Disruptive plasma simulations in EAST including 3D effects

Chen, S.L.; Villone, F.; Sun, Yuan; Rubinacci, G.; Ventre, Salvatore; Xiao, Bingjia; Luo, Z.P.; Guo, Youming; Wang, H.H.; Shi, Tonghui; Chen, D.L.; Liu, L.; Huang, Yao

doi:10.1088/1741-4326/ab3b42

Cited by 8 publications

(23 citation statements)

References 23 publications

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“…The calculations are performed with CarMa0NL code [18,[20][21][22], that solves evolutionary equilibrium of axisymmetric plasmas in the presence of three-dimensional volumetric conductors. The 3D capabilities of the code are employed for design of plasma facing components for COMPASS-U that will be discussed in a separate publication.…”

Section: Numerical Resultsmentioning

confidence: 99%

“…To set up the CarMa0NL code [18,[20][21][22] for COMPASS-U we mesh the 2D region inside the first wall (shown in figure 3(a)) with triangles and 3D volumetric conductors with hexahedra. An integral formulation of the eddy current problem eliminates the necessity of meshing the vacuum region outside of the coupling surface (almost coincides with the first wall).…”

Section: Setup For Simulationsmentioning

confidence: 99%

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Global forces on the COMPASS-U wall during plasma disruptions

Yanovskiy¹,

Isernia²,

Pustovitov³

et al. 2021

Nucl. Fusion

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First, it is shown that during electromagnetic transients in COMPASS-U the poloidal field coils must drain sizeably the current from the vessel and, therefore, reduce disruption forces and their duration. Next, the role of poloidal eddy current (which is absent in some approaches) in the dynamics of vertical and radial forces is found to be essential. Finally, to verify the CarMa0NL modelling for COMPASS-U, the numerical results are cross-validated with general analytical predictions (Pustovitov 2015 Nucl. Fusion 55 113032): the computed vertical force on the tokamak wall is found to be almost zero during rapid (jump-like) transients, as it should be because of strong skin-effect. This test proves the credibility of the simulation model and computational realization.

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Section: Numerical Resultsmentioning

confidence: 99%

Section: Setup For Simulationsmentioning

confidence: 99%

Global forces on the COMPASS-U wall during plasma disruptions

Yanovskiy¹,

Isernia²,

Pustovitov³

et al. 2021

Nucl. Fusion

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“…Its effect on the plasma equilibrium was discussed more than 50 years ago [50]. Later the resistive wall mode and disruption dynamics have been studied with careful account of the tokamak wall inhomogeneity [26,38,39,41,43,51]. In all cases the cuts, ribs and ports restrain the current pathways, which may affect the amplitude of the n = 1 harmonic of b on the outer side of the wall.…”

Section: Discussionmentioning

confidence: 99%

“…Calculations are performed with CarMa0NL code [25,26,40,43,44], which solves evolutionary equilibrium of 2D plasma in the presence of 3D volumetric conductors. This means that the plasma is supposed to be in equilibrium at each time instant.…”

Section: Formulation Of the Taskmentioning

confidence: 99%

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Sideways forces on asymmetric tokamak walls during plasma disruptions

Yanovskiy¹,

Isernia²,

Pustovitov³

et al. 2022

Nucl. Fusion

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In the quarter century since the danger of sideways force on tokamak wall during disruptions was first recognized, substantial progress has been made in understanding the connection between plasma kink and the force. Less is known, however, about the effect of the wall asymmetry on the force generation. Here, we explore how irregularly situated ports lead to large sideways forces even for a symmetric driver such as a typical current quench. Further, we compare the effectiveness of both mechanisms.

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Characterization of disruption halo current between ‘W-Like’ graphite divertor and ‘ITER-Like’ divertor structure on EAST tokamak

Chen¹,

Granetz²,

Zeng³

et al. 2020

Plasma Phys. Control. Fusion

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The general characteristics of disruption halo currents, including current flowing paths between the components, are studied in the experiments of EAST tokamak with 'W-Like' graphite divertor and 'ITER-like' tungsten divertor. It is found that lower hybrid waves can efficiently reheat minor disruption plasma, this can drive plasma current for tens, or even hundreds, of milliseconds. The reheated plasma can lead to lower loop voltage and of course lower halo current. Additionally, it is confirmed that helium can not rapidly cool down plasmas with high thermal energy, but Argon can shut down plasma rapidly even with a little amount of gas. Until now no runaway electron plateau has been observed both in Argon and Helium mitigation experiments. The EAST disruption database shows that: (1) Larger loop voltage is driven in vertical displacement event disruptions than in major disruptions. (2) Halo currents decrease with the decrease of vertical displacement. (3) The boundary of I h Ip0 × TPF is 0.72, less than the limit shown in IDDB. The experimental results described here can help to improve the design of the planned upgrade of the EAST lower divertor, and provide physics information for the ITER divertor.

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Disruptive plasma simulations in EAST including 3D effects

Cited by 8 publications

References 23 publications

Global forces on the COMPASS-U wall during plasma disruptions

Global forces on the COMPASS-U wall during plasma disruptions

Sideways forces on asymmetric tokamak walls during plasma disruptions

Characterization of disruption halo current between ‘W-Like’ graphite divertor and ‘ITER-Like’ divertor structure on EAST tokamak

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