Abstract
At the end of 2005, for the first time a poloidal Liquid Lithium Limiter (LLL), with Capillary Porous System, has been tested on the high field medium size tokamak FTU. In this experimental campaign the LLL was applied in ohmic plasma discharges. The experimental data clearly show that the litization of FTU vacuum vessel permits to obtain better plasma performances. The experimental conditions in the edge of the FTU plasma have been simulated with the 2D multifluid code TECXY. The measured radial profiles of plasma density and temperature have been compared to the results of calculations and very good agreement has been found.
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