Thermo-mechanical analysis of plasma grid for 120 keV/50 A accelerator in EAST neutral beam injector

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Fusion Engineering and Design Pub Date : 2025-04-15 DOI:10.1016/j.fusengdes.2025.115047

Fang Wang , Yuanlai Xie , Yahong Xie , Yuming Gu , Qianxu Wang , Longbin Liu , Yang Zhu , Huihui Hong , Bin Li , Jianglong Wei , Kun Tian

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引用次数: 0

Abstract

High-current ion sources are critical components in neutral beam injection (NBI) systems for magnetic confinement fusion, with their performance directly determining the efficiency and reliability of the entire NBI system. With increasing demands for neutral beam injection heating in magnetic confinement fusion research, developing ion sources with higher beam energy and power has become a primary research focus. In response to new design requirements for 120 keV/50 A ion sources, this study investigates the thermodynamic performance of a newly designed plasma grid for a 120 keV/50 A triode accelerator under long-pulse high-power operating conditions. A thermal-stress coupling analysis model was established using numerical methods that coupled FLUENT with finite element software. Through systematic analysis, molybdenum was identified as the optimal material choice, and the minimum required cooling water mass flow rate for safe operation under long-pulse high-power conditions was determined to be 0.426 kg/s. In-depth analysis under the most severe operating conditions demonstrated that the maximum Von-Mises equivalent stress remains below the material yield strength. The reliability of the numerical model was validated through experimental results from the EAST-NBI comprehensive test platform, providing crucial evidence for safe operation under long-pulse high-power conditions. This work presents significant value for advancing the development of high-performance neutral beam injection systems.

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EAST 中性束注入器中 120 keV/50 A 加速器等离子网格的热机械分析

大电流离子源是中性束注入（NBI）磁约束聚变系统的关键部件，其性能直接决定了整个系统的效率和可靠性。随着中性束注入加热在磁约束聚变研究中的应用需求日益增加，开发具有更高束流能量和功率的离子源已成为研究的重点。为了响应120 keV/50 A离子源的新设计要求，本研究研究了新设计的120 keV/50 A三极管加速器等离子体栅格在长脉冲高功率工作条件下的热力学性能。采用FLUENT与有限元软件耦合的数值方法，建立了热应力耦合分析模型。通过系统分析，确定钼为最佳材料选择，确定长脉冲大功率条件下安全运行所需的最小冷却水质量流量为0.426 kg/s。在最恶劣工况下的深入分析表明，最大Von-Mises等效应力仍低于材料屈服强度。通过EAST-NBI综合试验平台的试验结果验证了数值模型的可靠性，为长脉冲高功率条件下的安全运行提供了重要依据。这项工作对推进高性能中性束注入系统的发展具有重要的价值。

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 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.