Abstract:The Alborz tokamak is a D-shape cross section tokamak that is under construction in Amirkabir University of Technology. The most important part of the tokamak design is the design of TF coils. In this paper a refined design of the TF coil system for the Alborz tokamak is presented. This design is based on cooper cable conductor with 5 cm width and 6 mm thickness. The TF coil system is consist of 16 rectangular shape coils, that makes the magnetic field of 0.7 T at the plasma center. The stored energy in total … Show more
“…Design of this tokamak consists of several major parts which are under study and construction by different members of the tokamak team (Mardani et al 2012a;2012b;Mardani and Amrollahi 2013).…”
Section: Introductionmentioning
confidence: 99%
“…Alborz tokamak is an experimental system under construction at the Amirkabir University of Technology (AUT) with major and minor radii of 45 cm and 15 cm respectively, and a toroidal magnetic field of Bt 6 1T (Mardani et al 2012). Design of this tokamak consists of several major parts which are under study and construction by different members of the tokamak team (Mardani et al 2012a;2012b;Mardani and Amrollahi 2013).…”
Alborz tokamak is an educational system for studying plasma phenomena in many physics and engineering experiments. A hot filament and a reverse discharge loop are used in the tokamak as the pre-ionization system. The hot cathode prepares a local initial electron density, then the reverse discharge loop trigger the ionization avalanche by means of inducing a toroidal electric field. The parameters of the hot filament are determined in order to produce the desired electron source. Filament temperature is simulated by using three-dimensional finite element method. The average values of filament temperature and electron density at the plasma core (at the end of pre-ionization process) were calculated and are about 2750 K and 10 19 m −3 , respectively. The resultant electron density and equivalent plasma resistivity due to reverse discharge loop are also calculated. In this paper, the simulation results, optimum structural style, the obtained parameters, the temperature of different parts of the filament and produced electron density are presented and discussed.
“…Design of this tokamak consists of several major parts which are under study and construction by different members of the tokamak team (Mardani et al 2012a;2012b;Mardani and Amrollahi 2013).…”
Section: Introductionmentioning
confidence: 99%
“…Alborz tokamak is an experimental system under construction at the Amirkabir University of Technology (AUT) with major and minor radii of 45 cm and 15 cm respectively, and a toroidal magnetic field of Bt 6 1T (Mardani et al 2012). Design of this tokamak consists of several major parts which are under study and construction by different members of the tokamak team (Mardani et al 2012a;2012b;Mardani and Amrollahi 2013).…”
Alborz tokamak is an educational system for studying plasma phenomena in many physics and engineering experiments. A hot filament and a reverse discharge loop are used in the tokamak as the pre-ionization system. The hot cathode prepares a local initial electron density, then the reverse discharge loop trigger the ionization avalanche by means of inducing a toroidal electric field. The parameters of the hot filament are determined in order to produce the desired electron source. Filament temperature is simulated by using three-dimensional finite element method. The average values of filament temperature and electron density at the plasma core (at the end of pre-ionization process) were calculated and are about 2750 K and 10 19 m −3 , respectively. The resultant electron density and equivalent plasma resistivity due to reverse discharge loop are also calculated. In this paper, the simulation results, optimum structural style, the obtained parameters, the temperature of different parts of the filament and produced electron density are presented and discussed.
“…For this reason we choose a D-shape cross section vacuum vessel for Alborz tokamak. The toroidal magnetic field is about 0.85 T at the major radius of the tokamak, major and minor radii are 0.15 m and 0.45 m respectively, edge safety factor is 3 and the maximum plasma current is 45 kA [4].…”
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