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          Institute: MPI für Plasmaphysik     Collection: Conference Papers     Display Documents

ID: 60023.0, MPI für Plasmaphysik / Conference Papers
Equilibria and stability of JET discharges with zero core current density
Authors:Stratton, B. C.; Hawkes, N. C.; Huysmans, G. T. A.; Breslau, J. A.; Zakharov, L. E.; Alper, B.; Budny, R. V.; Challis, C. D.; De Angelis, R.; Drozdov, V.; Fenzi, C.; Giroud, C.; Hender, T. C.; Hobirk, J.; Jardin, S. C.; Joffrin, E.; Lomas, P. J.; Lotte, P.; Mailloux, J.; Park, W.; Rachlew, E.; Reyes-Cortes, S.; Solano, E.; Tala, T.; Zastrow, K.-D.; EFDA-JET Contributors
Publisher:International Atomic Energy Agency
Place of Publication:Vienna
Date of Publication (YYYY-MM-DD):2003
Title of Proceedings:Fusion Energy 2002
Sequence Number:EX/C3-1Rb
Physical Description:CD-ROM
Name of Conference/Meeting:19th Fusion Energy Conference
Place of Conference/Meeting:Lyon (FR)
(Start) Date of Conference/Meeting
End Date of Conference/Meeting 
Review Status:Internal review
Audience:Experts Only
Abstract / Description:Injection of Lower Hybrid Heating and Current Drive (LHCD) into the current ramp-up phase of JET discharges has produced extremely reversed q-profiles characterized by a core region of near zero current density (within Motional Stark Effect diagnostic measurement errors). Non-inductive, off-axis co-current drive induces a back electromotive force inside the non-inductive current radius that drives a negative current in the plasma core. The core current density does not go negative, although current diffusion calculations indicate that there is sufficient LHCD to cause this. A possible explanation of the core current density clamping near zero is that MHD instabilities redistribute the core current soon after it goes negative. This is seen in reduced MHD simulations in cylindrical geometry and nonlinear resistive MHD simulations in toroidal geometry which predict that these discharges undergo n=0 reconnection events which clamp the core current near zero. Understanding the physics of the current hole in present devices is important for enabling predictions of current profile evolution in next step facilities with strong non-inductive current drive.
External Publication Status:published
Document Type:Conference-Paper
Communicated by:N. N.
Affiliations:MPI für Plasmaphysik/Tokamak Theory (TOK)
External Affiliations:Princeton Plasma Physics Laboratory, Princeton, NJ, USA; Euratom/UKAEA Fusion Association, Culham Science Centre, Abingdon, UK; Association Euratom-CEA, Cadarache, France; Association Euratom-ENEA sulla Fusione, CRE Frascati, Roma, Italy; FOM-Institut voor Plasmafysica "Rijnhiuzen", Associatie EURATOM-FOM, Niewgen, The Netherlands; KTH-Physics, SCFAB, VR Association, Stockholm, Sweden; Euratom/IST Association, Centro de Fusao Nuclear, Lisboa, Portugal; Association EURATOM-CIEMAT para Fusion, CIEMAT, Spain and EFDA CSU JET, Abingdon, UK; Association Euratom-TEKES, VTT Chemical Technology, Espoo, Finland
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