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. When this ratio is increased, the (m, n) = (2, 1) external kink is stabilized at beta approximately equal to 1% for inverse rotational transform profiles in the region q < 2 and an aspect ratio A approximately equal to 10.
Bibliographic Reference: Article: Plasma Physics and Controlled Fusion (1998)
Record Number: 199810716 / Last updated on: 1998-06-08
Original language: en
Available languages: en