Tokamak ITER, 3D-FEM analyses of the magnetic field of types version of coils system for magnetic confinement of plasma

被引:0
|
作者
Vycudilik, Marcel [1 ]
Brezina, Antonin [1 ]
Stoklas, Petr [1 ]
Marek, Martin [1 ]
Misak, Stanislav [1 ]
机构
[1] VSB TU Ostrava, Fac Elect Engn & Comp Sci, Dept Elect Power Engineing, Ostrava 70833, Czech Republic
关键词
thermonuclear fusion; magnetic confinement; tokamak; ITER; poloidial field coils; central solenoid;
D O I
暂无
中图分类号
TE [石油、天然气工业]; TK [能源与动力工程];
学科分类号
0807 ; 0820 ;
摘要
The paper presents the results of independent analysis of the magnetic field excitation by coils of the ITER tokamak. The analysis is based on the 3D model of the tokamak type version of the design excitation coils. The post contains a brief description of the tokamak design and coil system. The actual calculation of the magnetic field is carried out by using FEM methods for different variants of excitation coils. Current status of the ITER project can be found on the website www.iter.org.
引用
收藏
页码:1309 / 1312
页数:4
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