2022
DOI: 10.1016/j.cossms.2022.101001
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Role of electronic energy loss on defect production and interface stability: Comparison between ceramic materials and high-entropy alloys

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Cited by 17 publications
(7 citation statements)
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“…The distribution of grain size matches well with the Xe-ions induced displacement damage. Actually, irradiation induced grain growth was also reported in other literatures, e.g., Pt and Au films irradiated by Ar ions [24], ZrO 2 film irradiated by Au ions [25], NiFeCoCrCu nanocrystalline HEAs irradiated by Ni and Au ions [26]. However, grain size evolution along the ions penetration depth as shown in this study was seldom reported.…”
Section: Resultssupporting
confidence: 67%
“…The distribution of grain size matches well with the Xe-ions induced displacement damage. Actually, irradiation induced grain growth was also reported in other literatures, e.g., Pt and Au films irradiated by Ar ions [24], ZrO 2 film irradiated by Au ions [25], NiFeCoCrCu nanocrystalline HEAs irradiated by Ni and Au ions [26]. However, grain size evolution along the ions penetration depth as shown in this study was seldom reported.…”
Section: Resultssupporting
confidence: 67%
“…This decrease in the migration rate can be explained by an increase in deformation inclusions that prevent the migration of defects, thereby forming agglomerates or highly defective areas. It should also be noted that this significant difference in the structural distortion values for different ions may be due to the fact that in the case of irradiation with Xe 22+ heavy ions, the region subjected to structural distortion along the ion motion trajectory is considerably larger, and high values of ionization losses in the collision of incident particles with the crystal structure result in the formation of a large number of point and vacancy defects [ 3 , 4 ]. Therefore, high ionization losses of incident Xe 22+ ions can initiate a greater number of structural distortions, which, at high irradiation fluences, can lead to accelerated amorphization and degradation, as shown in several studies on the irradiation of nitride ceramics [ 32 , 34 ].…”
Section: Resultsmentioning
confidence: 99%
“…Interest in the study of radiation damage in nuclear structural materials is associated with the possibility to study kinetics of changes in structural, strength, and thermophysical parameters in near-surface layers, and to establish the dose dependences of the degradation of material properties [ 1 , 2 ]. First, these studies are aimed at establishing the relationship between changes in the properties of materials and the dose (fluence) of radiation, as well as the type of ionizing radiation and its energy [ 3 , 4 ]. These studies provide a large amount of experimental data on the properties of nuclear materials, the totality of which further allows us to assess how applicable these materials are in the declared field of nuclear energy, as well as their criteria for resistance to external influences [ 5 , 6 ].…”
Section: Introductionmentioning
confidence: 99%
“…Moreover, the experimental data obtained can be used to deduce the kinetics of the accumulation of radiation damage and its subsequent evolution within materials. It is worth noting that in this context, the duration of damage accumulation and its progression in the affected layer is a critical factor which is not only dependent on the type of irradiation (the ion type, energy, and irradiation mode) but also on the time frame [14,15]. As a rule, the most vulnerable point in a structural material subjected to external influences is the near-surface layer with a thickness of the order of several microns (10-20 ”m) in which, due to the nature of the interaction of ionizing radiation, all structural changes caused by irradiation are concentrated.…”
Section: Statement Of the Reason For Studying Radiation Damage In Cer...mentioning
confidence: 99%