Advances in H-mode physics for long-pulse operation on EAST

Wan, Baonian; Li, Jiangang; Guo, H.Y.; Liang, Yun-Feng; Xu, Guosheng; Wang, Liang; Gong, Xianzu

doi:10.1088/0029-5515/55/10/104015

Cited by 133 publications

(101 citation statements)

References 55 publications

Supporting

Mentioning

Contrasting

Unclassified

Order By: Relevance

“…EAST has been technically upgraded with an advanced divertor configuration and heating scheme similar to ITER. 19 The machine can be flexibly operated in single null (SN) and double null (DN) divertor configurations. Here, we only focus on the upper single null (USN) discharges.…”

Section: Methodsmentioning

confidence: 99%

Effect of ∇B drift on the H-mode power threshold in upper single null plasmas with ITER-like tungsten divertor on EAST

Chen

Niu

et al. 2018

Physics of Plasmas

View full text Add to dashboard Cite

show abstract

Section: Methodsmentioning

confidence: 99%

Effect of ∇B drift on the H-mode power threshold in upper single null plasmas with ITER-like tungsten divertor on EAST

Chen

Niu

et al. 2018

Physics of Plasmas

View full text Add to dashboard Cite

show abstract

“…The experimental advanced superconducting tokamak (EAST) 12 is the first full superconducting tokamak with advanced configuration in the world. Its purpose is to explore To obtain high performance plasma in EAST, some auxiliary heating and current drive methods have been developed, including electron cyclotron resonant heating (ECRH) and neutral beam injection (NBI) system.…”

Section: Experimental Set-upmentioning

confidence: 99%

Control of sawtooth via ECRH on EAST tokamak

Yuan

et al. 2016

Physics of Plasmas

Self Cite

View full text Add to dashboard Cite

Localized electron heating produced by electron cyclotron resonant heating (ECRH) system has been proven to be powerful tools for controlling sawtooth instabilities, because such system allows to directly modify the local plasma parameters that determine the evolution of sawtooth periods. In this paper, we present the experimental results carried out on experimental advanced superconducting tokamak (EAST) with regard to sawtooth period control via ECRH. The electron cyclotron heating system on EAST was capable of inject electron cyclotron wave toward certain locations inside or outside q = 1 magnetic surface on the poloidal cross section, which renders us able to investigate the evolution of sawtooth period against the ECRH deposition position. It is found that when ECRH deposition position is inside the q = 1 surface, the sawtooth oscillation is destabilized (characterized by reduced sawtooth period). So far, inside the q = 1 surface, there are not enough EAST experiment data that can reveal more detailed information about the relation between ECRH deposition position and sawtooth period. When ECRH deposition is outside the q = 1 surface, the sawtooth oscillation is stabilized (characterized by prolonged sawtooth period), and the sawtooth periods gradually decrease as ECRH deposition position sweeps away from q = 1 surface. The sawtooth periods reach maximum when ECRH deposition position falls around q = 1 surface. The magnetic shear at q = 1 surface is calculated to offer insights for the temporal evolution of sawtooth. The result has been found consistent with the Porcelli model.

show abstract

“…Recently, great efforts [4] have been made on both physics and technology fronts to accomplish this mission with all ITER-relevant auxiliary heating and current drive systems, enabling the investigation of plasma profile control by coupling/integration of various combinations. By means of the 4.6 GHz and 2.45 GHz lower hybrid current drive (LHCD) systems, H-mode can be obtained and maintained at relatively high density, even up to ne ~ 4.5 × 10 19 m -3 , where a current drive effect is still observed; A new small/no ELM Hmode regime has been demonstrated to be a good solution to the problem of divertor transient heat load, which facilitate the exploration of long-pulse highperformance H-mode operation on EAST.…”

Section: Introductionmentioning

confidence: 99%

Recent progress of RF-dominated experiments on EAST

et al. 2017

View full text Add to dashboard Cite

Abstract. The research of EAST program is mostly focused on the development of high performance steady state scenario with ITER-like poloidal configuration and RF-dominated heating schemes. With the enhanced ITER-relevant auxiliary heating and current drive systems, the plasma profile control by coupling/integration of various combinations has been investigated, including lower hybrid current drive (LHCD), electron cyclotron resonance heating (ECRH) and ion cyclotron resonance heating (ICRH). The 12 MW ICRH system has been installed on EAST. Heating and confinement studies using the Hydrogen Minority Heating scheme have been investigated. One of the importance challenges for EAST is coupling higher power into the core plasma, experiments including changing plasma position, electron density, local gas puffing and antenna phasing scanning were performed to improve ICRF coupling efficiency on EAST. Results show that local gas injection and reducing the k|| can improve the coupling efficiency directly. By means of the 4.6 GHz and 2.45 GHz LHCD systems, H-mode can be obtained and sustained at relatively high density, even up to ne ~ 4.5 × 10 19 m -3, where a current drive effect is still observed. Meanwhile, effect of source frequency (2.45GHz and 4.6GHz) on LHCD characteristic has been studied on EAST, showing that higher frequency improves penetration of the coupled LH (lower hybrid) power into the plasma core and leads to a better effect on plasma characteristics. Studies demonstrate the role of parasitic effects of edge plasma in LHCD and the mitigation by increasing source frequency. Experiments of effect of LH spectrum and plasma density on plasma characteristics are performed, suggesting the possibility of plasma control for high performance. The development of a 4MW ECRH system is in progress for the purpose of plasma heating and MHD control. The built ECRH system with 1MW source power has been successfully put into use on EAST in 2015. H-mode discharges with L-H transition triggered by ECRH injection were obtained and its effects on the electron temperature, particle confinement and the core MHD stabilities were observed. By further exploring and optimizing the RF combination for the sole RF heating and current drive regime, fully non-inductive H-mode discharges with V loop~0 V has progressed steadily in the 2016 campaign. The overview of the significant progress of RF dominated experiments is presented in this paper.

show abstract

Advances in H-mode physics for long-pulse operation on EAST

Cited by 133 publications

References 55 publications

Effect of ∇B drift on the H-mode power threshold in upper single null plasmas with ITER-like tungsten divertor on EAST

Effect of ∇B drift on the H-mode power threshold in upper single null plasmas with ITER-like tungsten divertor on EAST

Control of sawtooth via ECRH on EAST tokamak

Recent progress of RF-dominated experiments on EAST

Contact Info

Product

Resources

About