Home / Store / Journals / Electronic Articles / Fusion Science and Technology / Volume 60 / Number 1
S. J. Zweben, R. A. Ellis, P. Titus, A. Xing, H. Zhang
Fusion Science and Technology
Volume 60 / Number 1 / July 2011 / Pages 197-202
Format:electronic copy (download)
It may be possible to replace conventional actively cooled tokamak divertor plates with a set of rapidly moving, passively cooled divertor plates on rails. These plates would absorb the plasma heat flux with their thermal inertia for ~10-30 sec, and would then be removed from the vessel for processing. When outside the tokamak, these plates could be cooled, cleaned, recoated, inspected, and then returned to the vessel in an automated loop. This scheme could provide near-optimal divertor surfaces at all times, and avoid the need to stop machine operation for repair of damaged or eroded plates. We describe various possible divertor plate designs and access geometries, and discuss an initial design for a movable and removable divertor module for NSTX-U.
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