Atomistic modelling of fracture for irradiated materials

核电站用压力容器(RPV)钢含有大量的合金化元素，具有非常复杂的性能。辐照效应影响杂质向晶界流动，改变溶质偏析，导致脆化和降低使用性能。该项目是开发多尺度脆化模型的Enente欧洲联盟的一部分。PHD项目的目标是在辐照材料的多尺度模型中剩余的最后空白之一：将中子辐照与机械性能的变化联系起来。该模型将通过EDF和CEA(都在巴黎)的合作伙伴进行的实验来验证。

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).