Overview of EAST experiments on the development of high-performance steady-state scenario

Wan, Baonian; Liang, Yun-Feng; Gong, Xianzu; Li, J.G.; Xiang, Nong; Xu, G. S.; Sun, Yuan; Wang, Liang; Qian, J.; Liu, H.Q.; Zhang, X.D.; Hu, Liqun; Hu, Jiansheng; Liu, F.K.; Hu, Chaoqun; Zhao, Yanping; Zeng, Long; Wang, M.; Xu, Handong; Luo, Guang–Nan; Garofalo, A. M.; Ekedahl, A.; Zhang, L.; Zhang, X.J.; Huang, J.; Ding, Bojiang; Zang, Qing; Li, M.H.; Ding, Fang; Ding, Siye; Lyu, Bo; Yu, Yaowei; Zhang, T.; Zhang, Y.; Li, G.Q.; Xia, Tianyang

doi:10.1088/1741-4326/aa7861

Cited by 146 publications

(105 citation statements)

References 48 publications

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“…As a long-term research programme, EAST aims to provide a suitable platform to address physics and technology issues relevant to steady-state advanced high-performance H-mode plasmas with ITER-like configuration, plasma control and heating schemes [1]. In the past few years, EAST has been upgraded with an ITER-like active cooling tungsten divertor, and it is capable to handle a power load up to 10 MW/m 2 for a steady-state operation.…”

Section: Introductionmentioning

confidence: 99%

Recent advances in EAST physics experiments in support of steady-state operation for ITER and CFETR

et al. 2019

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The recent EAST experimental progress since the last IAEA FEC in 2016 is presented. First demonstration of >100 seconds time scale long-pulse steady-state scenario with a good plasma performance (H98(y2) ~ 1.1) and a good control of impurity and heat exhaust with the tungsten divertor has been successfully achieved on EAST using the pure RF power heating and current drive. The extended operation regimes have been obtained (βP~2.5 & βN~1.9 of using RF&NB and βP~1.9 & βN~1.5). High bootstrap current fraction up to 47% was achieved with q95~6.0-7.0. The interaction effect between the ECH and two LHW systems has been investigated for enhanced current drive and improved confinement quality. ELM suppression using the n= 2 RMPs has been achieved at q95 (≈ 3.2-3.7) with standard type-I ELMy H-mode operational window in EAST. Reduction of the peak heat flux on the divertor was demonstrated using the active radiation feedback control. An increase in the total heating power and improvement of the plasma confinement are expected using a 0-D model prediction for higher bootstrap fraction. Towards long pulse, high bootstrap current fraction operation, a new lower ITER-like tungsten divertor with active watercooling will be installed, together with further increase and improvement of heating and current drive capability.

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Section: Introductionmentioning

confidence: 99%

Recent advances in EAST physics experiments in support of steady-state operation for ITER and CFETR

et al. 2019

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“…Recently, a variety of high performance discharges were achieved on EAST, in which #62585 is an important one. Many interesting physics, such as edge-localized modes (ELMy) [1] and Alfven eigenmodes (AEs) [2] triggered by fast ions, are observed in this shot. To study the physics involved, the plasma equilibrium, which can give very useful information such as plasma geometry, safety factor, pressure and current profiles, is necessary for performing data analysis and physics modeling and simulations.…”

Section: Introductionmentioning

confidence: 94%

Kinetic equilibrium reconstruction for the NBI- and ICRH-heated H-mode plasma on EAST tokamak

Zheng¹,

Xiang²,

CHEN³

et al. 2018

Plasma Sci. Technol.

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The equilibrium reconstruction is important to study the tokamak plasma physical processes. To analyze the contribution of fast ions to the equilibrium, the kinetic equilibria at two time-slices in a typical H-mode discharge with different auxiliary heatings are reconstructed by using magnetic diagnostics, kinetic diagnostics and TRANSP code. It is found that the fast-ion pressure might be up to one-third of the plasma pressure and the contribution is mainly in the core plasma due to the neutral beam injection power is primarily deposited in the core region. The fast-ion current contributes mainly in the core region while contributes little to the pedestal current. A steep pressure gradient in the pedestal is observed which gives rise to a strong edge current. It is proved that the fast ion effects cannot be ignored and should be considered in the future study of EAST.

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“…ASIPP developed a batch manufacturing technology for ITER-like water-cooled full W-PFC which employs copper alloy (CuCrZr) as a heat sink material and the hot isostatic pressing (HIP) method to join the W-PFM and the CuCrZr heat sink together [6]. Therewith ASIPP upgraded the EAST upper divertor from the bolted graphite tile PFC [7] into the ITER-like watercooled full W-PFC in 2014, and the W divertor came into service successfully [8][9][10][11]. Fully non-inductive steadystate H-mode plasmas (H 98, y2 ~ 1.1) were achieved with a duration of more than 60 s in 2016 experimental campaign [10] and further extended to ~ 100 s in 2017 campaign with a good control of impurity and heat exhaust benefiting from the upper W divertor [11].…”

Section: Application Of Tungsten As Plasma-facing Materials In Eastmentioning

confidence: 99%

“…Therewith ASIPP upgraded the EAST upper divertor from the bolted graphite tile PFC [7] into the ITER-like watercooled full W-PFC in 2014, and the W divertor came into service successfully [8][9][10][11]. Fully non-inductive steadystate H-mode plasmas (H 98, y2 ~ 1.1) were achieved with a duration of more than 60 s in 2016 experimental campaign [10] and further extended to ~ 100 s in 2017 campaign with a good control of impurity and heat exhaust benefiting from the upper W divertor [11]. A new lower W divertor is designed [12] and will replace the existing graphite divertor in 2020.…”

Section: Application Of Tungsten As Plasma-facing Materials In Eastmentioning

confidence: 99%

Plasma–tungsten interactions in experimental advanced superconducting tokamak (EAST)

et al. 2019

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Tungsten (W) is used as the armor material of the International Thermonuclear Experimental Reactor (ITER) divertor and is regarded as the potential first wall material of future fusion reactors. One of the key challenges for the successful application of W in fusion devices is effective control of W at an extremely low concentration in plasma. Understanding and control of W erosion are not only a prerequisite for W impurity control, but also vital concerns to plasma-facing component (PFC) lifetime. Since the application of ITER-like water-cooled full W divertor in EAST in 2014, great efforts were made to investigate W erosion by experiment and simulation. A spectroscopic system was developed to provide a real-time measurement of W sputtering source. Both experiment and simulation results indicate that carbon (C) is the dominant impurity causing W sputtering in L-mode plasmas, which comes from the erosion of C plasma-facing material (PFM) in the lower divertor and the main chamber limiters. The mixture layer on the surface of W PFCs formed through redeposition or the wall coating can effectively suppress W erosion. Increasing the plasma density and radiation can reduce incident ion energy, thus alleviating W sputtering. In H-mode plasmas, control of edge localized mode (ELM) via resonant magnetic perturbation (RMP) proves to be capable of suppressing intra-ELM W erosion. The experiences and lessons from the EAST W divertor are beneficial to the design, manufacturing and operation of ITER and beyond.

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Overview of EAST experiments on the development of high-performance steady-state scenario

Cited by 146 publications

References 48 publications

Recent advances in EAST physics experiments in support of steady-state operation for ITER and CFETR

Recent advances in EAST physics experiments in support of steady-state operation for ITER and CFETR

Kinetic equilibrium reconstruction for the NBI- and ICRH-heated H-mode plasma on EAST tokamak

Plasma–tungsten interactions in experimental advanced superconducting tokamak (EAST)

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