DocumentCode
1059914
Title
Safety Analysis of the 70 kA ITER HTS Current Lead Demonstrator
Author
Heller, R.
Author_Institution
Forschungszentrum Karlsruhe, Karlsruhe, Germany
Volume
19
Issue
3
fYear
2009
fDate
6/1/2009 12:00:00 AM
Firstpage
1504
Lastpage
1507
Abstract
For the superconducting magnet system of the International Thermonuclear Experimental Reactor, ITER, 60 current leads for a total current of more than 2500 kA are needed. The use of High Temperature Superconductor current leads (HTS-CL) will reduce the resultant large refrigerator load considerably. Within the EU Fusion Technology Programme, the Forschungszentrum Karlsruhe and CRPP have developed and built a 70 kA HTS-CL demonstrator optimized for 50 K Helium operation. In 2004-2005, the CL was successfully tested with 50 K as well as 80 K Helium, and finally with LN2. In the meantime, ITER has decided to use HTS-CLs for the magnet system and China has taken the responsibility to provide the sc feeders for ITER including the current leads. In this paper, the performance of a 70 kA HTS-CL in fault conditions will be analysed using the FZK-CRPP demonstrator as a model. In particular, the quench performance and the safety behavior in case of a loss-of-flow accident (LOFA) will be described and an extrapolation of the leads performance in real ITER conditions will be given. Finally the effect of different shunt materials is discussed.
Keywords
Tokamak devices; fusion reactor safety; refrigerators; superconducting magnets; 70 kA ITER HTS current lead demonstrator; EU Fusion Technology Programme; HTS-CL; International Thermonuclear Experimental Reactor; high temperature superconductor current; loss-of-flow accident; refrigerator; safety analysis; shunt materials; superconducting magnet system; Current leads; fusion magnets; high temperature superconductor;
fLanguage
English
Journal_Title
Applied Superconductivity, IEEE Transactions on
Publisher
ieee
ISSN
1051-8223
Type
jour
DOI
10.1109/TASC.2009.2017839
Filename
5067119
Link To Document