Title :
Safety Analysis of the 70 kA ITER HTS Current Lead Demonstrator
Author_Institution :
Forschungszentrum Karlsruhe, Karlsruhe, Germany
fDate :
6/1/2009 12:00:00 AM
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;
Journal_Title :
Applied Superconductivity, IEEE Transactions on
DOI :
10.1109/TASC.2009.2017839