Achieving effective bonding between W-75Cu composite and CuCrZr alloy via spark plasma sintering

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Fusion Engineering and Design Pub Date : 2025-02-01 DOI:10.1016/j.fusengdes.2024.114791

Changcheng Sang , Dang Xu , Kaichao Fu , Ruizhi Chen , Pengqi Chen , Yingwei Lu , Yonghong Xia , Qiu Xu , Jigui Cheng

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Abstract

In this study, spark plasma sintering (SPS) was employed to achieve the simultaneous sintering and bonding of W-75Cu composite with CuCrZr alloy. The effects of the sintering temperature on the microstructure evolution and properties of the W-75Cu/CuCrZr joints were systematically investigated and their thermal shock resistance was evaluated. The results indicated that a dense and defect-free joint was obtained at 950 °C, demonstrating the maximum shear strength (216.5 MPa) and thermal conductivity (237.9 W/(m·K)). Fracture analysis revealed that failure predominantly occurred within the W-75Cu matrix, confirming robust interfacial bonding. Additionally, after 200 thermal shock cycles at 450 °C-RT, the W-75Cu/CuCrZr joint maintained a high joint strength (172.7 MPa) without visible cracks on the interface, thereby demonstrating excellent joint reliability and thermal shock resistance. This study highlights the advantages of SPS technology in promoting the densification of the matrices and achieving high-performance joints, providing valuable technical insights for achieving a reliable bonding between the W-Cu FGM (high Cu content) and the CuCrZr heat sink material.

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来源期刊

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

CiteScore

3.50

自引率

23.50%

发文量

275

审稿时长

3.8 months

期刊介绍： The journal accepts papers about experiments (both plasma and technology), theory, models, methods, and designs in areas relating to technology, engineering, and applied science aspects of magnetic and inertial fusion energy. Specific areas of interest include: MFE and IFE design studies for experiments and reactors; fusion nuclear technologies and materials, including blankets and shields; analysis of reactor plasmas; plasma heating, fuelling, and vacuum systems; drivers, targets, and special technologies for IFE, controls and diagnostics; fuel cycle analysis and tritium reprocessing and handling; operations and remote maintenance of reactors; safety, decommissioning, and waste management; economic and environmental analysis of components and systems.