Abstract
Numerical modelling of 13CH4 injection into the outer divertor plasma of the full tungsten, vertical target of ASDEX Upgrade is presented. The SOLPS5.0 code package is used to calculate a realistic scrape-off layer plasma background corresponding to L-mode discharges in the attached divertor plasma regime. The ERO code is then used for detailed modelling of the hydrocarbon break-up, re-deposition and re-erosion processes. The deposition patterns observed at two different poloidal locations are shown to strongly reflect the cross-field gradients in divertor plasma density and temperature, as well as the local plasma collisionality. Experimental results with forward and reversed BT, accompanied by numerical modelling, also point towards a significant poloidal hydrocarbon E×B drift in the divertor region.
Original language | English |
---|---|
Article number | 014019 |
Journal | Physica Scripta |
Issue number | T138 |
DOIs | |
Publication status | Published - 2009 |
MoE publication type | A1 Journal article-refereed |
Event | 12th International Workshop on Plasma-Facing Materials and Components for Fusion Applications, PFMC-12 - Jülich, Germany Duration: 11 May 2009 → 14 May 2009 |
Keywords
- plasma physics
- tokamaks
- plasma-material interactions