Parametric study of neutral beam injection heating and current drive in NCST

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Fusion Engineering and Design Pub Date : 2025-02-28 DOI:10.1016/j.fusengdes.2025.114897

X.X. Zhang, X.C. Chen, S.Q. Liu, H. Chen, X.F. Wu

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引用次数: 0

Abstract

In order to study the physics associated with high-

β

plasma and fast ions, we are exploring auxiliary heating method suitable for NanChang Spherical Tokamak(NCST). The NUBEAM code is used for numerically simulate NCST neutral beam injection (NBI) to provide relevant physical predictions. The NBI injection geometry is optimized to maximize deposition and current drive, thus avoiding excessive losses. The effects of density, electron temperature and plasma current on heating and current drive are discussed. The results show that the deposited power increases and the loss decreases with the increase of plasma density and current. The electron temperature primarily influences the fraction of power deposited on ion and electron, and the increase of electron temperature leads to a higher proportion of power deposited on ions. Lower electron density and higher electron temperature are favorable for neutral beam current drive. Under the same power conditions, the efficiency of low energy beam is superior to that of high energy beam, with the beam energy ranging from 15–25 keV.

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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.