Speaker
Dr
Petr Khvostenko
(NRC"Kurchatov Institute")
Description
Presently, the Tokamak T-15MD is being built. The magnet system of the Tokamak T-15MD will obtain and confine the hot plasma in the divertor configuration. Plasma parameters are a major radius of 1.48 m, a minor radius of 0.67 m, an elongation of 1.7-1.9 and a triangularity of 0.3-0.4. Tokamak T-15MD will equipped with the auxiliary plasma heating and current drive (Paux =15 - 20 MW) systems. One of the main tasks of experimental study program on T-15MD is the obtaining of physical and technological data needed both for ITER project support and fusion neutron source creation. The manufacturing of the Tokamak T-15MD magnet system and of vacuum chamber shell was completed. At present time, the preliminary assembly of the magnet system is conducted at the plant in Bryansk. The disassembly of the superconducting tokamak T-15 should be finished in middle of 2016 and T-15MD assembling must begin in NRC “Kurchatov Institute” in the end of 2016. Status of engineering systems modernization is presented too.
| Country or International Organization | Russian Federation |
|---|---|
| Paper Number | FIP/P7-40 |
Primary author
Dr
Petr Khvostenko
(NRC"Kurchatov Institute")
Co-authors
Dr
Alexei Sushkov
(NRC"Kurchatov Institute")
Dr
Eduard Bondarchuk
(JSC"NIIEFA")
Dr
Gennady Notkin
(NRC"Kurchatov Institute")
Dr
Igor Anashkin
(NRC"Kurchatov Institute")
Dr
Igor Levin
(NRC"Kurchatov Institute")
Dr
Mikhail Sokolov
(NRC"Kurchaton Institute")
Mr
Nikolay Injutin
(GKMP group)
Prof.
Oleg Filatov
(JSC"NIIEFA")
Prof.
Valery Belyakov
(JSC"NIIEFA")
Dr
Vyacheslav Krylov
(JSC"NIIEFA")
