Reduction of plastic anisotropy of zircaloy cladding by neutron irradiation. (II). Numerical simulations of yield loci.:Numerical Simulations of Yield Loci

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Initial plastic deformation behavior of zirconium alloy fuel cladding was described quantitatively by the deformation system of single crystal of a-zirconium, and a model was proposed to simulate the yield behavior of polycrystalline material. Based on the model, effects of crystallographic texture and stress state on the plastic deformation of the cladding were evaluated. Conclusions obtained from this investigation are :<BR>(1) The proposed model shows good agreement with the von Mises' yield criteria for a material with isotropic properties.<BR>(2) Plastic anisotropy of the cladding decreases when neutron irradiation affects prism slip more strongly than the other deformation systems.<BR>(3) Dominant deformation systems for axial tension or internal pressurization of the cladding are predicted to be prism slip or tensile twin, respectively, when the stress state of the cladding reaches the yield condition.
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