Atomistic modelling of fracture for irradiated materials

核电站用压力容器钢由于含有大量的合金元素，其性能非常复杂。辐照效应影响杂质向晶界流动，改变溶质偏析，导致脆化和操作性能降低。该项目是ENTENTE欧洲联盟开发脆化多尺度模型的一部分。博士项目的目标是辐照材料多尺度建模中最后的空白之一：将中子辐照与机械性能的变化联系起来。该模型将由EDF和CEA（均在巴黎）的合作伙伴进行实验验证。

Pressure vessel (RPV) steels used in nuclear power plants have very complex behaviour due to the large number of alloying elements. Irradiation effects affect the flow of impurities towards grain boundaries, modifying solute segregation and leading to embrittlement and reduced operational performance. This project is part of the ENTENTE European consortium developing a multiscale model for embrittlement. The PhD project targets one of the last remaining gaps within the multiscale modelling of irradiated materials: linking neutron irradiation to variation of mechanical properties. The model will be validated by experiments carried out by partners at EDF and CEA (both in Paris).