Theory of irradiation deformation in non-cubic metals: Effects of anisotropic diffusion

Woo, C.H.

doi:10.1016/0022-3115(88)90096-7

Cited by 165 publications

(114 citation statements)

References 32 publications

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“…The lack of understanding of void formation behaviour at the atomic scale has adversely affected the development of advanced theoretical models to predict void evolution under irradiation. This is evidenced by the fact that existing models [27][28][29][30][31][32][33][34][35][36][37] cannot accurately predict the void evolution at the atomic level that is experimentally observed in the current study. Specifically, it is observed here that the void formation is largely controlled by the atomic process on the void surfaces, a phenomenon that has not been reported before and can only be observed in situ at atomic scale.…”

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confidence: 55%

In-situ atomic-scale observation of irradiation-induced void formation

et al. 2013

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The formation of voids in an irradiated material significantly degrades its physical and mechanical properties. Void nucleation and growth involve discrete atomic-scale processes that, unfortunately, are not yet well understood due to the lack of direct experimental examination. Here we report an in-situ atomic-scale observation of the nucleation and growth of voids in hexagonal close-packed magnesium under electron irradiation. The voids are found to first grow into a plate-like shape, followed by a gradual transition to a nearly equiaxial geometry. Using atomistic simulations, we show that the initial growth in length is controlled by slow nucleation kinetics of vacancy layers on basal facets and anisotropic vacancy diffusivity. The subsequent thickness growth is driven by thermodynamics to reduce surface energy. These experiments represent unprecedented resolution and characterization of void nucleation and growth under irradiation, and might help with understanding the irradiation damage of other hexagonal close-packed materials.

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confidence: 55%

In-situ atomic-scale observation of irradiation-induced void formation

et al. 2013

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“…Better corrosion resistance, and hence reduced hydrogen ingress, has recently been shown to correlate with decreased irradiation-induced growth strain [12], a macroscopic deformation process that is characterised in tube by axial expansion and radial contraction. It is generally accepted that growth strain is a result of an excess of interstitials in prismatic planes and vacancies in basal planes as a result of the diffusional anisotropy of irradiation-induced point defects in hcp systems [13][14][15][16][17]. The evolution of intermetallic phases under irradiation is of importance to the system as a whole, as mechanical behaviour and corrosion properties are intrinsically dependent on microstructural features.…”

Section: Introductionmentioning

confidence: 99%

Nano-scale chemical evolution in a proton-and neutron-irradiated Zr alloy

Harte

Topping

Frankel

et al. 2017

Journal of Nuclear Materials

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A. Harte et al., Nano-scale chemical evolution in a proton-and neutron-irradiated Zr alloy J. Nucl. Mater. Accepted Jan. 2017 Nano-scale chemical evolution in a proton-and neutron-irradiated Zr alloy (Fe,Ni). This is accomplished through ultra-high spatial resolution scanning transmission electron microscopy and the use of energy-dispersive X-ray spectroscopic methods. Fe-depletion is observed from both SPP types after irradiation with both irradiative species, but is heterogeneous in the case of Zr(Fe,Cr) 2 , predominantly from the edge region, and homogeneously in the case of Zr 2 (Fe,Ni). Further, there is evidence of a delay in the dissolution of the Zr 2 (Fe,Ni) SPP with respect to the Zr(Fe,Cr) 2 . As such, SPP dissolution results in matrix supersaturation with solute under both irradiative species and proton irradiation is considered well suited to emulate the effects of neutron irradiation in this context. The mechanisms of solute redistribution processes from SPPs and the consequences for irradiation-induced growth phenomena are discussed.

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“…The parameter quantifies the preferential absorption of SIAs, compared to absorption of vacancies, by dislocations. It is regarded as the intrinsic driving force for void swelling in the standard rate theory model [2,3]. In this model, only Frenkel pairs (FPs) are considered and therefore excess vacancies are absorbed by voids.…”

Section: Introductionmentioning

confidence: 99%

Multiscale calculations of dislocation bias in fcc Ni and bcc Fe model lattices

Chang

Olsson

Terentyev

et al. 2015

Nuclear Instruments and Methods in Physics Research Section B:

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a b s t r a c tIn order to gain more insights on void swelling, dislocation bias is studied in this work. Molecular static simulations with empirical potentials are applied to map the dislocation-point defects interaction energies in both fcc Ni and bcc Fe model lattices. The interaction energies are then used to numerically solve the diffusion equation and obtain the dislocation bias. The importance of the dislocation core region is studied under a the temperature range 573-1173 K and the dislocation densities 10 12 -10 15 m À2 . The results show that larger dislocation bias is found in the fcc Ni than in the bcc Fe under different temperatures and dislocation densities. The anisotropic interaction energy model is used to obtain the dislocation bias and the result is compared to that obtained using the atomistic interaction model, the contribution from the core structure is then shown in both the Ni lattice and the Fe lattice.

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Theory of irradiation deformation in non-cubic metals: Effects of anisotropic diffusion

Cited by 165 publications

References 32 publications

In-situ atomic-scale observation of irradiation-induced void formation

In-situ atomic-scale observation of irradiation-induced void formation

Nano-scale chemical evolution in a proton-and neutron-irradiated Zr alloy

Multiscale calculations of dislocation bias in fcc Ni and bcc Fe model lattices

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