POWER TRANSPORT TO THE POLOIDAL DIVERTOR EXPERIMENT SCOOP LIMITER.

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

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 languageEnglish (US)
Pages (from-to)145-152
Number of pages8
JournalFusion Technology
Volume12
Issue number1
DOIs
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