| Article ID | Journal | Published Year | Pages | File Type |
|---|---|---|---|---|
| 6745593 | Fusion Engineering and Design | 2015 | 4 Pages |
Abstract
Presently, the Tokamak T-15 is being upgraded. The magnet system of the Tokamak T-15 upgrade will obtain and confine the hot plasma in the divertor configuration. Plasma parameters are a major radius of 1.48Â m, a minor radius of 0.67Â m, an elongation of 1.7-1.9 and a triangularity of 0.3-0.4. The magnet system includes the toroidal winding and the poloidal magnet system. The poloidal magnet system generates the divertor with single null and double null magnetic configurations. The power supply system provides the necessary current scenarios in the windings of the magnet system. All elements of the magnet system will be manufactured by the end of 2015. The Tokamak T-15 upgrade should begin operations in 2016.
Keywords
Related Topics
Physical Sciences and Engineering
Energy
Energy Engineering and Power Technology
Authors
P.P. Khvostenko, E.A. Azizov, D.E. Alfimov, V.A. Belyakov, E.N. Bondarchuk, A.N. Chudnovsky, V.N. Dokuka, A.A. Kavin, R.R. Khayrutdinov, M.V. Khokhlov, B.A. Kitaev, S.V. Krasnov, I.I. Maximova, A.N. Labusov, V.E. Lukash, A.B. Mineev, V.P. Muratov,