Just: Concept development and status

Just: Concept development and status

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 a...

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Veröffentlicht in:Plasma devices and operations 1997-07, Vol.5 (2), p.99-126
Hauptverfasser: Azizov, E. A., Dvorkin, N. Ya, Filatov, O. G., Gardymov, G. P., Garypov, I. S., Golant, V. E., Glukhikh, V. A., Ioganson, V. I., Kady-ogly, I. A., Khayrutdinov, R. R., Krylov, V. A., Leykin, I. N., Lukash, V. E., Mineev, A. B., Notkin, G. E., Polevoy, A. R., Shakhovets, K. G., Tsaun, S. V., Velikhov, E. P., Vinogradovand, N. I., Vorobiev, G. M.
Format: Artikel
Sprache:eng
Schlagworte:
conceptual design
fusion plasma
low aspect ratio tokamak
spherical tokamak
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Zusammenfassung: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; B to = 2.1 T; I p = 10-14 MA, P AUX = 15-20 MW; P FUS∼ 50 MW, t burn ∼ 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.
ISSN:1051-9998
1029-4929
DOI:10.1080/10519999708228023