函数参数化在Aditya-U托卡马克等离子体位置估计中的应用

IF 2 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Sameer Kumar , Kumudni Tahiliani , Praveenlal Edappala , Praveena Kumari , I Suresh , Surya Kumar Pathak , Daniel Raju , Rakesh L Tanna , Rohit Kumar , Harshita Raj , Joydeep Ghosh , Aditya-U Team
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引用次数: 0

摘要

通过对磁探头数据进行函数参数化处理,实现了托卡马克控制系统等离子体位置的快速准确测量。在Aditya-U托卡马克中,在等离子体柱周围安装了一个由16个探针组成的极向阵,并采用基于函数参数化技术的算法估计了等离子体的位置。该方法的验证是通过在真空容器内不同位置放置电流回路来完成的。结果表明,当测头数量从7个增加到16个时,测量精度有所提高。此外,为了实现未来的实时位置测量,在7个探头中使用积分器电路对探头输出进行时间积分,并将扩展到所有探头。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Application of function parametrization for plasma position estimation in Aditya-U tokamak
The fast and accurate measurement of plasma position for the tokamak control system is determined by the application of function parametrization on the magnetic probe data. In Aditya-U tokamak, a poloidal array of 16 probes is installed around the plasma column, and the plasma position has been estimated by an algorithm based on the function parametrization technique. The validation of the method is done by placing a current loop inside the vacuum vessel at different positions. It is found that the measurement accuracy improved as the number of probes was increased from 7 to 16. Also, to enable the real-time position measurement in the future, time integration of the probe output is enabled using the integrator circuits in 7 probes, which will be extended to all the probes.
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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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