DocumentCode
2760163
Title
Circuit Analyses of the Filament Ion Source Power Supplies for the ITER Neutral Beam Test Facility
Author
Bigi, M. ; Zanotto, L.
Author_Institution
Consorzio RFX, Euratom-ENEA Assoc., Padova
fYear
2005
fDate
Sept. 2005
Firstpage
1
Lastpage
4
Abstract
This paper describes circuit simulations of the filament heating circuit for the neutral beam test facility of the international thermonuclear experimental reactor (ITER). The novel features of ITER filament heating circuit are studied both in normal operation and under fault conditions. The proposed scheme is found capable of performing as required and results are illustrated useful for further detailing of the design
Keywords
Tokamak devices; fusion reactor design; fusion reactor ignition; fusion reactor operation; fusion reactor theory; ion sources; plasma beam injection heating; plasma sources; power supplies to apparatus; ITER neutral beam test facility; circuit analysis; fault conditions; filament heating circuit; filament ion source power supplies; normal operation; plasma device; Circuit analysis; Circuit faults; Circuit simulation; Deuterium; Heating; Inductors; Ion sources; Power supplies; Structural beams; Test facilities;
fLanguage
English
Publisher
ieee
Conference_Titel
Fusion Engineering 2005, Twenty-First IEEE/NPS Symposium on
Conference_Location
Knoxville, TN
Print_ISBN
0-4244-0150-X
Electronic_ISBN
0-4244-0150-X
Type
conf
DOI
10.1109/FUSION.2005.252939
Filename
4018973
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