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 1×1018W-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 |
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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 |
Keywords
- plasma physics
- tokamaks
- divertors
- plasma-material interactions