Global ideal MHD stability of plasmas with toroidal, helical and vertical field coils
A simple configuration that consists of a set of toroidal, helical and vertical field coils is used to calculate free boundary equilibria with nonzero plasma current and approximately helically symmetric plasma boundary shape. 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: Plasma Physics and Controlled Fusion (1998)
Record Number: 199810425 / Last updated on: 1998-03-31
Original language: en
Available languages: en