SOLPS-ITER numerical evaluation about the effect of drifts in a divertor configuration of ASDEX-Upgrade and a limiter configuration of J-TEXT
H. Wu, P. Shi, F. Subba, H. Sun, M. Wischmeier, R. Zanino, the ASDEX, Upgrade Team

TL;DR
This study uses SOLPS-ITER simulations to analyze how plasma drifts influence the HFSHD region in both divertor and limiter configurations of tokamaks, with a focus on J-TEXT and AUG devices, revealing effects on plasma detachment and temperature profiles.
Contribution
It applies validated models from AUG divertor simulations to J-TEXT limiter configurations, demonstrating the impact of drifts on plasma behavior and detachment regimes.
Findings
Drifts cause partial detachment of inner targets in both devices.
Electron temperature decreases in detached regimes, especially at the outer targets.
Drifts influence neutral density and plasma parameters in the SOL region.
Abstract
The High Field High Density Region (HFSFD) has been experimentally observed in both divertor and limiter tokamak devices. In order to numerically reproduced the HFSHD region in the limiter tokamak device J-TEXT, we first performed SOLPS-ITER simulations on the J-TEXT limiter tokamak with the activation of drifts, which is associated with the HFSHD region. The validated physical models, which is from ASDEX Upgrade (AUG) divertor modelling including full drifts and currents, were applied. Through a gas puffing rate scan, both attached and detached regimes were numerically obtained in the AUG divertor and J-TEXT limiter. The key plasma parameters in the J-TEXT limiter are evaluated with and without drifts that have a qualitative performance like AUG except the roll-overment of the total ion flux at the targets. The drift effects on the target profiles are investigated in which the maximum…
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Taxonomy
TopicsMagnetic confinement fusion research · Fusion materials and technologies · Superconducting Materials and Applications
