Numerical simulation of electron cyclotron current drive characteristics on EAST

Wei, Wei; Ding, Bojiang; Zhang, Xinjun; Wang, Xiaojie; Li, Miaohui; Kong, E. H.; Zhang, Lei

doi:10.1088/1674-1056/23/5/055201

Cited by 12 publications

(10 citation statements)

References 23 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…On EAST, the LHCD and ECRH are used to drive current. However, the simulations showed generally the driven currents vanishes at the edge region [26,45,46]. The simulation result shown in figure 5(b) indicates that the fast ion current contributes only a few percentages at the top of the pedestal and vanishes in the pedestal.…”

Section: Edge Current Profile Constraintmentioning

confidence: 91%

Kinetic equilibrium reconstruction for the NBI- and ICRH-heated H-mode plasma on EAST tokamak

Zheng¹,

Xiang²,

CHEN³

et al. 2018

Plasma Sci. Technol.

View full text Add to dashboard Cite

The equilibrium reconstruction is important to study the tokamak plasma physical processes. To analyze the contribution of fast ions to the equilibrium, the kinetic equilibria at two time-slices in a typical H-mode discharge with different auxiliary heatings are reconstructed by using magnetic diagnostics, kinetic diagnostics and TRANSP code. It is found that the fast-ion pressure might be up to one-third of the plasma pressure and the contribution is mainly in the core plasma due to the neutral beam injection power is primarily deposited in the core region. The fast-ion current contributes mainly in the core region while contributes little to the pedestal current. A steep pressure gradient in the pedestal is observed which gives rise to a strong edge current. It is proved that the fast ion effects cannot be ignored and should be considered in the future study of EAST.

show abstract

Section: Edge Current Profile Constraintmentioning

confidence: 91%

Kinetic equilibrium reconstruction for the NBI- and ICRH-heated H-mode plasma on EAST tokamak

Zheng¹,

Xiang²,

CHEN³

et al. 2018

Plasma Sci. Technol.

View full text Add to dashboard Cite

show abstract

“…For the given equilibrium parameters of EAST, the deposition of EC power was greatly dependent on the scanning of launcher position, and both the poloidal and toroidal steering angles. It is found that a launch from Z = 30 cm (the vertical position) is the best scheme for core localized heating and the suppression of neoclassical tearing modes [14,15].…”

Section: Layout Designmentioning

confidence: 99%

Research activities and progress on the long pulse ECRH launcher for EAST

et al. 2019

Self Cite

View full text Add to dashboard Cite

A long pulse Electron Cyclotron Resonance Heating (ECRH) system is developed on EAST tokamak for plasma heating and current profile tailoring. The ECRH system is designed to operate at 140GHz and to inject 4MW CW power. With respect to the physical objectives of the newly built ECRH system, a quasi-optical launcher is designed to inject 4MW continuous wave into plasma through an equatorial port. Gaussian beams delivered from evacuated corrugation waveguides will be focused and reflected by high thermal conductive metal mirrors, and then steered by using push-rod steering mechanism with entire scanning range of ±25° toroidally and over 30° poloidally in plasma cross section. The mirrors are carefully designed with mega watts power handling capability and optimum optical characteristics. The performance of steering mechanism has been tested before installation, an open-loop control system for ECRH launcher has been implemented for required mirror movement and proper polarization between plasma discharges. This paper will present the overall design and progress of the launcher, along with the performance in EAST campaigns. Considerations and possible upgrade of the design features relevant to long pulse operation are discussed.

show abstract

“…The toroidal injection angle β is the counter-clockwise angle measured from the direction of the major radius on the equatorial plane at the launch point. [25] 1.0 The parameters of the HL-2M tokamak are as follows: [26] major radius R = 1.78 m, minor radius a = 0.65 m, elongation κ = 1.87, triangularity δ = 0.45, plasma current I P = 1.0 & 2.0 MA, and the magnetic field at magnetic axis B t = 1.82 T for SD1 and B t = 2.0 T for SD2. The scenarios of the two single-null diverted HL-2M equilibria, shown in Fig.…”

Section: Toray Code and The Parameters Of Hl-2mmentioning

confidence: 99%

Numerical analysis of the optimized performance of the electron cyclotron wave system in a HL-2M tokamak

Gong

Dong

et al. 2016

Chinese Phys. B

View full text Add to dashboard Cite

The capabilities of current drive, neoclassical tearing mode (NTM) stabilization, and sawtooth control are analyzed for the electron-cyclotron wave (ECW) system in a HL-2M tokamak. Better performance of the upper launcher is demonstrated in comparison with that of a dropped upper launcher, in terms of J EC /J bs for NTM stabilization and I ECCD /(∆ρ tor ) 2 for sawtooth control. 1-MW ECW power is enough for the 3/2 NTM stabilization, and 1.8-MW ECW power is required to suppress 2/1 NTM in a single null divertor equilibrium with 1.2-MA toroidal current with the upper launcher. Optimization simulation of electron-cyclotron current drive (ECCD) is carried out for three mirrors in an equatorial port, indicating that the middle mirror has a good performance compared with the top and bottom mirrors. The results for balanced co-and counter-ECCD in an equatorial port are also presented.

show abstract

Numerical simulation of electron cyclotron current drive characteristics on EAST

Abstract: 韦维) a)b) , Ding Bo-Jiang(丁伯江) a) † , Zhang Xin-Jun(张新军) a) , Wang Xiao-Jie(王晓洁) a) , Li Miao-Hui(李妙辉) a) , Kong Er-Hua(孔二华) a) , and Zhang Lei(张磊) a) a)

Cited by 12 publications

References 23 publications

Kinetic equilibrium reconstruction for the NBI- and ICRH-heated H-mode plasma on EAST tokamak

Kinetic equilibrium reconstruction for the NBI- and ICRH-heated H-mode plasma on EAST tokamak

Research activities and progress on the long pulse ECRH launcher for EAST

Numerical analysis of the optimized performance of the electron cyclotron wave system in a HL-2M tokamak

Contact Info

Product

Resources

About

Numerical simulation of electron cyclotron current drive characteristics on EAST

Abstract: 韦 维) a)b) , Ding Bo-Jiang(丁伯江) a) † , Zhang Xin-Jun(张新军) a) , Wang Xiao-Jie(王晓洁) a) , Li Miao-Hui(李妙辉) a) , Kong Er-Hua(孔二华) a) , and Zhang Lei(张 磊) a) a)

Cited by 12 publications

References 23 publications

Kinetic equilibrium reconstruction for the NBI- and ICRH-heated H-mode plasma on EAST tokamak

Kinetic equilibrium reconstruction for the NBI- and ICRH-heated H-mode plasma on EAST tokamak

Research activities and progress on the long pulse ECRH launcher for EAST

Numerical analysis of the optimized performance of the electron cyclotron wave system in a HL-2M tokamak

Contact Info

Product

Resources

About

Abstract: 韦维) a)b) , Ding Bo-Jiang(丁伯江) a) † , Zhang Xin-Jun(张新军) a) , Wang Xiao-Jie(王晓洁) a) , Li Miao-Hui(李妙辉) a) , Kong Er-Hua(孔二华) a) , and Zhang Lei(张磊) a) a)