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Return To: Session FTP - Fusion Technology (Wednesday, 21 October)
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(This paper was rapporteured in lecture FT1/3)
J. Kißlinger , C. D. Beidler ,
E. Harmeyer , F. Herrnegger , H. Wobig , W. Maurer
Max-Planck-Institut für Plasmaphysik,
EURATOM-Ass. D-85748 Garching, Federal Republic of Germany
Abstract
The magnetic fields of Advanced Stellarator configurations can be
generated by 3D-shaped modular coils . The shapes of these coils are calculated
for a given Helias field configuration. This method allows one to optimize the
field according to criteria of optimum plasma performance in a preceding
step. The coil system of the Helias reactor considered here is roughly four
times as large as the Wendelstein 7-X device and produces about the same field
configuration. The maximum field strength of 10T at the coils is small enough
to use NbTi superconductors at 1.8K. The `cable-in-conduit ' conductor is
designed for a nominal current of 37.5 kA and has an aluminium alloy jacket.
In order to reduce the maximum field on the conductor, the winding pack of
each coil is split into two rectangular parts with 9x16 turns each. These two
sub-winding packs are in a common enclosing coil housing with a central web
for mechanical stiffening. The coils are mutually connected by support
elements forming a toroidal vault. Finite-element calculations show that the
coils tend to become more circular and planar under the magnetic force load
and require local reinforcements of the coil housings.
IAEA 1999