Hydride growth behaviors in lamellar U-2Nb alloy

IF 2.8 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY

Journal of Nuclear Materials Pub Date : 2025-04-05 DOI:10.1016/j.jnucmat.2025.155793

Wenliang Xu , Dawu Xiao , Wenyuan Wang , Denglei Chen , Sheng Zhang , Min Wu , Zili Yuan , Rongguang Zeng , Hefei Ji , Fan Liu , Tao Fa , Bin Su , Xinchun Lai

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引用次数: 0

Abstract

Hydride growth behaviors are known to be governed by microstructure and stress, but the interplay of the two factors remain unclear. In this work, the growth behaviors of uranium hydride (UH₃) in lamellar U-2Nb alloy were systematically investigated. The growth of UH₃ in U-2Nb samples was controlled by cathodically hydrogen charging with different current densities. The hydrides were categorized into three types based on their growth rate and nucleation sites: (1) blisters at α-U lamellae, (2) fast growth families around inclusions, and (3) fishbone-like families at prior α-U grain boundaries (GBs). Surface and cross-sectional morphologies of these hydrides were examined by focused-ion-beam (FIB) milling and scanning electron microscope (SEM). The results showed that, governed by lamellar microstructure, the hydride propagation along the lamellar direction (LD) was observed throughout the hydriding progress. Meanwhile, the preference of spherical hydrides was enhanced by increasing strain energy. The volume expansion induced tensile fields and cracks were found dominating the formation of acicular UH₃, and the hydrides could penetrate far into the matrix through the α-U lamellae. Furthermore, the hydride growth behaviors and their corresponding hydriding mechanisms in lamellar U-2Nb alloy, covering microscopic and early macro scale, are elucidated in this work.

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来源期刊

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.