The superconducting magnet system for the Tokamak Physics experiment (
TPX) will be the first all superconducting magnet system for a Tokamak
, where the poloidal field coils, in addition to the toroidal field co
ils are superconducting. The magnet system is designed to operate in a
steady slate mode, and to initiate the plasma discharge ohmically. Th
e toroidal field system provides a peak field of 4.0 Tesla on the plas
ma axis at a plasma major radius of 2.25 m. The peak field on the niob
ium 3-tin, cable-in-conduit (CIC) conductor is 8.4 Tesla for the 16 to
roidal field coils. The toroidal field coils must absorb approximately
5 kW due to nuclear heating, eddy currents, and other sources. The po
loidal field system provides a total of 18 volt seconds to initiate th
e plasma and drive a plasma current up to 2 MA. The poloidal field sys
tem consists of 14 individual coils which are arranged symmetrically a
bove and below the horizontal mid plane. Four pairs of coils make up t
he central solenoid, and three pairs of poloidal ring coils complete t
he system. The poloidal field coils all use a cable-in-conduit conduct
or, using either niobium 3-tin (NB3Sn) or niobium titanium (NbTi) supe
rconducting strands depending on the operating conditions for that coi
l. All of the coils are cooled by flowing supercritical helium, with i
nlet and outlet connections made on each double pancake. The supercond
ucting magnet system has gone through a conceptual design review, and
is in preliminary design started by the LLNL/MIT/PPPL collaboration. A
number of changes have been made in the design since the conceptual d
esign review, and are described in this paper. The majority of the des
ign and all fabrication of the magnet system will be accomplished by i
ndustry, which will shortly be taking over the preliminary design. The
magnet system is expected to be completed in early 2000.