Characterization of dislocation loops and chromium-rich precipitates in ferritic iron-chromium alloys as means of void swelling suppression

QC 20120124. Symposium on Nuclear Materials and Materials for Fusion held at the E-MRS 2006 Spring Meeting, Nice, FRANCE, MAY 29-JUN 02, 2006
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.

Olsson, PärPhysique des Solides Irradiés et des Nanostructures, CP23, Université Libre de Bruxelles(Swepub:kth)u1wo7ztz (författare)
Malerba, L. (författare)
Barashev, A. V. (författare)
Physique des Solides Irradiés et des Nanostructures, CP23, Université Libre de Bruxelles (creator_code:org_t)

Ingår i:Journal of Nuclear Materials: Elsevier BV362:2-3, s. 167-1730022-31151873-4820

Av författaren/redakt...: Terentyev, D.; Olsson, Pär; Malerba, L.; Barashev, A. V.

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