Abstract

Projected operation of the poloidal field divertor is described for the Princeton Reference Design Tokamak Reactor. A relatively cold plasma blanket will form outside the separatrix and will constitute a thermal connection between the hot plasma and the exhaust chamber. The plasma blanket is expected to be a good absorber of slow neutrals. Simple one-dimensional models of the diverted plasma provide estimates of the plasma density distribution and particle flux to the walls. Recycling of particles with the divertor walls may amount to ten times the particle throughput of the reactor. The magnetic field configuration is also discssed.

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