Conceptual design of SST-1 tokamak

Volume

1

fYear

1995

fDate

30 Sep-5 Oct 1995

Firstpage

481

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;

fLanguage

English

Publisher

ieee

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

Type

conf

DOI

10.1109/FUSION.1995.534265

Filename

534265