Experimental Thermonuclear Installation Tokamak T-15MD

Abstract

At present, the T-15MD tokamak is being built and its supporting technological systems are being modernized at the National Research Center Kurchatov Institute in the framework of the federal target-oriented program “New Generation Nuclear Power Technologies in 2010–2015 and in Prospect to 2020.” The T-15MD magnet system is to ensure producing and confinement of hot plasma in the divertor configuration. The T-5MD plasma parameters are as follows: major radius R0 = 1.48 m, minor radius a = 0.67 m, elongation k95 = 1.7–1.9, triangularity δ95 = 0.3–0.4, plasma current Ip = 2 MA, and toroidal magnetic field at the plasma axis BTO = 2 T. The tokamak will be equipped with an auxiliary plasma heating and current drive system (Paux = 15–20 MW), which will enable achieving a high plasma temperature (Ti ~ Te of 5–9 keV) and a plasma density (ne ≈ 1020 m–3) during a discharge with a pulse duration of up to 30 s. The magnet system includes a toroidal winding and a poloidal magnet system. The poloidal magnet system may generate the one- or two-null divertor magnetic configuration. The power supply system provides the necessary current scenarios in the magnet system windings. The T-15MD magnet together with the vacuum vessel was pre-assembled at the NPO GKMP Ltd. plant in Bryansk. All elements of the magnet system and the vacuum vessel are delivered to the National Research Center Kurchatov Institute in Moscow, where the T-15MD tokamak will be assembled. The technological systems are to be reconstructed by the end of 2019. The physical start-up of the T-15MD is scheduled for December 2020.