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首页> 外文期刊>Fusion Engineering and Design >1-D thermal-hydraulic analysis of the high temperature superconducting current leads for the ITER magnet system from 5 Kto300 K
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1-D thermal-hydraulic analysis of the high temperature superconducting current leads for the ITER magnet system from 5 Kto300 K

机译：ITER磁体系统从5 Kto300 K的高温超导电流引线的一维热工水力分析

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摘要

The magnet system of ITER includes high temperature superconducting (HTS) current leads with a maximum current of 68 kA for the toroidal field (TF) coils, 55 kA for the poloidal field (PF)/central solenoid (CS) coils and 10 kA for the control coils (CC), respectively. Although different in terms of size and operative conditions, the ITER HTS current leads have been all designed on the basis of an established concept, which was successfully developed for the LHC at CERN and proven by the so-called 70 kA "demonstrator" lead made by KIT and by the ITER pre-prototypes made by ASIPP in China. A broad R&D campaign has been undertaken by ASIPP and CERN in order to find optimized designs for each component of the leads. Nevertheless, a comprehensive picture of the performance of the entire HTS current leads is not yet available. In this paper, a steady state, full length, thermal-hydraulic 1-D modeling is applied to the study of the three types (TF, PF/CS, CC) of ITER HTS current leads. The results of this predictive analysis are then compared with relevant ITER requirements. It was found that the present design of the HTS current leads will fulfill these specifications.
机译：ITER的磁体系统包括高温超导（HTS）电流引线，对于环形场（TF）线圈，最大电流为68 kA，对于极场（PF）/中央螺线管（CS）线圈，最大电流为55 kA，对于环形场（PF）/中央螺线管（CS）线圈，最大电流为10 kA。分别是控制线圈（CC）。尽管在大小和操作条件方面有所不同，但ITER HTS电流引线均基于既定概念进行设计，该概念已为CERN的LHC成功开发，并通过所谓的70 kA“演示器”引线进行了验证。由KIT以及ASIPP在中国制造的ITER原型。 ASIPP和CERN开展了广泛的研发活动，以便为引线的每个组件找到最佳设计。但是，尚无法获得整个HTS电流导线性能的全面描述。本文将稳态，全长，热工一维模型应用于ITER HTS电流引线的三种类型（TF，PF / CS，CC）的研究。然后将此预测分析的结果与相关的ITER要求进行比较。已经发现，HTS电流引线的当前设计将满足这些规范。

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