1-D thermal-hydraulic analysis of the high temperature superconducting current leads for the ITER magnet system from 5 K to 300 K

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• 作者：Enrico Rizzo ; Pierre Bauer ; Reinhard Heller ; Laura Savoldi Richard ; Roberto Zanino
• 关键词：Nuclear fusion ; ITER ; Superconducting magnets ; HTS current leads ; Thermal-hydraulic analysis
• 刊名：Fusion Engineering and Design
• 出版年：December, 2013
• 年：2013
• 卷：88
• 期：12
• 页码：3125-3131
• 全文大小：1481 K

文摘

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 鈥渄emonstrator鈥?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.