Analytical studies on the hotspot temperature of cable-in-conduit conductors

被引:8
|
作者
Yoshida, K
Takigami, H
Kubo, H
机构
[1] ITER, EDA Naka Joint Work Site, Naka, Ibaraki 3110193, Japan
[2] Japan Atom Energy Res Inst, Naka, Ibaraki 3110193, Japan
关键词
superconducting; hotspot; quench; CICC; ITER; fusion;
D O I
10.1016/S0011-2275(01)00132-1
中图分类号
O414.1 [热力学];
学科分类号
摘要
This paper describes an analytical study to review the hotspot temperature design criterion of the cable-in-conduit conductors for the ITER magnet system. The ITER magnet system uses three kinds of cable-in-conduit conductors for the Toroidal Field (TF) coils, the Central Solenoid (CS) and the Poloidal Field (PF) coils. The amount of copper in the superconducting cable has been defined by using the classical hotspot temperature design criterion that is based on the adiabatic condition. In the current design, ITER superconducting cables include a large number of pure copper strands to satisfy the classical criterion. However, the temperature and stress in the conduit and insulations after quench can be simulated with the quench simulation program and stress analysis program using the latest analysis tools. This analysis shows that the strand temperature is dominated by the conduction along strands and the heat capacity of other conductor materials and coolant. The hotspot temperature depends strongly on the delay time for quench detection. This analysis provides an estimation of the delay times for quench detection. The thermal and stress analysis can provide the maximum allowable temperature after quench by determination of a failure or a functional disorder condition of the jacket material and turn insulation. In conclusion, it is found that the current density of the cable space can be increased, by reducing the extra copper strand, thereby, allowing a reduction of the coil radial build. (C) 2001 Elsevier Science Ltd. All rights reserved.
引用
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页码:583 / 594
页数:12
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