Characteristics of major plasma discharge disruption in the Globus-M spherical tokamak

Journal Article · Sat Apr 15 00:00:00 EDT 2017 · Plasma Physics Reports

DOI:https://doi.org/10.1134/S1063780X17040110· OSTI ID:22760350

Gusev, V. K.; Iblyaminova, A. D. ^[1]; Kavin, A. A.; Kamenshchikov, S. N. ^[2]; Kurskiev, G. S. ^[1]; Lobanov, K. M.; Mineev, A. B. ^[2]; Petrov, Yu. V.; Tolstyakov, S. Yu. ^[1]

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1. Russian Academy of Sciences, Ioffe Institute (Russian Federation)
2. Efremov Institute of Electrophysical Apparatus (Russian Federation)

The characteristics of the major disruption of plasma discharges in the Globus-M spherical tokamak are analyzed. The process of current quench is accompanied by the loss of the vertical stability of the plasma column. The plasma boundary during the disruption is reconstructed using the algorithm of movable filaments. The plasma current decay is preceded by thermal quench, during which the profiles of the temperature and electron density were measured. The data on the time of disruption, the plasma current quench rate, and the toroidal current induced in the tokamak vessel are compared for hydrogen and deuterium plasmas. It is shown that the disruption characteristics depend weakly on the ion mass and the current induced in the vessel increases with the disruption time. The decay rate of the plasma toroidal magnetic flux during the disruption is determined using diamagnetic measurements. Such a decay is a source of the poloidal current induced in the vessel; it may also cause poloidal halo currents.

• OSTI ID: 22760350
• Journal Information: Plasma Physics Reports, Vol. 43, Issue 4; Other Information: Copyright (c) 2017 Pleiades Publishing, Ltd.; Country of input: International Atomic Energy Agency (IAEA); ISSN 1063-780X
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
ALGORITHMS
DEUTERIUM
ELECTRON DENSITY
FILAMENTS
HYDROGEN
MAGNETIC FLUX
PLASMA
SPHERICAL CONFIGURATION
TOKAMAK DEVICES