Helium removal from tokamaks
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.
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