Abstract
Power transport to the Poloidal Divertor Experiment graphite scoop limiter was measured during both ohmic- and neutron-beam-heated discharges by observing its front face temperatures using an infrared camera. Measurements were made as a function of plasma density, current, position, fueling mode, and heating power for both co- and counter-neutral beam injection. The measured thermal load on the scoop limiter was 25 to 50% of the total plasma heating power. The measured peak front face midplane temperature was 1500 degree C, corresponding to a peak surface power density of 3 kw/cm**2. Symmetric and asymmetric thermal loads were observed. The asymmetric heat loads were predominantly skewed toward the respective ion drift directions for both co- and counterinjected beams. The results of transport calculations are consistent with the direction and magnitude of the observed asymmetries.
Original language | English (US) |
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Pages (from-to) | 145-152 |
Number of pages | 8 |
Journal | Fusion Technology |
Volume | 12 |
Issue number | 1 |
DOIs | |
State | Published - 1987 |
All Science Journal Classification (ASJC) codes
- General Engineering