Conductors of the ITER magnets

被引：29

作者：

Bessette, D ^{[1
]}

Mitchell, N ^{[1
]}

Zapretilina, E ^{[1
]}

Takigami, H ^{[1
]}

机构：

[1] ITER Naka, JCT, Naka, Ibaraki 3110193, Japan

来源：

IEEE TRANSACTIONS ON APPLIED SUPERCONDUCTIVITY | 2001年 / 11卷 / 01期

关键词：

cable in conduit; superconductor;

D O I：

10.1109/77.920072

中图分类号：

TM [电工技术]; TN [电子技术、通信技术];

学科分类号：

0808 [电气工程]; 0809 [电子科学与技术];

摘要：

Nb3Sn and NbTi Cable in Conduit Conductors (CICCs) cooled by a supercritical helium forced flow are considered in the ITER magnets. The design of the various CICCs relies on consideration of cost and manufacture as well as on the R&D performed on conductors for the ITER Model Coils. The amount of superconducting strand is optimized to satisfy operational requirements such as a minimum temperature margin, a heat power balance for stability (Stekly parameter), and a maximum hot spot temperature in case of quench, The conductor design and the main results of the conductor thermohydraulic analysis are discussed including consideration of nonuniform current distribution among superconducting strands.

引用

页码：1550 / 1553

页数：4

共 9 条

[1]

Nuclear heat, disruption loads and other AC losses and their impact on the ITER toroidal field coils conductor design [J].