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Return To: Session FTP - Fusion Technology (Wednesday, 21 October)
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M. Porkolab , P. T. Bonoli , J. Ramos ,
J. Schultz
MIT Plasma Science and Fusion Center, Cambridge, Massachusetts
02139, USA
W. N. Nevins
Lawrence Livermore National Laboratory, PO Bo x 808 (L-637),
Livermore, CA 94551, USA
Abstract
A new reduced size ITER-RC superconducting tokamak concept is
proposed with the goals of studying burn physics either in an inductively
driven standard tokamak (ST) mode of operation, or in a quasi-steady state
advanced tokamak (AT) mode sustained by non-inductive means. This is
achieved by reducing the radiation shield thickness protecting the
superconducting magnet by 0.34 m relative to ITER and limiting the burn mode
of operation to pulse lengths as allowed by the TF coil warming up to the
current sharing temperature. High gain (
) burn physics studies
in a reversed shear equilibrium, sustained by RF and NB current drive
techniques, may be obtained.
IAEA 1999