原子炉圧力容器鋼の高照射量領域の照射脆化予測,6; 粒界偏析シミュレーション

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

海老原 健一   ; 山口 正剛   ; 西山 裕孝 ; 鬼沢 邦雄 ; 松澤 寛*

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

第一原理計算で見積もった拡散係数を組み込んだ反応拡散方程式を用いた原子炉圧力容器鋼における照射偏析シミュレーションにより、リンの粒界偏析量を評価し、粒界リン偏析量に対する照射量及び照射速度の影響について考察した。さらに、照射欠陥の移動に対する炭素の効果を考慮し、粒界リン偏析への影響についても考察した。

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.