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Incorporating dislocation loop interactions from dislocation dynamics to crystal plasticity model of irradiated UO2

  • Matti Lindroos
  • , Adrien Pivano
  • , Bruno Michel
  • , Claire Onofri
  • , Janne Heikinheimo*
  • *Corresponding author for this work
  • Research Institute for Nuclear Systems for Low-Carbon Energy Production (IRESNE)

Research output: Contribution to journalArticleScientificpeer-review

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Abstract

Accurate assessment of the irradiation-induced hardening of the fuel requires sophisticated multiscale micromechanical modeling framework. This work proposes a method to link dislocation dynamics (DDD) and crystal plasticity (CP) to evaluate the effect of dislocation loops on UOstrengthening and localization phenomena. Dislocation dynamics is used to quantify dislocation to dislocation loop interaction with respect to the incident angle of gliding dislocation and prismatic loop habit plane. The change in flow resistance provides the effective interaction coefficient depending on dislocation loop size and dislocation type (edge or screw component). Anisotropic dispersed barrier hardening model is then established based on DDD results, which is used to formulate slip resistance at CP level amplified with anisotropic dislocation loop interactions. We utilize the CP model to investigate changes in yield stress and strain hardening/softening due to the presence of dislocation loops in UO2. These results give perspective how dislocation loops alter plastic deformation and strengthening in UO2 for the first time at microstructural scale via CP modeling.
Original languageEnglish
Article number114709
JournalComputational Materials Science
Volume269
DOIs
Publication statusPublished - 20 May 2026
MoE publication typeA1 Journal article-refereed

Funding

This research has received funding from the EURATOM OperaHPC Project under grant agreement No 101061453.

Keywords

  • Crystal plasticity
  • Dislocation loop
  • Irradiation
  • Porosity
  • Strain localization
  • Uranium dioxide

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