钎焊参数和Zr-Cu-Ti粉末填充金属对SiC陶瓷接头显微组织和力学性能的影响

IF 2.1 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Design Pub Date : 2025-09-19 DOI:10.1016/j.nucengdes.2025.114456

Bofang Zhou , Zixuan Leng , Wuman Wang , Zhaojie Zhang , Hongxia Zhang

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引用次数: 0

摘要

研究了钎焊SiC陶瓷时的钎焊参数（温度、保温时间）和Zr-Cu-Ti填充金属中Ti的含量。在950 ~ 1150℃的温度下，用5 wt%的Ti，结合20 min，在反应层中形成ZrC和Zr2Si相，剪切强度在1050℃时达到峰值63 MPa，然后下降，在反应层和填充金属之间的界面处断裂。在1050℃下，反应层厚度随着保温时间（5 ~ 45 min）的增加而增加，达到最佳强度（20 min时厚度为1.4 μm）。当Ti含量为0 ~ 15 wt%时，反应层中出现Ti5Si3相，由于与Zr2Si和ZrC的热膨胀失配，降低了接头的剪切强度。随着Ti含量的增加，抗剪强度先升高后降低，在Ti含量为5 wt%时达到峰值。

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Effect of brazing parameter and Zr-Cu-Ti powder filler metal on the microstructure and mechanical properties of SiC ceramic joints

Brazing parameters (temperature, holding time) and Ti content in Zr-Cu-Ti filler metal for brazing SiC ceramic are investigated in this paper. Successful bonding was achieved at 950∼1150 °C for 20 min using 5 wt% Ti, forming ZrC and Zr₂Si phases in the reaction layer, and the shear strength peaked at 63 MPa (1050 °C) before declining, fracturing at the interface between the reaction layer and the filler metal. At 1050 °C, reaction layer thickness increased with holding time (5∼45 min), reaching optimal strength (1.4 μm thickness at 20 min). The Ti₅Si₃ phase emerged in the reaction layer on 0∼15 wt% Ti, reducing the shear strength of the joint due to thermal expansion mismatch with Zr₂Si and ZrC. The shear strength first increased then decreased with Ti content, peaking at 5 wt% Ti.

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来源期刊

Nuclear Engineering and Design 工程技术-核科学技术

CiteScore

3.40

自引率

11.80%

发文量

377

审稿时长

5 months

期刊介绍： Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology. Fundamentals of Reactor Design include: • Thermal-Hydraulics and Core Physics • Safety Analysis, Risk Assessment (PSA) • Structural and Mechanical Engineering • Materials Science • Fuel Behavior and Design • Structural Plant Design • Engineering of Reactor Components • Experiments Aspects beyond fundamentals of Reactor Design covered: • Accident Mitigation Measures • Reactor Control Systems • Licensing Issues • Safeguard Engineering • Economy of Plants • Reprocessing / Waste Disposal • Applications of Nuclear Energy • Maintenance • Decommissioning Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.