Ideal MHD stability of plasmas with toroidal helical and vertical field coils
A simple configuration consisting in a set of toroidal, helical and vertical field coils is used to calculate free boundary equilibria with nonzero plasma current and approximately helical plasma boundary. The amount of helical boundary deformation is controlled by the ratio of the current in the helical field coils to the current in the toroidal field coils.
Bibliographic Reference: Article: Fusion Theory Proceedings of the Seventh European Fusion Theory Conference, Forschungszentrum Jülich (1998) pp. 251-254
Record Number: 199810834 / Last updated on: 1998-07-20
Original language: en
Available languages: en