DocumentCode :
2759043
Title :
Design of the TF Coil for a Tokamak Fusion Power Reactor with YBCO Tape Superconductors
Author :
Ando, Takehiro ; Nishio, S.
Author_Institution :
Nippon Adv. Tech. Corp., Ibaraki
fYear :
2005
fDate :
Sept. 2005
Firstpage :
1
Lastpage :
4
Abstract :
A low aspect ratio tokamak, VECTOR was designed by Japan Atomic Energy Research Institute (JAERI) to provide the high cost performance necessary for a commercial power reactor. The maximum magnetic field within the winding of the toroidal field (TF) coil is about 20 T. The applicability of high temperature superconductor YBCO tape to the TF coil conductor is considered. YBCO tape is well known to have higher critical current density. However, YBCO tape has magnetic instability due to flux jumps. The magnetic field at which the first flux jump occurs is estimated to be 6.8 T at 33 K. Therefore, to prevent flux jumps, the winding is divided into three (higher, middle and lower field) winding packs and the maximum self magnetic field produced by each winding pack is less than 6.8 T. The low field winding pack is cooled first down to 33 K and operated up to its nominal current. In this case, the middle and higher field winding packs are maintained above 90 K. Next, in similar process the middle pack is operated. Finally, the higher pack is operated, and 20 T is generated without flux jump. The nominal current for every winding pack is 40 kA. Thus it is possible to apply YBCO tape to the TF coil and YBCO tape will be expected to play an important role in the realization of tokomak fusion power reactors with low construction and operation costs, and high performance plasma
Keywords :
Tokamak devices; critical current density (superconductivity); fusion reactor design; high-temperature superconductors; plasma toroidal confinement; superconducting coils; superconducting tapes; Japan Atomic Energy Research Institute; TF coil design; VECTOR; YBCO tape superconductors; commercial power reactor; construction costs; critical current density; flux jumps; high performance plasma; high temperature superconductor; higher field winding packs; lower field winding packs; magnetic field; magnetic instability; middle field winding packs; operation costs; tokamak fusion power reactor; toroidal field coil winding; Conductors; Costs; Fusion reactor design; High temperature superconductors; Inductors; Superconducting coils; Superconductivity; Tokamaks; Toroidal magnetic fields; Yttrium barium copper oxide; 20 T coil; VECTOR; YBCO; flux jump; fusion reactor;
fLanguage :
English
Publisher :
ieee
Conference_Titel :
Fusion Engineering 2005, Twenty-First IEEE/NPS Symposium on
Conference_Location :
Knoxville, TN
Print_ISBN :
0-4244-0150-X
Electronic_ISBN :
0-4244-0150-X
Type :
conf
DOI :
10.1109/FUSION.2005.252876
Filename :
4018910
Link To Document :
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