Overview of recent HL-2A experiments

Duan, X.R.; Liu, Yi; Xu, M.; Yan, L.; Xu, Yuan; Song, X.M.; Dong, J.Q.; Ding, X.T.; Chen, L.Y.; Lü, B.; Liu, D.Q.; Rao, J.; Weimin, Xuan; Yang, Qingwei; Zheng, Guoyao; Zou, X.L.; Liu, Y.Q.; Zhong, W.L.; Zhao, K.J.; Ji, Xiao; Mao, W.C.; Wang, Q.M.; Li, Q.; Cao, Jianfei; Cao, Z.; Lei, Guangjiu; Zhang, J.H.; Li, X.D.; Bai, Xue; Cheng, J.; Chen, W.; Cui, Z.Y.; Delpech, L.; Diamond, P. H.; Dong, Y.B.; Ekedahl, A.; Hoang, T.; Huang, Yuanqing; Ida, K.; Itoh, Kazuya; Itoh, Susumu; Isobe, M.; Inagaki, S.; Mazon, D.; Morita, S.; Peysson, Y.; Shi, Z.B.; Wang, X. G.; Xiao, Guoliang; Yu, D.L.; Yu, Liming; Zhang, Y.P.; Zhou, Yixuan; Cui, C.H.; Feng, B.B.; Huang, M.; Li, Y.G.; Li, B.; Li, G.S.; Li, H.J.; Li, Qing; Peng, Jianhui; Wang, Y.Q.; Yuan, B.S.; Liu, Yong; Team, Hl A

doi:10.1088/1741-4326/aa6a72

Cited by 36 publications

(15 citation statements)

References 28 publications

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“…However, they are almost invisible in spectrograms with r d 11 cm, indicating that the HFCMs are localized in the plasma core. When the LHW is injected at t = 800 ms, the plasma enters into I-phase type-III ELMy H-mode [21] and the HFCMs disappear as the core T i decreases and the n e increases. Figure 2 shows that there exist strong and steady ITBs at the T i profiles during the observation of HFCMs, and the normalized length scales of the T i gradients are very large, i.e.…”

Section: Resultsmentioning

confidence: 99%

Kinetic electromagnetic instabilities in an ITB plasma with weak magnetic shear

Chen¹,

Yu²,

Ma³

et al. 2018

Nucl. Fusion

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Kinetic Alfvén and pressure gradient driven instabilities are very common in magnetized plasmas, both in space and the laboratory. These instabilities will be easily excited by energetic particles (EPs) and/or pressure gradients in present-day fusion and future burning plasmas. This will not only cause the loss and redistribution of the EPs, but also affect plasma confinement and transport. Alfvénic ion temperature gradient (AITG) instabilities with the frequency ω BAE < ω < ω TAE and the toroidal mode numbers n = 2−8 are found to be unstable in NBI internal transport barrier plasmas with weak shear and low pressure gradients, where ω BAE and ω TAE are the frequencies of the beta-and toroidicity-induced Alfvén eigenmodes, respectively. The measured results are consistent with the general fishbone-like dispersion relation and kinetic ballooning mode equation, and the modes become more unstable the smaller the magnetic shear is in low pressure gradient regions. The interaction between AITG activity and EPs also needs to be investigated with greater attention in fusion plasmas, such as ITER (Tomabechi and The ITER Team 1991 Nucl. Fusion 31 1135), since these fluctuations can be enhanced by weak magnetic shear and EPs.

