Results of the Testing of ITER CC HTS Current Lead Prototypes

被引：22

作者：

Ding, K. ^{[1
]}

Zhou, T. ^{[1
]}

Liu, C. ^{[1
]}

Du, Q. ^{[1
]}

Fernandez, A. Vergara ^{[2
]}

Zhu, S. ^{[1
]}

Devred, A. ^{[2
]}

Bauer, P. ^{[2
]}

Feng, H. ^{[1
]}

Fernandez-Hernando, L. ^{[2
]}

Lu, K. ^{[1
]}

Lee, S. ^{[2
]}

Huang, X. ^{[1
]}

Niu, E. ^{[4
]}

Song, Y. ^{[1
]}

Taylor, T. ^{[5
]}

Yang, Y. ^{[3
]}

机构：

[1] Chinese Acad Sci, Inst Plasma Phys, Hefei 230031, Peoples R China

[2] ITER Int Org, F-13067 St Paul Les Durance, France

[3] Univ Southampton, Inst Cryogen, Southampton SO17 1BJ, Hants, England

[4] ITER China Domest Agcy, F-13067 St Paul Les Durance, France

[5] CERN, CH-1211 Geneva, Switzerland

来源：

IEEE TRANSACTIONS ON APPLIED SUPERCONDUCTIVITY | 2016年 / 26卷 / 04期

关键词：

Bi-2223; current lead; heat exchanger; ITER;

D O I：

10.1109/TASC.2016.2520300

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 ; 0809 ;

摘要：

According to the procurement agreement with the International Thermonuclear Experimental Reactor project, the Institute of Plasma Physics, Chinese Academy of Sciences (ASIPP) in China is responsible for the construction and performance testing of 31 sets of feeder systems, which contain also 60 high-temperature superconducting (HTS) current leads. In 2014/2015, three pairs of prototype current leads of three different types are being built and tested. A first pair of correction coil (CC) type, 10-kA current lead prototypes was built and cold tested in ASIPP in early 2015. The test items cover the joint resistance, overheating time test, mass flow consumption in steady-state operation for various currents, and the pulsed current scenario test. This paper presents the test results for the prototype CC 10-kA HTS current leads.

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