用Wendelstein 7-X仿星器的可见发射模式估计等离子体大小

IF 2 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
A. Buzás , C. Biedermann , G. Cseh , G. Kocsis , M. Krause , T. Szepesi , M. Szűcs , The W7X Team
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引用次数: 0

摘要

由于Wendelstein 7-X仿星器的三维结构复杂且缺乏轴对称,使得等离子体尺寸的确定变得非常复杂。等离子体周围可见辐射带的有效半径(reff)给出了一个合适的估计。本研究提出了一种利用W7-X快速相机系统确定折射率的新方法。我们将预处理的EDICAM图像与合成图像相关联,合成图像基于来自单个通量表面的无限薄辐射层的预期发射。图像经过预处理,使该方法对墙壁反射和增加的分流辐射可靠。估计了辐射带的宽度,这与湍流结构的研究有关。我们演示了这种方法在分离和“呼吸等离子体”情况下的应用。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Estimating plasma size by visible emission patterns in the Wendelstein 7-X stellarator
Determining the plasma size in the Wendelstein 7-X stellarator is complicated by the complex 3D structure and lack of axial symmetry. The effective radius (reff) of the visible radiation belt around the plasma gives a suitable estimate. This study presents a novel method to determine reff using the W7-X fast camera system. We correlate preprocessed EDICAM images with synthetic images based on the expected emissions of infinitesimally thin radiating layers from individual flux surfaces. Images are preprocessed to make the method reliable against wall reflections and increased divertor radiation. The width of the radiation belt is also estimated, which is relevant in the study of turbulent structures. We demonstrate the applications of this method in the case of detached and “breathing plasmas”.
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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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