TY - JOUR
T1 - Displacement cascades in Fe-Cr
T2 - A molecular dynamics study
AU - Terentyev, Dmitry
AU - Malerba, Lorenzo
AU - Chakarova, Roumiana
AU - Nordlund, Kai
AU - Olsson, Pâr
AU - Rieth, Michael
AU - Wallenius, Janne
N1 - Score = 10
PY - 2006/2
Y1 - 2006/2
N2 - Displacement cascades up to 50 keV have been simulated in Fe-10%Cr by molecular dynamics (MD), using an embedded-atom method (EAM) interatomic potential which satisfactorily reproduces the interaction between Cr atoms and point-defects in α-Fe. In particular, the potential can reproduce the strong interaction with self interstitial atoms characteristic of Fe-Cr alloys. The results, when compared to the case of pure Fe, show that the presence of Cr does not significantly influence either the ballistic phase of the cascade, or the primary damage state, in terms of number of surviving defects or clustered fraction. However, the fraction of Cr atoms in interstitial position greatly exceeds the alloy concentration, in agreement with some experimental indications, and this feature is expected to influence the long-term evolution of radiation damage in the alloy. The mechanisms leading to the accumulation of Cr in interstitial positions and the expected trapping effect on interstitial clusters are analysed and discussed.
AB - Displacement cascades up to 50 keV have been simulated in Fe-10%Cr by molecular dynamics (MD), using an embedded-atom method (EAM) interatomic potential which satisfactorily reproduces the interaction between Cr atoms and point-defects in α-Fe. In particular, the potential can reproduce the strong interaction with self interstitial atoms characteristic of Fe-Cr alloys. The results, when compared to the case of pure Fe, show that the presence of Cr does not significantly influence either the ballistic phase of the cascade, or the primary damage state, in terms of number of surviving defects or clustered fraction. However, the fraction of Cr atoms in interstitial position greatly exceeds the alloy concentration, in agreement with some experimental indications, and this feature is expected to influence the long-term evolution of radiation damage in the alloy. The mechanisms leading to the accumulation of Cr in interstitial positions and the expected trapping effect on interstitial clusters are analysed and discussed.
KW - Fe-Cr
KW - Molecular dynamics
KW - Radiation damage
UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/ezp_27109
U2 - 10.1016/j.jnucmat.2005.10.013
DO - 10.1016/j.jnucmat.2005.10.013
M3 - Article
SN - 0022-3115
VL - 349
SP - 119
EP - 132
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
IS - 1-2
ER -