Abstract
Analytic and two-dimensional computational solutions 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 multiplied by 10**1**3 cm** minus **3 or less and the thermal diffusivity in the edge region is 2 multiplied by 10**4 cm**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 a low plasma temperature near the limiter should be considered a likely possibility.
Original language | English (US) |
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Pages (from-to) | 320-327 |
Number of pages | 8 |
Journal | Fusion Technology |
Volume | 9 |
Issue number | 2 |
DOIs | |
State | Published - 1986 |
Externally published | Yes |
ASJC Scopus subject areas
- Engineering(all)