Simulation of helicon wave current drive on the Experimental Advanced Superconducting Tokamak under high poloidal beta scenarios

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

Fusion Engineering and Design Pub Date : 2025-03-22 DOI:10.1016/j.fusengdes.2025.114968

Daozheng Zi , Zehou Cheng , Shuheng Sun , Miaohui Li , Xinxia Li

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引用次数: 0

Abstract

The high poloidal beta (

β_{p}

) scenario serves as a promising operational mode for tokamak fusion reactors. In this paper, the helicon wave current drive under high

β_{p}

scenarios on the EAST device is studied numerically. Theoretical analysis based on the fast wave dispersion relation indicates that a higher wave frequency enhances wave power absorption in the device. GENRAY/CQL3D simulations indicate that an effective on-axis plasma current drive can generally be achieved. Scans of plasma parameters reveal that lower plasma density and higher plasma temperature contribute to higher current drive efficiency. Moreover, a scheme of combined current drive using lower hybrid waves and helicon waves in the device is analyzed, resulting in significant complementarity in the current drive profile and a positive synergistic effect on the net current drive. This work is expected to provide a new perspective for the next stage of EAST operations.

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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.