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With an anticipated power flux across the separatrix up to 300 MW of an ITER-like fusion reactor, conventional measures of power spread lead to a peak power load at the target plates in the order of 30 MW m{-2}, far beyond the technically feasible limit for stationary operation. Radiative cooling by seed impurities appears to be the most promising plasma-physical option to reduce the target power load, but extrapolations of present experiments predict an only marginally tolerable increase of the plasma effective charge Z(eff). The completely detached H-mode (CDH) in ASDEX Upgrade demonstrates radiative H-mode operation within the operational range exhibiting high-frequent type-III edge localized modes (ELM) and target power load in the order of 10% of the heating power. At present, open questions on high density reactor operation are related to radiative instabilities as well as edge transport enhancement and H-mode impairment observed in several tokamaks under high density conditions.

Additional information

Authors: KALLENBACH A ET AL, Max-Planck-Institut für Plasmaphysik, Garching bei München (DE)
Bibliographic Reference: Article: Fusion Engineering and Design, Vol. 36 (1997), pp. 101-108
Record Number: 199711341 / Last updated on: 1997-10-16
Original language: en
Available languages: en