The T-15 Fusion Products Study: Plans and Diagnostics

Autor: A. V. Khramenkov, S. V. Trusillo, V. G. Merezhkin, S.V. Popovichev, V. S. Zaveriaev, V. D. Maisyukov
Rok vydání: 1996
Předmět:
Zdroj: Diagnostics for Experimental Thermonuclear Fusion Reactors ISBN: 9781461380207
DOI: 10.1007/978-1-4613-0369-5_78
Popis: 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.
Databáze: OpenAIRE