Passive Plasma Vertical Stabilization in a Single-Turn Tokamak Configuration

Dong, J. Q.; Montalvo, E.; Carrera, R.; Rosenbluth, M. N.

doi:10.13182/fst93-a30118

Cited by 3 publications

(1 citation statement)

References 5 publications

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“…The information about the magnetohydrodanymic (MHD) equilibrium configuration is essential in tokamak experiment for either the control of the configurations [1,2] or the detailed information, e.g., the profiles of plasma parameters such as safety factor q, pressure p and current density j. Quite a few numerical codes have been successfully developed and used in the past few decades [3∼5] .…”

Section: Introductionmentioning

confidence: 99%

MHD Equilibrium Configuration Reconstructions for HL-2A Tokamak

何志雄

2011

Plasma Sci. Technol.

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The EFIT (Equilibrium Fitting) code is modified for the equilibrium configuration reconstruction in HL-2A. Signals from Langmuir probe (LP) at the divertor target plates are employed in the reconstruction of divertor configurations. The results show that discharge #2895 starts with a limiter configuration and develops gradually into a divertor configuration after t = 230 ms. This transition process is clearly demonstrated by the LP signals for the reconstruction. The profiles of plasma parameters such as safety factor q, pressure and current density as well as the evolution of major shape parameters of plasma, such as the boundary magnetic fluxes, the positions of both x-point and magnetic axis, are calculated from the reconstructed configurations. The possibility to apply the method to the swing of strike point on the target plate is discussed.

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Section: Introductionmentioning

confidence: 99%

MHD Equilibrium Configuration Reconstructions for HL-2A Tokamak

何志雄

2011

Plasma Sci. Technol.

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Extensions to single filament modelling of a tokamak plasma

et al. 1997

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Adjustments are described that should be made to a single filament description of a tokamak plasma if accurate modelling of a non-linear MHD simulation is to be achieved. It is shown that although the single filament model is excellent for purely radial, or purely vertical, fields, it does not describe the gradients of these fields. A simple scalar correction to the gradient terms in the model is found to facilitate the accurate prediction of the growth rate of the vertical instability. An extension to the modelling of X points is also presented. The corrected multi-pole model is shown to be appropriate for the design of robust controllers

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Hybrid Method for Tokamak MHD Equilibrium Configuration Reconstruction

Dong

Zhang

et al. 2007

Chinese Phys. Lett.

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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 in the reconstruction. The profiles of plasma parameters such as pressure and safety factor for reconstructed HL-2A tokamak configurations with the hybrid and the free boundary methods are compared. The possibility for applications of the method to swing the separatrix strike point on the divertor target plate is discussed.

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Passive Plasma Vertical Stabilization in a Single-Turn Tokamak Configuration

Cited by 3 publications

References 5 publications

MHD Equilibrium Configuration Reconstructions for HL-2A Tokamak

MHD Equilibrium Configuration Reconstructions for HL-2A Tokamak

Extensions to single filament modelling of a tokamak plasma

Hybrid Method for Tokamak MHD Equilibrium Configuration Reconstruction

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