Abstract
Net erosion and deposition of tungsten (W) in the ASDEX Upgrade divertor were determined after the 2007 campaign by using thin W marker stripes. ASDEX Upgrade had full-W plasma-facing components during this campaign. The inner divertor and the roof baffle were net W deposition areas with a maximum deposition of about 1×1018 W-atoms cm-2 in the private flux region below the inner strike point. Net erosion of W was observed in the whole outer divertor, with the largest erosion close to the outer strike point. Only a small fraction of the W eroded in the main chamber and in the outer divertor was found in redeposits in the inner divertor, while a large fraction was either redeposited at unidentified places in the main chamber or has formed dust.
| Original language | English |
|---|---|
| Article number | 014039 |
| Number of pages | 7 |
| 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
- divertors
- plasma-material interactions
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