

Carruthers

Barron

et al. 2021

Entropy

195

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“…Their response is unlike that of the widely used austenitic steels, e.g., Type 304 or 316, which are more susceptible to radiation-induced swelling than is Ni. [6,25] The NiFe binary alloy exhibits more than an order of magnitude less swelling than Ni, suggesting that the addition of Fe has a stronger suppression effect on void nucleation and growth than the addition of Co, similar to the behavior previously observed in NiCu binary alloys [26]. The two ternary alloys, NiCoFe and NiCoCr, both have lower swelling than their mutual binary base, NiCo-; and alloying with Fe is more effective in reducing swelling than is alloying with Cr.…”

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confidence: 64%

Effects of compositional complexity on the ion-irradiation induced swelling and hardening in Ni-containing equiatomic alloys

et al. 2016

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The impact of compositional complexity on the ion-irradiation induced swelling and hardening is studied in Ni and six Ni-containing equiatomic alloys with face-centered cubic structure. The irradiation resistance at the temperature of 500 °C is improved by controlling the number and, especially, the type of alloying elements. Alloying with Fe and Mn has a stronger influence on swelling reduction than does alloying with Co and Cr. The quinary alloy NiCoFeCrMn, with known excellent mechanical properties, has shown 40 times higher swelling tolerance than nickel.

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“…Nickel and various single-phase nickel alloys have been used in studying the alloying effects in irradiation induced defect evolution [1][2][3][4]. Heavy-ions and neutrons are commonly used as the irradiation source to investigate the effect of alloying elements on defect cluster formation, such as swelling and radiation-induced segregation [1][2][3][4]. In some cases, minor elements in nickel alloys existed in the form of ordered solutes [1,[4][5][6][7] and their distributions were not completely random.…”

Section: Introductionmentioning

confidence: 99%

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

Yang

Jin

et al. 2017

Journal of Nuclear Materials

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Pure nickel and three nickel containing single-phase concentrated solid solution alloys (SP-CSAs) have been irradiated using 3 MeV Ni 2+ ions at to fluences of and. The radiation-induced voids were characterized using cross sectional transmission electron microscopy that distributions of voids and dislocation loops were presented as a function of depth. A various degree of void suppression was observed on the tested samples and a defect clusters migration mechanism was proposed for NiCo. In order to sufficiently understand the defect dynamics in these SP-CSAs, the injected interstitial effect has been taken into account along with the 1-dimentional (1-D) and 3-dimentional (3-D) interstitial movement mechanisms.

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Effects of 14 MeV nickel ion irradiation on nickel-copper alloys observed in cross-section

Cited by 12 publications

References 12 publications

High-Entropy Alloys for Advanced Nuclear Applications

High-Entropy Alloys for Advanced Nuclear Applications

Effects of compositional complexity on the ion-irradiation induced swelling and hardening in Ni-containing equiatomic alloys

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

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