Abstract
Plasma confinement schemes may be viewed as being related through evolutionary trends. The mirror machine represents an open magnetic geometry which was superseded by the closed magnetized toroidal geometries. Additionally, these toroidal geometries evolved by transference of coil current (Stellarators) to plasma currents (tokamaks). The Stellarator has essentially no plasma current, while the tokamak (as represented by ITER in Figure 1) has a major toroidal current. The Spheromak goes further and successfully incorporates a significant fraction of the poloidal current of the tokamak’s toroidal field coils as a plasma current.
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© 1997 Springer Science+Business Media New York
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Koloc, P.M. (1997). Fusion Implications of Free-Floating PlasmakTM Magnetoplasmoids. In: Panarella, E. (eds) Current Trends in International Fusion Research. Springer, Boston, MA. https://doi.org/10.1007/978-1-4615-5867-5_31
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DOI: https://doi.org/10.1007/978-1-4615-5867-5_31
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