Calculations of Settings in the Protection and Blocking Circuits of the Power Supply System of Electromagnetic Windings and the Duration of Plasma Discharges in T-15MD Tokamak

被引：1

作者：

Khvostenko, P. P. ^{[1
]}

Bondarchuk, E. N. ^{[2
]}

Kavin, A. A. ^{[2
]}

Leonov, V. M. ^{[1
]}

Chudnovskiy, A. N. ^{[1
]}

机构：

[1] Natl Res Ctr, Kurchatov Inst, Moscow 123098, Russia

[2] JSC NIIEFA, St Petersburg 196641, Russia

来源：

PHYSICS OF ATOMIC NUCLEI | 2021年 / 84卷 / 07期

关键词：

tokamak; plasma; divertor configuration; magnetic system; toroidal and poloidal coils; power supply system; protection and blocking system; water cooling system; discharge duration; calculation program; MHD;

D O I：

10.1134/S1063778821070061

中图分类号：

O57 [原子核物理学、高能物理学];

学科分类号：

070202 ;

摘要：

At the present time, the construction of the T-15MD Tokamak is being completed at the National Research Center Kurchatov Institute. The magnet system of the Tokamak T-15MD should provide generation and confinement of the hot plasma in the divertor configuration. The design plasma parameters are as follows: major radius of 1.48 m, minor radius of 0.67 m, elongation of 1.7-1.9 and triangularity of 0.3-0.4, plasma current of 2 MA, toroidal magnetic field on the plasma axis of 2 T. The electromagnetic system includes toroidal and poloidal coils. The installation will be equipped with the auxiliary plasma heating and current drive in quasi-stationary discharges lasting hundreds of seconds. Scenarios of quasi-stationary plasma discharges are determined by the capabilities of the electromagnetic system to create and maintain an equilibrium magnetic configuration of the plasma column. Trouble-free operation of the power supply is provided by the protection and blocking system. This work is devoted to calculations of the maximum duration of currents in toroidal and poloidal windings in order to avoid their overheating, as well as the duration and scenarios of quasi-stationary plasma discharges.

引用

页码：1332 / 1341

页数：10

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