Abstract
The presence of even small amount of carbon interstitial impurity affects properties of Fe and Fe-based
ferritic alloys. From earlier experiments it follows that carbon exhibits considerably strong interaction
with lattice defects and therefore influences their mobility, hence affecting the evolution of the microstructure
under irradiation. This work is dedicated to understanding the interaction of carbon–vacancy
complexes with glissile dislocation loops, which form in Fe, Fe-based alloys and ferritic steels under irradiation.
We apply large scale atomistic simulations coupled with the so-called ‘metallic–covalent bonding’
interatomic model for the Fe–C system, known to be the most consistent interatomic model available
today. With these techniques we have studied (i) the stability of vacancy–carbon clusters; (ii) the interaction
of octahedral carbon with ½h1 1 1i loops; (iii) possibility of the dynamic drag of carbon by ½h1 1 1i
loops and (iv) the interaction of ½h1 1 1i loops with the most stable vacancy–carbon clusters expected to
occur under irradiation. Finally, we have shown that carbon–vacancy complexes act as strong traps for
½h1 1 1i loops.
Original language | English |
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Pages (from-to) | 272-284 |
Number of pages | 13 |
Journal | Journal of Nuclear Materials |
Volume | 408 |
Issue number | 3 |
DOIs | |
State | Published - 31 Jan 2011 |