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Multiscale modeling of crystal plasticity in Reactor Pressure Vessel steels: Prediction of irradiation hardening

机译:反应堆压力容器钢材晶体可塑性的多尺度建模:辐照硬化预测

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摘要

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. (C) 2018 Elsevier B.V. All rights reserved.
机译:通过捕获温度和应变速率敏感性的组成方程描述了辐照反应器压力容器(RPV)钢的塑性行为。流量应力分解成与RPV钢特有的微观结构特征相关的基本组分,例如菱形内碳化物,位错网络和变形限制。假设脱位在{110}和{112}晶片平面上进行移动,并提出了简化的相互作用矩阵。在没有可调节的参数的情况下获得预测的屈服应力,并且在大量的实验结果上与大的温度范围内的大量实验结果密切相关。最后,考虑了辐射缺陷的贡献,用于使用原子和错位动态结果。在簇尺寸和密度和强度方面,在细节中分析溶质簇的效果。与中子辐照的RPV钢上的实验数据库进行了讨论并进行了讨论的结果。 (c)2018年elestvier b.v.保留所有权利。

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