Multiscale modelling of plastic flow localization in irradiated materials
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The strain-hardening behaviour of a tempered martensitic iron-chromium-carbon model was examined in terms of dislocation mechanics. Tensile tests of this body-centered cubic alloy were carried out from 77 up to 293 K. A specific relationship between the fl ...
Modeling of the constitutive behavior was undertaken for Fe- Cr-C tempered martensitic alloys. Tensile tests were carried out at room temperature and constant nominal strain rate. In order to obtain a fully martensitic structure with different prior austen ...
When irradiated, metals undergo significant internal damage accumulation and degradation of mechanical properties. Damage takes the form of a high number density of nanosize defect clusters (stacking-fault tetrahedrons (SFTs) or interstitial loops). The al ...
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A detailed study of the strain-hardening on a Fe-9Cr-0.1C tempered martensitic model alloy has been undertaken in the temperature range of 77-343 K. The true stress-true strain curves were calculated from tensile test data. In the framework of a phenomenol ...
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The present workshop dealt both theoretically and experimentally with issues of primary damage and irradiation induced defect evolution, helium and other impurities, dislocation-defect interactions, deformation to large plastic strains and fracture. It was ...
