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research article

On locating the poloidal field coils for tokamak vertical position control

Lister, J. B.  
•
Martin, Y.  
•
Moret, J. M.  
1996
Nuclear Fusion

The TCV tokamak has 16 poloidal field coils for plasma shaping, distributed around the vacuum vessel. Experiments are described that determine the relative merits of different coil positions for controlling the unstable vertical movement of elongated plasmas. The results show over an order of magnitude variation in the amplitude of the plasma vertical position response to voltages applied to the different coils. The currents induced in the vessel, the required reactive feedback power and the ohmic power dissipated in the vessel all depend strongly on the coil location. Coils on the inboard, small major radius, side of the vacuum vessel are particularly effective at producing fast vertical displacements. A comparison of the results of two separate experiments with the predictions of a rigid current displacement model shows that the relative merits of the different coil positions are adequately explained by this model.

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Type
research article
DOI
10.1088/0029-5515/36/11/I08
Author(s)
Lister, J. B.  
Martin, Y.  
Moret, J. M.  
Date Issued

1996

Publisher

IOP Publishing Ltd

Published in
Nuclear Fusion
Volume

36

Issue

11

Start page

1547

End page

1560

Editorial or Peer reviewed

REVIEWED

Written at

EPFL

EPFL units
CRPP  
SPC  
Available on Infoscience
April 16, 2008
Use this identifier to reference this record
https://infoscience.epfl.ch/handle/20.500.14299/21374
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