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

被引：0
|
作者：
Song, Wulin [1 ]
Han, Xue [1 ]
Cheng, Huanlin [1 ]
Tang, Qi [1 ]
Wang, Huacai [1 ]
Ji, Songtao [1 ]
机构：
[1] China Inst Atom Energy, Beijing 102413, Peoples R China
来源：
JOURNAL OF NUCLEAR MATERIALS | 2025年 / 607卷
关键词：
Neutron irradiation; Zirconium alloy; Fuel Cladding Chemical Interaction layer (FCCI); Transmission Kikuchi Diffraction (TKD); Texture; OXIDE TEXTURE; BONDING LAYER; INTERFACE; OXIDATION; FILMS; ZRO2; IRRADIATION; EVOLUTION; STRESSES; PHASE;
D O I：
10.1016/j.jnucmat.2025.155699
中图分类号：
T [工业技术];
学科分类号：
08 ;
摘要：
A comprehensive characterization of the Fuel Cladding Chemical Interaction (FCCI) layer in a Zr-1Nb alloy with a burnup of 41GWd & sdot;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 alpha-Zr, monoclinic zirconia and tetragonal zirconia are (1011) alpha-Zr || (010) m-ZrO2 and (101)m-ZrO2 || (100) t-ZrO2. It appears that the dominant force for texture development in the FCCI formed on this alloy is the alpha-Zr to m-ZrO2 and m-ZrO2 to tZrO2 transformation stress which is independent with metal substrate orientation.
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页数：14
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