Joining and characterization of SPTAs/V/CLAM steel joints using SPDB technique with different current directions

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Xiaoyue Tan , Chenjun Xu , Weihong Liu , Yuming Chen , Qingbo Tu , Andrey Litnovsky , Laima Luo , Yucheng Wu
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Abstract

Joining the dissimilar materials faces great challenge due to their different physical and chemical performances. In this study, the SPTAs/V/CLAM steel joints were produced by the spark plasma diffusion bonding (SPDB) technique. Investigation of the roles of current direction on the atomic diffusion behavior at interfaces by a scanning electron microscopy and an equipped energy dispersive spectrometer. It is found that the thickness of the diffusion layer at the SPTAs/V interface is independent on the current direction. However, there shows a thicker diffusion layer (σ and vanadium carbide phases) at the V/CLAM steel interface when the current flows through from CLAM steel side to SPTAs side. It is owing to the direction of the electron wind force coincides with the diffusion direction of dominated atom (V). The produced SPTAs/V/CLAM steel joints show good shear strength (201±24 MPa) and thermal cycling performance (35 cycles). In addition, a skillful method was proposed to quantify the directional effect of current on the interdiffusion between Fe and V, accounting for 36.7 %. This study provides a practical and theoretical support on joining dissimilar materials by designing current direction using SPDB technique.
不同电流方向SPDB技术对SPTAs/V/CLAM钢接头的连接及表征
由于不同材料的物理和化学性能不同,其连接面临着很大的挑战。本研究采用火花等离子体扩散连接(SPDB)技术制备了SPTAs/V/CLAM钢接头。用扫描电子显微镜和能谱仪研究电流方向对界面原子扩散行为的影响。结果表明,SPTAs/V界面扩散层厚度与电流方向无关。然而,当电流从CLAM钢侧向SPTAs侧流过时,在V/CLAM钢界面处出现了较厚的扩散层(σ相和碳化钒相)。这是由于电子风的方向与主导原子(V)的扩散方向一致。制备的SPTAs/V/CLAM钢接头具有良好的抗剪强度(201±24 MPa)和热循环性能(35次循环)。此外,还提出了一种量化电流对Fe和V相互扩散的方向性影响的方法,占36.7%。本研究为利用SPDB技术设计电流方向连接异种材料提供了理论和实践支持。
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
Fusion Engineering and Design
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.
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