Litcius/Paper detail

Stellarator-tokamak energy confinement comparison based on ASDEX Upgrade and Wendelstein 7-X hydrogen plasmas

U. Stroth, G. Fuchert, M. Beurskens, G. Birkenmeier, P. A. Schneider, E.R. Scott, K. J. Brunner, Florian Günzkofer, P. Hacker, O. Kardaun, J. Knauer, K. Rahbarnia, D. Zhang

2020Nuclear Fusion14 citationsDOI

Abstract

Abstract A confinement database with mainly electron-heated hydrogen plasmas from ASDEX Upgrade and Wendelstein 7-X was assembled. Stellarator confinement scaling expressions describe both standard discharges in the stellarator and L-mode plasmas in the tokamak similarly well and indicate a similar quality of energy confinement in both devices. While the energy confinement time in ASDEX Upgrade benefits from the smaller aspect ratio of the device, the transport coefficients in Wendelstein 7-X appear to be smaller possibly due to reduced average magnetic field curvature. A physics based confinement scaling is derived from a model that successfully describes transport in tokamaks. The dimensionally correct scaling has very similar parameter dependencies as the stellarator scalings and reproduces also the trends in the data from ITER L- and H-mode databases reasonably well. On the basis of this scaling, which represents the confinement times of the present data base, average tokamak L-mode and H-mode confinement is 7% lower and 76% higher, respectively.

Topics & Concepts

StellaratorASDEX UpgradeTokamakScalingPlasmaMagnetic confinement fusionPhysicsWendelstein 7-XAtomic physicsNuclear physicsComputational physicsMathematicsGeometryMagnetic confinement fusion researchIonosphere and magnetosphere dynamicsFusion materials and technologies