Influence of defect dynamics on the nanoindentation hardness in NiCoCrFePd high entropy alloy under high dose Xe+3 irradiation

Hussain, Abid; Khan, Sabah; Sharma, S.K.; Sudarshan, K.; Sharma, Saurabh Kumar; Singh, Chetan; Kulriya, P.K.

doi:10.1016/j.msea.2022.144523

Cited by 13 publications

(5 citation statements)

References 48 publications

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“…The dislocation density in HEAs depends on the amount of point defects and their mobility in three dimensions, which in turn depend on helium. It was shown that dislocations can form from the agglomeration of point defects, and the dislocation density increases with irradiation fluence for NiCoCrFePd HEA irradiated by Xe 3+ ions [ 59 ]. Helium irradiation also affects the diffusion of point defects, and therefore changes the distribution of the dislocations in HEAs [ 31 ].…”

Section: Resultsmentioning

confidence: 99%

Composition and Structure of NiCoFeCr and NiCoFeCrMn High-Entropy Alloys Irradiated by Helium Ions

et al. 2023

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High-entropy alloys (HEAs) have prospects for use as nuclear structural materials. Helium irradiation can form bubbles deteriorating the structure of structural materials. The structure and composition of NiCoFeCr and NiCoFeCrMn HEAs formed by arc melting and irradiated with low-energy 40 keV He2+ ions and a fluence of 2 × 1017 cm−2 have been studied. Helium irradiation of two HEAs does not change the elemental and phase composition, and does not erode the surface. Irradiation of NiCoFeCr and NiCoFeCrMn with a fluence of 5 × 1016 cm−2 forms compressive stresses (−90 … −160 MPa) and the stresses grow over −650 MPa as fluence increases to 2 × 1017 cm−2. Compressive microstresses grow up to 2.7 GPa at a fluence of 5 × 1016 cm−2, and up to 6.8 GPa at 2 × 1017 cm−2. The dislocation density rises by a factor of 5–12 for a fluence of 5 × 1016 cm−2, and by 30–60 for a fluence of 2 × 1017 cm−2. Stresses and dislocation density in the HEAs change the most in the region of the maximal damage dose. NiCoFeCrMn has higher macro- and microstresses, dislocation density, and a larger increase in their values, with an increasing helium ion fluence compared to NiCoFeCr. NiCoFeCrMn a showed higher radiation resistance compared to NiCoFeCr.

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Section: Resultsmentioning

confidence: 99%

Composition and Structure of NiCoFeCr and NiCoFeCrMn High-Entropy Alloys Irradiated by Helium Ions

et al. 2023

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“…L d defines the irradiation depth, N 0 def is the peak irradiation defect density at the maximum irradiation depth, and n ≥ 0 is the parameter describing the defect distribution profile. With the increase in irradiation dose, the defect distribution after the directional migration to the surface also has a certain influence on the parameter (n) [39]. Then, when the plastic region is still completely contained within the irradiation region, the average defect density in the plastic region is…”

Section: Nanoindentation After Irradiationmentioning

confidence: 99%

Irradiation-Hardening Model of TiZrHfNbMo0.1 Refractory High-Entropy Alloys

Fan,

Wang,

et al. 2024

Entropy

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In order to find more excellent structural materials resistant to radiation damage, high-entropy alloys (HEAs) have been developed due to their characteristics of limited point defect diffusion such as lattice distortion and slow diffusion. Specially, refractory high-entropy alloys (RHEAs) that can adapt to a high-temperature environment are badly needed. In this study, TiZrHfNbMo0.1 RHEAs are selected for irradiation and nanoindentation experiments. We combined the mechanistic model for the depth-dependent hardness of ion-irradiated metals and the introduction of the scale factor f to modify the irradiation-hardening model in order to better describe the nanoindentation indentation process in the irradiated layer. Finally, it can be found that, with the increase in irradiation dose, a more serious lattice distortion caused by a higher defect density limits the expansion of the plastic zone.

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“…It is an irresistible trend to obtain clean, low-carbon, and safe energy generated from next generation fission and future fusion energy reactors to meet the needs of human society and industrial development in the long term [ 1 , 2 , 3 , 4 , 5 ]. The absence of compatible structural materials for extreme environments of high temperature, high neutron flux, and chemical reactivity hinders the development of advanced reactors [ 6 , 7 ].…”

Section: Introductionmentioning

confidence: 99%

“…Table 1. The values of T m (K), r (nm), ρ (g/cm 3 ), and VEC of some reduced-activation elements. Ordinarily, the He atoms produced by transmutation reaction would aggregate and form large-scale He bubbles for the limited solubility in the metals, which strongly deteriorated the mechanical properties of the alloys after irradiation [51].…”

Section: Introductionmentioning

confidence: 99%

He-ion Irradiation Effects on the Microstructures and Mechanical Properties of the Ti-Zr-Hf-V-Ta Low-Activation High-Entropy Alloys

Zhang

Wang

et al. 2023

Materials

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High-entropy alloys (HEAs) have shown promising potential applications in advanced reactors due to the outstanding mechanical properties and irradiation tolerance at elevated temperatures. In this work, the novel low-activation Ti2ZrHfxV0.5Ta0.2 HEAs were designed and prepared to explore high-performance HEAs under irradiation. The microstructures and mechanical properties of the Ti2ZrHfxV0.5Ta0.2 HEAs before and after irradiation were investigated. The results showed that the unirradiated Ti2ZrHfxV0.5Ta0.2 HEAs displayed a single-phase BCC structure. The yield strength of the Ti2ZrHfxV0.5Ta0.2 HEAs increased gradually with the increase of Hf content without decreasing the plasticity at room and elevated temperatures. After irradiation, no obvious radiation-induced segregations or precipitations were found in the transmission electron microscope results of the representative Ti2ZrHfV0.5Ta0.2 HEA. The size and number density of the He bubbles in the Ti2ZrHfV0.5Ta0.2 HEA increased with the improvement of fluence at 1023 K. At the fluences of 1 × 1016 and 3 × 1016 ions/cm2, the irradiation hardening fractions of the Ti2ZrHfV0.5Ta0.2 HEA were 17.7% and 34.1%, respectively, which were lower than those of most reported conventional low-activation materials at similar He ion irradiation fluences. The Ti2ZrHfV0.5Ta0.2 HEA showed good comprehensive mechanical properties, structural stability, and irradiation hardening resistance at elevated temperatures, making it a promising structural material candidate for advanced nuclear energy systems.

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Influence of defect dynamics on the nanoindentation hardness in NiCoCrFePd high entropy alloy under high dose Xe+3 irradiation

Cited by 13 publications

References 48 publications

Composition and Structure of NiCoFeCr and NiCoFeCrMn High-Entropy Alloys Irradiated by Helium Ions

Composition and Structure of NiCoFeCr and NiCoFeCrMn High-Entropy Alloys Irradiated by Helium Ions

Irradiation-Hardening Model of TiZrHfNbMo0.1 Refractory High-Entropy Alloys

He-ion Irradiation Effects on the Microstructures and Mechanical Properties of the Ti-Zr-Hf-V-Ta Low-Activation High-Entropy Alloys

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