Abstract
This study focuses on the removal of trapped D from thick codeposits on
JET divertor tiles via thermo-oxidation. The tiles were removed from the
JET Mark II Gas Box divertor after the 1998–2001 campaign. These
codeposits have Be concentrations of up to ~60% Be/(Be + C) and their
thicknesses range from 10 to 270 µm. Laser thermal desorption
spectroscopy was used to determine the D removal rates and final
remaining D concentrations following oxidation. Estimates of the carbon
removed during oxidation were obtained from mass-loss measurements. The
initial rate of D removal was found to be much higher for the thick
codeposits of this study than for the previously studied codeposits with
thicknesses in the range 1–5 µm (from TFTR, DIII-D and JET). This is
despite the large Be concentrations. For oxidation performed at 623 K
(350 °C) and 21 kPa (160 Torr) O2 pressure the initial D
removal rates were found to increase linearly with increasing 'inherent'
D content; about 50% of the inherent D was removed from all specimens
in the first 15 min—independent of Be content and codeposit thickness.
Following 8 h of oxidation, the fraction of D removed was >85% for
all specimens, again, independent of Be content and thickness.
Original language | English |
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Article number | 035008 |
Number of pages | 9 |
Journal | Nuclear Fusion |
Volume | 48 |
Issue number | 3 |
DOIs | |
Publication status | Published - 2008 |
MoE publication type | A1 Journal article-refereed |
Keywords
- JET
- divertor plasma
- divertor tiles
- fusion energy
- fusion reactors
- plasma
- oxidation