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The "hybrid" regime is a candidate scenario for ITER, with a potential for longer inductive pulse at high fusion gain. Compared to conventional H-mode, these "hybrid" discharges feature improved confinement and beta, an improved long-pulse capability, as well as q (min) maintained at or slightly above 1. This particular shape of the q-profile has been attributed to a specific MHD activity, though this explanation is still controversed. In this work, we discuss the results of resistive current diffusion applied to those regimes. We also address the heat transport in the Hybrid regime, in order to investigate the origin of its improved confinement properties. Transport modelling of such discharges is just a starting activity, and remains a challenge for the models available today. A multi-machine comparison is carried out here, in order to test the commonality of the transport physics.

Additional information

Authors: IMBEAUX F (EDITOR), Departement de Recherches sur la Fusion Controlee, Association Euratom-CEA sur la Fusion, CEA Cadarache, Saint-Paul-lez-Durance (FR)
Bibliographic Reference: An oral paper given at: 31st EPS Conference on Controlled Fusion and Plasma Physics Organised by: CCLRC Rutherford Appleton Laboratory (GB); EURATOM/UKAEA Fusion Association (GB); Imperial College London Held at: Imperial College London (
Availability: Available from Association EURATOM-CEA, Departement de Recherches sur la Fusion Controlee, CEA Cadarache, F-13108 St Paul-Lez-Durance, France Tel: (+33) 4 42 25 70 01; Fax: (+33) 4 42 25 64 21 E-mail:
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