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The characteristics of ergodic divertor (ED); deuterium plasmas in the Tore Supra tokamak are discussed. The core plasma confinement is not degraded by the presence of the ED; the electron density and temperature profiles are not modified. The ED configuration compares well with a classical X point divertor: intrinsic impurities are screened out, the power load is deflected to dedicated surfaces, and density control through particle pumping is possible. Up to 5.5 MW of ion cyclotron resonance power and 3 MW of lower hybrid power have been successfully used, power exhaust being mainly by radiation (80%).

Additional information

Authors: MICHELIS C, CEA, Département de Recherches sur la Fusion Contrôlée, CEN Cadarache, Saint-Paul-lez-Durance (FR)
Bibliographic Reference: Article: Nuclear Fusion, Vol. 35 (1995) No. 9, pp. 1133-1153
Record Number: 199511513 / Last updated on: 1995-11-03
Original language: en
Available languages: en