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Abstract

Optimised shear (OS) experiments in JET can generate an internal transport barrier (ITB) during a high power heating phase early in the plasma discharge. A strong link is generally observed between the formation of the barrier and the location of an integer q magnetic surface within a low magnetic shear (s = r/q(dq/dr)) region of the plasma. However, if the q-profile for such experiments is modified by applying lower hybrid heating and current drive (LHCD) before the main heating pulse, to provide a region of reduced or negative magnetic shear in the plasma core, ITBs can be formed the location of which does not exhibit any apparent association with a particular internal magnetic surface. Initial results suggest that q-profile modification using an LHCD prelude can also be used to reduce the heating power level required for ITB generation.

Additional information

Authors: CHALLIS C D ET AL, UKAEA Fusion Centre, Abingdon, Oxon (GB);CONWAY G D, Max-Planck-Institut f?r Plasmaphysik, Garching (DE);SIPS A C C, Max-Planck-Institut f?r Plasmaphysik, Garching (DE);GORMEZANO C, ENEA sulla Fusione, Centro Ricerche Energia ENEA Frascati, Rome (IT);PODDA S, ENEA sulla Fusione, Centro Ricerche Energia ENEA Frascati, Rome (IT);JOFFRIN E, CEA Cadarache, D?partment de Recherche sur la Fusion Contrtl?e, St-Paul-Lez-Durance (FR);MAZON D, CEA Cadarache, D?partment de Recherche sur la Fusion Contrtl?e, St-Paul-Lez-Durance (FR);RIMINI F G, CEA Cadarache, D?partment de Recherche sur la Fusion Contrtl?e, St-Paul-Lez-Durance (FR);STRATTON B C, University of Princeton, Princeton Plasma Physics Laboratory, NJ (US);TESTA D, Massachusetts Institute of Technology, Plasma Science and Fusion Center, Cambridge (US)
Bibliographic Reference: An article published in: Plasma Physics and Controlled Fusion, Vol.43 (2001), pp.861-879
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