锆合金-4中二相粒子的原子探针研究

IF 3.2 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY
Siyu Huang , Levi Tegg , Sima Aminorroaya Yamini , Vidur Tuli , Patrick Burr , Ingrid McCarroll , Limei Yang , Katie L. Moore , Julie M. Cairney
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引用次数: 0

摘要

锆(Zr)合金,如Zircaloy-4 (Zy-4),在核应用中广泛用于包层。Zy-4由α-Zr基体和多种第二相粒子(SPPs)组成。这些析出物在决定合金的整体性能方面起着至关重要的作用,因此了解它们的组成对这些核材料的开发至关重要。利用特定位置聚焦离子束发射和原子探针层析成像技术研究了该合金中Zr(Fe,Cr)2和Zr2(Si,Fe)两种SPPs,并测量了析出相/基体界面合金元素的组成和分布。在Zr2(Fe,Si)析出相中,残余Cu和B均向基体界面偏析,而Sn仅向基体界面偏析。在Zr(Fe,Cr)2与基体的界面处观察到氢的偏析。
本文章由计算机程序翻译,如有差异,请以英文原文为准。

Atom probe study of second-phase particles in Zircaloy-4

Atom probe study of second-phase particles in Zircaloy-4
Zirconium (Zr) alloys, such as Zircaloy-4 (Zy-4), are widely used for cladding in nuclear applications. Zy-4 consists of an α-Zr matrix and various second phase particles (SPPs). These precipitates play a crucial role in determining the overall alloy performance, so understanding their composition is essential for the development of these nuclear materials. We have studied two SPPs in this alloy, Zr(Fe,Cr)2 and Zr2(Si,Fe), using site-specific focused ion-beam lift-out and atom probe tomography, and measured the composition and distribution of alloying elements at the precipitate/matrix interface. Residual Cu and B segregated to the interfaces of both precipitates and the matrix while Sn only segregated to the interface in the Zr2(Fe,Si) precipitate. Hydrogen segregation was observed at the interface of Zr(Fe,Cr)2 and the matrix.
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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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