Development and Preliminary Commissioning Results of a Long Pulse 140 GHz ECRH System on EAST Tokamak (Invited)

Xu, Handong; Wang, Xiaojie; Liu, Fukun; Zhang, Jian; Huang, Yiyun; Shan, Jiafang; Wu, Dajun; Hu, Huaichuan; Li, Bo; Li, Miaohui; Yang, Yong; Feng, Jingcheng; Xu, W.; Tang, Yunying; Wei, Wei; Xu, Liqing; Liu, Yong; Zhao, Hailin; Lohr, J.; Gorelov, Y.A.; Anderson, James P.; Ma, Wendong; Wu, Zege; Wang, Jian; Zhang, Liyuan; Guo, Fei; Sun, Hong-xiang; Yan, Xinsheng

doi:10.1088/1009-0630/18/4/19

Cited by 46 publications

(29 citation statements)

References 18 publications

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“…22 Furthermore, the ECRH power has been injected using the standard second harmonic scheme which provides pure electron heating with 80% absorption of a source power below 0.5 MW. 23 All global parameters are averaged over a time interval of 10 ms in the L-mode phase just before the time of the L-H transition, as will be shown in Sec. III.…”

Section: -2mentioning

confidence: 99%

Effect of ∇B drift on the H-mode power threshold in upper single null plasmas with ITER-like tungsten divertor on EAST

Chen

Niu

et al. 2018

Physics of Plasmas

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Section: -2mentioning

confidence: 99%

Effect of ∇B drift on the H-mode power threshold in upper single null plasmas with ITER-like tungsten divertor on EAST

Chen

Niu

et al. 2018

Physics of Plasmas

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“…It is seen that the locations can be varied in the region of < 0.8 and good agreement between the experiments and simulations are achieved, which validates the steerable performance of the launcher. Good plasma heating effects were obtained during ohmic target plasma [8] and H-mode phase by 400 kW EC waves injection. As shown in Fig.9, the electron temperature measured by electron-cyclotron emission (ECE) radiometer increases globally during ECRH phase.…”

Section: Preliminary Results From Ecrhmentioning

confidence: 99%

“…As one of the most promising external heating methods, a long pulse electron cyclotron resonance heating (ECRH) system [7,8] with 4MW power is under development at the frequency of 140 GHz (2nd harmonic X mode injection at a field of 2.5 Tesla), it will be used to provide central heating, optimize the plasma profiles for high pressure and good confinement as well as suppression of magneto-hydrodynamic (MHD) instabilities by a flexible two-mirror steerable antenna. At present, 1MW system was put into operation since 2015.…”

Section: Ecrh Systemmentioning

confidence: 99%

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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“…Gycom gyrotrons are employed in the No.1 and No.3 systems, CPI gyrotrons are used in the No.2 and No.4 systems. Two gyrotron systems were installed in 2014 and the first short pulse EC wave injection has been demonstrated successfully during the EAST 2015 Spring campaign [5]. Significant plasma heating and MHD instability suppression effects were observed.…”

Section: ．Introductionmentioning

confidence: 99%

Recent progress of the development of a long pulse 140GHz ECRH system on EAST

Wang

Zhang

et al. 2019

EPJ Web Conf.

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A long pulse ECRH system with a goal of 140GHz 4MW 100~1000s has been developed to meet the requirement of steady-state operation on EAST. Gycom gyrotrons are employed in the No.1 and No.3 systems, CPI gyrotrons are used in the No.2 and No.4 systems. The development of the two Gycom gyrotron systems has been finished. The first short pulse EC wave injection has been demonstrated successfully during the EAST 2015 Spring campaign. In the commissioning and operation towards steadystate operation, 0.4MW 100s has been injected to plasma successfully by using the No.1 system, 4.7keV 102s L-mode and 102s H-mode plasma have been achieved on EAST with the help of ECRH. Recently, a longest pulse of 0.55MW 1000s has been obtained based on calorimetric dummy load measurements on the No.3 gyrotron. The No.2 gyrotron also has been installed and partially tested, 500kW 80s has been demonstrated in the dummy load. The remaining No.4 gyrotron will be ready to test in 2018 or 2019. The whole 4MW system will be completed within two years. The 400s fully non-inductive H-mode operation would be expected in the next four years in the condition of fully tungsten diverter on EAST.

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Development and Preliminary Commissioning Results of a Long Pulse 140 GHz ECRH System on EAST Tokamak (Invited)

Cited by 46 publications

References 18 publications

Effect of ∇B drift on the H-mode power threshold in upper single null plasmas with ITER-like tungsten divertor on EAST

Effect of ∇B drift on the H-mode power threshold in upper single null plasmas with ITER-like tungsten divertor on EAST

Recent progress of RF-dominated experiments on EAST

Recent progress of the development of a long pulse 140GHz ECRH system on EAST

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