Power Handling of LiMIT during Exposure to EAST plasma

Liquid lithium PFCs offer an attractive solution to the issues faced by solid high Z PFCs such as: the sputtering of high Z impurities into the plasma core, fuzz formation due to helium implantation and thermal damage (melting, blistering and cracking.) By presenting a constantly refreshing surface a flowing lithium surface prevents damage to the PFC, via a reduction in sputtering of solid material and convective heat removal by the liquid, increasing component lifetime. The utilization of lithium presents several other benefits for fusion plasmas through impurity removal, helium ash pumping and a reduction in anomalous transport within the plasma. To further the development of lithium PFCs a LiMIT type limiter has been exposed to the EAST plasma, this work will present the experimental results from the campaign alongside a COMSOL model developed to calculate the conductive heat flux incident on LiMIT. During NBI heated shots in EAST the plate experienced a calculated peak conductive heat flux of 8MWm^-2 further supplemented by the heat stored convectively in the lithium and the heat dissipated by the lithium vapor cloud, ultimately resulting in LiMIT withstanding a heat flux 10MWm^-2 without sustaining any macroscopic damage.