Hybrid parallelization of the XTOR-2F code for the simulation of two-fluid MHD instabilities in tokamaks

Marx, A.; Lütjens, H.

doi:10.1016/j.cpc.2016.10.014

Cited by 7 publications

(9 citation statements)

References 40 publications

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“…In this respect the simulation of these events with 3D MHD codes is crucial. For other non-linear MHD codes investigating VDEs, refer, e.g., to references [272][273][274][275] and references therein.…”

Section: Vertical Displacement Events and Halo Current Dynamicsmentioning

confidence: 99%

The JOREK non-linear extended MHD code and applications to large-scale instabilities and their control in magnetically confined fusion plasmas

et al. 2021

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JOREK is a massively parallel fully implicit non-linear extended magneto-hydrodynamic (MHD) code for realistic tokamak X-point plasmas. It has become a widely used versatile simulation code for studying large-scale plasma instabilities and their control and is continuously developed in an international community with strong involvements in the European fusion research programme and ITER organization. This article gives a comprehensive overview of the physics models implemented, numerical methods applied for solving the equations and physics studies performed with the code. A dedicated section highlights some of the verification work done for the code. A hierarchy of different physics models is available including a free boundary and resistive wall extension and hybrid kinetic-fluid models. The code allows for flux-surface aligned iso-parametric finite element grids in single and double X-point plasmas which can be extended to the true physical walls and uses a robust fully implicit time stepping. Particular focus is laid on plasma edge and scrape-off layer (SOL) physics as well as disruption related phenomena. Among the key results obtained with JOREK regarding plasma edge and SOL, are deep insights into the dynamics of edge localized modes (ELMs), ELM cycles, and ELM control by resonant magnetic perturbations, pellet injection, as well as by vertical magnetic kicks. Also ELM free regimes, detachment physics, the generation and transport of impurities during an ELM, and electrostatic turbulence in the pedestal region are investigated. Regarding disruptions, the focus is on the dynamics of the thermal quench (TQ) and current quench triggered by massive gas injection and shattered pellet injection, runaway electron (RE) dynamics as well as the RE interaction with MHD modes, and vertical displacement events. Also the seeding and suppression of tearing modes (TMs), the dynamics of naturally occurring TQs triggered by locked modes, and radiative collapses are being studied.

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Section: Vertical Displacement Events and Halo Current Dynamicsmentioning

confidence: 99%

The JOREK non-linear extended MHD code and applications to large-scale instabilities and their control in magnetically confined fusion plasmas

et al. 2021

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“…XTOR-2F [6]). Such simulations are computationally expensive due to the resolution and number of time steps necessary and require a certain level of parallelisation [7]. Since a saturated state without equilibrium flows is characterised by being time-independent, an equilibrium code can in theory obtain a saturated state, satisfying the force balance equation j × B − ∇p = 0.…”

Section: Introductionmentioning

confidence: 99%

Free boundary 3D ideal MHD equilibrium calculations for non-linearly saturated current driven external kink modes in tokamaks

et al. 2018

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It is shown that free boundary 3D equilibrium calculations in tokamak geometry are capable of capturing the physics of non-linearly saturated external kink modes for monotonic current and q profiles typical of standard (baseline) plasma scenarios. The VMEC ideal MHD equilibrium model exhibits strong flux surface corrugations of the plasma vacuum boundary, driven by the core current profile. A method is presented which conveniently extracts the amplitude of the corrugation in terms of Fourier components in straight field line coordinates. The Fourier spectrum, and condition for non-linear corrugation agrees well with linear simulations, and the saturated amplitude agrees well with non-linear analytic calculations.

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“…In this section, a full nonlinear MHD 3D code, M3D, has been employed to model both the SC and SSM for a realistic EAST plasma, in order to find the key factor which mends the bifurcation between the SC and the SSM. The SC has been modeled by many numerical codes in low β and small S tokamak plasma, such as M3D [24,25], NIMROD [26], XTOR-2F [27] and M3D + K [28]. A very recent nonlinear simulation work with M3D-C1 has successfully modeled an SC due to the SSM in a tokamak plasma with a high β, q 0 ≽ 1 and S = 10 6 [29].…”

Section: Results Of Nonlinear M3d Simulation With M3d Codementioning

confidence: 99%

Observation of helical m/n = 1/1 saturated steady mode in EAST pure electron heating scenario with q₀ ≼ 1

Xu¹,

Li²,

Zhou³

et al. 2020

Nucl. Fusion

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We observed for the first time a helical m/n = 1/1 (m is the poloidal mode number and n is the toroidal mode number) saturated steady mode (SSM) in the center of the EAST electron heating dominant plasma where the core safety factor was close to but slightly below unity and the profile had an extreme peak at the plasma center ( is the electron temperature). An internal crash can be caused by the dynamics of the SSM, and its influence on the electron temperature profile is as large as that of a typical sawtooth crash (SC) in magnitude. Due to the weak magnetic shear in the core, the SSM regularly exhibits an m/n = 2/2 harmonic component. For low shear auxiliary heated plasma, the SSM cannot cause the degradation of plasma confinement ( or ), but an SC is indeed a harmful factor. Three-dimensional resistive magnetohydrodynamic simulations with a realistic EAST strong elongated magnetic configuration, a high Lundquist number () and a strong central peaked pressure profile, have been made to demonstrate the formation of the SSM in the case of and the destabilization of the SC in another case with . These nonlinear simulation results agree well with the observations of both the SSM and SC in EAST electron heating dominant discharges with an extreme central peaked . An M3D simulation found that the SC is caused by additional newly developed harmonics of the m/n = 1/1 helical instability. Nonlinear simulation also predicted a modulation of the SSM on current in the plasma core, which is favorable for maintaining in the plasma core. Furthermore, nonlinear simulation also showed that a small toroidal plasma flow can be generated by the SC.

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Hybrid parallelization of the XTOR-2F code for the simulation of two-fluid MHD instabilities in tokamaks

Cited by 7 publications

References 40 publications

The JOREK non-linear extended MHD code and applications to large-scale instabilities and their control in magnetically confined fusion plasmas

The JOREK non-linear extended MHD code and applications to large-scale instabilities and their control in magnetically confined fusion plasmas

Free boundary 3D ideal MHD equilibrium calculations for non-linearly saturated current driven external kink modes in tokamaks

Observation of helical m/n = 1/1 saturated steady mode in EAST pure electron heating scenario with q₀ ≼ 1

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Hybrid parallelization of the XTOR-2F code for the simulation of two-fluid MHD instabilities in tokamaks

Cited by 7 publications

References 40 publications

The JOREK non-linear extended MHD code and applications to large-scale instabilities and their control in magnetically confined fusion plasmas

The JOREK non-linear extended MHD code and applications to large-scale instabilities and their control in magnetically confined fusion plasmas

Free boundary 3D ideal MHD equilibrium calculations for non-linearly saturated current driven external kink modes in tokamaks

Observation of helical m/n = 1/1 saturated steady mode in EAST pure electron heating scenario with q0 ≼ 1

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Observation of helical m/n = 1/1 saturated steady mode in EAST pure electron heating scenario with q₀ ≼ 1