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U.S. Department of Energy
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SLPX: superconducting long-pulse experiment

Conference ·
OSTI ID:6412629
The principal objectives of the SLPX--Superconducting Long-Pulse Experiment--are to demonstrate quasi-steady operation of 3 to 5 MA hydrogen and deuterium plasmas at high temperature and high thermal wall loading, and to develop reliable operation of a prototypical reactor magnetics systems featuring a toroidal assembly of high-field niobium-tin coils. This report summarizes the results of an engineering scoping study for the SLPX. A range of sizes has been investigated, from a TF (toroidal-field) coil aperture of 2.6 m x 3.65 m, to an aperture of 3.1 m x 4.8 m, and with a maximum field at the Nb/sub 3/Sn conductor of 10 to 12 Tesla. The poloidal-field magnetics system utilizes superconducting ohmic-heating and d.c. EF coils located outside the TF coils, together with normal-conducting EF and divertor coils located inside the TF coils. For the largest embodiment, the D-shaped plasma in hydrogen operation has major radius = 3.6 m, half-width = 0.90 m, elongation < 1.5, and B = 7,2 T. Maximum plasma current of 5.0 MA can be maintained for a 30-s flat-top when Z/sub eff/approximately 1. A single-null poloidal magnetic divertor disposes of particles and heat diffusing out of the current channel, thereby helping to insure the feasibility of quasi-steady operation.
Research Organization:
Princeton Univ., NJ (USA). Plasma Physics Lab.
DOE Contract Number:
EY-76-C-02-3073
OSTI ID:
6412629
Report Number(s):
PPPL-1481; CONF-780966-1
Country of Publication:
United States
Language:
English