Experimental evidence of several contributions to the radiation damage in ferritic alloys

INCAS: an analytical model to describe displacement cascades

“…Hence, according to the initial energy of SKAs, damage zones may have different consequences on the microstructure of irradiated materials. As an example, in reactor pressure vessel steels (e.g., [18,19]), it is now admitted that for high SKA energies the density of residual Frenkel pairs may be locally high enough to induce the formation of germs of point defect clusters and solute-atom/vacancy clusters; whereas for low SKA energies the density of residual Frenkel pairs is locally too low to lead to the formation of germs of solute-atom/vacancy clusters and consequently only germs of point defects clusters are expected. In the REVE approach, we make the distinction between the two cases by supposing that:…”

Interactions between dislocations and irradiation-induced defects in light water reactor pressure vessel steels

“…These defects have a radius lower than about 1.5 nm and a number density of some 10 24 m À3 , for a fluence of some 10 19 n cm À2 (E P 1 MeV) and an irradiation temperature of about 290°C (e.g. [20]). They contain Cu, Mn, Ni, Si atoms and a high concentration of Fe atoms (about 85%) which gives them a dilute aspect (they are often called ÔatmospheresÕ or ÔcloudsÕ of solute atoms).…”

RPV-1: A Virtual Test Reactor to simulate irradiation effects in light water reactor pressure vessel steels

“…Experimental work showed that the displacement cascades ease the nucleation of point defect clusters or loops as well as of vacancy-solute clusters in RPV steels [23,25,38,39]. Simulation studies (e.g.…”