Title :
Conceptual design of a superconducting coil system cooled by forced flow He II for the central column of NET
Author :
Ciazynski, Daniel ; Duchateau, J.L. ; Turck, B.
Author_Institution :
DRFC STIF, Cadarache, France
fDate :
3/1/1988 12:00:00 AM
Abstract :
The poloidal field and ohmic heating coils for the Next European Torus Tokamak are envisioned for operation at magnetic fields as high as 10-14 T. To increase the maximum flux sweep, present designs either use niobium tin for the superconducting coils or inset a copper coil cooled by liquid nitrogen in the NbTi coil or even both. Based on experience with the TORE SUPRA, the authors argue that cooling NbTi to a lower temperature is a highly competitive and safe alternative. Two solutions are investigated: the first uses a 40-kA cable wound in double pancakes. The second makes use of several conductors layer-wound with current supplied in parallel. The novel aspect of both solutions is that He II circulates inside the conductor itself, introducing the advantages of a force-flow-cooled conductor at the cost of the implementation of a circulating device.
Keywords :
Tokamak devices; coils; cooling; fusion reactor materials; fusion reactor theory and design; niobium alloys; superconducting magnets; titanium alloys; 40 kA; NbTi; Next European Torus; double pancakes; flux sweep; forced flow He II; ohmic heating coils; superconducting coil system; superfluid 4He; Conductors; Copper; Heating; Helium; Niobium compounds; Superconducting coils; Tin; Titanium compounds; Tokamaks; Toroidal magnetic fields;
Journal_Title :
Magnetics, IEEE Transactions on