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Abstract
Concept of the Joint Upgraded Spherical Tokamak (JUST) – a multifunctional facility for working out of physical regimes (discharge scenarios, mode of buming, limits of working plasma parameters), promising divertor devices and testing of reactor materials is presented.
The proposed JUST parameters are: R = 1.8 m; a = 1.2 m; A = 1.5; k = 2.3; Bto = 2.1 T; Ip = 10-14 MA, P AUX = 15-20 MW; P FUS∼ 50 MW, tburn ∼ 10 s.
Results of the preliminary study of the tokamak design are presented. Wide use of Russian industrial experience in creation of super-powerful electro-generators and advanced technologies of airspace complexes is planned.