DocumentCode
2114561
Title
Automated calculation of DIII-D neutral beam availability
Author
Phillips, J.C. ; Hong, R.M. ; Scoville, B.G.
Author_Institution
Gen. Atomics, San Diego, CA, USA
fYear
1999
fDate
1999
Firstpage
511
Lastpage
514
Abstract
The neutral beam systems for the DIII-D tokamak are an extremely reliable source of auxiliary plasma heating, capable of supplying up to 20 MW of injected power, from eight separate beam sources into each tokamak discharge. The high availability of these systems for tokamak operations is sustained by careful monitoring of performance and following up on failures. One of the metrics for this performance is the requested injected power profile as compared to the power profile delivered for a particular pulse. Calculating this was a relatively straightforward task, however innovations such as the ability to modulate the beams and more recently the ability to substitute an idle beam for one which has failed during a plasma discharge, have made the task very complex
Keywords
fusion reactor design; fusion reactor ignition; fusion reactor operation; fusion reactor theory; plasma beam injection heating; plasma toroidal confinement; 20 MW; DIII-D neutral beam availability; DIII-D tokamak; NBI; automated calculation; auxiliary plasma heating; fusion reactor design; tokamak operations; Availability; Condition monitoring; Fault location; Heating; Particle beam injection; Particle beams; Plasma sources; Power system reliability; Technological innovation; Tokamaks;
fLanguage
English
Publisher
ieee
Conference_Titel
Fusion Engineering, 1999. 18th Symposium on
Conference_Location
Albuquerque, NM
Print_ISBN
0-7803-5829-5
Type
conf
DOI
10.1109/FUSION.1999.849890
Filename
849890
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