H. W. Kugel, R. Budny, R. Fonck, Robert James Goldston, B. Grek, R. Kaita, S. Kaye, R. J. Knize, D. Manos, R. McCann, D. McCune, K. McGuire, D. K. Owens, D. Post, G. Schmidt

Research output: Contribution to journalArticle


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 languageEnglish (US)
Pages (from-to)145-152
Number of pages8
JournalFusion Technology
Issue number1
StatePublished - Jan 1 1987

All Science Journal Classification (ASJC) codes

  • Engineering(all)

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    Kugel, H. W., Budny, R., Fonck, R., Goldston, R. J., Grek, B., Kaita, R., Kaye, S., Knize, R. J., Manos, D., McCann, R., McCune, D., McGuire, K., Owens, D. K., Post, D., & Schmidt, G. (1987). POWER TRANSPORT TO THE POLOIDAL DIVERTOR EXPERIMENT SCOOP LIMITER. Fusion Technology, 12(1), 145-152. https://doi.org/10.13182/FST87-A25058