TY - JOUR
T1 - Monte Carlo study of decorated dislocation loops in FeNiMnCu model alloys
AU - Bonny, Giovanni
AU - Terentyev, Dmitry
AU - Zhurkin, Evgeny
AU - Malerba, Lorenzo
A2 - Bakaev, Alexander
N1 - Score = 10
PY - 2014/6/2
Y1 - 2014/6/2
N2 - Radiation-induced embrittlement of bainitic steels is the lifetime limiting factor of reactor pressure vessels in existing nuclear light water reactors. The primary mechanism of embrittlement is the obstruction of dislocation motion by nano-metric defects in the bulk of the material due to irradiation. Such features are known to be solute clusters that may be attached to point defect clusters. In this work we study the thermal stability of solute clusters near edge dislocation lines and loops with Burgers vector b=½ [111] and b=[100] in FeNiMnCu model alloys by means of Metropolis Monte Carlo simulations. It is concluded that small dislocation loops may indeed act as points for heterogeneous nucleation of solute precipitates in reactor pressure vessel steels and increase their thermodynamic stability up to and above normal reactor operating temperatures. We also found that, in the presence of dislocation-type defects, the Ni content determines the thermodynamic driving force for precipitation, rather than the Mn content.
AB - Radiation-induced embrittlement of bainitic steels is the lifetime limiting factor of reactor pressure vessels in existing nuclear light water reactors. The primary mechanism of embrittlement is the obstruction of dislocation motion by nano-metric defects in the bulk of the material due to irradiation. Such features are known to be solute clusters that may be attached to point defect clusters. In this work we study the thermal stability of solute clusters near edge dislocation lines and loops with Burgers vector b=½ [111] and b=[100] in FeNiMnCu model alloys by means of Metropolis Monte Carlo simulations. It is concluded that small dislocation loops may indeed act as points for heterogeneous nucleation of solute precipitates in reactor pressure vessel steels and increase their thermodynamic stability up to and above normal reactor operating temperatures. We also found that, in the presence of dislocation-type defects, the Ni content determines the thermodynamic driving force for precipitation, rather than the Mn content.
KW - Monte Carlo
KW - reactor pressure vessel steels
KW - dislocation loop
UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/ezp_135646
UR - http://knowledgecentre.sckcen.be/so2/bibref/11578
U2 - 10.1016/j.jnucmat.2014.05.051
DO - 10.1016/j.jnucmat.2014.05.051
M3 - Article
SN - 0022-3115
VL - 452
SP - 486
EP - 492
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
ER -