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Section: Resultsmentioning

confidence: 99%

Kinetic electromagnetic instabilities in an ITB plasma with weak magnetic shear

Chen¹,

Yu²,

Ma³

et al. 2018

Nucl. Fusion

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“…The simulations are run for the preparation of the tokamak HL-2M, currently under construction at the SWIP laboratory [27]. HL-2M aims to investigate the potential benefit of advanced divertor geometries with respect to the reduction of peak heat loads onto the divertor targets, with up to 20 MW of additional power available.…”

Section: Hl-2m Tokamak and Configurationsmentioning

confidence: 99%

Impact of an alternative divertor configuration on plasma detachment: pure deuterium simulations using the SOLEDGE2D-EIRENE edge transport code for HL-2M scenarios

Mao¹,

Fedorczak²,

Ciraolo³

et al. 2019

Nucl. Fusion

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The SOLEDGE-EIRENE edge plasma code provides solutions for particle & energy transport in the plasma edge within complex and realistic 2D geometries [1]. In this work, divertor detachment is simulated on the HL-2M alternative magnetic configurations in pure Deuterium plasma. Starting from typical HL-2M low single-null (SN) configuration, the snowflake plus (SF+) and snowflake minus (SF-) configurations have been investigated. Detachment of the outer target is studied in these configurations during plasma density ramps controlled by a fueling source, at constant input power and constant radial transport coefficients. Some typical characteristics of detachment, like threshold, depth and upstream window of detachment are investigated. In the three geometries, detachment onset and evolution with upstream plasma density is characterized by the gradual displacement of a radiation front from the outer target to the main X-point, as observed in experiments. It is found that, whatever the detachment in terms of particle, momentum or power dissipation, the detachment threshold is dominated primarily by the geometrical structure of divertor plate and it does not exhibit dependence on the magnetic configuration of the diverted plasma volume. In particular, the parallel connection length in the divertor is not found to affect the detachment threshold, in contrast with simple expectations from the 2-point model, but in agreement with experimental findings.

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“…[2] To avoid such damages and safely guard the continued operation of future high performance devices, various disruption avoidance systems (DAS) are designed, such as the electron cyclotron current drive (ECCD) or Heating (ECRH), [3][4][5][6] to suppress the instability of the dominant magnetic islands by modifying the current and pressure profile within. Facing this, disruption mitigation systems (DMS) such as the shattered pellet injection (SPI) [7][8][9][10][11][12][13][14][15][16][17] or other massive material injection (MMI) [18][19][20][21][22][23][24][25] techniques are used to deplete the majority of thermal energy via radiation loss during the TQ, and raise the density to help with runaway electron suppression during the CQ phase.…”

Section: Introductionmentioning

confidence: 99%

Stability impacts from the current and pressure profile modifications within finite sized island

Sun

2023

Chinese Phys. B

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The stability (or instability) of finite sized magnetic island could play a significant role in disruption avoidance or disruption mitigation dynamics. Especially, various current and pressure profile modifications, such as the current drive and heating caused by electron cyclotron wave, or the radiative cooling and current expulsion caused by the Shattered Pellet Injection could be applied within the island to modify its stability, thus change the ensuing dynamics. In this study, we calculate the mode structure modification caused by such profile changes within the island using the perturbed equilibrium approach, thus obtain the change of stability criterion ∆′ and assess the corresponding quasi-linear island stability. The positive helical current perturbation is found to always stabilize the island, while the negative one is found to do the opposite, in agreement with previous results. The pressure bump or hole within the island has a more complicated stability impact. In the small island regime, its contribution is monotonic, with pressure bump tends to stabilize the island while pressure hole destabilizes it. This effect is relatively weak, though, due to the cancellation of the pressure term’s odd parity contribution in the second derivatives of the mode structure. In the large island regime, such cancellation is broken due to the island asymmetry, and the pressure contribution to stability is manifested, which is non-monotonic. The stability analysis in this paper helps to more accurately clarify the expected island response in the presence of profile modifications caused by disruption avoidance or mitigation systems.

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Overview of recent HL-2A experiments

Cited by 36 publications

References 28 publications

Kinetic electromagnetic instabilities in an ITB plasma with weak magnetic shear

Kinetic electromagnetic instabilities in an ITB plasma with weak magnetic shear

Impact of an alternative divertor configuration on plasma detachment: pure deuterium simulations using the SOLEDGE2D-EIRENE edge transport code for HL-2M scenarios

Stability impacts from the current and pressure profile modifications within finite sized island

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