Lithium is considered to be a possible plasma facing material in some divertor concepts of a future thermonuclear tokamak reactor. Lithium is evaporated from the divertor plate surface and ionized under and taking out very high thermal loads from theplate. Experiments are described in validation of the choice concerning the practicla realization of a liquid lithium evaporating surface (capillary structure). First, the steady state lithium plasma parameters were investigated in the SPRUT-4 linear device, in beam-plasma discharges in crossed electric and magnetic fields. The next part of the experiments was devoted to the high power load of a lithium cpaillary porous target with an electron beam followed by lithim vapour and plasma generation. The results were obtained for high efficiency of heat removal from the loaded surface in the range of 1-25 MW/m~2. The measured lithium evaporation rate was established to reach 1 kg m~-2 s~-1.
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