DocumentCode
298271
Title
Conceptual design of the neutral beamline for TPX long pulse operation
Author
Wright, K.E. ; Dahlgren, F. ; Fan, H.M. ; Grisham, L.R. ; Hammersand, F.G. ; Kamperschroer, J.H. ; Lontai, L.M. ; Oldaker, M.E. ; Rogoff, P.
Author_Institution
Plasma Phys. Lab., Princeton Univ., NJ, USA
Volume
1
fYear
1993
fDate
11-15 Oct 1993
Firstpage
492
Abstract
The Tokamak Physics Experiment (TPX) will require a minimum of 8.0 megawatts of Neutral Beam heating power to be injected into the plasma for pulse lengths up to one thousand (1000) seconds to meet the experimental objectives. The Neutral Beam Injection System (NBIS) for initial operation on TPX will consist of one neutral beamline (NBL) with three ion sources. Provisions will be made for a total of three NBLs. The NBIS will provide 5.5 MW of 120 keV D0 and 2.5 MW of partial-energy D0 at 60 keV and 40 keV. The system also provides for measuring the neutral beam power, limits excess cold gas from entering the torus, and provides independent power, control, and protection for each individual ion source and accelerating structure. The Neutral Beam/Torus Connecting Duct (NB/TCD) includes a vacuum valve, an electrical insulating break, alignment bellows, vacuum seals, internal energy absorbing protective elements, beam diagnostics and bakeout capability. The NBL support structure will support the NBL, which will weigh approximately 80 tons at the proper elevation and withstand a seismic event. The NBIS currently operational on the Tokamak Fusion Test Reactor (TFTR) at the Princeton Plasma Physics Laboratory (PPPL) is restricted to injection pulse lengths of two (2) seconds by the limited capability of various energy absorbers. This paper describes the modifications and improvements which will be implemented for the TFTR Neutral Beamlines and the NB/TCD to satisfy the TPX requirements
Keywords
Tokamak devices; fusion reactor design; ion sources; particle beam diagnostics; particle beam injection; plasma beam injection heating; 1000 s; 120 keV; 2.5 MW; 40 keV; 5.5 MW; 60 keV; 8 MW; 80 ton; NB/TCD; Neutral Beam Injection System; Neutral Beam heating power; Neutral Beam/Torus Connecting Duct; TFTR Neutral Beamlines; TPX long pulse operation; Tokamak Physics Experiment; alignment bellows; bakeout capability; beam diagnostics; electrical insulating break; excess cold gas; internal energy absorbing protective elements; ion sources; neutral beam power; neutral beamline; partial-energy; pulse lengths; seismic event; torus; vacuum seals; vacuum valve; Elementary particle vacuum; Heating; Ion sources; Niobium; Particle beam injection; Particle beams; Physics; Plasma sources; Power measurement; Tokamaks;
fLanguage
English
Publisher
ieee
Conference_Titel
Fusion Engineering, 1993., 15th IEEE/NPSS Symposium on
Conference_Location
Hyannis, MA
Print_ISBN
0-7803-1412-3
Type
conf
DOI
10.1109/FUSION.1993.518379
Filename
518379
Link To Document