Title :
Design methods and actual performances of conductors for the superconducting coils of tokamaks
Author :
Turck, B. ; Bessette, D. ; Ciazynski, D. ; Duchateau, J.L.
Author_Institution :
CEA, Centre d´´Etudes Nucleaires de Cadarache, France
Abstract :
Conductors presently retained for the coils of large fusion machines are cable-in-conduit conductors made of about one thousand of superconducting strands cabled inside a jacket and cooled by a forced flow of helium. The current density is the key parameter for die machine design, as it reacts strongly on the size and on the cost. An optimized conductor design has been pursued to maximize the current density while fulfilling several criteria regarding protection, stability and safety margin. The influence of some parameters such as: field, strain, effective diameter of filaments and heat transfer coefficient is analyzed. A Nb3Sn conductor developed by CEA relevant for NET/ITER has been tested successfully at 6.2 K up to 50 kA and 12 T. Following the same concept a complete design of a conductor for the central solenoid of ITER is proposed
Keywords :
fusion reactor design; fusion reactor materials; fusion reactors; heat transfer; niobium compounds; superconducting coils; 12 T; 50 kA; 6.2 K; CICC; NET/ITER; Nb3Sn; Nb3Sn conductor; cable-in-conduit conductors; central solenoid; current density; field; filament effective diameter; forced flow He-cooling; heat transfer coefficient; large fusion machines; optimized conductor design; protection; safety margin; stability; strain; superconducting coils; superconducting strands; tokamaks; Cable shielding; Conductors; Costs; Current density; Design methodology; Design optimization; Helium; Protection; Superconducting cables; Superconducting coils;
Conference_Titel :
Fusion Engineering, 1993., 15th IEEE/NPSS Symposium on
Conference_Location :
Hyannis, MA
Print_ISBN :
0-7803-1412-3
DOI :
10.1109/FUSION.1993.518417
