Progress of high power and long pulse ECRH system in EAST

Wang, Xiaojie; Liu, Fei; Shan, Jiafang; Xu, Handong; DajunWu,; Li, Bo; Wei, Wei; Zhang, Jian; Huang, Yisheng; Tang, Yue; Xu, Wenhai; Hu, Huaichuan; Wang, Jian; Xu, Long; Zhang, Liyuan; Feng, Jingcheng

doi:10.1016/j.fusengdes.2015.03.042

Cited by 43 publications

(21 citation statements)

References 12 publications

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“…EAST is a superconducting tokamak with flexible divertor configurations (lower single null, double null and upper single null (USN)), major radius R 0 ≤ 1.9 m, minor radius a ≤ 0.45 m [24]. Recently EAST has been equipped with four auxiliary heating methods, including low hybrid waves (LHWs) [25], ion cyclotron resonance heating (ICRH) [26], electron cyclotron resonance heating (ECRH) [27], and neutral beam injection (NBI) [28]. The discharges used in this paper are operated in the USN configuration with a tungsten upper divertor.…”

Section: Methodsmentioning

confidence: 99%

Edge turbulence characteristics and transport during the ELM mitigation with n = 1 resonant magnetic perturbation on EAST

et al. 2020

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The edge localized mode (ELM) has been mitigated by n = 1 resonant magnetic perturbation (RMP) in EAST tokamak. The turbulence characteristics and transport during the ELM mitigation have been measured by a series of diagnostics. The edge coherent mode (ECM) with a frequency about 25 kHz almost disappears when ELM is mitigated. The scrape-off layer (SOL) radial turbulent transport is measured by a four-tip Langmuir probe mounted on the manipulator at the outer midplane, exhibiting a strong enhancement of outward particle during the ELM mitigation in the SOL region (3–25 mm outside the LCFS). This enhanced outward radial transport is mainly driven by the low frequency turbulence (< 50 kHz), and is compared with the particle flux deposited on divertor targets quantitatively, revealing a good agreement with each other. It is suggested that a new channel for particle exhaust induced by the low frequency turbulence is beneficial to maintain the ELM mitigation by RMP.

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Section: Methodsmentioning

confidence: 99%

Edge turbulence characteristics and transport during the ELM mitigation with n = 1 resonant magnetic perturbation on EAST

et al. 2020

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“…[21] The RF heating methods, routinely used in EAST long-pulse and steadystate operated discharges, include two sets of LHW heating systems (a maximum power of 4 MW at 2.45 GHz, and a maximum power of 6 MW at 4.6 GHz), [22,23] two sets of ion cyclotron resonance frequency (ICRF) heating systems with a maximum total power of 12 MW in a frequency range of 25 MHz-70 MHz, [24] and two sets of ECRH systems with a maximum total heating power of 1 MW at 140 GHz. [25] Moreover, EAST has upgraded the plasma facing components (PFCs) to optimize the capacity of the heat load. The present main PFCs materials in EAST vacuum are W/Cu mono-blocks with active water-cooling for the upper divertor, molybdenum (Mo, Z = 42) plates for the first wall, and SiC-coated graphite tiles for the lower divertor.…”

Section: Methodsmentioning

confidence: 99%

Reduction of impurity confinement time by combined heating of LHW and ECRH in EAST*

Xu¹,

Wu²,

Zhang³

et al. 2021

Chinese Phys. B

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The core impurity confinement properties are experimentally investigated in the Experimental Advanced Superconducting Tokamak (EAST) plasma heated by lower hybrid wave (LHW) and electron cyclotron resonance heating (ECRH) (LHW+ECRH). It is shown that the impurity confinement time (τ imp) in the L-mode plasma jointly heated by LHW and ECRH is weakly dependent on electron density but strongly dependent on the heating power, thus it is shorter than that in LHW-only heated L-mode plasma with the similar plasma parameters. The combined heating of LHW and ECRH can reduce the collisionality and indicates a more effective heating method for core τ imp reduction and normalized poloidal beta (β P) improvement. It should be emphasized that in this high β P operation window the small ELM regime can be accessed, and an L-mode level τ imp (40 ms–80 ms) and high β N (∼ 1.7) can be obtained simultaneously. It means that this typical small ELMy H-mode regime has an advantage in avoiding the serious tungsten accumulation, and will be competitive in future long-pulse steady-state and high-performance operation with high-Z material plasma-facing components.

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“…In order to support the planned physical research on EAST, the auxiliary heating system was upgraded in 2020. The heating system includes neutral beam injection (NBI) [4], lower hybrid wave (LHW) [5] heating and current drive, ion cyclotron range-of frequency (ICRF) [6] heating and electron cyclotron heating (ECH) [7]. A high-power NBI system consisting of two injectors was employed on EAST for plasma heating and current drive.…”

Section: East Heating Upgradementioning

confidence: 99%

Current status of ECE system on EAST tokamak

Zhao

Zhou

et al. 2023

EPJ Web Conf.

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The electron cyclotron emission (ECE) diagnostic on the experimental advanced superconducting tokamak (EAST) has had a major upgrade since 2020, when EAST heating system also went through a significant upgrade, including one NBI system changed from counter-current to co-current (moving from port F to port D), and the antenna and the installation port of LHW and ICRF system have also been changed. The quasi-optical (QO) antenna of P port ECE system has been redesigned, the main purpose of which is to add one oblique ECE view. The angle with respect to perpendicular to the magnetic field is about 10°, which will facillitate measurement of the electron velocity distribution altered by LHW system. The ellipsoidal mirror has also been moved close to the plasma, about 70 cm away from the plasma center, and the poloidal beam waist radius in the plasma has been optimised to be less than 3 cm. The CECE system has also been moved from port G to port C. The frequency coverage of the CECE system has been upgraded to 104-132 GHz by adding one radio frequency (RF) module. Also in the intermediate frequency (IF) module, 8 narrow-band filters have been added to improve the spacial coverage of the system. On port F, a new superheterodyne radiometer with narrow-band filters in IF module has been installed. It consists of eight channels, the radial coverage is about 8 cm, the main purpose of this new system is to study the fine structure of magnetic island.

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Progress of high power and long pulse ECRH system in EAST

Cited by 43 publications

References 12 publications

Edge turbulence characteristics and transport during the ELM mitigation with n = 1 resonant magnetic perturbation on EAST

Edge turbulence characteristics and transport during the ELM mitigation with n = 1 resonant magnetic perturbation on EAST

Reduction of impurity confinement time by combined heating of LHW and ECRH in EAST*

Current status of ECE system on EAST tokamak

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