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Multiscale modeling of crystal plasticity in Reactor Pressure Vessel steels: Prediction of irradiation hardening
Journal of Nuclear Materials ( IF 3.1 ) Pub Date : 2018-11-20 , DOI: 10.1016/j.jnucmat.2018.11.028
Ghiath Monnet , Ludovic Vincent , Lionel Gélébart

The plastic behavior of irradiated Reactor Pressure Vessel (RPV) steels is described by constitutive equations capturing the temperature and strain rate sensitivities. The flow stress is decomposed into its fundamental components associated with the microstructure features peculiar to RPV steels, such as carbides, dislocation network and deformation confinement inside grains. Dislocations are assumed to move on the {110} and {112} crystallographic planes and a simplified interaction matrix is proposed. The predicted yield stress is obtained without adjustable parameters and found in close agreement with a large number of experimental results over a large temperature range. Finally, the contribution of radiation defects is accounted for using atomistic and dislocation dynamics results. The effect of solute cluster is analyzed in details in terms of the cluster size and density and strength. Results are discussed and compared with an experimental database on neutron-irradiated RPV steels.



中文翻译:

反应堆压力容器钢的晶体可塑性多尺度建模:辐射硬化的预测

辐照反应堆压力容器(RPV)钢的塑性行为通过捕获温度和应变率敏感性的本构方程来描述。流变应力被分解为与RPV钢特有的显微组织特征相关的基本成分,例如碳化物,位错网络和晶粒内部的变形限制。假设位错在{110}和{112}晶面上移动,并提出了简化的相互作用矩阵。在没有可调参数的情况下获得了预期的屈服应力,并且与在较大温度范围内的大量实验结果非常吻合。最后,利用原子动力学和位错动力学结果来解释辐射缺陷的贡献。从团簇的大小,密度和强度方面详细分析了溶质团簇的作用。对结果进行了讨论,并与中子辐照的RPV钢的实验数据库进行了比较。

更新日期:2018-11-20
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