EC heating and current drive studies during current ramp-up in Tore-Supra
Experiments aimed at tailoring the plasma current profile by heating and current drive during the ramp-up phase of a discharge have been carried out in most Tokamak devices, using all the available heating and CD systems from Neutral Beam Injection (NBI) to Lower Hybrid Current Drive (LHCD), Ion Cyclotron Resonance Heating (ICRH) and Electron Cyclotron Resonance Heating (ECRH). The ultimate objective of such experiments is the production of enhanced central confinement with flat or reversed magnetic shear. In Tore-Supra, encouraging results were already obtained with a combination of LHCD, ICRH and FWEH before a major vessel refurbishment. Recently, these studies have been resumed and given a new impetus by the installation of a highly flexible, although power limited, 118GHz Electron Cyclotron Heating and Current Drive (ECH/CD) system.
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: email@example.com
Record Number: 200417627 / Last updated on: 2004-07-13
Original language: en
Available languages: en