Abstract

Non-linear magnetohydrodynamic (MHD) simulations play an essential role in active research and understanding of tokamak plasmas for the realization of a fusion power plant. The development of MHD codes such as JOREK is a key aspect of this research effort. In this paper, we present an operational version of the full-MHD model implemented in JOREK, a significant advancement from the reduced-MHD model used for previous studies, where assumptions were made on the perpendicular dynamics and the toroidal magnetic field. The final model is presented in detail, and benchmarks are performed using both linear and non-linear simulations, including comparisons between the new full-MHD model of JOREK and the previously extensively studied reduced-MHD model, as well as results from the linear full-MHD code CASTOR3D. For the cases presented, this new JOREK full-MHD model is numerically and physically reliable, even without the use of numerical stabilization methods. Non-linear modeling results of typical tokamak instabilities are presented, including disruption and edge-localized-mode physics, most relevant to current open issues concerning future tokamaks such as ITER and DEMO.

Highlights

  • Industrial electricity production using nuclear fusion power would greatly contribute to the reduction of greenhouse gas emissions and of long-lived radioactive nuclear waste, while providing electricity to society without the limit of an exhaustible natural resource

  • We present an operational version of the full-MHD model implemented in JOREK, a significant advancement from the reduced-MHD model used for previous studies, where assumptions were made on the perpendicular dynamics and the toroidal magnetic field

  • We describe the essential physical and numerical ingredients of the full-MHD model implemented in JOREK, including visco-resistive and diffusive effects, sources, diamagnetic rotation and neoclassical friction, boundary conditions, and normalization

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Summary

INTRODUCTION

Industrial electricity production using nuclear fusion power would greatly contribute to the reduction of greenhouse gas emissions and of long-lived radioactive nuclear waste, while providing electricity to society without the limit of an exhaustible natural resource. The periodic nature of the torus ensures that charged particles, which approximately follow magnetic field lines, are not lost at the end of open field lines like in linear plasma devices This periodicity can be subject to resonance and instabilities. Previous studies of MHD instabilities with the JOREK code relied on a reduction of the full-MHD system This reduction, known as reduced MHD, assumes that the toroidal magnetic field is constant in time and that the perpendicular velocity (perpendicular with respect to the magnetic field) is approximately poloidal.. This reduction, known as reduced MHD, assumes that the toroidal magnetic field is constant in time and that the perpendicular velocity (perpendicular with respect to the magnetic field) is approximately poloidal.26,27 The latter assumption is mostly kept for simplicity in formulating the equations. V summarizes the work and lays out the further improvements required for future studies of tokamak instabilities

PHYSICS MODEL AND NUMERICAL METHODS
Numerical methods
Basis of the full-MHD formulation
Choice of gauge
Diffusion coefficients and sources
Extended MHD
Projection and coordinate system
Boundary conditions
COMPARISON OF FULL-MHD AND REDUCED-MHD
Where reduced-MHD fails
Peeling-ballooning modes in a circular plasma
Peeling-ballooning modes in an X-point plasma
Peeling-ballooning modes in a spherical tokamak
Diamagnetic effects and neoclassical friction
NON-LINEAR SIMULATIONS
Core MHD and disruptions
MAST scrape-off layer filament dynamics
JET ELM simulation
Findings
SUMMARY AND FUTURE WORKS
Full Text
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