Closed form expressions are derived for the energy of elastic interaction between dislocation loops, and between dislocation loops and vacancy clusters, to enable simulations of elastically biased microstructural evolution of irradiated materials. The derivations assume the defects are separated by distances greater than their size. The resulting expressions are well suited for real-space simulations of microstructural evolution involving thousands of elastically interacting defects in 3D. They play a similar role to interatomic potentials in molecular dynamics simulations
International audienceLow-alloy ferritic steel (16MND5) is used for pressure vessels in French nucle...
The aim of this collaborative research work was to apply predictive, physically based multiscale mod...
International audienceModification of materials using ion beams has become a widespread route to imp...
Irradiation induces a high concentration of defects in the structural materials of nuclear reactors,...
Small dislocation loops formed from self-interstitial atoms (SIAs) are commonly found in irradiated ...
This study contributes to the development of a 'fundamental, atomistic basis' to inform ma...
The formation and evolution of defect microstructures in irradiated materials is analysed in the fra...
Using a personnel computer, we have simulated the diffusion and agglomeration of point defects in th...
Internal microstructural length scales play a fundamental role in the strength and ductility of a ma...
In order to improve the dislocation bias (DB) model of swelling under irradiation, a large scale of ...
Irradiation hardening due to voids can be a significant result of radiation damage in metals, but tr...
Multiscale modeling, including molecular dynamics (MD) and discrete dislocation dynamics (DDD) metho...
cited By 1International audienceNumerous dislocation loops are often observed in irradiated and nucl...
Predicting strains, stresses and swelling in nuclear power plant components exposed to irradiation d...
The ability to predict the behavior of structural components in a nuclear power plant is critical to...
International audienceLow-alloy ferritic steel (16MND5) is used for pressure vessels in French nucle...
The aim of this collaborative research work was to apply predictive, physically based multiscale mod...
International audienceModification of materials using ion beams has become a widespread route to imp...
Irradiation induces a high concentration of defects in the structural materials of nuclear reactors,...
Small dislocation loops formed from self-interstitial atoms (SIAs) are commonly found in irradiated ...
This study contributes to the development of a 'fundamental, atomistic basis' to inform ma...
The formation and evolution of defect microstructures in irradiated materials is analysed in the fra...
Using a personnel computer, we have simulated the diffusion and agglomeration of point defects in th...
Internal microstructural length scales play a fundamental role in the strength and ductility of a ma...
In order to improve the dislocation bias (DB) model of swelling under irradiation, a large scale of ...
Irradiation hardening due to voids can be a significant result of radiation damage in metals, but tr...
Multiscale modeling, including molecular dynamics (MD) and discrete dislocation dynamics (DDD) metho...
cited By 1International audienceNumerous dislocation loops are often observed in irradiated and nucl...
Predicting strains, stresses and swelling in nuclear power plant components exposed to irradiation d...
The ability to predict the behavior of structural components in a nuclear power plant is critical to...
International audienceLow-alloy ferritic steel (16MND5) is used for pressure vessels in French nucle...
The aim of this collaborative research work was to apply predictive, physically based multiscale mod...
International audienceModification of materials using ion beams has become a widespread route to imp...