A5086629122- Magnetic confinement fusion research
- Ionosphere and magnetosphere dynamics
- Laser-Plasma Interactions and Diagnostics
- Fusion materials and technologies
Dutch Institute for Fundamental Energy Research
2016-2017
Divertor detachment is explored on the TCV tokamak in alternative magnetic geometries. Starting from typical single-null shapes, poloidal flux expansion at outer strikepoint varied by a factor of 10 to investigate X-divertor characteristics, and total 70 study properties super-X divertor. The effect an additional X-point near target investigated divertors. Detachment studied these plasmas during Ohmic density ramps with ion B drift away primary X-point. threshold, depth detachment, stability...
Divertor detachment in the TCV tokamak has been investigated through experiments and modelling. Density ramp were carried out ohmic heated L-mode pulses with ion ∇B drift directed away from primary X-point, similar to previous studies [1]. Before roll-over current outer strike point, C III Dα emission leg recede slowly point toward at a rate of ∼2.0 × 10−19 m/m−3 along magnetic field as electron temperature reduces increasing density. Around onset detachment, upstream density profile target...