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Ergodic divertor operation on Tore Supra is characterized by good performance in terms of divertor physics. Control of particle recirculation and impurity screening are related to the symmetry, both poloidally and toroidally, of the shell of open field limes and to its radial extent. Feedback control of the divertor plasma temperature has led to controlled radiative divertor experiments. In particular, good performance is obtained when the plasma is controlled to be at a temperature comparable to the energy involved in the atomic process. For standard discharges with 5 MW total power and ICRH heating, the low parallel energy flux = 10 MW m{-2} is reduced to = 3 MW m{-2} with nitrogen injection. This is achieved at a modest cost in core dilution. Despite the large volume of open lines, the ergodic divertor does not reduce the possible current in the discharge since stable discharges are achieved with q(sep) = 2. It is shown that the reorganization of the current profile in conjunction with a transport barrier in the electron temperature on the separatrix stabilizes the tearing mode. Confinement follows the standard L mode confinement. In a few cases at high density and with no gas injection (wall fuelled discharges), RI-like modes are reported with a modest increase in confinement. Despite the lack of core fuelling on Tore Supra, high densities during ICRH pulses can be achieved with Greenwald fractions f(G) = 1. Compatibility with both ICRH and LH is demonstrated.

Additional information

Authors: GHENDRIH P, CEA Cadarache, D?partment de Recherche sur la Fusion Contrtl?e, St-Paul-Lez-Durance (FR)
Bibliographic Reference: An article published in: Nuclear Fusion, Vol.41, No.10 (2001), pp.1401-1412
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