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- W58720103 abstract "Impurities must be controlled in high temperature tokamak plasmas because the impurity radiation can limit the plasma temperature to values below that required for ignition. Impurity influx can be reduced with the use of the magnetic divertor configuration, which surrounds the hot dense plasma with a much cooler plasma that contacts material walls only on open field lines. In DIII-D, good H-mode confinement has been obtained with up to 6MW of neutral-beam injection. This report summarizes the essential features of divertor operation for DIII-D H-mode plasmas. The report is divided into sections which briefly describe the DIII-D tokamak and relevant diagnostics, summarize the divertor plasma parameters obtained during the H-mode and describe the heat loads on the divertor target plates, and present the results of measurements of the central radiation and impurity content using data from an EUV spectrometer and a 21 channel bolometer array. 6 refs., 8 figs." @default.
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- W58720103 date "1987-11-01" @default.
- W58720103 modified "2023-09-26" @default.
- W58720103 title "A summary of divertor operation in DIII-D" @default.
- W58720103 hasPublicationYear "1987" @default.
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