Weidong Song , Zhonghao Huo , Lijun Xiao , Lifang Wang , Jun Chen , Meizhen Xiang
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引用次数: 0
Abstract
Several high-entropy alloys (HEAs) show considerable promise as structural materials for nuclear energy applications, owing to their exceptional mechanical properties and radiation resistance. However, there is limited understanding of how pre-existing dislocation loops in these HEAs influence their radiation resistance. This study employs molecular dynamics (MD) simulations to investigate the influence of pre-existing dislocation loops on the irradiation resistance of FeNiCoCrCu HEA, focusing on the evolution of point defects, the formation of defect clusters, and the interactions between dislocation loops and point defects during irradiation process. Consequently, the interaction between irradiation-induced point defects and pre-existing dislocation loops leads to an increase in the number of point defects and defect clusters. This is attributed to the reduction in formation energy of point defects by the dislocation loop, which promotes their generation and alters their distribution, thereby inhibiting recombination between them. Point defects migrate toward the dislocation loop under stress field interactions, with the loop exhibiting preferential absorption of interstitial atoms over vacancies, serving as predominant sinks for defect accumulation. Furthermore, the presence of dislocation loops mitigates elemental segregation. During irradiation, dislocation loops absorb vacancies via positive climb and interstitials via negative climb. Meanwhile, the position and shape of the dislocation loop undergo changes, and its length increases. Notably, the FeNiCoCrCu HEA demonstrates enhanced resistance to pre-existing vacancy loop interactions compared to pure Ni, as evidenced by fewer irradiation-induced defects and reduced dislocation loop evolution post-irradiation. These findings elucidate the intricate interplay of defect dynamics in irradiated HEAs and provide critical insights for designing radiation-tolerant HEA systems.
几种高熵合金(HEAs)因其优异的机械性能和抗辐射性,有望成为核能应用领域的结构材料。然而,人们对这些高熵合金中预先存在的位错环如何影响其抗辐射性的了解十分有限。本研究采用分子动力学(MD)模拟来研究预先存在的位错环对 FeNiCoCrCu HEA 抗辐照性的影响,重点关注辐照过程中点缺陷的演变、缺陷簇的形成以及位错环和点缺陷之间的相互作用。结果表明,辐照诱导的点缺陷与预先存在的位错环之间的相互作用导致点缺陷和缺陷簇数量的增加。这是由于位错环路降低了点缺陷的形成能量,促进了点缺陷的产生并改变了它们的分布,从而抑制了它们之间的重组。在应力场的相互作用下,点缺陷会向位错环迁移,位错环会优先吸收间隙原子而不是空位,成为缺陷积累的主要汇。此外,差排环的存在还能缓解元素偏析。在辐照过程中,位错环通过正爬升吸收空位,通过负爬升吸收间隙。同时,位错环的位置和形状发生变化,长度增加。值得注意的是,与纯镍相比,FeNiCoCrCu HEA 对预先存在的空位环相互作用具有更强的抵抗力,这表现在辐照后辐照诱导的缺陷更少,位错环演变更少。这些发现阐明了辐照 HEA 中缺陷动力学错综复杂的相互作用,为设计耐辐射 HEA 系统提供了重要启示。
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.