The role of neutral gas in validated global edge turbulence simulations

Nuclear Fushion

article

W. Zholobenko¹  A. Stegmeir¹  M. Griener¹  G.D. Conway¹  T. Body¹  D. Coster¹  F. Jenko¹  the ASDEX Upgrade Team¹ 

[1] Max-Planck-Institut für Plasmaphysik

关键词: neutrals–plasma interaction;    turbulence simulations;    ASDEX Upgrade tokamak;    edge and scrape-off layer;    validation;    Braginskii;   

DOI  :  10.1088/1741-4326/ac1e61

来源: Institute of Physics Publishing Ltd.

【 摘 要 】

To make predictions for and design fusion reactors, a multitude of physical processes must be considered. In the edge and scrape-off layer (SOL), turbulent fluctuations intertwine with the plasma background, which is largely determined by neutral gas, and magnetic geometry plays an important role. A diffusive neutrals model has now been implemented in the global Braginskii edge turbulence code GRILLIX. The code is based on the flux-coordinate independent (FCI) approach, which allows efficient turbulence simulations in diverted equilibria. We validate simulations across the ASDEX Upgrade edge and SOL against measurements in discharge# 36190, and find much better agreement thanks to the neutrals. Disentangling the effects of the neutral gas, we find that it affects the plasma in several ways. Firstly, the ionization of neutrals modifies the radial profiles of plasma density and temperature, leading to a transition of the turbulence drive from the general ballooning type to the ion temperature gradient type. Secondly, strong poloidal asymmetries can be induced due to divertor recycling, depending on the ionization pattern. As ballooned perpendicular plasma transport is stronger at the low-field side, neutrals penetrate deeper into the plasma at the high-field side, leading to significant ionization and radiation there. With increasing divertor neutrals density, the targets cool down while plasma density increases, more strongly at the high-field side. Much of the dynamics take place directly around theX -point and along the separatrix, which can be resolved by the FCI approach. Potential remains in extending the model and the code, but our results build confidence that predictive capability is within reach for major design questions for fusion reactors, such as the near SOL fall-off length.

【 授权许可】

Unknown