辐照环形铀- 10zr燃料中的纳米级聚类和裂变产物偏析

IF 3.2 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY

Journal of Nuclear Materials Pub Date : 2025-09-05 DOI:10.1016/j.jnucmat.2025.156150

Arnold Pradhan , Sohail Shah , Daniele Salvato , Jason Harp , Luca Capriotti , Mukesh Bachhav , Indrajit Charit , Tiankai Yao

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引用次数: 0

摘要

在铀(U)中加入锆（Zr）是为了提高快堆金属燃料的性能。本研究采用透射电子显微镜（TEM）和原子探针断层扫描（APT）研究了在先进试验堆（ATR）辐照的环形U- 10zr金属燃料中U和Zr的纳米级聚类，以及裂变产物（FPs）的分离。结果揭示了在辐照燃料截面内不同径向位置团簇的形状、大小和化学成分的变化。与富铀团簇相比，富锆团簇表现出更高的FPs浓度，这可能是由于在寿命结束时冷却过程中燃料基体中Zr和FPs的共沉淀。这项工作补充了辐照铀- 10zr金属燃料中燃料成分和裂变产物在多个长度尺度上分布的研究。

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Nanoscale clustering and fission product segregation in irradiated annular U-10Zr fuel

Zirconium (Zr) is added to uranium (U) to improve the performance of metallic fuel for fast reactor applications. This study employs transmission electron microscopy (TEM) and atom probe tomography (APT) to investigate nanoscale clustering of U and Zr, as well as segregation of fission products (FPs), in annular U-10Zr (in weight) metallic fuel irradiated at the Advanced Test Reactor (ATR). The results reveal variations in the shape, size, and chemical composition of clusters at different radial locations within the irradiated fuel cross-section. Zr-rich clusters exhibit higher concentration of FPs compared to U-rich clusters, potentially due to the co-precipitation of Zr and FPs in the fuel matrix during cooling at the end-of-life. This work complements the study of fuel constituents and fission product distribution across multiple length scales in irradiated U-10Zr metallic fuel.

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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.