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Helium, as the ash of burning D-T plasma, is an unavoidable impurity component present in near future tokamak experiments with significant alpha particle heating. Its efficient removal from the burning zone of a D-T fusion reactor (or lack thereof) will play a key role in the achievement of economic fusion power production. A survey is given of the issues related to this question. Since there is as yet no experimental experience with thermonuclear plasma significantly heated by fusion products, this review is based on results from simulation experiments of helium injection into hydrogen or deuterium tokamak plasmas, and from numerical transport code work. Both kinds of results are discussed with reference to ignition criteria obtained for steady D-T burning, which have been reformulated in terms relevant to the ash removal problem.

Additional information

Authors: REITER D ET AL., Institut für Plasmaphysik, Kernforschungsanlage Jülich GmbH, Jülich (DE);BAELMANS M, Katholieke Universiteit Leuven, Department of Mechanical Engineering, Heverlee (BE);BEHRISCH R, Max-Planck-Institut für Plasmaphysik, Garching bei München (DE);SCHNEIDER R, Max-Planck-Institut für Plasmaphysik, Garching bei München (DE)
Bibliographic Reference: Article: Plasma Physics and Controlled Fusion, Vol. 33 (1991) No. 13, pp. 1579-1600
Record Number: 199210251 / Last updated on: 1994-12-02
Original language: en
Available languages: en