Electron heating by ion Bernstein wave in the HT-7 tokamak

Zhao, Yanping; Li, J; Luo, Junhua; Wan, Baonian; Mao, Yuzhou; Yang, Bao; Lin, Binbin; Gong, Xuzhong; Gao, Xiang; Yang, Xiuda; Jie, Yu; Liu, S; Xie, Songbai; Wan, Y. X.

doi:10.1088/0741-3335/43/3/309

Cited by 31 publications

(8 citation statements)

References 14 publications

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“…[11][12][13] It is not easy to get high performance steady-state H-mode in HT-7 due to several problems, such as magnetohydrodynamic ͑MHD͒ instability, high impurity radiation, and edge recycling. The features of IBW and LHCD are integrated to obtain long pulse high performance discharges by proper optimization of operation, particularly, choosing a strategy to avoid MHD activities.…”

Section: Resultsmentioning

confidence: 99%

Long pulse enhanced confinement discharges in the HT-7 superconducting tokamak by ion Bernstein wave heating and lower hybrid wave current drive

Wan

Luo

et al. 2003

Physics of Plasmas

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Significant progress has been made on the HT-7 superconducting tokamak (R=1.22 m, a=0.27 m) in the past year toward obtaining advanced operating modes in steady state. By combining ion Bernstein wave and lower hybrid current drive edge-localized-mode-free limiter H-mode discharges with H89∼2, βN*H89>3 have been obtained that lasted for 53 τE. A well-boronized wall prevented further impurity accumulation and the large pumping kept the recycling at a very low level. The density was kept almost constant with the feedback control. The noninductive driven current fraction is about 60% and bootstrap fraction is about 18%. The central electron temperature is about 2.6 keV and density above 2×1019 m−3. With reduced plasma parameters of central Te∼1.5 keV and ne0∼2×1019 m−3, H89∼1.45, βN∼1.1, the improved confinement phase lasts for more than 100 τE with the noninductive driven current fraction ∼70%.

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Section: Resultsmentioning

confidence: 99%

Long pulse enhanced confinement discharges in the HT-7 superconducting tokamak by ion Bernstein wave heating and lower hybrid wave current drive

Wan

Luo

et al. 2003

Physics of Plasmas

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“…For the long pulse discharges in HT-7, direct electron heating via electron Landau damping (ELD) from IBW was observed [5] . LHW also deposits the power to electrons in the HT-7 experiment.…”

Section: Methods Of Power Balance Analysismentioning

confidence: 99%

“…The LHCD system consists of a multijunction grill (2∼12), a wave system of 1.2 MW with a frequency of 2.45 GHz. A multichannel hard X-ray (HXR) pinhole diagnostic is used in HT-7 to study the spatial and energy distribution of the electrons accelerated by LHW in a range of 20 keV to 200 keV [5] . The electron density profile n e (r) is measured by a 5-channel far infrared laser interferometer.…”

Section: Relevant Diagnosticsmentioning

confidence: 99%

Methods of Power Balance Analysis and Estimation of Current Density Profile for LHCD and IBW Discharges in HT-7 Tokamak

Zhang

Wan

Shi

et al. 2008

Plasma Sci. Technol.

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In this paper a simple code has been developed to analyze power balance and qualitatively evaluate current profiles for discharges with lower hybrid current drive (LHCD) and ion Bernstein wave (IBW) heating in the HT-7 tokamak. Electron and ion thermal diffusivity, profiles of the bootstrap current density and total plasma current density can be estimated by this code using the experimental data. This code offers an easy and reasonable means to understand plasma transport in HT-7.

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“…The magnetic potential F can be calculated by putting the size detail into the last formula: to provide the magnetic intensity 2000 Gs, the magnetic potential of biasing magnet F is 2×10 4 A; and that of ±400 Gs, the excitation potential of variable magnet F is 3.8×10 3 A.…”

Section: Biasing Magnet Designmentioning

confidence: 99%

“…Ion cyclotron range of frequency (ICRF) heating has been employed in tokamaks as one of the most successful auxiliary heating tools [1][2][3][4][5] and has been adopted in the EAST, which is a fully superconducting tokamak with an elongated crosssection and has been operated. The essence of ICRF is that the ion cyclotron wave injected from the exterior interacts with plasma to heat the plasma.…”

Section: Introductionmentioning

confidence: 99%

Tunable biasing magnetic field design of ferrite tuner for ICRF heating system in EAST

Xu¹,

Song²,

Chen³

et al. 2017

Plasma Sci. Technol.

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Ion cyclotron range of frequency (ICRF) heating has been used in tokamaks as one of the most successful auxiliary heating tools and has been adopted in the EAST. However, the antenna load will fluctuate with the change of plasma parameters in the ICRF heating process. To ensure the steady operation of the ICRF heating system in the EAST, fast ferrite tuner (FFT) has been carried out to achieve real-time impedance matching. For the requirements of the FFT impedance matching system, the magnet system of the ferrite tuner (FT) was designed by numerical simulations and experimental analysis, where the biasing magnetic circuit and alternating magnetic circuit were the key researched parts of the ferrite magnet. The integral design goal of the FT magnetic circuit is that DC bias magnetic field is 2000 Gs and alternating magnetic field is ±400 Gs. In the FTT, E-type magnetic circuit was adopted. Ferrite material is NdFeB with a thickness of 30 mm by setting the working point of NdFeB, and the ampere turn of excitation coil is 25 through the theoretical calculation and simulation analysis. The coil inductance to generate alternating magnetic field is about 7 mH. Eddy-current effect has been analyzed, while the magnetic field distribution has been measured by a Hall probe in the medium plane of the biasing magnet. Finally, the test results show the good performance of the biasing magnet satisfying the design and operating requirements of the FFT.

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Electron heating by ion Bernstein wave in the HT-7 tokamak

Cited by 31 publications

References 14 publications

Long pulse enhanced confinement discharges in the HT-7 superconducting tokamak by ion Bernstein wave heating and lower hybrid wave current drive

Long pulse enhanced confinement discharges in the HT-7 superconducting tokamak by ion Bernstein wave heating and lower hybrid wave current drive

Methods of Power Balance Analysis and Estimation of Current Density Profile for LHCD and IBW Discharges in HT-7 Tokamak

Tunable biasing magnetic field design of ferrite tuner for ICRF heating system in EAST

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