Design and preliminary thermal validation of the WEST actively cooled upper divertor
Abstract
Design of WEST upper divertor target, regarding integration and thermal load specifications.
• The proposed concept enables to sustain in steady state, at least, a maximum heat flux of 8 MWm -2 .
• The plasma incident surface is covered with a <30 m thick W coating.
• HHF tests up to 10.5 MWm -2 were successfully performed on the upper divertor prototype.
• Upper divertor targets will be fabricated and installed in the vacuum chamber in 2015.