Effects of Cu ion irradiation in Cu50Zr45Ti5 metallic glass

Carter, Jesse; Fu, E.G.; Martin, Michael; Xie, Guoqiang; Zhang, X.; Wang, Y. Q.; Wijesundera, D.; Wang, X. M.; Chu, W. K.; Shao, Lin

doi:10.1016/j.scriptamat.2009.03.060

Cited by 62 publications

(14 citation statements)

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“…Surface treatments, such as the shot peening [23] and laser pulse processing [24,25] of metallic glasses demonstrate that the structural changes on the surface could result in residual stresses on the surface, which could further modify the plastic-deformation ability of metallic glasses [23,24]. Ion irradiation, an alternative method, can also induce structural modification of the surface of metallic glasses [26][27][28][29][30][31][32][33][34][35][36][37]. When metallic glasses are ion-irradiated, the most dominant mechanism involves the inelastic collisions between high-energy ions and solids that can generate certain activated units, such as structural defects and nano-crystallization [27][28][29][30][31][32][33][34][35].…”

Section: і Introductionmentioning

confidence: 99%

“…However, this discrepancy in the values can be compensated by the diffusion collisions can create displacement cascades and thermal spikes. The center of the cascade forms vacancy-rich regions and absorbs abundant energy to cause melting and resolidification[30,33,56]. Therefore, the viscous flow can occur on the surface of the metallic glass irradiated at 0.5 dpa, and the cascade center generates large amount of defects, such as free volumes.Moreover, accompanying the viscous flow, collective atoms participate in the shift and rearrangement, bringing out the uniformity of the glassy phase.…”

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Manipulation of free volumes in a metallic glass through Xe-ion irradiation

et al. 2016

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The origin of the deformation in metallic glasses is attributed to rearrangements of atoms in some structurally weak spots behaving as flow units, which are associated with free volumes. In the present study, Xe-ion beam is used to manipulate the free-volume fraction, and influence on the mechanical behavior of a Zr-based metallic glass. The irradiation at low dosages can change the structure by increasing the free volume, and by homogenising the distribution of free volume. The increase in the free-volume fraction is equivalent to the increase in the deformation temperature, thus resulting in the decrease in the yield strength. The analysis of stochastic strain burst size in the metallic glass irradiated at different dosages indicates that the strain burst depends on the yield strength and homogeneity of the glassy phase. The results of this study highlight the fact that the quantitative manipulation of the homogeneity and the amount of free volumes can be achieved through low-dose ion irradiation, which can modify the mechanical behavior of metallic glasses.

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Section: і Introductionmentioning

confidence: 99%

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Manipulation of free volumes in a metallic glass through Xe-ion irradiation

et al. 2016

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“…Although glassy states are generally metastable, some glasses may possess large kinetic barriers to the nucleation of a crystalline phase. Several studies on metallic glasses have shown that a direct crystallization in the damage cascade core is unlikely considering because the cooling rates during the thermal spike quenching stages are typically a few orders of magnitudes higher than the critical cooling rates required for crystallization [18]. Therefore, the local molten zone formed in the damage cascade core maintains a glassy state upon thermal spike quenching and subsequent cooling at longer time scales.…”

Section: Introductionmentioning

confidence: 99%

Superior radiation tolerant materials: Amorphous silicon oxycarbide

Nastasi

Price

et al. 2015

Journal of Nuclear Materials

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a b s t r a c tWe studied the radiation tolerance of amorphous silicon oxycarbide (SiOC) alloys by combining ion irradiation, X-ray diffraction (XRD) and transmission electron microscopy (TEM). The amorphous SiOC alloys thin films were grown via co-sputtering from SiO 2 and SiC (amorphous phase) targets either on a surface oxidized Si (100) substrate or on a sodium chloride substrate. By controlling the sputtering rate of each target, SiOC alloys with different compositions (1:2, 1:1, 2:1 ratios) were obtained. These alloys were irradiated by 100 keV He + ions at both room temperature and 600°C with damage levels ranging from 1 to 20 displacements per atom (dpa). TEM characterization shows no sign of crystallization, void formation or segregation in all irradiated samples. Our findings suggest that SiOC alloys are a class of promising radiation-tolerant materials.

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“…However, MGs will develop ordered structures if enough energy is supplied. Numerous studies have shown that nanocrystals can be formed under annealing [8], deformation [9], bending [10], nanoindentation [11] and ion or electron irradiation [12][13][14][15][16]. Although the specific mechanisms that induce partial crystallization are different in each of these cases, the general crystallization phenomena are typically associated with enhanced atomic mobility.…”

Section: Introductionmentioning

confidence: 99%