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Easyres umich5/2/2023 For reliable start-up, a pre-ionization system with two cost-effective homemade magnetron power supplies is also prepared. According to initial double null merging start-up scenario using the partial solenoid coils, appropriate power supplies for driving a toroidal field coil, outer poloidal field coils, and the partial solenoid coils are fabricated and successfully commissioned. A unique design feature of the VEST is two partial solenoid coils installed at both vertical ends of a center stack, which can provide sufficient magnetic fluxes to initiate tokamak plasmas while keeping a low aspect ratio configuration in the central region. Finally, the structural assessment of the vacuum vessel is performed in order to verify its integrity during normal and off-normal events in phase 3.Ī new spherical torus called VEST (Versatile Experiment Spherical Torus) is designed, constructed and successfully commissioned at Seoul National University. 2011) and computing EM forces through a finite element model (FEM) taking into account the effects of both eddy and halo currents (Roccella et al. The modeling has been carried out by combining equilibrium scenarios obtained through the FIESTA code (Cunningham, 2013), estimating VDE and disruption time-scales by comparing other machines (Chen et al. We present, here, the EM and structural analysis performed for the design of SMART. The EM loads are mainly produced by: the poloidal flux variation during the thermal and current quench, halo currents (Boozer, 2013) that flow into the vacuum vessel and interacts with the toroidal magnetic field and toroidal flux variation during the thermal and current quench. As a consequence, a detailed evaluation of the EM loads during plasma disruptions is mandatory for the correct dimensioning of the machine, in particular the vacuum vessel. In particular, vertical displacement events (VDEs) and disruptions (Boozer, 2012) are most important as they can cause severe damage to the components directly exposed to the plasma due to the significant electromagnetic (EM) and thermal loads delivered over ms timescales. Such operating conditions present notable challenges to the design and verification of SMARTs structural integrity during normal and off-normal operations. The operation of SMART will cover three phases reaching a maximum plasma current ( The SMall aspect ratio tokamak (SMART) is a new spherical device, that is, currently being constructed at the University of Seville. We target the transient control of guiding the plasma to a desired flow at a particular short time instant, where it is expected that the flow had been designed offline to be the desired one from the point of view of steady state operation. The objective functional for the optimal control problem are subject to set of constraint equations, Navier-Stokes and Maxwell equations. In an attempt to control a Tokamak device, this paper investigates an optimal control problem for an incompressible, viscous, electrically conducting MHD fluid confined in a closed toroidal region in the presence of an applied current. The development, design and control of the design has been an important area of research, and a significant target is to effectively confine the extremely hot plasma inside its hollow torus-shaped body without touching its boundary for a prolonged period of time. It is a torus-shaped device that confines plasma by a strong magnetic field. The Tokamak device is the most promising candidate for producing sustainable electric power by nuclear fusion. The topologies and control strategy of the power supplies are explained, together with a model in MATLAB Simulink to simulate the power supplies performance, proving their feasibility before the construction of the system. The design of flexible and modular power supplies, based on IGBTs and supercapacitors, is presented. An analytical thermal model is employed to obtain the cross sections of each coil and, finally, their dimensions and parameters. Taking the current waveforms for these set of coils as starting point, each of them has been designed to withstand the Joule heating during the tokamak operation time. The design foresees a central solenoid, 12 toroidal field coils and 8 poloidal field coils. This contribution presents the design of the coils and power supplies of the machine. The goal of the machine is to achieve a toroidal field of 1 T, a plasma current of 500 kA and a pulse length of 500 ms for a plasma with a major radius of 0.4 m and minor radius of 0.25 m. A new spherical tokamak, the SMall Aspect Ratio Tokamak (SMART), is currently being designed at the University of Seville.
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