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An Experimental Survey on Mechanical Property Characterisations of Ion-irradiated Silicon Carbides

机译:离子辐照碳化硅机械性能特征的实验调查

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SiC and SiC/SiC composites have a great potential for the structural material of advanced nuclear reactors. The irradiation behaviours of SiC are important and an ion irradiation is a useful tool to simulate the expected core conditions of fusion and GEN-IV nuclear reactors. Generally, however, the radiation-induced range by ion irradiation is limited to a few micrometers. Therefore, in the case of ion-irradiated SiC, a measurement of its mechanical properties is not straightforward and thus, advanced evaluation methods are continuously being requested to establish a data base for mechanical property changes of radiation-induced materials. In this work, indentation tests are proposed for evaluating the mechanical properties of ion-irradiated SiCs. The low-temperature irradiation produced various defects in the SiC such as point defect clusters, dislocation loops and amorphous phases. These various irradiation defects were observed by TEM, which existed as a function of the penetrated ion depth. The amorphous phases and the other defects seem to provide contrary results for the hardness. The changes of the mechanical properties were exhibited with increasing indentation loads. The experimental evaluation by using the indentation techniques was discussed with relation between microstructures and the mechanical properties.
机译:SiC和SiC / SiC复合材料具有高级核反应堆结构材料的潜力。 SiC的照射行为是重要的,并且离子辐射是模拟融合和IV核反应堆的预期核心条件的有用工具。然而,通常,通过离子照射的辐射诱导的范围限制为几微米。因此,在离子照射的SiC的情况下,其机械性能的测量并不简单,因此,连续地要求进行高级评估方法以建立辐射诱导材料的机械性能变化的数据库。在这项工作中,提出了用于评估离子照射SICS的机械性能的压痕试验。低温照射在SiC中产生了各种缺陷,例如点缺陷簇,位错环和非晶阶段。通过TEM观察到这些各种辐射缺陷,其作为渗透离子深度的函数存在。无定形阶段和其他缺陷似乎为硬度提供了相反的结果。随着压痕载荷的增加,表现出机械性能的变化。通过使用微结构和机械性能之间的关系讨论了使用压痕技术的实验评价。

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