DIII-D RESEARCH OPPORTUNITIES FORUM FOR THE 2013 EXPERIMENTAL CAMPAIGN
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ID | Title | Research Area | Name | Affiliation |
Time Req'ed |
ITPA Joint Exp |
ITER IO Urgent Research Task |
66 details | 13C-methane injection into USN re C migration to walls and ITER decision about PFC target material | Plasma-material Interface | U of Toronto | Yes | Yes | Yes | |
70 details | DIMES test of misaligned CFC tile to establish size of misalignment needed to disrupt ITER | Plasma-material Interface | U of Toronto | Yes | No | No | |
89 details | Mo, W, Al, Be DiMES net/gross erosion experiments | Plasma-material Interface | U of Toronto | Yes | Yes | Yes | |
90 details | Carbon-13 in He Plasma erosion/deposition experiment to benchmark DIVIMP code being used by ITER | Plasma-material Interface | Commonwealth Fusion Systems | No | No | No | |
128 details | Carbon-13 in He Plasma erosion/deposition experiment to benchmark DIVIMP code being used by ITER | Plasma-material Interface | Commonwealth Fusion Systems | No | No | No | |
206 details | Studies of arcing on divertor PFC surfaces | Plasma-material Interface | UCSD | No | No | No | |
207 details | Dust generation from deposited layers and leading edges | Plasma-material Interface | UCSD | No | No | No | |
215 details | Control of tungsten PFC erosion by local gas injection | Plasma-material Interface | UCSD | No | No | No | |
233 details | C erosion and D up-take at high surface temperature | Plasma-material Interface | GA | No | No | No | |
241 details | C-13 and background carbon | Plasma-material Interface | GA | No | No | No | |
314 details | Optimization of castellation for a new W-divertor of ITER: studies of shaped castellation in DIII-D | Plasma-material Interface | UCSD | No | Yes | Yes | |
368 details | Investigation of extreme outer wall heating caused by the DIII-D TBM | Plasma-material Interface | LLNL | No | Yes | Yes |