Advanced divertor concept design and analysis for HL-2M

Zheng, Guo; Xu, X. Q.; Ryutov, D. D.; Xia, Tie; Duan, Xuru; He, Hao; Pan, Yuwei

doi:10.1016/j.fusengdes.2016.06.026

Cited by 9 publications

(4 citation statements)

References 15 publications

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“…(a) Tests and qualification of various advanced divertor concepts, such as snowflake (SF) and tripod [49,50], on both physics and technological aspects; (b) Tests and validation of high heat flux plasma-facing components; (c) Investigation of burning plasma physics and design of scenarios compatible with advanced divertor configurations.…”

Section: The Tokamak Hl-2mmentioning

confidence: 99%

“…The combination of the flexible magnet coil system and the open structure divertor, allows HL-2M to test and qualify in various advanced divertor concepts, such as the SF and the tripod configurations. An example of some single-null divertor configurations foreseen in HL-2M is shown in figure 17 with elongation κ = 1.6-1.8 and minor radius a ∼ 0.65 m. The second X-points of the two configurations are designed to be above and below the target plate to form a large wetted area and a longer connection length, toward divertor heat and particle flux control [49,50].…”

Section: Magnet Coil System and Divertor Configurationsmentioning

confidence: 99%

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Progress of HL-2A experiments and HL-2M program

Duan¹,

Xu²,

Zhong³

et al. 2022

Nucl. Fusion

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Since the last IAEA Fusion Energy Conference in 2018, significant progress of the experimental program of HL-2A has been achieved on developing advanced plasma physics, edge localized mode (ELM) control physics and technology. Optimization of plasma confinement has been performed. In particular, high-N H-mode plasmas exhibiting an internal transport barrier have been obtained (normalized plasma pressure N reached up to 3). Injection of impurity improved the plasma confinement. ELM control using resonance magnetic perturbation (RMP) or impurity injection has been achieved in a wide parameter regime, including Types I and III. In addition, the impurity seeding with supersonic molecular beam injection (SMBI) or laser blow-off (LBO) techniques has been successfully applied to actively control the plasma confinement and instabilities, as well as the plasma disruption with the aid of disruption prediction. Disruption prediction algorithms based on deep learning are developed. A prediction accuracy of 96.8% can be reached by assembling convolutional neural network (CNN). Furthermore, transport resulted from a wide variety of phenomena such as energetic particles and magnetic islands have been investigated. In parallel with the HL-2A experiments, the HL-2M mega-ampere class tokamak was commissioned in 2020 with its first plasma. Key features and capabilities of HL-2M are briefly presented.

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Section: The Tokamak Hl-2mmentioning

confidence: 99%

Section: Magnet Coil System and Divertor Configurationsmentioning

confidence: 99%

Progress of HL-2A experiments and HL-2M program

Duan¹,

Xu²,

Zhong³

et al. 2022

Nucl. Fusion

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“…to studying high-performance plasma physics issues, the plasma edge and divertor physics by exploring various divertor concepts (e.g. snowflake, tripod) [7][8][9], as well as plasma-wall interaction. The high power heating and current drive system allows the machine to study a variety of operation scenarios.…”

Section: Integrated Plasma Scenario Analysis For the Hl-2m Tokamakmentioning

confidence: 99%

Integrated plasma scenario analysis for the HL-2M tokamak

et al. 2019

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HL-2M is a new medium-sized tokamak under construction at the Southwestern Institute of Physics, dedicated to supporting the critical physics and engineering issues of ITER and CFETR. Analyzing integrated plasma scenarios is essential for assessing performance metrics and foreseeing physics as well as the envisaged experiments of HL-2M. This paper comprehensively presents the kind of expected discharge regimes (conventional inductive (baseline), hybrid and steady-state) of HL-2M based on the integrated suite of codes METIS. The simulation results show that the central electron temperature of the baseline regime can achieve more than 10 keV by injecting 27 MW of heating power with a plasma current of I p = 3 MA and Greenwald fraction f G = 0.65, with the thermal energy and β N reaching 5 MJ and 2.5, respectively. The hybrid regime with f ni = 80%–90% can be realized at I p = 1–1.4 MA with f G around 0.5, where β N is 2.3–2.5 with H 98(y ,2) = 1.1. Because of the effect of the on-axis NBCD, the hybrid steady state, at I p = 1.0 and 1.2, can be achieved more easily than the steady state regimes with reversed shear, corresponding to β N = 2.6 and 3.4. Such studies show that HL-2M is a flexible tokamak with a significant capacity for generating a broad variety of plasmas as a consequence of the different heating and current drive systems installed.

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“…Indications of detachment were observed in the first EAST experiments [166]. Significant heat flux reduction was observed in SOLPS simulations of attached divertor regimes due to snowflake geometry effects in the planned HL-2M tokamak [167,168] and the Chinese Fusion Experimental Tokamak Reactor [169]. Modeling of detachment in snowflake divertor configurations for these devices is also starting [132,170].…”

Section: Studies Of Radiative Plasma Detachment In Advanced Magnetic ...mentioning

confidence: 99%

A review of radiative detachment studies in tokamak advanced magnetic divertor configurations

Soukhanovskii

2017

Plasma Phys. Control. Fusion

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The present vision for a plasma-material interface in the tokamak is an axisymmetric poloidal magnetic X-point divertor. Four tasks are accomplished by the standard poloidal X-point divertor: plasma power exhaust; particle control (D/T and He pumping); reduction of impurity production (source); and impurity screening by the divertor scrape-off layer. A low-temperature, low heat flux divertor operating regime called radiative detachment is viewed as the main option that addresses these tasks for present and future tokamaks. Advanced magnetic divertor configuration has the capability to modify divertor parallel and cross-field transport, radiative and dissipative losses, and detachment front stability. Advanced magnetic divertor configurations are divided into four categories based on their salient qualitative features: (1) multiple standard X-point divertors; (2) divertors with higher order nulls; (3) divertors with multiple X-points; and (4) long poloidal leg divertors (and also with multiple X-points). This paper reviews experiments and modeling in the area of radiative detachment in the advanced magnetic divertor configurations.

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Advanced divertor concept design and analysis for HL-2M

Cited by 9 publications

References 15 publications

Progress of HL-2A experiments and HL-2M program

Progress of HL-2A experiments and HL-2M program

Integrated plasma scenario analysis for the HL-2M tokamak

A review of radiative detachment studies in tokamak advanced magnetic divertor configurations

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