Author/Authors :
Khripunov، نويسنده , , B.I. and Petrov، نويسنده , , V.B. and Shapkin، نويسنده , , V.V. and Antonov، نويسنده , , N.V. and Pleshakov، نويسنده , , A.S. and Rupyshev، نويسنده , , A.S. and Prokhorov، نويسنده , , D.Yu. and Evtikhin، نويسنده , , V.A. and Lyublinsky، نويسنده , , I.E. and Vertkov، نويسنده , , V.V.، نويسنده ,
Abstract :
A liquid lithium surface is considered for application in divertor of a fusion tokamak-reactor. Lithium surface has been realized in experimental mock-ups and its operation has been demonstrated under high power load at reactor relevant heat fluxes. Lithium targets have been developed on the basis of capillary pore structures. A vertical working surface was investigated under steady-state electron beam. The range of power loads 1–50 MW/m2 was covered by the studies. Long-duration experiments were performed on thermally stabilized targets at 1–10 MW/m2. Evaporation was shown to be efficient mechanism of power removal and a high lithium mass loss rate was measured. Operation of the facility with plasma at 0.2 g/s of lithium flow was shown. The problem of lithium balance in divertor and SOL is discussed. Pumping of lithium is possible by solid and liquid metal wall structures in reactor conditions in the divertor channel.
