Experiment and simulation of ELM in NBI heated plasma on EAST tokamak

Geng, Kangning; Tang, Tengfei; Kong, Defeng; Zhang, Shoubiao; Zhang, Tao; Huang, Chongxiang; Wu, Muquan; Jiang, Di; Lyu, Bo; Wang, Liang; Gao, Wei; Liu, Zixi; Liu, A.D.; Duan, Yanmin; Zhang, Ling; Ye, Jie; Zang, Qing; Zhu, Xiang; Hao, Baolong; Wang, Ke; Lin, Xiaohui; Huang, Jianjun; Wan, Yuanxi; Gao, Xiang

doi:10.1088/1741-4326/abe08e

Cited by 3 publications

(2 citation statements)

References 33 publications

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“…By using the Doppler reflectometer, the edge radial electric fields produced by NBIs on the EAST were about 2 kV m −1 for 1 MW co-current NBI case and 6 kV m −1 for 1 MW counter-current NBI case [36,37]. Note that in our model, the beam injection power is 2 MW.…”

Section: The Radial Electric Field Produced By Nbimentioning

confidence: 83%

Simulations of the radial electric field induced by neutral beam injection in a tokamak

Xu¹,

Xu²,

Zhang³

et al. 2021

Nucl. Fusion

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A model based on Poisson’s equation has been proposed to study the radial electric field induced by neutral beam injection (NBI). The radial electric field is produced by charge separation of beam induced electrons and beam ions. The charge separation is produced by redistribution and loss of NBI ions, which is due to the magnetic drift and collision effects. The birth and steady-state distributions of NBI fast ions related to charge separation were numerically computed by the orbit code GYCAVA and the NBI code TGCO. According to our model, the neoclassical polarization density of bulk ions has a great shielding effect on the radial electric field due to charge separation. The simulation results show that NBI ions can produce a significant radial electric field (∼10 kV m−1) in the core region. The counter-current NBI (injection anti-parallel to the plasma current) can produce a negative radial electric field, which is due to the magnetic drift and collision effects of NBI ions. While the co-current injection (injection parallel to the plasma current) produces a positive radial electric field in the core region, which is mainly related to the magnetic drift of NBI ions. The dependence of the radial electric field on the injection direction and the beam energy of NBI has been investigated. As the beam energy increases, the magnitudes of the electric field for counter-injections increase and the magnitude of the electric field for co-current perpendicular injection decrease.

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Section: The Radial Electric Field Produced By Nbimentioning

confidence: 83%

Simulations of the radial electric field induced by neutral beam injection in a tokamak

Xu¹,

Xu²,

Zhang³

et al. 2021

Nucl. Fusion

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show abstract

“…It is assumed that the ion pressure P i = 1/2P for both the equilibrium and perturbed components. The toroidal flow could modulate the ELM in EAST, and the simulation using BOUT++ suggests the net flow shear could reduce the ELM size [24]. So, the simulated ELM size will be increased due to the lack of toroidal flow in the case with higher heating power.…”

Section: Nonlinear Simulation Using Bout++mentioning

confidence: 99%

Study on filament width of type-I ELM in EAST using VUV imaging system and simulation

Ming

Tang²,

Shi³

et al. 2022

Nucl. Fusion

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The poloidal width of the filaments induced by the Type-I edge localized mode has power dependence in EAST. The poloidal widths of the filaments observed by the high-speed vacuum ultraviolet (VUV) imaging system are proportional to the heating power and the ELM size. To understand this power dependence, the BOUT++ nonlinear simulations have been performed with the reconstructed equilibriums from the experimental measurements in this paper. The synthetic filament structures from BOUT++ nonlinear simulation match the experimental observations by the VUV imaging system. The BOUT++ nonlinear simulations also reproduce the power dependence of the filament widths and the ELM size. The filament width and the ELM size are inversely proportional to the toroidal mode number. The low-n mode has a broader radial and poloidal structure, which causes the larger filament width and ELM size. In the high input power case, the mode spectrum shifts to low-n, a result of increasing peeling drive. Besides, we found the β_p in a higher input power case leads to a broader pedestal, expanding the radial mode structure of the Peeling-Ballooning mode.

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All superconducting tokamak: EAST

Wang

Zhang

et al. 2023

AAPPS Bull.

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Experimental Advanced Superconducting Tokamak (EAST) was built to demonstrate high-power, long-pulse operations under fusion-relevant conditions, with major radius R = 1.9 m, minor radius a = 0.5 m, and design pulse length up to 1000s. It has an ITER-like D-shaped cross-section with two symmetric divertors at the top and bottom, accommodating both single null and double null divertor configurations. EAST construction was started in 2000, and its first plasma was successfully obtained in 2006. In the past 15 years, plasma-facing components, plasma heating, diagnostics, and other systems have been upgraded step by step to meet its mission on exploring of the scientific and technological bases for fusion reactors and studying the physics and engineering technology issues with long pulse steady-state operation. An advanced steady-state plasma operation scenario has been developed, and plasma parameters were greatly improved. Meanwhile, front physics on the magnetic confinement plasmas have been systemically investigated and lots of fruitful results were realized, covering transport and confinement, MHD stabilities, pedestal physics, divertor and scrap-off layer (SOL) physics, and energetic particle physics. This brief review of EAST on engineering upgrading, stand-steady operation scenario development, and plasma physics investigation would be useful for the reference on construction and operation of a superconducting tokamak, such as ITER and future fusion reactor.

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Experiment and simulation of ELM in NBI heated plasma on EAST tokamak

Cited by 3 publications

References 33 publications

Simulations of the radial electric field induced by neutral beam injection in a tokamak

Simulations of the radial electric field induced by neutral beam injection in a tokamak

Study on filament width of type-I ELM in EAST using VUV imaging system and simulation

All superconducting tokamak: EAST

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