Mechanical analysis of tail structures in the next-generation fully superconducting tokamak CS HTS

IF 2 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Fusion Engineering and Design Pub Date : 2026-04-01 Epub Date: 2026-01-24 DOI:10.1016/j.fusengdes.2026.115632

Yi Yu , HouXiang Han

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引用次数: 0

Abstract

The Tail structure is a crucial component of high-temperature superconducting coils, providing both mechanical load transfer and reliable electrical connectivity between conductor leads. In this study, we designed and analyzed a Tail structure for a next-generation fully superconducting tokamak. We performed a coupled multi-physics analysis using finite element software to evaluate the mechanical performance of the proposed system under operational loads. The simulation revealed a maximum stress intensity of 1065.9 MPa, while linearized stress amplitudes remained within the allowable design limits, confirming adequate structural safety, and the minimum fatigue life of the structural components exceeds 127,000 cycles. We also developed and validated specialized welding fixtures through a series of welding experiments. All the welds successfully passed the quality inspections and met the technical specifications required for the procedure qualification, offering essential technical support for the construction of superconducting fusion devices.

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下一代全超导托卡马克cshts尾结构力学分析

尾部结构是高温超导线圈的关键组成部分，提供机械负载传递和导体引线之间可靠的电气连接。在这项研究中，我们设计并分析了下一代全超导托卡马克的尾部结构。我们使用有限元软件进行了耦合多物理场分析，以评估所提出系统在运行载荷下的机械性能。模拟结果表明，最大应力强度为1065.9 MPa，线性化应力幅值保持在设计允许范围内，结构安全可靠，结构部件的最小疲劳寿命超过12.7万次。我们还通过一系列焊接实验开发和验证了专用焊接夹具。所有焊缝均顺利通过质量检验，达到工序合格要求的技术规范，为超导聚变装置的建设提供了必要的技术支持。

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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.