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.
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.