Progress of Divertor Heat and Particle Flux Control in EAST for Advanced Steady-State Operation in the Last 10 Years

Wang, Liang; Xu, G. S.; Hu, Jiansheng; Li, K. D.; Yuan, Q.P.; Liu, Junbiao; Ding, Fang; Yu, Yi; Luo, Z.P.; Xu, Jichan; Meng, Lingyi; Wu, Kai; Zhang, B.; Chen, M. W.; Deng, G. Z.; Liu, X. J.; Yang, Zhendong; Liu, S. C.; Ding, Rui; Zuo, Guizhong; Sun, Zhuo; Wu, Jinyong; Cao, Bin; Zhang, Y.; Duan, Yanmin; Zhang, L.; Qian, Xinyuan; Li, An; Chen, L.; Jia, M.; Si, H.; Xia, Tianyang; Sun, Youwen; Chen, Y. P.; Li, Qingfeng; Luo, Guang–Nan; Yao, Damao; Xiao, Bingjia; Gong, Xianzu; Zhang, X. D.; Wan, Baonian; Wang, H. Q.; Guo, H.Y.; Eldon, D.; Garofalo, A. M.; Liang, Y.; Xu, Shuai; Sang, Chaofeng; Wang, D. Z.; Dai, Shuyu; Sun, Jizhong; Ding, Hongbin; Maingi, R.; Gan, Kaifu; Zou, X. L.; Du, Hua

doi:10.1007/s10894-021-00290-9

Cited by 11 publications

(11 citation statements)

References 86 publications

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“…Both onset of detachment at outer and inner divertors, it is a good regime to achieve steady-state H-mode operation with the radiative divertor, which has been verified in the EAST radiation feedback control experiments. [15,29] The radiation belts at Loc.1 are similar to the observation of the 'MARFE-like X-point radiation' at AUG [33] and JET. [37] But the 2-D distribution of radiation area cannot be given on EAST, thus, we are not completely sure yet if it is the same as 'MARFElike X-point radiation' phenomenon.…”

Section: Discussionsupporting

confidence: 70%

“…Shot #81577 is operated to feedback control the total radiated power by injecting pulsed impurity gas, while shot #80608 is operated to feedback control the peak ion saturation current near strike point by injecting continuous impurity gas. [14,16,29] In the following, the characteristics of HFS radiation belts in the two discharges with different magnetic fields will be investigated.…”

Section: Resultsmentioning

confidence: 99%

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Evolution of the high-field-side radiation belts during the neon seeding plasma discharge in EAST tokamak

Xu¹,

Wang²,

Xu³

et al. 2022

Chinese Phys. B

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Divertor detachment achieved by injecting impurities or increasing density is always accompanied with various local radiation phenomena in the boundary or core plasma. This paper presents the formation and evolution of the high-field-side (HFS) radiation belts during the neon seeding plasma discharge in upper single null configuration with two directions of toroidal magnetic field in EAST tokamak. The neon mixed with deuterium seeding can induce the divertor detachment with strong radiation belts in the HFS scrape-off layer (SOL) region. With the increase of the radiation power, the plasma discharge will transit from H-mode to L-mode, meanwhile the radiation belts move away from the near X-point to HFS SOL. When the radiation power is high enough, the radiation belts begin to move further to the other X-point along the HFS SOL, and even cause plasma disruption. The results indicate that the behavior of the radiation belts is related to the radiation power, plasma confinement performance and state of divertor detachment, which is useful for developing better feedback control methods to achieve high-performance radiative divertor operation mode.

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Section: Discussionsupporting

confidence: 70%

Section: Resultsmentioning

confidence: 99%

Evolution of the high-field-side radiation belts during the neon seeding plasma discharge in EAST tokamak

Xu¹,

Wang²,

Xu³

et al. 2022

Chinese Phys. B

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“…These advances in heat and particle exhaust techniques have contributed to a series of EAST achievements, including H-mode operation for over 100 s. 57 By employing the water-cooling ITER-like upper W divertor, along with physics control and optimization approaches for divertor heat and particle exhaust, the EAST has achieved a record long-pulse H-mode operation of over 100 s in the USN configuration; the peak divertor target temperature, global recycling, W concentration, and core confinement performance are shown in Figure 4 . This steady-state scenario was characterized by a fully non-inductive current drive and high-frequency small-amplitude ELMs, which verified the stable control capability of heat and particle exhausts using the ITER-like tungsten divertor at a timescale of 100 s. When the long-pulse discharge reaches wall thermal and particle equilibria, the steady-state peak heat flux on the divertor plates is maintained at ∼3.3 MW/m 2 and the particle exhaust rate at ∼6.6×10 20 D/s.…”

Section: The East Project and Related Activitiesmentioning

confidence: 99%

Recent progress in Chinese fusion research based on superconducting tokamak configuration

et al. 2022

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“…In EAST experiments, it is usually observed that the longpulse steady-state operation of H-mode plasma is restricted by a considerable increase in the core radiation induced by accumulated W impurities [13], with the tolerance of W concentration in the core region as ∼10 −4 [14,15]. ASDEX-Upgrade experiments revealed that the acceptable W concentration is about 2 × 10 −5 in the confined plasma with an H-factor of 1.2 [16].…”

Section: Introductionmentioning

confidence: 99%

Simulation study of the influence of E× B drift on tungsten impurity transport in the scrape-off layer

Guo,

Xu,

Mao

et al. 2023

Nucl. Fusion

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Future fusion reactors such as ITER have adopted tungsten (W) as the plasma-facing materials (PFMs) in the divertor region. It is crucial to keep the W concentration in the core plasma at an extremely low level. Great efforts have been put forward on understanding the W transport in the scrape-off layer (SOL), which is related to the source of the core W contamination. In this work, the influence of E×B drift on the W impurity transport in the SOL is studied by numerical simulations for a model case based on EAST upper single-null configuration with high recycling divertor plasma. The W transport is simulated using DIVIMP on the background plasma obtained from SOLPS-ITER simulation including drifts. The E×B drift of the W ions is introduced according to the background electric field. Therefore, both the direct E×B drift effect of W ion itself and the indirect effect via background plasma on the W transport process in the SOL can be studied. We focus on the influence on the flux of W impurities entering confined plasma across the last closed flux surface Γenter, which is expected to be proportional to the core W concentration. It is found that Γenter is mainly from the outer (inner) target under favorable (unfavorable) toroidal field BT, and can be increased by more than one order of magnitude compared with the case without drifts. It reflects the significant influence of E×B drift effects. The detailed effects due to the background plasma and the poloidal and radial E×B drift of W ion, as well as the related mechanisms, are analyzed for the three stages of W transport in the SOL, including the effective sputtering from the target, the leakage from the divertor and the entry into the confined plasma.

show abstract

Progress of Divertor Heat and Particle Flux Control in EAST for Advanced Steady-State Operation in the Last 10 Years

Cited by 11 publications

References 86 publications

Evolution of the high-field-side radiation belts during the neon seeding plasma discharge in EAST tokamak

Evolution of the high-field-side radiation belts during the neon seeding plasma discharge in EAST tokamak

Recent progress in Chinese fusion research based on superconducting tokamak configuration

Simulation study of the influence of E× B drift on tungsten impurity transport in the scrape-off layer

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