Revealing the Strain Effect on Radiation Response of Amorphous–Crystalline Cu-Zr Laminate
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11837_2019_3932_ReferencePDF.pdf
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Author(s) •
Jin, Miaomiao
Cao, Penghui
Date Issued
December 2019
Journal
JOM: The Journal of The Minerals, Metals & Materials Society
Publisher
Springer Science and Business Media LLC
Citation
Jin, Miaomiao and Penghui Cao. "Revealing the Strain Effect on Radiation Response of Amorphous–Crystalline Cu-Zr Laminate." JOM: The Journal of The Minerals, Metals & Materials Society 72, 2 (December 2019): 868–876. © 2019 The Minerals, Metals & Materials Society
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Author's final manuscript
Abstract
Nanocrystalline materials containing amorphous intergranular films (AIFs) exhibit excellent mechanical properties, radiation resistance, and thermal stability and may serve as promising candidate materials for use in advanced nuclear energy systems. The aim of this work is to reveal the effect of mechanical stress on the radiation damage behavior of AIF systems. Based on a bicrystal Cu system with Zr-doped AIFs, molecular dynamics is used to simulate the radiation process and examine the AIF sink efficiency, defect propensity, defect size distribution, and Zr mixing under uniaxial and hydrostatic strain conditions. The results show that the sink efficiency of the glue-like AIFs is not compromised under applied strains. The anisotropy resulting from the intrinsic microstructure and elastic deformation leads to a distinct radiation response, where extension (contraction) of the structure perpendicular to the AIFs increases (decreases) the vacancy density. The strain-dependent defect density, along with the cluster size distributions, can be interpreted based on the variations in the defect formation energy and anisotropic defect diffusion. Finally, the Zr mixing induced by collision cascades is found to be insensitive to the mechanical strains. These findings provide meaningful information towards understanding the stress effect on the radiation response of AIF systems.
MIT Department
Massachusetts Institute of Technology. Department of Nuclear Science and Engineering
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DOI of Published Version
https://doi.org/10.1007/s11837-019-03932-8