Study and analysis of the design considerations for controlling vertical plasma position in ADITYA-U tokamak

IF 2 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Fusion Engineering and Design Pub Date : 2025-01-01 Epub Date: 2024-11-28 DOI:10.1016/j.fusengdes.2024.114736
Rohit Kumar , Harshita Raj , Vinay Menon , Deepti Sharma , Darshan Parmar , Dinesh Sharma , Vishal Jain , YSS Srinivas , Shivam Gupta , Rakesh Tanna , Ashok Mankani , Joydeep Ghosh
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Abstract

This paper presents design considerations of a new power supply and a new coil system for the vertical plasma position control in ADITYA-U tokamak. The main objective is to improve overall plasma performance compared to the existing open-loop system. Feedback stabilization of the plasma vertical position in ADITYA-U tokamak will play a vital role. Vertical Displacement Events (VDE) can be triggered during shaped plasma operation and requires proper control to avoid plasma disruptions. A radial magnetic field created by exterior coils will arrest the vertical plasma position against unwanted VDEs. Therefore, procurement of a new power supply namely, active position magnet control power supply (APMC-PS) is proposed to fulfill the vertical position control requirement in the ADITYA-U tokamak. This work presents the overall requirement for an active control system to improve the vertical control capability in the mid-size machine without passive stabilisers. The proposed scheme will support a reduction in time response with relatively less apparent power for controlling the vertical plasma position.
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ADITYA-U托卡马克等离子体垂直位置控制设计考虑的研究与分析
本文介绍了ADITYA-U托卡马克垂直等离子体位置控制的新型电源和新型线圈系统的设计思想。与现有的开环系统相比,主要目标是提高等离子体的整体性能。在ADITYA-U托卡马克中,等离子体垂直位置的反馈稳定起着至关重要的作用。垂直位移事件(VDE)可以在成形等离子体操作过程中触发,需要适当的控制以避免等离子体中断。外部线圈产生的径向磁场将阻止等离子体的垂直位置,以对抗不需要的vde。因此,为了满足ADITYA-U托卡马克的垂直位置控制需求,建议采购一种新型电源,即主动位置磁控电源(APMC-PS)。本文提出了一种主动控制系统的总体要求,以提高中型机床无被动稳定器的垂直控制能力。所提出的方案将支持以相对较少的视在功率来控制等离子体垂直位置的时间响应的减少。
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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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