MHD-driven internal coils for tokamak divertor operation

Author

Tekula, M.S. ; Bromberg, L.

Author_Institution

MRAT, Sanford, ME, USA

Volume

2

fYear

1993

fDate

11-15 Oct 1993

Firstpage

1134

Abstract

In this paper a system evaluation of MHD coils for divertor coil and as passive stabilizer against plasma vertical displacements is presented. The advantages of placing the poloidal field coils are quantified. Large decreases in the conventional divertor coil current and associated torques in the toroidal field system are obtained when the current in the MHD coil is as little as 1 MA. To generate this current, flows of ~1 m/s are needed. The sensitivity of the separatrix to changing plasma or external coil currents is evaluated. Finally, the use of low activation metals in in the coil segments is evaluated

Keywords

fusion reactor materials; fusion reactors; plasma instability; plasma magnetohydrodynamics; 1 MA; MHD-driven internal coils; coil segments; divertor coil current; external coil currents; low activation metals; passive stabilizer; plasma currents; plasma vertical displacements; poloidal field coils; separatrix; tokamak divertor operation; toroidal field system torques; Coils; Conductors; Copper; Lithium; Magnetohydrodynamics; Physics; Plasmas; Tokamaks; Toroidal magnetic fields; Voltage;

fLanguage

English

Publisher

ieee

Conference_Titel

Fusion Engineering, 1993., 15th IEEE/NPSS Symposium on

Conference_Location

Hyannis, MA

Print_ISBN

0-7803-1412-3

Type

conf

DOI

10.1109/FUSION.1993.518523

Filename

518523