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The erosion of the graphite divertor plates in the ASDEX Upgrade tokamak is measured spectroscopically. Spatial profiles of the D(0) and C(+) influxes across the outer target plate are determined from measured absolute line intensities. Plasma parameters (n(e), T(e)) at the target, which are required to determined the appropriate photon emission efficiencies for these lines, are obtained from an in vessel reciprocating Langmuir probe above the target plate. Yields for the erosion of the graphite by the incident D(+) flux are determined from the ratio of the measured C(+) to D(0) fluxes. Over a range of moderate densities the measured yields of < / = 4% are explicable in terms of physical sputtering alone. Chemical sputtering by low energy Franck-Condon neutrals probably contributes, however, to the total erosion. At higher densities detachment of the plasma from the targets occurs owing to formation of a MARFE near the X point. Under these conditions localized physical sputtering of the targets ceases. The impurity level (Z (eff)) is, however, maintained following detachment, indicating a corresponding maintenance of carbon influx, perhaps due to chemical erosion of the total graphite surface and/or an improvement in particle confinement in the detached state.

Additional information

Authors: FIELD A R, Institut für Plasmaforschung der Universität Stuttgart (DE);GARCIA-ROSALES C, Institut für Plasmaforschung der Universität Stuttgart (DE);LIEDER G, Institut für Plasmaforschung der Universität Stuttgart (DE);PITCHER C S, Princeton University, Princeton Plasma Physics Laboratory (US);RADTKE R, Max-Planck-Institut für Plasmaphysik, Garching bei München (DE)
Bibliographic Reference: Article: Nuclear Fusion, Vol. 36 (1996) No. 2, pp. 119-131
Record Number: 199610401 / Last updated on: 1996-04-15
Original language: en
Available languages: en
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