The evolution of irradiation defects and hardening of CVD-SiC induced by He ions irradiation at 800°C

IF 2.8 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY

Journal of Nuclear Materials Pub Date : 2024-09-19 DOI:10.1016/j.jnucmat.2024.155419

Qiqi Li , Xiaoyue Li , Zhenbo Zhu , Xiangbin Ding , Min Liu

引用次数: 0

Abstract

In this study, 500 keV He ions were used to irradiate CVD-SiC samples at 800 °C. The influence of doses on the microstructural evolution and hardness of the irradiated samples were investigated by TEM, Raman, and nanoindentation. TEM results show that He bubbles and dislocation loops appeared after irradiation, and their number densities increased with doses, resulting in the gradual decrease of the intensity of the TO peak in Raman spectra. Moreover, He platelets with strain field were observed in both stacking faults and matrixes. Nanoindentation results indicated that the irradiation hardening occurred, and the hardening degree was positively correlated with the irradiation dose.

查看原文本刊更多论文

800°C He 离子辐照诱导的 CVD-SiC 辐照缺陷和硬化的演变

本研究使用 500 keV He 离子在 800 °C 下辐照 CVD-SiC 样品。通过 TEM、拉曼和纳米压痕研究了剂量对辐照样品微观结构演变和硬度的影响。TEM 结果表明，辐照后出现了 He 气泡和位错环，其数量密度随剂量的增加而增加，导致拉曼光谱中 TO 峰的强度逐渐降低。此外，在堆叠断层和基体中都观察到了带有应变场的 He 小板。纳米压痕结果表明发生了辐照硬化，硬化程度与辐照剂量呈正相关。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

求助全文

约1分钟内获得全文求助全文

来源期刊

Journal of Nuclear Materials 工程技术-材料科学：综合

CiteScore

5.70

自引率

25.80%

发文量

601

审稿时长

63 days

期刊介绍： The Journal of Nuclear Materials publishes high quality papers in materials research for nuclear applications, primarily fission reactors, fusion reactors, and similar environments including radiation areas of charged particle accelerators. Both original research and critical review papers covering experimental, theoretical, and computational aspects of either fundamental or applied nature are welcome. The breadth of the field is such that a wide range of processes and properties in the field of materials science and engineering is of interest to the readership, spanning atom-scale processes, microstructures, thermodynamics, mechanical properties, physical properties, and corrosion, for example. Topics covered by JNM Fission reactor materials, including fuels, cladding, core structures, pressure vessels, coolant interactions with materials, moderator and control components, fission product behavior. Materials aspects of the entire fuel cycle. Materials aspects of the actinides and their compounds. Performance of nuclear waste materials; materials aspects of the immobilization of wastes. Fusion reactor materials, including first walls, blankets, insulators and magnets. Neutron and charged particle radiation effects in materials, including defects, transmutations, microstructures, phase changes and macroscopic properties. Interaction of plasmas, ion beams, electron beams and electromagnetic radiation with materials relevant to nuclear systems.