Hybrid Method for Tokamak MHD Equilibrium Configuration Reconstruction

He, Hao; Dong, J. Q.; Zhang, Jinhua; Jiang, Haibin

doi:10.1088/0256-307x/24/2/054

Chinese Phys. Lett.

2007

DOI: 10.1088/0256-307x/24/2/054

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Hybrid Method for Tokamak MHD Equilibrium Configuration Reconstruction

Hao He

J. Q. Dong

Jinhua Zhang

et al.

Abstract: A hybrid method for tokamak MHD equilibrium configuration reconstruction is proposed and employed in the modified EFIT code. This method uses the free boundary tokamak equilibrium configuration reconstruction algorithm with one boundary point fixed. The results show that the position of the fixed point has explicit effects on the reconstructed divertor configurations. In particular, the separatrix of the reconstructed divertor configuration precisely passes the required position when the hybrid method is used … Show more

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Cited by 6 publications

References 9 publications

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Minimum Fisher regularization of image reconstruction for infrared imaging bolometer on HL-2A

Gao

Liu

et al. 2013

Review of Scientific Instruments

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An infrared imaging bolometer diagnostic has been developed recently for the HL-2A tokamak to measure the temporal and spatial distribution of plasma radiation. The three-dimensional tomography, reduced to a two-dimensional problem by the assumption of plasma radiation toroidal symmetry, has been performed. A three-dimensional geometry matrix is calculated with the one-dimensional pencil beam approximation. The solid angles viewed by the detector elements are taken into account in defining the chord brightness. And the local plasma emission is obtained by inverting the measured brightness with the minimum Fisher regularization method. A typical HL-2A plasma radiation model was chosen to optimize a regularization parameter on the criterion of generalized cross validation. Finally, this method was applied to HL-2A experiments, demonstrating the plasma radiated power density distribution in limiter and divertor discharges.

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Minimum Fisher regularization of image reconstruction for infrared imaging bolometer on HL-2A

Gao

Liu

et al. 2013

Review of Scientific Instruments

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Control system of neoclassical tearing modes in real time on HL-2A tokamak

Yan

Song

et al. 2017

Review of Scientific Instruments

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The stability and performance of tokamak plasmas are routinely limited by various magneto-hydrodynamic instabilities, such as neoclassical tearing modes (NTMs). This paper presents a rather simple method to control the NTMs in real time (RT) on a tokamak, including the control principle of a feedback approach for RT suppression and stabilization for the NTMs. The control system combines Mirnov, electron cyclotron emission, and soft X-ray diagnostics used for determining the NTM positions. A methodology for fast detection of 2/1 or 3/2 NTM positions with 129 × 129 grid reconstruction is elucidated. The forty poloidal angles for steering the electron cyclotron resonance heating (ECRH)/electron cyclotron current drive launcher are used to establish the alignment of antenna mirrors with the center of the NTM and to ensure launcher emission intersecting with the rational surface of a magnetic island. Pilot experiments demonstrate the RT control capability to trace the conventional tearing modes (CTMs) in the HL-2A tokamak. The 2/1 CTMs have been suppressed or stabilized by the ECRH power deposition on site or with the steerable launcher.

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Preliminary results of ELMy H-mode experiments on the HL-2A tokamak

et al. 2010

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Typical ELMy H-mode discharges have been achieved on the HL-2A tokamak with combined auxiliary heating of NBI and ECRH. The minimum power required is about 1.1 MW at a density of 1.6 × 10 19 m −3 and increases with a decrease in density, almost independent of the launching order of the ECRH and NBI heating. The energy loss by each edge localized mode (ELM) burst is estimated to be lower than 3% of the total stored energy. At a frequency of typically 400 Hz, the energy confinement time is only marginally reduced by the ELMs. The supersonic molecular beam injection fuelling is found to be beneficial for triggering an L-H transition due to less induced recycling and higher fuelling efficiency. The dwell time of the L-H transition is 20-200 ms, and tends to decrease as the power increases. The delay time of the H-L transition is 10-30 ms for most discharges and is comparable to the energy confinement time. The ELMs with a period of 1-3 ms are sustained for more than ten times the energy confinement time with enhanced confinement factor H 89 > 1.5, which tends to decrease with the total heating power. The confinement time in the H-mode discharges increases with plasma current approximately linearly.

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Hybrid Method for Tokamak MHD Equilibrium Configuration Reconstruction

Cited by 6 publications

References 9 publications

Minimum Fisher regularization of image reconstruction for infrared imaging bolometer on HL-2A

Minimum Fisher regularization of image reconstruction for infrared imaging bolometer on HL-2A

Control system of neoclassical tearing modes in real time on HL-2A tokamak

Preliminary results of ELMy H-mode experiments on the HL-2A tokamak

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