Abstract
A future tokamak reactor has to fulfill several requirements: good confinement properties to achieve ignition at low external heating power; high stability at minimal toroidal magnetic field strength; and efficient helium removal from the system for continuous burn. These conditions have to be met under circumstances, where the material, surrounding the burning plasma, is loaded to its limits. During steady state burn the first wall will be exposed to neutron fluxes of about 3 MW/m2. Additionally 600 MW is deposited into the plasma by the fusion α-particles, conducted to the plasma boundary and has to be removed from there at a tolerable power density. The wall is further exposed to a He-flux of 1.2 • 1021 s-1 and a deuterium and tritium flux which is about a factor of 20 larger. An implication of these figures is that several tens of tons of wall material are eroded and re-deposited during one year of reactor operation /1/.
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