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Current Ramping and Profile Shaping with Lower Hybrid Current Drive in the Petula-B Tokamak

  • D. van Houtte
  • P. Blanc
  • G. Briffod
  • P. Chabert
  • M. Clément
  • C. Gormezano
  • W. Hess
  • G. T. Hoang
  • G. Ichtchenko
  • G. Melin
  • A. Panzarella
  • F. Parlange
  • J. C. Vallet
Part of the Ettore Majorana International Science Series book series (EMISS)

Abstract

Up to recent years, the conventional inductively driven tokamak was the basis for a potential thermonuclear reactor. In tokamak devices, the magnetic confinement of the plasma is obtained by combining a transverse magnetic field with a toroidal current acting as the secondary in a transformer circuit 1. Consequently the toroidal plasma current cannot be driven continuously with the result being that a tokamak is a device which suffers from thermal and mechanical stresses and fatigue associated with a pulsed cycle 2. In addition, the ohmic heating (OH) coils system is very complex and occupies too much space. In order to overcome these major obstacles towards the future existence of a reactor, special attention has been given these last years to non inductive current drive concept such as Neutral Beam or RF driven mechanisms.

Keywords

Current Drive Plasma Current Ohmic Heating Poloidal Field Loop Voltage 
These keywords were added by machine and not by the authors. This process is experimental and the keywords may be updated as the learning algorithm improves.

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Copyright information

© Springer Science+Business Media New York 1986

Authors and Affiliations

  • D. van Houtte
    • 1
  • P. Blanc
    • 1
  • G. Briffod
    • 1
  • P. Chabert
    • 1
  • M. Clément
    • 1
  • C. Gormezano
    • 1
  • W. Hess
    • 1
  • G. T. Hoang
    • 1
  • G. Ichtchenko
    • 1
  • G. Melin
    • 1
  • A. Panzarella
    • 1
  • F. Parlange
    • 1
  • J. C. Vallet
    • 1
  1. 1.CENGAssociation EURATOM-CEA DRFCGrenobleFrance

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