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.
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© 1996 Plenum Press, New York
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Zaveriaev, V.S., Maisyukov, V.D., Khramenkov, A.V., Merezhkin, V.G., Popovichev, S.V., Trusillo, S.V. (1996). The T-15 Fusion Products Study: Plans and Diagnostics. In: Stott, P.E., Gorini, G., Sindoni, E. (eds) Diagnostics for Experimental Thermonuclear Fusion Reactors. Springer, Boston, MA. https://doi.org/10.1007/978-1-4613-0369-5_78
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DOI: https://doi.org/10.1007/978-1-4613-0369-5_78
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