Liquid lithium as a plasma-facing material was tested for the first time on a high field medium size tokamak, FTU. A liquid Li reservoir supplies a mesh of capillaries that is movable from shot to shot in the scrape-off layer (SOL) plasma to act as a secondary limiter. An almost complete lithization of the vacuum vessel walls is obtained in about three discharges. Plasmas cleaner than boronization and titanization, with lower radiation losses and smaller impurity content are produced. The SOL electron temperature increases, ΔT e ∼ 10 eV, while density (ne) is less affected. The 2D multifluid code TECXY explains this only if a strong reduction of plasma recycling on the walls and main limiter occurs, consistent with the high Li hydrogen pumping capability. This property also permits a much tighter control of the plasma density. With the Li limiter inserted inside the vessel poloidal asymmetries develop in the SOL that TECXY explains with a local increase of radiation, caused by enhanced evaporation/sputtering of Li. New regimes can be produced in such conditions with a clear increase in |∇n e/ne| and of the peaking factor ne0/ <n e ≫ 2 at the Greenwald density limit , without any direct central particle fuelling. © 2007 IOP Publishing Ltd.
All Science Journal Classification (ASJC) codes
- Nuclear Energy and Engineering
- Condensed Matter Physics
Pericoli-Ridolfini, V., Apicella, M. L., Mazzitelli, G., Tudisco, O., & Zagórski, R. (2007). Edge properties with the liquid lithium limiter in FTU - Experiment and transport modelling. Plasma Physics and Controlled Fusion, 49(7), -. [S09]. https://doi.org/10.1088/0741-3335/49/7/S09