The T-15 Fusion Products Study: Plans and Diagnostics View Full Text


Ontology type: schema:Chapter     


Chapter Info

DATE

1996

AUTHORS

V. S. Zaveriaev , V. D. Maisyukov , A. V. Khramenkov , V. G. Merezhkin , S. V. Popovichev , S. V. Trusillo

ABSTRACT

The Tokamak T-15 was designed and constructed in the end of 80’s in the Kurchatov Institute, Tokamak T-15 is one of the comparatively large machines in the world and it is suitable for a number of important studies concerning alpha particle problem. It is a classical tokamak with a circular cross section and without a diverter. The main machine parameters and the expected plasma parameters are following: R=243 cm, a=70 cm, -Btor=1.5–3 T, Ip=0.5–1.5MA, Ti(0)=l–2keV (Ohmic regime), shot duration is 5 s and more. The T-15 has 24 superconducting toroidal magnetic coils, the ripple at the plasma edge is about 0.7%. The main feature of machine is a planned additional Electron Cyclotron Resonance Heating (ECRH), 6–8 MW of absorbed power. The Neutral Beam Injection (NBI) Heating will be also available with a beam energy 40 keV (in future up to 80 keV) and the total beam power about 6–8 MW. More... »

PAGES

625-633

Book

TITLE

Diagnostics for Experimental Thermonuclear Fusion Reactors

ISBN

978-1-4613-8020-7
978-1-4613-0369-5

Identifiers

URI

http://scigraph.springernature.com/pub.10.1007/978-1-4613-0369-5_78

DOI

http://dx.doi.org/10.1007/978-1-4613-0369-5_78

DIMENSIONS

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