Numerical implications of including drifts in SOLPS-ITER simulations of EAST

Author:

Boeyaert D.123ORCID,Carli S.2ORCID,Dekeyser W.2ORCID,Wiesen S.3ORCID,Baelmans M.2ORCID

Affiliation:

1. Department of Nuclear Engineering and Engineering Physics, University of Wisconsin-Madison 1 , 1500 Engineering Drive, Madison, Wisconsin 53706, USA

2. Department of Mechanical Engineering, KU Leuven 2 , Celestijnenlaan 300, 3001 Leuven, Belgium

3. Forschungszentrum Jülich GmbH, Institut für Energie- und Klimaforschung—Plasmaphysik 3 , 52425 Jülich, Germany

Abstract

The inclusion of drifts in plasma edge codes like SOLPS-ITER is required to match simulation data with experimental profiles. However, this remains numerically challenging. In this paper, the effect of some numerical factors on the final plasma solution is investigated. This study is performed on three EAST simulations in the upper single null configuration: an attached purely deuterium case, an attached case with limited Ne-seeding, and a detached Ne-seeded case. The effects of the anomalous conductivity and anomalous thermo-electric coefficient on the plasma potential are investigated. Next, the effect of the employed grids is shown. In order to investigate these effects, accurate drift simulations are needed. Therefore, the employed time step and numerical parameters are discussed for the three studied simulations. For all presented simulations, it is verified that the restriction of the grid to the first flux surface tangent to the main chamber wall is sufficient within the context of non-extended simulations. This means that the main power dissipation takes place inside the simulated domain, and only a small fraction of the power is leaving the B2.5 grid through the grid boundary closest to the first wall. Finally, the effect of drifts on the asymmetry between the inner and outer target for EAST simulations is demonstrated.

Funder

EUROfusion

U.S. Department of Energy

College of Engineering, University of Wisconsin-Madison

Publisher

AIP Publishing

Reference25 articles.

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5. F. Reimold , “ Experimental studies and modeling of divertor plasma detachment in H-mode discharges in the ASDEX upgrade tokamak,” Ph.D. thesis ( Technische Universität München—Faculty of Physics, 2014).

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