DocumentCode
2059161
Title
Center conductor design for the compact spherical torus reactor
Author
Snead, L.L. ; Steiner, D.
Author_Institution
Rensselaer Polytech. Inst., Troy, NY, USA
fYear
1989
fDate
2-6 Oct 1989
Firstpage
890
Abstract
The spherical torus (ST) concept has been previously proposed as a means of achieving high plasma β at low aspect ratio and low magnetic field. The center post performance is presently analyzed as a function of operating time for a representative spherical torus reactor with the following parameters: (1) 2000-MW thermal power; (2) 1.45-m major radius; (3) 1.17-m minor radius (A =1.22); (4) elongation, 2.2; and (5) toroidal field on axis 0.824 T. The key engineering issues for the center post design are the resistive loss, magnet coolant velocity, conductor temperatures, and physical erosion of the magnet by the coolant flow. Specifically, resistive loss can be as high as 111 MW, with peak conductor temperature under 300°C, requiring a peak coolant velocity of approximately 12 m/s
Keywords
fusion reactor theory and design; 0.824 T; 1.17 m; 111 MW; 2000 MW; 300 degC; center post performance; centre conductor; compact spherical torus reactor; conductor temperatures; design; erosion; magnet; magnet coolant velocity; operating time; resistive loss; thermal power; Conductors; Coolants; Inductors; Magnetic analysis; Performance analysis; Performance loss; Plasma temperature; Thermal conductivity; Thermal engineering; Toroidal magnetic fields;
fLanguage
English
Publisher
ieee
Conference_Titel
Fusion Engineering, 1989. Proceedings., IEEE Thirteenth Symposium on
Conference_Location
Knoxville, TN
Type
conf
DOI
10.1109/FUSION.1989.102361
Filename
102361
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