First plasma scenario development for HL-2M

Xianming, Song; Li, J.X.; Leuer, J.A.; Zhang, J.H.

doi:10.1016/j.fusengdes.2019.111254

Cited by 12 publications

(6 citation statements)

References 3 publications

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“…I p is mainly controlled by CS coil voltage, while for R p , PF8 is used for the FB control. The control law is a combination of FF + FB, where the FF trajectory is computed as described in [8] using plasma equilibria snapshots and a simple plasma resistance model for flux consumption [13].…”

Section: Feedback Control Scheme On Plasma Parametersmentioning

confidence: 99%

“…Wall conditioning on HL-2M consists of baking and glow discharge cleaning, and it is observed that impurities (H 2 O, N 2 , CO 2 , etc) absorbed in the first wall can be effectively removed. The loop voltage is provided by the swing of the central solenoid (CS) and poloidal field (PF) coils currents, and the trajectory of that coil's currents is provided by the work from [8].…”

Section: Introductionmentioning

confidence: 99%

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Plasma initiation and preliminary magnetic control in the HL-2M tokamak

Song

Zhou

et al. 2021

Nucl. Fusion

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The first plasmas have been achieved in the HL-2M tokamak by fulfilling the usual criteria for plasma breakdown, i.e. optimal working gas pressure, field null configuration of poloidal magnetic field, reasonable toroidal electrical field and clean wall conditions. The characterization of plasma initiation, such as identification of initiation time and position, is performed by diagnostic data analysis and numerical simulation. A model-based method, which enables dedicated pick-up sensors to estimate plasma radial position in real time, is applied for the limiter plasma shape in the first plasma commissioning phase. For a circular cross-section plasma, feedback control on plasma current and radial position allowed us to extend discharge durations to ∼250 ms associated with a 120 kA plasma current in flat-top. Preliminary plasma equilibrium reconstruction by the NICE code from pick-up sensors and flux loops, as well as interferometry measurements, gives plasma boundaries, plasma profiles of toroidal current density and safety factor, as well as electron density, in an offline way.

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Section: Feedback Control Scheme On Plasma Parametersmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Plasma initiation and preliminary magnetic control in the HL-2M tokamak

Song

Zhou

et al. 2021

Nucl. Fusion

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“…Several papers discussed the results of simulations of various aspects of plasma scenarios and their control in preparation for the operation of JT-60SA [180,181], HL-2M [182], ITER [183] and even Demo [184]. Extensive simulations of JT-60SA scenarios exploiting a wide range of modelling tools were presented by Hayashi et al [180] in preparation for the Simulation of simultaneous q-profile control and fast β p control in EAST using combined LHCD and ICRF power, based on a model-predictive kinetic control approach.…”

Section: Advanced Controlmentioning

confidence: 99%

“…This analysis was complemented by that of De Tommasi et al [181], who discussed 2D and 3D modelling of the plasma start-up and disruptions to support the development of the magnetic controllers required for real-time equilibrium control in JT-60SA. Modelling studies performed in support of first plasma operation of HL-2M, currently under construction in Chengdu, were presented by Song et al [182], who described the principal components of the simulation framework used. To minimize operational risk, it is foreseen to limit initial current operation to 200 kA with a current flat-top duration of ~1 s, and plasma scenarios with both limiter and divertor plasma shapes have been analyzed (figure 45).…”

Section: Advanced Controlmentioning

confidence: 99%

27th IAEA Fusion Energy Conference: summary of sessions EX/C, EX/S and PPC

Campbell¹

2020

Nucl. Fusion

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Developments presented at the 27th IAEA Fusion Energy Conference in several areas of experimental magnetic confinement fusion research relating to confinement physics, plasma stability, plasma performance and control are reviewed. First results were reported from significant new stellarator and tokamak facilities and wide-ranging studies of issues such as disruption mitigation, control of edge localized modes (ELMs), the influence of hydrogenic isotope on heat and particle transport, optimization of ELMy H-modes and advanced H-modes and the application of advanced control techniques have been performed in support of the preparations for ITER operation.

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“…The Joint European Torus (Joffrin et al, 2019), nevertheless, retains a capability for experiments with deuterium-tritium plasmas. As discussed later, several significant new non-nuclear facilities are currently in the development phase: JT-60SA, a Japan-EU collaboration (Barabaschi et al, 2019), the Divertor Test Tokamak (DTT) in Italy (Albanese et al, 2019), HL-2M (Song et al, 2019) in China and COMPASS-Upgrade (Panek et al, 2017) in the Czech Republic.…”

Section: Introduction -The Path Towards Fusion Electricitymentioning

confidence: 99%