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

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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.

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© 1986 Springer Science+Business Media New York

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van Houtte, D. et al. (1986). Current Ramping and Profile Shaping with Lower Hybrid Current Drive in the Petula-B Tokamak. In: Knoepfel, H. (eds) Tokamak Start-up. Ettore Majorana International Science Series. Springer, Boston, MA. https://doi.org/10.1007/978-1-4757-1889-8_14

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  • DOI: https://doi.org/10.1007/978-1-4757-1889-8_14

  • Publisher Name: Springer, Boston, MA

  • Print ISBN: 978-1-4757-1891-1

  • Online ISBN: 978-1-4757-1889-8

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