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氢氦协同辐照对钨中缺陷演化及力学性能影响

Effect of Hydrogen and Helium Co-irradiation on Defect Evolution and Mechanical Properties of Tungsten

  • 摘要: 金属钨是聚变堆中重要的面向等离子材料,纯钨在氢氦混合束辐照下的辐照损伤效应研究对于理解该材料在聚变堆中的服役行为具有重要意义。本工作在500 ºC下用氢氦混合束注入高纯钨样品,完成了三种不同的氢氦注入剂量的实验。注入实验后分别使用纳米压痕仪和场发射透射电子显微镜(TEM)测试辐照前后试样的纳米硬度随深度的变化和微观缺陷。结果发现:在所有注量下,离子辐照都将导致钨的硬化;随着注量的增加,样品体硬度先增加后减小;TEM观测结果显示,辐照损伤导致气泡和位错环的生成;随着注量的增加,气泡的平均直径先是从1.03 nm增加到1.12 nm,而后减小至1.05 nm,气泡的数密度随辐照注量的增加而增大;位错尺寸从4.12 nm增加到5.39 nm,但位错环数密度却减小了几乎一半。最后讨论了硬度变化与微结构演化的关系,发现氢氦混合束注入后材料硬度的变化主要与位错环有关。

     

    Abstract: Tungsten is an important plasma-oriented material in fusion reactor. The study of radiation damage effect of pure tungsten under H/He mixed beam irradiation is of great significance for understanding the service behavior of this material in fusion reactor. In this work, high purity tungsten samples were irradiated with H/He mixed beam at 500 ºC, and three different H/He irradiation fluences. After the implantation experiment, nano-indentation instrument and field emission transmission electron microscope (TEM) were used to measure the changes of hardness with depth and the microscopic defects of the samples before and after irradiation. The results show that the ion irradiation will lead to the hardening of tungsten under all irradiation fluences. With the increase of irradiation fluence, the hardness of the sample increases first and then decreases. TEM results show that irradiation damage results in the formation of bubbles and dislocation loops. The average diameter of the bubble increases from 1.03 to 1.12 nm and then decreases to 1.05 nm. The number density of the bubble increases with the increase of the irradiation fluence. The dislocation size increases from 4.12 to 5.39 nm, but the dislocation loop number density is reduced by almost half. Finally, the relationship between hardness change and microstructure evolution is discussed. It is found that the hardness change after H/He mixed beam injection is mainly related to dislocation loops.

     

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