Abstract

Analytic and two-dimensional computational solution for the plasma parameters near a toroidally symmetric limiter are illustrated for the projected parameters of a tokamak fusion core experiment (TFCX). The temperature near the limiter plate is below 20 eV, except when the density 10 cm inside the limiter contact is 8 x 10/sup 13/ cm-/sup 3/ or less and the thermal diffusivity in the edge region is 2 x 10/sup 4/ cm/sup 2//S or less. Extrapolation of recent experimental data suggests that neither of these conditions is likely to be met near ignition in TFCX, so as a low plasma temperature near the limiter should be considered a likely possibility.

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