par Terentyev, Dimitri ;Malerba, Lorenzo;Olsson, Pär;Barashev, Alexander A.V.
Référence Journal of nuclear materials, 362, 2-3, page (167-173)
Publication Publié, 2007-05
Référence Journal of nuclear materials, 362, 2-3, page (167-173)
Publication Publié, 2007-05
Article révisé par les pairs
Résumé : | We have used both ab initio and empirical potential based molecular dynamics and static calculations to parameterize a model accounting for the mobility of self-interstitial clusters and small dislocation loops in Fe-Cr alloys depending on Cr content. Particularly, we have considered the interval of 5-15% of Cr, corresponding to the typical concentration of Cr in ferritic/martensitic steels. The mobility of self-interstitial clusters and small dislocation loops was found to be strongly reduced in the presence of Cr due to attractive interaction between self-interstitials and Cr atoms, whereas Cr-rich precipitates act as repulsive obstacles. The results obtained allow the experimental trend of swelling measurements in neutron and high-energy electron irradiated Fe-Cr alloys to be interpreted and explained. © 2007 Elsevier B.V. All rights reserved. |