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

IF 2 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Fusion Engineering and Design Pub Date : 2025-05-01 Epub 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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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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中性束注入加热和电流驱动的参数化研究

为了研究高β等离子体和快离子的物理特性，我们正在探索适合南昌球形托卡马克（NCST）的辅助加热方法。NUBEAM代码用于NCST中性束注入（NBI）的数值模拟，以提供相关的物理预测。优化了NBI注入几何形状，以最大限度地提高沉积和电流驱动，从而避免了过多的损耗。讨论了密度、电子温度和等离子体电流对加热和电流驱动的影响。结果表明，随着等离子体密度和电流的增大，沉积功率增大，损耗减小。电子温度主要影响沉积在离子和电子上的功率比例，电子温度的升高导致沉积在离子上的功率比例升高。较低的电子密度和较高的电子温度有利于中性束流的驱动。在相同功率条件下，低能束流的效率优于高能束流，束流能量在15 ~ 25 keV之间。

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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.