Identifying He- and H-vacancy complexes in 3C-SiC by temperature-dependent positron annihilation lifetime calculations

IF 2.8 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY
Hongtao Zhang , Qiang Li , Long Yan , Xian Tang , Guo-Dong Cheng
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引用次数: 0

Abstract

The effect of temperatures ranging from 0 K to 1000 K on the positron lifetime of He- or H-vacancy complexes in 3C-SiC are studied using first-principles calculations. We observed a steady decrease in the formation energy of H-vacancy complexes upon additional H introduction, in contrast to the variation tendency of formation energies seen in He-vacancy complexes. The intrinsic vacancies (VSi, VC, and VSi+C) exhibit different decrease in positron lifetime with the addition of He or H atoms, with the effect of He being more pronounced. Moreover, VC and its impurity-vacancy complexes are almost incapable of trapping delocalized positrons, with positron lifetimes close to those of the bulk. Positron lifetime calculations for the complexes show no significant temperature dependence from 0 K to 1000 K, except in the case of VC. The above results are interpreted by analysis of electron density, positron density, positron ground-state energy, and positron trapping energy analysis. The results provide a reference for future in-situ temperature-dependent positron lifetime experiments on impurity-vacancy complexes in 3C-SiC.
用温度相关的正电子湮灭寿命计算来识别3C-SiC中的He和h空位配合物
用第一性原理计算方法研究了温度在0 ~ 1000 K范围内对3C-SiC中He或h空位配合物正电子寿命的影响。我们观察到H-空位配合物的形成能在额外引入H后稳定下降,与H-空位配合物的形成能变化趋势相反。本征空位(VSi、VC和VSi+C)的正电子寿命随着He或H原子的加入而有不同程度的降低,其中He的影响更为明显。此外,VC及其杂质-空位配合物几乎不能捕获离域正电子,正电子寿命接近体。除VC外,这些配合物的正电子寿命计算表明,从0 K到1000 K没有明显的温度依赖性。以上结果通过电子密度分析、正电子密度分析、正电子基态能分析和正电子捕获能分析来解释。研究结果为3C-SiC中杂质-空位配合物的原位温度依赖正电子寿命实验提供了参考。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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来源期刊
Journal of Nuclear Materials
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.
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