MEPHIST-0 Tokamak Toroidal Magnetic Field System

Krat, S.; Pryshvitsyn, A. S.; Alieva, A. I.; Efimov, N. E.; Vinitskiy, E. A; Bulgadaryan, D. G.; Vorobyov, G. M.; Kurnaev, V.А.

doi:10.1134/s1063778821120024

Cited by 6 publications

(2 citation statements)

References 8 publications

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“…The poloidal magnetic field system of the MEPHIST-0 tokamak consists of four pairs of coils (PF coils) and a central solenoid (CS), located symmetrically relative to the vacuum chamber [21]. Their positions are given in table 2 [1,11].…”

Section: Basic Machine Parametersmentioning

confidence: 99%

Application of integrated simulation environment SIEMNED to the analysis of the MEPHIST-0 tokamak operation

Sychugov¹,

Soloviev²,

Zhilkin³

et al. 2023

Plasma Sci. Technol.

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The paper presents the results of numerical simulation of plasma equilibrium and stability in the MEPHIST-0 tokamak with SIEMNED software and comparison of simulation results with experiment. The determined characteristics of the vacuum chamber shows that it significantly affects the entire discharge. For various scenarios of the inductor operation, a comparison of experimental data and simulated currents and magnetic fields induced in the chamber was carried out. For the steady state tokamak operation, a numerical study of equilibrium plasma configurations was carried out depending on the currents in the poloidal magnetic field coils and plasma current. The vertical plasma instability is investigated. The limiting values of plasma ellipticity preventing the vertical plasma instability was numerically determined. Numerical simulations show that plasma equilibrium is supported by induced currents. It was shown numerically that magnetic configuration with "zero of higher order" have been obtained before plasma shot, suggesting consistence between the simulation results and observation..

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Section: Basic Machine Parametersmentioning

confidence: 99%

Application of integrated simulation environment SIEMNED to the analysis of the MEPHIST-0 tokamak operation

Sychugov¹,

Soloviev²,

Zhilkin³

et al. 2023

Plasma Sci. Technol.

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“…The main characteristic of this installation is the simplest possible design resulting in a substantial reduction in the time required for preparing and executing various experiments. In contrast to the traditional tokamak TF system, in which each coil is represented as one standalone element, The TF system of the MEPhIST-0 is a single continuous toroidal solenoid [8]. This system consists of 12 D-shaped [9] copper segments connected to each other in sequence, as illustrated in figure 1.…”

Section: Introductionmentioning

confidence: 99%

Vertical stray field measurements using an electron beam in the MEPhIST-0 tokamak

Vinitskiy,

Efimov,

Prishvitsyn

et al. 2023

Plasma Phys. Control. Fusion

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In the MEPhIST-0 tokamak, toroidal magnetic coil system is implemented as a single continuous toroidal solenoid. This design ensures synchronized operation of each segment of the solenoid and requires only one power supply line to operate. However, this configuration has the downside of introducing stray vertical and radial magnetic field components, which result from the inclination of the solenoid segments. Such stray fields can be measured using an electron beam, as previously demonstrated in experiments on T-15, TEXTOR, KSTAR, and SST-1. This paper describes the parameters of the experiment and presents the main results obtained from the MEPhIST-0 tokamak. Two experimental techniques for measuring the vertical magnetic field are discussed: one with a change in the current direction in the toroidal solenoid and one without. The ratio of the stray vertical field to the toroidal field was found to be approximately 0.5%. The conducted experiments highlight the necessity of compensating for the stray vertical field using additional poloidal coils.

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