Prediction of radiation embrittlement for highly irradiated reactor vessel steels, 6; Simulation of grain-boundary segregation

Ebihara, Kenichi   ; Yamaguchi, Masatake   ; Nishiyama, Yutaka ; Onizawa, Kunio ; Matsuzawa, Hiroshi*

The irradiated-induced phosphorous segregation in a reactor pressure vessel steel was simulated using the reaction-diffusion equations which include the diffusion constants evaluated by the first principles calculation. The influences of the dose and the dose rate on the phosphorous grain boundary coverage were estimated from the simulation results. Furthermore, by including the effect of carbon on the migration of the radiation defects, the influence of carbon on the phosphorous grain boundary coverage was also estimated.