Structure of the fuel-cladding chemical interaction (FCCI) layer of a high burnup Zr-1Nb nuclear fuel cladding

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

Journal of Nuclear Materials Pub Date : 2025-03-01 DOI:10.1016/j.jnucmat.2025.155699

Wulin Song , Xue Han , Huanlin Cheng, Qi Tang, Huacai Wang, Songtao Ji

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引用次数: 0

Abstract

A comprehensive characterization of the Fuel Cladding Chemical Interaction (FCCI) layer in a Zr-1Nb alloy with a burnup of 41GWd·tU⁻¹ has been performed utilizing primary techniques including Optical Microscopy (OM), Transmission Electron Microscopy (TEM), and Transmission Kikuchi Diffraction (TKD). The results indicate that the FCCI layer characterized in this study is mainly composed of tetragonal zirconia on both the cladding and fuel sides, with monoclinic zirconia in between. Additionally, the strong fiber texture in monoclinic and tetragonal zirconia aligns well with that in the water-side oxide film. The orientation relationships between α-Zr, monoclinic zirconia and tetragonal zirconia are (

\bar{1}

011) _α-Zr || (010) _m-ZrO2 and (10

\bar{1}

)_m-ZrO2 || (100) _t-ZrO2. It appears that the dominant force for texture development in the FCCI formed on this alloy is the α-Zr to m-ZrO₂ and m-ZrO₂ to t-ZrO₂ transformation stress which is independent with metal substrate orientation.

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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.