MHD stability analysis for advanced tokamak modes in the KSTAR device

Yi, Sumin; Kim, J.Y.; Ryu, Chang‐Mo

doi:10.1016/j.fusengdes.2010.05.031

Cited by 4 publications

(3 citation statements)

References 11 publications

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“…To setup the initial condition for simulation, the plasma equilibrium was established using TOQ code [49] which is an inverse solver of the Grad-Shafranov equation [50]. The plasma parameters similar to the KSTAR shot # 13122 (as given in section 3) are used to establish the equilibrium.…”

Section: Fwr2d Simulation For Elmsmentioning

confidence: 99%

Estimation of the radial size and density fluctuation amplitude of edge localized modes using microwave interferometer array

et al. 2016

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Section: Fwr2d Simulation For Elmsmentioning

confidence: 99%

Estimation of the radial size and density fluctuation amplitude of edge localized modes using microwave interferometer array

et al. 2016

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“…Finally, a detailed analysis has been done for the ideal MHD stability limit of the KSTAR target AT modes [31]. For a set of model equilibria with the reverse-shear q-profile the stability boundaries of the low-n external kink modes were calculated using the two codes of DCON and GATO.…”

Section: Analysis and Predictionmentioning

confidence: 99%

Overview of KSTAR initial operation

Kwon¹,

Oh²,

Yang³

et al. 2011

Nucl. Fusion

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Since the successful first plasma generation in the middle of 2008, three experimental campaigns were successfully made for the KSTAR device, accompanied with a necessary upgrade in the power supply, heating, wall-conditioning and diagnostic systems. KSTAR was operated with the toroidal magnetic field up to 3.6 T and the circular and shaped plasmas with current up to 700 kA and pulse length of 7 s, have been achieved with limited capacity of PF magnet power supplies. The mission of the KSTAR experimental program is to achieve steady-state operations with high performance plasmas relevant to ITER and future reactors. The first phase (2008–2012) of operation of KSTAR is dedicated to the development of operational capabilities for a super-conducting device with relatively short pulse. Development of start-up scenario for a super-conducting tokamak and the understanding of magnetic field errors on start-up are one of the important issues to be resolved. Some specific operation techniques for a super-conducting device are also developed and tested. The second harmonic pre-ionization with 84 and 110 GHz gyrotrons is an example. Various parameters have been scanned to optimize the pre-ionization. Another example is the ICRF wall conditioning (ICWC), which was routinely applied during the shot to shot interval. The plasma operation window has been extended in terms of plasma beta and stability boundary. The achievement of high confinement mode was made in the last campaign with the first neutral beam injector and good wall conditioning. Plasma control has been applied in shape and position control and now a preliminary kinetic control scheme is being applied including plasma current and density. Advanced control schemes will be developed and tested in future operations including active profiles, heating and current drives and control coil-driven magnetic perturbation.

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“…For these equilibria, we use the GATO code to perform the ideal MHD stability analysis. We only compute the ideal MHD stability boundary for n = 1 (n is the toroidal mode number), since β N is limited by global low n instabilities [3,14,15] . Our convergence calculation shows a mesh of N ψ × N x = 160 × 320 is sufficient to determine the stability.…”

Section: Gato Code and Ideal Mhd Stabilitymentioning

confidence: 99%

Ideal MHD Stability Prediction and Required Power for EAST Advanced Scenario

Chen¹,

Li²,

Qian³

et al. 2012

Plasma Sci. Technol.

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The Experimental Advanced Superconducting Tokamak (EAST) is the first fully superconducting tokamak with a D-shaped cross-sectional plasma presently in operation. The ideal magnetohydrodynamic (MHD) stability and required power for the EAST advanced tokamak (AT) scenario with negative central shear and double transport barrier (DTB) are investigated. With the equilibrium code TOQ and stability code GATO, the ideal MHD stability is analyzed. It is shown that a moderate ratio of edge transport barriers' (ETB) height to internal transport barriers' (ITBs) height is beneficial to ideal MHD stability. The normalized beta βN limit is about 2.20 (without wall) and 3.70 (with ideal wall). With the scaling law of energy confinement time, the required heating power for EAST AT scenario is calculated. The total heating power P t increases as the toroidal magnetic field BT or the normalized beta βN is increased.

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MHD stability analysis for advanced tokamak modes in the KSTAR device

Cited by 4 publications

References 11 publications

Estimation of the radial size and density fluctuation amplitude of edge localized modes using microwave interferometer array

Estimation of the radial size and density fluctuation amplitude of edge localized modes using microwave interferometer array

Overview of KSTAR initial operation

Ideal MHD Stability Prediction and Required Power for EAST Advanced Scenario

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