Abstract
Hydrogen retention in the divertor tokamak ASDEX Upgrade is studied by surface analysis and gas balances methods. Comparing carbon and tungsten plasma facing components (PFCs), the deuterium content of deposits at the divertor plates has dropped by a factor of 13. With tungsten PFCs only 0.7% of the puffed hydrogen is retained, including a significant amount deeply implanted in the tungsten coatings at the outer divertor. Gas balances for ITER relevant high density H-mode discharges lead to a hydrogen retention averaged over a discharge of 8.2±3.3% for tungsten PFCs and 23±7% for carbon PFCs. For tungsten PFCs wall saturation is observed, i.e. only 1.5±3.5% of the puffed gas is retained after reaching steady state conditions. Within the error bars all hydrogen outgasses within 15 min.
Original language | English |
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Article number | 085031 |
Journal | Nuclear Fusion |
Volume | 49 |
Issue number | 8 |
DOIs | |
State | Published - 2009 |
Externally published | Yes |