Optimized calculation of the synergy conditions between electron cyclotron current drive and lower hybrid current drive on EAST

Wei, Wei; Ding, Bingjun; Peysson, Y.; Decker, J.; Li, Miaohui; Zhang, Xinjun; Wang, Xiaojie; Zhang, Lei

doi:10.1088/1674-1056/25/1/015201

Cited by 7 publications

(2 citation statements)

References 18 publications

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“…Compared with the simulation results of ECCD performance using Toray code [24] and C3PO/LUKE code [25] on EAST, a difference is found on CFETR in the generation of the parasitic effect of second-harmonic absorption at high frequency. This may be related to the parameters affecting the wave absorption in the Doppler-shifted resonance between the waves and a small portion of the electron population.…”

Section: Launch Positionmentioning

confidence: 79%

Evaluation of electron cyclotron current drive performance for CFETR

Wei¹,

Wang²,

Li³

2019

Plasma Sci. Technol.

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A number of simulations of electron cyclotron current drive (ECCD) have been carried out for the China Fusion Engineering Test Reactor (CFETR) using the C3PO/LUKE code to investigate the performance and optimize schemes of power injection for the design of the launcher. The operation ranges of the toroidal field, cutoff density, and resonance layer location are given at different source frequencies in CFETR phases I and II. A comparison of ECCD performance between the horizontal and top port launch is presented. ECCD efficiency EC g ( ) estimated for CFETR phase I is 0.21 EC g = for top port launch and 0.20 EC g = for horizontal port launch. The ECCD efficiency and second-harmonic absorption is calculated at different wave frequencies (from 170 to 230 GHz) in CFETR phase II. It is found that the highest driven efficiency is obtained at 210 GHz with the toroidal field of 6.5 T, and the second-harmonic absorption increases rapidly with the increase of frequency.

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Section: Launch Positionmentioning

confidence: 79%

Evaluation of electron cyclotron current drive performance for CFETR

Wei¹,

Wang²,

Li³

2019

Plasma Sci. Technol.

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“…Neoclassical tearing mode (NTM) is a new tearing instability in toroidal plasma, which appears and is recognized as a factor to degrade plasma performance and may even lead to disruptions when the driven force of bootstrap current is considered. [1][2][3][4] So far, people have come up with many ways to inhibit NTM, including the use of electron cyclotron current drive (ECCD), [5,6] lower hybrid current drive, [7,8] externally applied resonant magnetic perturbations, [9,10] neutral beam injection, as well as using plasma rotation. Among those, ECCD is one of the most effective ways since it can deposit current in plasma region flexibly, and the current drive efficiency can reach a high level as well.…”

Section: Introductionmentioning

confidence: 99%

Neoclassical tearing mode stabilization by electron cyclotron current drive for HL-2M tokamak*

Li¹,

Dong²,

Ji³

et al. 2021

Chinese Phys. B

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Investigation of neoclassical tearing mode and its suppression by electron cyclotron current drive (ECCD) has been carried out in HL-2M tokamak. The current driving capability of the electron cyclotron wave is evaluated. It is found that the deposition location can be effectively controlled by changing the poloidal angle. The validation of electron cyclotron wave heating and current driving has been demonstrated for the upper launcher port. We show that 3.0 MW and 2.5 MW modulated ECCD can completely stabilize (2,1) and (3,2) NTMs, respectively. The non-modulated ECCD, radial misalignment as well as current profile broadening have deleterious effect on the NTM stabilization. The time required for suppression of (3,2) mode is shorter than that required for the suppression of (2,1) mode. Moreover, the time needed for complete stabilization at different initial island width has been quantitatively presented and analyzed.

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Conceptual design of CFETR ECRH equatorial launcher and upper launcher

et al. 2019

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The Electron Cyclotron Resonance Heating (ECRH) system of China Fusion Engineering Test Reactor (CFETR) is designed to inject 20 MW RF power into the plasma for heating and current drive (H&CD) applications. The ECRH system consists of 20 gyrotrons, the associated power supplies, the transmission lines and one launcher. In order to compare the launcher performance from equatorial and upper ports, two types of launcher are designed in this paper. In equatorial launcher (EL), twenty in-vessel transmission lines are divided into four groups. Every five gaussian beams from in-vessel transmission lines face one fixed focusing mirror and one steering mirror. All gaussian beams are injected into the plasma with optimal toroidal and poloidal angles calculated by C3PO/LUKE code. In upper launcher (UL), twenty-one transmission lines are supposed and divides into three groups. Every seven gaussian beams are injected into one fixed focusing mirrors and all twenty-one beams reflected to one common steering mirror finally. The optical transmission characteristics and the convergence information of gaussian beams are checked and optimized. The EL or UL is installed on the equatorial or upper port with a port-plug modular structure.

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Optimized calculation of the synergy conditions between electron cyclotron current drive and lower hybrid current drive on EAST

Cited by 7 publications

References 18 publications

Evaluation of electron cyclotron current drive performance for CFETR

Evaluation of electron cyclotron current drive performance for CFETR

Neoclassical tearing mode stabilization by electron cyclotron current drive for HL-2M tokamak*

Conceptual design of CFETR ECRH equatorial launcher and upper launcher

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