Recent experimental results from the HL-1M tokamak and progress in the HL-2A project

Liu, Y.; Yan, Jing; Zhou, Caipin; Ding, X.T.; Wang, S.J.; Wang, E.Y.; Lianghua, Yao; Mao, W.C.; Pan, C.H.; Team, Hl M; Team, Hl A

doi:10.1088/0029-5515/44/2/021

Cited by 23 publications

(14 citation statements)

References 7 publications

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“…Most of the current generation medium sized tokamaks (HL-1M [1], COMPASS [2], ASDEX [3]) have been upgraded by incorporation of shaped plasma operation with innovative divertor configurations. The principal goal of employing a divertor configuration is to reduce the particle-wall interaction, where the charged particles striking on the wall located farther from the main plasma.…”

Section: Introductionmentioning

confidence: 99%

Overview of operation and experiments in the ADITYA-U tokamak

et al. 2019

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First indigenously built tokamak ADITYA, operated over 2 decades with circular poloidal limiter has been upgraded to a tokamak named ADITYA Upgrade for the purpose having shape plasma operation with open divertor geometry. Experiment research in ADITYA-U has made significant progress, since last FEC 2016. After installation of PFC and standard tokamak diagnostics, the Phase-I plasma operations were conducted from December 2016 with graphite toroidal belt limiter. Purely Ohmic discharges in circular plasmas supported by Filament pre-ionization was obtained. The plasma parameters, Ip ~ 80-95 kA, duration ~ 80-180 ms with toroidal field (max.) ~ 1T and chord-averaged electron density ~ 2.5 x 10^19 m^-3 has been achieved. Being a medium sized tokamak, runaway electron (RE) generation, transport and mitigation experiments have always been one of the prime focus of ADITYA-U. MHD activities and density enhancement with H2 gas puffing studied. The Phase-I operation was completed in March 2017. The Phase-II operation preparation in ADITYA-U includes calibration of magnetic diagnostics followed by commissioning of major diagnostics and installation of baking system. After repeated cycles of baking the vacuum vessel up to ~ 130°C, the Phase-II operations resumed from February 2018 and are continuing to achieve plasma parameters close to the design parameters of circular limiter plasmas using real time plasma position control. Hydrogen gas breakdown was observed in more than ~2000 discharge including Phase-I and Phase-II operation without a single failure. Several experiments, including the primary RE control with lower E/P operation and secondary RE control with fuelling of Supersonic Molecular Beam Injection as well as sonic H2 gas puffing during current flat-top and Neon gas puffing for better plasma confinement are undergoing. The dismantling of ADITYA and reassembling of ADITYA-U along with experimental results of Phase-I and Phase-II operations from ADITYA-U will be discussed.

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Section: Introductionmentioning

confidence: 99%

Overview of operation and experiments in the ADITYA-U tokamak

et al. 2019

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“…HL-2A tokamak [7,8] is characterized by upper and lower closed divertor chambers, with main parameters of major radius R = 1.65 m and minor radius a = 0.4 m. Auxiliary heating experiments have been carried out on the HL-2A tokamak, using an electron cyclotron resonance heating (ECRH) system, a neutral beam injector (NBI) and a lower hybrid current drive (LHCD) system. Three heating methods have been applied on HL-2A to heat the plasma simultaneously.…”

Section: Experimental Conditionsmentioning

confidence: 99%

Features of spontaneous and pellet-induced ELMs on the HL-2A tokamak

Huang¹,

Liu²,

Nie³

et al. 2012

Nucl. Fusion

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The pellet pacing ELM mitigation concept is being tested in some tokamaks such as ASDEX Upgrade, DIII-D and JET. By increasing the ELM frequency, the ELM size can be reduced and eventually suppressed to meet the lifetime requirements on ITER target plates. In the HL-2A tokamak, ELMy H-mode operation is routinely performed and small type-III ELMs with a high repetition rate and some type-I (or possibly large type-III) ELM events are observed. Large ELMs are often preceded by strong coherent magnetic oscillations, and produce obvious perturbations on plasma current I p , electron densityn edge at the edge, stored energy W E , etc. The coherent magnetic oscillations before an ELM crash or during the ELM are measured by toroidal and poloidal Mirnov coils and analysed by the wavelet technique to study the spectral characteristics of the short time ELM events. Pellet injection experiments are performed in type-III ELMy H-mode plasmas and ELM-free H-mode plasmas to study the physics of pellet triggering ELM. The analyses of pellet-induced ELMs and spontaneous ELMs are presented. Because the pellet size is relatively large, it induces magnetic oscillations lasting longer than that of a natural ELM.

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“…1 MW LHCD and 1 MW ECRH systems have been installed in the device and off-axis current drive and heating will be carried out for studying the magnetic shear and the internal transport barrier. The advanced SMBI [4] fuelling will be developed with lower gas temperatures and higher gas pressures than those on the HL-1M and the effects of the SMBI on the plasma confinement will be investigated further. Pellet injection system and some new diagnostics are being prepared to study the pellet penetration process and ablation mechanism.…”

Section: Summary and Future Plansmentioning

confidence: 99%

“…The mission of the HL-2A project is to explore physics issues involved in advanced tokamaks. Most of the important issues of fusion physics, such as confinement improvement, divertor and scrape-off layer physics, wall conditioning, MHD instability and energetic particles, auxiliary heating and current drive, would be studied and explored on the HL-2A through the progressive improvement of the hardware [3,4]. For the first phase, the divertor (edge plasma) and confinement research are emphasized.…”

Section: Introductionmentioning

confidence: 99%

Recent advances in the HL-2A tokamak experiments

et al. 2005

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Two experiment campaigns were conducted on HL-2A tokamak in 2003 and in 2004 after the first plasma was obtained at the end of 2002. Progresses in many aspects have been made, especially in the divertor discharge and feedback control of plasma configuration. Up to now, the following operation parameters have been achieved: Ip = 320 kA, Bt = 2.2 T and discharge duration T d = 1580 ms. With the feedback control of plasma current and horizontal position, an excellent repeatability of discharge has been achieved. The tokamak has been operated at both limitor configuration and single null (SN) divertor configuration. The HL-2A SN divertor configuration is simulated with the MHD equilibrium code SWEQU. The divertor experiment results were compared with the simulation results obtained with B2. When the divertor configuration is formed, the impurity radiation in main plasma decreases remarkably. The plasma performances are improved significantly after siliconization.

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Recent experimental results from the HL-1M tokamak and progress in the HL-2A project

Cited by 23 publications

References 7 publications

Overview of operation and experiments in the ADITYA-U tokamak

Overview of operation and experiments in the ADITYA-U tokamak

Features of spontaneous and pellet-induced ELMs on the HL-2A tokamak

Recent advances in the HL-2A tokamak experiments

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