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 |
UN SDGs
This output contributes to the following UN Sustainable Development Goals (SDGs)
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SDG 7 Affordable and Clean Energy
Keywords
- plasma physics
- tokamaks
- plasma-material interactions
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