Upgrade possibilities for the central solenoid in CIT

Author

Bromberg, L. ; Wei, J. ; Montgomery, D.B. ; Cohn, D.R. ; McManamy, T.J.

Author_Institution

MIT Plasma Fusion Center, Cambridge, MA, USA

fYear

1989

fDate

2-6 Oct 1989

Firstpage

605

Abstract

Upgrade possibilities for the central OH (ohmic heating) solenoid in the CIT (Compact Ignition Tokamak) are discussed. A higher performance solenoid could be designed for either higher flux capability or longer pulse length. A solenoid that provides larger flux linkage while still satisfying the engineering and the physics constraints is described. The optimization scheme consists of grading the turns of the pancakes of the central solenoid, either radially (in a given pancake), axially (using different pancake geometry), or both. Increases between 10 and 20% in the flux-swing from the PF (poloidal field) system can thus be obtained, corresponding to 6-12 V-s. Detailed calculations of the plasma equilibrium and the power/energy requirements of these cases are presented. A comparison with the baseline case is made

Keywords

electromagnets; fusion reactor theory and design; CIT; Compact Ignition Tokamak; central solenoid; higher flux capability; higher performance solenoid; longer pulse length; optimization scheme; plasma equilibrium; power/energy requirements; upgrade possibilities; Coils; Conducting materials; Conductors; Current density; Plasmas; Power system modeling; Power transformer insulation; Pulse transformers; Solenoids; Stress;

fLanguage

English

Publisher

ieee

Conference_Titel

Fusion Engineering, 1989. Proceedings., IEEE Thirteenth Symposium on

Conference_Location

Knoxville, TN

Type

conf

DOI

10.1109/FUSION.1989.102292

Filename

102292