作者: F. Xu , R.A. Holt , M.R. Daymond
DOI: 10.1016/J.JNUCMAT.2009.07.006
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摘要: Abstract Texture development in zirconium reactor components greatly affects their in-service performance, particular influencing dimensional stability, hydride induced cracking and fracture. Understanding texture evolution terms of micromechanical deformation mechanisms contributes to improved engineering design the components. The during uni-axial Zircaloy-2 obtained using neutron diffraction was interpreted with a visco-plastic self-consistent model, based on an extensive data set achieved through situ ex measurements. In influences prism, basal, pyramidal〈a〉, pyramidal〈c + a〉 slip, tensile twinning, hardening due dislocation interactions were considered. Model parameters adjusted obtain simultaneous ‘best-fit’ stress–strain curves, Lankford coefficients, peak intensities three dimensions post-deformation textures, for specimens compressed or pulled principal directions relative slab texture. formation found be directly related activation different mechanisms. Pyramidal〈a〉 slip unnecessary modeling. Accounting between modes critical correctly predicting curves. This study provides further understanding plastic Zircaloy-2.