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离子辐照单晶镍及镍二元合金中缺陷范围和演变的直接观察

Direct Observation of Defect Range and Evolution in Ion-Irradiated Single Crystalline Ni and Ni Binary Alloys.

作者信息

Lu Chenyang, Jin Ke, Béland Laurent K, Zhang Feifei, Yang Taini, Qiao Liang, Zhang Yanwen, Bei Hongbin, Christen Hans M, Stoller Roger E, Wang Lumin

机构信息

Department of Nuclear Engineering and Radiological Science, University of Michigan, Ann Arbor, MI 48109-2104, USA.

Materials Science and Technology Division, Oak Ridge National Laboratory, Oak Ridge, TN 37831, USA.

出版信息

Sci Rep. 2016 Feb 1;6:19994. doi: 10.1038/srep19994.

Abstract

Energetic ions have been widely used to evaluate the irradiation tolerance of structural materials for nuclear power applications and to modify material properties. It is important to understand the defect production, annihilation and migration mechanisms during and after collision cascades. In this study, single crystalline pure nickel metal and single-phase concentrated solid solution alloys of 50%Ni50%Co (NiCo) and 50%Ni50%Fe (NiFe) without apparent preexisting defect sinks were employed to study defect dynamics under ion irradiation. Both cross-sectional transmission electron microscopy characterization (TEM) and Rutherford backscattering spectrometry channeling (RBS-C) spectra show that the range of radiation-induced defect clusters far exceed the theoretically predicted depth in all materials after high-dose irradiation. Defects in nickel migrate faster than in NiCo and NiFe. Both vacancy-type stacking fault tetrahedra (SFT) and interstitial loops coexist in the same region, which is consistent with molecular dynamics simulations. Kinetic activation relaxation technique (k-ART) simulations for nickel showed that small vacancy clusters, such as di-vacancies and tri-vacancies, created by collision cascades are highly mobile, even at room temperature. The slower migration of defects in the alloy along with more localized energy dissipation of the displacement cascade may lead to enhanced radiation tolerance.

摘要

高能离子已被广泛用于评估核电应用中结构材料的辐照耐受性以及改变材料性能。了解碰撞级联过程中及之后的缺陷产生、湮灭和迁移机制非常重要。在本研究中,使用了无明显预先存在缺陷汇的单晶纯镍金属以及50%Ni50%Co(NiCo)和50%Ni50%Fe(NiFe)的单相浓固溶体合金来研究离子辐照下的缺陷动力学。横截面透射电子显微镜表征(TEM)和卢瑟福背散射光谱沟道(RBS-C)光谱均表明,在高剂量辐照后,所有材料中辐射诱导缺陷团簇的范围远远超过理论预测深度。镍中的缺陷迁移速度比NiCo和NiFe中的快。空位型堆垛层错四面体(SFT)和间隙环在同一区域共存,这与分子动力学模拟结果一致。对镍的动力学激活弛豫技术(k-ART)模拟表明,碰撞级联产生的小空位团簇,如双空位和三空位,即使在室温下也具有很高的迁移率。合金中缺陷迁移较慢以及位移级联的能量耗散更局部化可能导致辐照耐受性增强。

https://cdn.ncbi.nlm.nih.gov/pmc/blobs/f014/4734288/008e6ef926ce/srep19994-f1.jpg

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