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Spherical torus [electronic resource] : an approach to compact fusion at low field. Initial ignition assessments

Published
Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1985.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Physical Description
Pages: 7 : digital, PDF file
Additional Creators
Oak Ridge National Laboratory and United States. Department of Energy. Office of Scientific and Technical Information
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Summary
Initial assessments of ignition devices based on the spherical torus concept suggest that an ignition spherical torus (IST) can be highly cost-effective and exceptionally small in unit size. Assuming advanced methods of current drive and confinement and beta scalings with plasma current, a D-T IST with a toroidal field of 2 to 3 T is estimated to have a major radius ranging from 1 m to 1.6 m, and a fusion power less than 60 MW. For the nominal IST (at 2 T and 1.6 m), the direct cost of the nuclear island is estimated to be about $120 M with a total direct cost about $340 M in mid-1984 dollars based on the Fusion Engineering Design Center (FEDC) cost algorithm. For ISTs with higher field and smaller size (e.g., at 3 T and 1 m), further reductions of the cost of the nuclear island are estimated. In case of confinement scaling with the plasma size only, strong plasma paramagnetism (self-generated magnetic field) in the spherical torus may still serve to compensate for the projected confinement shortfall.
Report Numbers
E 1.99:conf-850310-108
conf-850310-108
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Note
Published through SciTech Connect.
01/01/1985.
"conf-850310-108"
"DE85012890"
6. topical meeting on the technology of fusion energy, San Francisco, CA, USA, 3 Mar 1985.
Haines, J.R.; Hamilton, W.R.; Reid, R.L.; Gorker, G.E.; Strickler, D.J.; Peng, Y.K.M.; Lee, V.D.; Riemer, B.W.; Kalsi, S.S.; Borowski, S.K.
Funding Information
AC05-84OR21400
View MARC record | catkey: 14748156