DocumentCode
3002056
Title
Spherical stellarator approach
Author
Moroz, P.E.
Author_Institution
Wisconsin Univ., Madison, WI, USA
fYear
1996
fDate
3-5 June 1996
Firstpage
190
Abstract
Summary form only given. In this report, we present the results on the novel ultra low aspect ratio stellarator system with A=1.05-2, that can be called a spherical stellarator (SS) in analogy with the spherical tokamak (ST) concept. Coil configuration of SS features the central stack and differs from that of ST by inclination of external parts of the toroidal field coils. A few potential advantages of the SS configuration, over other approaches in magnetic confinement fusion, can be summarized as follows: (a) very compact design offering the low cost approach, (b) closed vacuum flux surfaces and no need, in principle, in the ohmic current transformer, (c) simple modular coil system, (d) easy access to the plasma, (e) more area for heat removal and the tritium breeding blanket in a reactor, (f) simple toroidally symmetric divertor, (g) enough space between the central stack and the plasma surface to put the blanket and protect the stack from intense fluxes of particles, heat and neutrons.
Keywords
stellarators; T breeding blanket; central stack; closed vacuum flux surfaces; coil configuration; heat flux; heat removal; magnetic confinement fusion; modular coil system; neutron flux; ohmic current transformer; particle flux; spherical stellarator approach; spherical tokamak; toroidal field coils; toroidally symmetric divertor; ultra low aspect ratio stellarator; very compact design; Coils; Costs; Current transformers; Fusion reactor design; Inductors; Magnetic confinement; Plasma confinement; Space heating; Tokamaks; Vacuum systems;
fLanguage
English
Publisher
ieee
Conference_Titel
Plasma Science, 1996. IEEE Conference Record - Abstracts., 1996 IEEE International Conference on
Conference_Location
Boston, MA, USA
ISSN
0730-9244
Print_ISBN
0-7803-3322-5
Type
conf
DOI
10.1109/PLASMA.1996.550832
Filename
550832
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