Pressure-less joining SiCf/SiC tube and Kovar alloy with AgCuInTi filler: Interfacial reactions and mechanical properties

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

Journal of Nuclear Materials Pub Date : 2024-11-08 DOI:10.1016/j.jnucmat.2024.155501

Xiongshuai Ji , Changqing Liu , Jianyuan Huang , Huafeng Zhang , Fengjiao Niu , Bo Chen , Jianguo Zhao , Yuanchao Zhao , Yajie Guo

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引用次数: 0

Abstract

The brazing of tube-bar structures is more difficult than that of traditional plate-plate structures, owing to the absence of pressure on the interface. In this study, AgCuInTi filler was employed to join SiC_f/SiC tube and Kovar alloy bar and the joining can be completed at a significantly lower temperature of 780 °C, benefiting from the addition of In. Moreover, the lower temperature not only hindered the formation of Fe₂Si and Ni₂Si at the ceramic interface, but also avoided the appearance of the Fe₂Ti phase in the joint. The typical microstructure of the joint was SiC_f/SiC-(TiC + Ti₅Si₃) layer + (Ag, In) (s, s) + Cu (s, s) + Cu₇In₃+ Ni₃Ti-Kovar. The finite element analysis indicated that lower brazing temperature can also reduce the level of residual stress compared to that of AgCuTi filler, which contributes to the maximum shear strength of 86.1 MPa despite the press-less joining. The fracture path originated from the SiC fibers, then passed through the interfacial reaction layer, and finally extended into the brazing seam.

查看原文本刊更多论文

无压连接碳化硅/碳化硅管和含 AgCuInTi 填料的 Kovar 合金：界面反应和机械性能

与传统的板-板结构相比，管-棒结构的钎焊更为困难，因为界面上没有压力。本研究采用 AgCuInTi 填料连接 SiCf/SiC 管和 Kovar 合金棒，由于添加了 In，连接可在 780 °C 的较低温度下完成。此外，较低的温度不仅阻碍了陶瓷界面上 Fe2Si 和 Ni2Si 的形成，还避免了接头中 Fe2Ti 相的出现。接头的典型微观结构为 SiCf/SiC-（TiC + Ti5Si3）层 + (Ag, In) (s, s) + Cu (s, s) + Cu7In3+ Ni3Ti-Kovar。有限元分析表明，与 AgCuTi 填料相比，较低的钎焊温度也能降低残余应力水平，这有助于在无压连接的情况下获得 86.1 MPa 的最大剪切强度。断裂路径源于碳化硅纤维，然后穿过界面反应层，最后延伸到钎缝。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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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.