Title :
Conceptual design of SST-1 tokamak
fDate :
30 Sep-5 Oct 1995
Abstract :
The superconducting steady-state tokamak (SST) will have major and minor radii of 1.05 m and 0.20 m respectively. The TF and PF coils will be superconducting (NbTi), while the ohmic transformer and correction coil system will be made of copper. Steady-state current drive, and also part of the current rampup, will be based on lower hybrid current drive (LHCD). ICRF and NBI will provide auxiliary heating. Fast vertical control will make use of saddle coils placed inside the vacuum vessel, while the PF coils will be used for shape control. The outer divertor will have a slot configuration to permit operation with high recycling and impurity injection
Keywords :
Tokamak devices; fusion reactor design; plasma radiofrequency heating; ICRF; LHCD; NBI; PF coils; SST; SST-1 tokamak; TF coils; auxiliary heating; conceptual design; fast vertical control; high recycling; impurity injection; major radius; minor radius; outer divertor; saddle coils; shape control; slot configuration; steady-state current drive; superconducting NbTi coils; superconducting steady-state tokamak; vacuum vessel; Copper; Heating; Impurities; Niobium compounds; Recycling; Shape control; Steady-state; Superconducting coils; Titanium compounds; Tokamaks;
Conference_Titel :
Fusion Engineering, 1995. SOFE '95. Seeking a New Energy Era., 16th IEEE/NPSS Symposium
Conference_Location :
Champaign, IL
Print_ISBN :
0-7803-2969-4
DOI :
10.1109/FUSION.1995.534265
