A coupled NBI-EC model in investigating the assistant effect on the current ramp-up in EAST

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Hongcan Liu , Qianhong Huang , Ji Wang , Xueyu Gong , Yuanlai Xie , Caichao Jiang , Yijun Zhong , Yuqing Chen , Xingyuan Xu , Wangbin Liu , Junfeng Liu , Ruoxin Bai
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引用次数: 0

Abstract

Simulations using TRANSP, ONETWO, and EFIT based on EAST device parameters analyzed the current ramp-up phase under combined neutral beam injection (NBI) and electron cyclotron (EC) injection. The evolution of the plasma current and changes in its profile were analyzed under conditions of 6.0 MW neutral beam injection (NBI) and 2.4 MW electron cyclotron wave (ECW) injection. The study focused on the profile of the current density, particularly the contributions from the Ohmic current, bootstrap current, and non-inductive driven currents. Results showed an approximately 80% reduction in Ohmic current and loop voltage, with volt-second consumption minimized to 0.135 V·s, the lowest compared to NBI or EC alone. This positive effect was attributed to the electron cyclotron wave (ECW) injecting, which elevated the electron temperature, thereby enhancing the efficiency of neutral beam current drive (NBCD). The increased electron temperature facilitated more effective thermalization of fast ions, leading to improved NBCD performance. Consequently, the overall current drive efficiency was significantly boosted, contributing to better plasma stability and confinement. This highlights the efficiency of NBI+EC heating in managing magnetic flux evolution and minimizing resistive losses.
一个耦合的NBI-EC模型用于研究东部电流上升的辅助效应
基于EAST器件参数,利用TRANSP、ONETWO和EFIT进行了模拟,分析了中性束注入(NBI)和电子回旋加速器(EC)联合注入下的电流上升相位。分析了6.0 MW中性束注入(NBI)和2.4 MW电子回旋波注入(ECW)条件下等离子体电流的演变及其剖面的变化。重点研究了电流密度的分布,特别是欧姆电流、自举电流和无感驱动电流的贡献。结果表明,与单独的NBI或EC相比,欧姆电流和回路电压降低了约80%,伏秒消耗降至0.135 V·s,最低。这一积极效应归因于电子回旋波(ECW)注入提高了电子温度,从而提高了中性束电流驱动(NBCD)的效率。电子温度的提高促进了快速离子的有效热化,从而改善了NBCD的性能。因此,整体电流驱动效率显著提高,有助于更好的等离子体稳定性和约束。这突出了NBI+EC加热在管理磁通演变和最小化电阻损耗方面的效率。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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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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