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Abstract

The ergodic divertor (ed) is expected to provide substantial advantages in controlling edge parameters and impurity concentrations in high temperature fusion plasmas. The ed coils produce a relatively broad toroidal (n) and poloidal (m) Fourier mode spectrum. They can be phased such that m/n resonant surfaces occur at several q values between 1.33 and 8. The width of the ergodic layer and the degree of stochasticity in the layer can be varied by changing the ed current or the radial position of the m(0)/n(0) resonant surface with respect to the coils. First experiments concentrate on particle confinement and impurity control. Numerical and analytical models will be used to analyse the results. Heat and particle transport experiments are underway and MHD studies will follow shortly. This should lead to a more complete assessment of ergodic divertor benefits for high temperature, long pulse fusion reactor plasmas and yield new insight into plasma surface interactions.

Additional information

Authors: EVANS T E, General Atomics, San Diego, Ca. (US);GROSMAN A, CEA, Département de Recherches sur la Fusion Contrôlée, Saint-Paul-lez-Durance (FR);CAPES H, CEA, Département de Recherches sur la Fusion Contrôlée, Saint-Paul-lez-Durance (FR);SAMAIN A, CEA, Département de Recherches sur la Fusion Contrôlée, Saint-Paul-lez-Durance (FR);GENRITH P, Oak Ridge National Laboratories, Oak Ridge (US)
Bibliographic Reference: Paper presented: 16th European Conference on Controlled Fusion and Plasma Physics, Venezia (IT), March 13-17, 1989
Availability: Available from (1) as Paper EN 34453 ORA
Record Number: 198910811 / Last updated on: 1994-12-01
Category: PUBLICATION
Original language: en
Available languages: en