Development of 4.6GHz lower hybrid current drive system for steady state and high performance plasma in EAST

Liu, F.K.; Li, J.G.; Shan, Jiafang; Wang, M.; Liu, L.; Zhao, Liang; Hu, Haiping; Feng, Jingcheng; Yang, Yilin; Jia, H.; Wang, X.J.; Wu, Zege; Ma, Wendong; Huang, Yisheng; Xu, Handong; Zhang, J.; Cheng, Min; Xu, Long; Li, M.H.; Li, Y.C.; Zang, Qing; Li, G.Q.; Ding, Bojiang

doi:10.1016/j.fusengdes.2016.10.020

Cited by 29 publications

(13 citation statements)

References 28 publications

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“…Two CW LHCD systems are installed and operated in EAST campaign [6]. There are a 4.0 MW / 2.45 GHz system and a new 6.0 MW/ 4.6 GHz system utilizing 2 individual multi-junction phase antennas.…”

Section: Lhw Systemmentioning

confidence: 99%

“…As indicated by the parametric instability (PI) measurement by a radio frequency (RF) loop antenna (Fig. 4), it is speculated to [11] has been further utilised for calculating the driven current profile [6]. Due to the PI effect, the power deposited in the edge region, which cannot contribute to useful LHCD mechanism, is different, leading to a different LH current profile.…”

Section: Fig 2 Demonstration Of Lh Spectrum On Controlling Current mentioning

confidence: 99%

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Recent progress of RF-dominated experiments on EAST

et al. 2017

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Abstract. The research of EAST program is mostly focused on the development of high performance steady state scenario with ITER-like poloidal configuration and RF-dominated heating schemes. With the enhanced ITER-relevant auxiliary heating and current drive systems, the plasma profile control by coupling/integration of various combinations has been investigated, including lower hybrid current drive (LHCD), electron cyclotron resonance heating (ECRH) and ion cyclotron resonance heating (ICRH). The 12 MW ICRH system has been installed on EAST. Heating and confinement studies using the Hydrogen Minority Heating scheme have been investigated. One of the importance challenges for EAST is coupling higher power into the core plasma, experiments including changing plasma position, electron density, local gas puffing and antenna phasing scanning were performed to improve ICRF coupling efficiency on EAST. Results show that local gas injection and reducing the k|| can improve the coupling efficiency directly. By means of the 4.6 GHz and 2.45 GHz LHCD systems, H-mode can be obtained and sustained at relatively high density, even up to ne ~ 4.5 × 10 19 m -3, where a current drive effect is still observed. Meanwhile, effect of source frequency (2.45GHz and 4.6GHz) on LHCD characteristic has been studied on EAST, showing that higher frequency improves penetration of the coupled LH (lower hybrid) power into the plasma core and leads to a better effect on plasma characteristics. Studies demonstrate the role of parasitic effects of edge plasma in LHCD and the mitigation by increasing source frequency. Experiments of effect of LH spectrum and plasma density on plasma characteristics are performed, suggesting the possibility of plasma control for high performance. The development of a 4MW ECRH system is in progress for the purpose of plasma heating and MHD control. The built ECRH system with 1MW source power has been successfully put into use on EAST in 2015. H-mode discharges with L-H transition triggered by ECRH injection were obtained and its effects on the electron temperature, particle confinement and the core MHD stabilities were observed. By further exploring and optimizing the RF combination for the sole RF heating and current drive regime, fully non-inductive H-mode discharges with V loop~0 V has progressed steadily in the 2016 campaign. The overview of the significant progress of RF dominated experiments is presented in this paper.

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Section: Lhw Systemmentioning

confidence: 99%

Section: Fig 2 Demonstration Of Lh Spectrum On Controlling Current mentioning

confidence: 99%

Recent progress of RF-dominated experiments on EAST

et al. 2017

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“…Experimental advanced superconducting tokamak (EAST) [1], the first fully superconducting tokamak, aims at high performance and long pulse operation up to 1000 s. Lower hybrid current drive (LHCD) has been a very important method to realize the design goal in EAST [2]. There are two LHCD systems operating at 2.45 GHz [3,4] and 4.6 GHz [5,6] respectively. Various physics experiments require different lower hybrid wave (LHW) power modes.…”

Section: Introductionmentioning

confidence: 99%

Development of lower hybrid wave power feedback control and experiments on EAST

Wang

Yang

et al. 2023

J. Inst.

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A new method of power feedback control for the lower hybrid wave (LHW) systems on the experimental advanced superconducting tokamak (EAST) is presented. Different methods are applied to control the power of two LHW systems with different frequency at 2.45 GHz and at 4.6 GHz, respectively. The old method is applied to control the 4.6 GHz LHW power through the exciter of klystrons, and the new one is used to control the 2.45 GHz LHW power through the high voltage power supply (HVPS) system. The new method has been applied in EAST and successfully assisted the development of relevant experiments such as loop voltage control, q profile control.

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“…In the 2014 campaign, upgraded H/CD systems were installed on EAST with MW LHCD power at GHz (Liu et al. 2016) and 12 MW of ICRF power with tunable frequency in the range 25–75 MHz (Zhao et al. 2014).…”

Section: Introductionmentioning

confidence: 99%

“…In the 2012 campaign, the world's longest pulse H-mode were achieved, lasting more than 30 s with LHCD and ICRF, as well as the longest pulse divertor plasma (411 s), which was fully driven by LHCD . In the 2014 campaign, upgraded H/CD systems were installed on EAST with 4.0/6.0 MW LHCD power at 2.45/4.60 GHz (Liu et al 2016) and 12 MW of ICRF power with tunable frequency in the range 25-75 MHz (Zhao et al 2014). In addition, a 8 MW NBI system was also installed on EAST (Hu et al 2016).…”

Section: Introductionmentioning

confidence: 99%

Predictive simulations of operation scenarios for EAST with METIS code

Ding

et al. 2017

J. Plasma Phys.

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Upgraded heating and current drive (H/CD) systems have been equipped on the Experimental Advanced Superconducting Tokamak (EAST). With the upgraded H/CD systems, the operation space of EAST is extended, and the ability to achieve higher performance is improved. In this paper, a 0.5 dimension transport code named Minute Embedded Tokamak Integrated Simulator (METIS) is applied to predict the EAST operation space and to assess the current drive capability of the 4.6 GHz lower hybrid current drive system. Predictive simulation of several EAST scenarios, including steady-state high confinement mode (H-mode), advanced regime, high normalized beta and high electron temperature, are also performed with the available H/CD systems. The simulation results provide a guidance for forthcoming advanced EAST experiments.

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Development of 4.6GHz lower hybrid current drive system for steady state and high performance plasma in EAST

Cited by 29 publications

References 28 publications

Recent progress of RF-dominated experiments on EAST

Recent progress of RF-dominated experiments on EAST

Development of lower hybrid wave power feedback control and experiments on EAST

Predictive simulations of operation scenarios for EAST with METIS code

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