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Tokamak ITER – Simulation of the distribution of magnetic field of coil excitation system for maintaining plasma

 

Fig. 1 View of the construction of the ITER tokamak
Fig. 1 View of the construction of the ITER tokamak

Tokamak ITER

Tokamaks are devices designed to create high-temperature plasma in toroidal discharge chamber. The plasmas ring is generated and stabilized by the magnetic field excited by the system of poloidal and toroidal coils. Tokamaks belong to the group of devices developed to achieve nuclear fusion. Currently there are operated more than 50 different types of tokamaks in the world. The largest and the most advanced tokamak is the project ITER, whose construction started in the French city of Cadarache in 2005. The ITER project is a global project involving a number of countries including the Czech Republic. The project aims to create a prototype of fusion power plant with an output of 500MW. View of the construction of the ITER tokamak is shown on the opening image. A more detailed description of the ITER tokamak is presented in the accompanying document and further information can be found on the official website www.iter.org .

The coil excitation system consists of a fundamental basis of magnetic maintenance of the plasma. Coil system is divided into four groups, and that is, the central solenoid coil, toroidal field coils, poloidal field coils and correction coils. The overall design of the coils system is shown in the following figure.

Fig. 2 Coils system of the ITER tokamak
Fig. 2 Coils system of the ITER tokamak

Simulation of the ITER tokamak’s magnetic field

The aim of the presented project was to analyze the distribution of the magnetic field in the discharge chamber of the tokamak for different operating states of excitation coils. For this purpose, the basic model of the tokamak was created in ANSYS program. Own calculation and analysis of the magnetic field was done for separate excitation central solenoid coil, toroidal field coils and poloidal field coils, and for the total combined excitation of these coils systems. The following images show the view of prepared model of the ITER tokamak, shown is the part of the model containing the tokamak torus and then the overall coil system used in the model.

Obr. 3 Pohled na provedení částí modelu tokamaku ITER_1 Obr. 3 Pohled na provedení částí modelu tokamaku ITER_2
Model of the torus Model of the coils

Fig. 3 View on the parts of the ITER tokamak model

The following table provides an overview of the basic samples of solved computational simulations of the distribution of the magnetic field with a small sample of calculation results in the form of distribution of magnetic flux density B[T] with marking of the considered operating current.

Central solenoid 45 [kA]
Obr. 4 - Centrální solenoid_1 obr. 4 - Centrální solenoid_2
Coils of toroidal field 68 [kA]
obr. 4 - Cívky toroidálního pole_1 Obr. 4 - Cívky toroidálního pole_2
Coils of poloidal field 45 [kA]
Obr. 4 - Cívky poloidálního pole_1 Obr. 4 - Cívky poloidálního pole_2
Coils of poloidal field CS=PF=45 [kA]; TF=68[kA]
Obr. 4 - Celý systém cívek_1 Obr. 4 - Celý systém cívek_2

Fig. 4 Overview of solved computational simulations of the ITER tokamak

 Work provides an independent analysis of the distribution of the ITER tokamak’s magnetic field corresponding to the shown configurations of coil groups and different sizes of operating currents. The detailed job description starts with a brief description and characteristics of the ITER project and subsequently there is a detailed overview of the results of the simulations.

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