Abstract
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.
Details
Original language | English |
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Pages (from-to) | 167-173 |
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Journal | Journal of Nuclear Materials |
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Volume | 362 |
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Issue number | 2-3 |
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DOIs | |
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Publication status | Published - 31 May 2007 |
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Event | E-MRS Spring Meeting - Symposium N: Nuclear Materials and Materials for Fusion - Nice, France Duration: 29 May 2006 → 2 Jun 2006 |
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