DocumentCode
2064822
Title
Assessment of possible implications of a neutral beam configuration for CIT
Author
Grisham, L.R. ; Cooper, W.S. ; Purgalis, P. ; Brown, T.
Author_Institution
Plasma Phys. Lab., Princeton Univ., NJ, USA
fYear
1989
fDate
2-6 Oct 1989
Firstpage
1000
Abstract
The present plans for the Compact Ignition Tokamak (CIT) call for the auxiliary heating to be done by RF techniques. However, R.J. Goldston (1988) has proposed that an alternative scenario might involve running TFTR (Tokamak Fusion Test Reactor)-type supershot plasmas with peaked density profiles. This would require central fueling by deuterium and tritium beams. The authors have performed a conceptual study of a system to inject negative-ion-based 300-keV beams of deuterium (D) and tritium (T) using the available port geometry. The authors report on the resulting conceptual design, the tritium usage during operation, and the implications for the test cell configuration
Keywords
Tokamak devices; fusion reactor theory and design; plasma heating; CIT; Compact Ignition Tokamak; D- beam injection; T; design; test cell configuration; Deuterium; Electrostatics; Ignition; Ion accelerators; Ion beams; Ion sources; Laboratories; Particle beams; Physics; Plasmas;
fLanguage
English
Publisher
ieee
Conference_Titel
Fusion Engineering, 1989. Proceedings., IEEE Thirteenth Symposium on
Conference_Location
Knoxville, TN
Type
conf
DOI
10.1109/FUSION.1989.102385
Filename
102385
Link To Document