Title :
Design and fabrication of forced-flow coils as an R&D program for Large Helical Device
Author :
Takahata, K. ; Yanagi, N. ; Mito, T. ; Yamamoto, J. ; Motojima, O. ; Nakamoto, K. ; Mizumaki, S. ; Kitamura, K. ; Wachi, Y. ; Shinohara, H. ; Yamamoto, K. ; Shibui, M. ; Uchida, T. ; Nakayama, K.
Author_Institution :
Nat. Inst. for Fusion Sci., Nagoya, Japan
fDate :
3/1/1991 12:00:00 AM
Abstract :
Two forced-flow cooled NbTi superconducting coils (TOKI-TF, PF) have been designed and fabricated. The helical coil (TOKI-TF) is a 1/4-scale model of the Large Helical Device (LHD). It has a major radius of 0.9 m, a minor radius of 0.25 m, and a pitch number of 4. Nominal current and maximum field were designed to be 8 kA and 2.8 T, respectively. Another coil (TOKI-PF) was fabricated for the demonstration of LHD poloidal field coils. It consists of two double pancakes with an inner radius of 0.6 m and an outer radius of 0.82 m. The nominal current of 25 kA simulates that of LHD poloidal field coils. Cable-in-conduit-type conductors were used for the both coils. The test facility was also constructed with a vacuum vessel, a liquid nitrogen shield, 30-kA power leads, a heat exchanger, and cryogenic supports. Design concepts and details are presented
Keywords :
coils; fusion reactor theory and design; niobium alloys; superconducting magnets; titanium alloys; type II superconductors; 2.8 T; 25 kA; 8 kA; Large Helical Device; NbTi superconducting coils; cable-in-conduit conductors; cryogenic supports; double pancakes; forced-flow coils; heat exchanger; helical coil; inner radius; liquid nitrogen shield; major radius; maximum field; minor radius; outer radius; pitch number; poloidal field coils; vacuum vessel; Cable shielding; Conductors; Cryogenics; Fabrication; Niobium compounds; Nitrogen; Superconducting cables; Superconducting coils; Test facilities; Titanium compounds;
Journal_Title :
Magnetics, IEEE Transactions on
