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Structural analysis of the International Thermonuclear Experimental Reactor magnet system: comparative study of two central solenoid configurations

机译:国际热核实验堆磁体系统的结构分析:两种中央螺线管配置的比较研究

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The International Thermonuclear Experimental Reactor (ITER) tokamak superconducting magnet system is designed to confine and control a 21 MA plasma during the various phases of pulsed operation. The central solenoid (CS) and poloidal coils are independently powered with currents that cycle during the pulse. The reference magnet system design includes a layer-wound 12 meter long CS that only allows one current density distribution. In an alternative design, which shows advantages for plasma shape control, the CS consists of three independently powered modules. In this paper the configurations are compared from the structural point of view.
机译:国际热核实验堆(ITER)托卡马克超导磁体系统旨在在脉冲运行的各个阶段限制和控制21 MA等离子体。中央螺线管(CS)和极向线圈由在脉冲期间循环的电流独立供电。参考磁体系统设计包括一个绕线的12米长的CS,该CS仅允许一个电流密度分布。在显示等离子体形状控制优势的替代设计中,CS由三个独立供电的模块组成。本文从结构的角度对配置进行了比较。

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