测量机械振动及其对 J-TEXT 托卡马克磁性诊断的影响

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Fusion Engineering and Design Pub Date : 2024-09-16 DOI:10.1016/j.fusengdes.2024.114670
Bo Hu, Song Zhou, Nengchao Wang, Yangbo Li, Feiyue Mao, Zhengkang Ren, Ying He, Chuanxu Zhao, Yonghua Ding, the J-TEXT team
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引用次数: 0

摘要

在 J-TEXT 托卡马克上观测到了机械振动及其对磁性诊断测量的深刻影响。为了解释振动引起的低频磁振荡,我们建立了一个分析模型。实验结果和分析模型之间的比较表明,真空容器的振动是沿着 J-TEXT 的两块基石产生的。通过对 J-TEXT 组件的振动测量,我们确定了振动的起源是磁化前磁场的快速变化。此外,我们还发现磁诊断和环形磁场之间的相对振动也是低频磁振荡的原因之一。这项工作获得的结果不仅对聚变装置的振动预测具有重要意义,而且有助于实验人员对获得的诊断结果进行输入修正。
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Measurement of the mechanical vibration and its impact on the magnetic diagnostics in the J-TEXT tokamak

The mechanical vibration and its profound impacts on the magnetic diagnostic measurement have been observed on the J-TEXT tokamak. To explain the low frequency magnetic oscillation induced by the vibration, an analytical model has been developed. The comparisons between the experimental results and the analytical model indicate that the vibration of the vacuum vessel is along two keystones of J-TEXT. Through vibration measurements of J-TEXT components, we have identified that the origin of vibration is the rapid change of the pre-magnetization field. Additionally, it is found that the relative vibrations between magnetic diagnostics and toroidal magnetic fields contribute to the low frequency magnetic oscillation. The results obtained in this work are not only important for the prediction of vibration in fusion devices, but also helpful for experimenters to input corrections in obtained diagnostic results.

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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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