Abstract
To date there is no adequate solution for high heat load plasma facing components of the next step fusion reactor among solid material options. A lithium-filled capillary porous systems (CPS) was proposed as a plasma facing material and experimental work on this subject is now in progress. Steady-state experiments with CPS-based target and lithium supply systems have shown successful operation at heat fluxes of 1–10 MW/m 2 during several hours. Experimental data is obtained on lithium CPS stability at heat flux up to 25–50 MW/m 2. The lithium CPS behaviour in contact with real tokamak plasma is considered for normal discharge condition at 10 MW/m 2 and for plasma disruption at 15 MJ/m 2. Erosion mechanism of lithium under tokamak plasma impact was analysed. Stability of lithium CPS in tokamak conditions was shown.
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