共存点缺陷下 W〈110〉/W〈112〉晶界自愈行为的 DFT 模拟

IF 2.8 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY
J. Suárez-Recio , D. Fernández-Pello , M.A. Cerdeira , C. González , R. Gonzalez-Arrabal , R. Iglesias
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引用次数: 0

摘要

轻杂质原子(LIAs),如氢和氦,往往会聚集在预先存在的固有点缺陷处。这种聚集会导致有害影响,尤其是在核聚变反应堆等环境中。在核聚变反应堆中,这种杂质会无处不在,导致不可接受的材料行为,从而使材料失去作为等离子体面层材料(PFM)的资格。延缓性能退化的一种方法是使用纳米结构的钨 (NW),这种材料具有高密度的晶界 (GB)。虽然我们已经研究了 GB 中单个 LIA 的行为,但在这项工作中,我们使用 ab initio 方法,介绍了在半相干 W/W 界面同时存在多个 LIA、空位和自间隙原子 (SIA) 的综合协同效应。我们的研究结果揭示了 LIA 与 SIA 之间复杂而有趣的竞争过程。当 SIA 的数量较少时,He 似乎会阻碍它们与空位的重组,从而使人们对 NW 的自愈能力产生怀疑。然而,当 SIA 的数量较多时,它们之间的相互排斥会导致相反的行为。因此,进行彻底的热力学评估以跟踪系统的演变是这些研究的关键后续步骤。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
DFT simulations of the self-healing behavior of a W〈110〉/W〈112〉 grain boundary in the presence of coexisting point defects
Light impurity atoms (LIAs), such as hydrogen and helium, tend to aggregate at pre-existing intrinsic point defects. This aggregation leads to detrimental effects, particularly in environments such as those foreseen in nuclear fusion reactors. There, such impurities would be ubiquitous, resulting in unacceptable material behavior that would unqualify the material as a Plasma Facing Material (PFM). One option to delay the degradation in performance is the use of nanostructured tungsten (NW), showing a large density of grain boundaries (GBs). Although we have already addressed the behavior of a single LIA in a GB, in this work we present the combined synergistic effects of the simultaneous presence of multiple LIAs, vacancies and Self-Interstitial Atoms (SIA) at semicoherent W/W interfaces using ab initio methods. Our results reveal a complex and interesting process in the competition between LIAs and SIAs. When the number of SIAs is low, He appears to hinder their recombination with vacancies, therefore casting doubts on the self-healing provided by NW. However, in the presence of larger numbers of SIAs, their mutual repulsion leads to the opposite behavior. Thus, a thorough thermodynamic assessment in which the evolution of the system may be tracked emerges as the crucial subsequent step in these investigations.
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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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