DocumentCode :
1949280
Title :
Lithium operations on the lithium tokamak experiment
Author :
Kozub, T. ; Majeski, R. ; Kaita, R. ; Granstedt, E. ; Jacobson, C. ; Lundberg, D. ; Timberlake, J.
Author_Institution :
Princeton Plasma Phys. Lab., Princeton Univ., Princeton, NJ, USA
fYear :
2011
fDate :
26-30 June 2011
Firstpage :
1
Lastpage :
3
Abstract :
The lithium tokamak experiment (LTX) is a small spherical tokamak currently operating to investigate the low recycling regime for magnetically confined plasmas through the utilization of liquid lithium coated plasma facing surfaces. The LTX machine is unique in that it incorporates inside the vacuum vessel a heated conducting shell that encloses about 80% of the last closed flux surface of the plasma. The conforming shell operates at temperatures up to 500°C and is coated with a thin liquid lithium film. Two retractable crucible evaporators are used to deposit the lithium film on the shell inner surfaces. Various methods and procedures for lithium deposition onto the shell surfaces have been tested by varying the component temperatures and vessel pressure, and utilizing concurrent glow discharge. Operating procedures and safety systems have been developed and implemented to ensure the safe operation with lithium at elevated temperatures. The machine has successfully operated with lithium coated shells demonstrating improved plasma performance as a result. Maintaining an active lithium surface between lithium evaporations was an issue and new features are currently being installed to address this. The machine has also been vented and the internal surfaces cleaned without any difficulty. Operating results, current status, ongoing upgrades and future plans will be presented.
Keywords :
Tokamak devices; fusion reactor operation; fusion reactor safety; lithium; plasma toroidal confinement; LTX machine; Li; active lithium surface; closed flux surface; glow discharge; liquid lithium coated plasma facing surfaces; liquid lithium film; lithium deposition; lithium evaporation; lithium operation; lithium tokamak experiment; low recycling regime; retractable crucible evaporators; safe operation; safety system; shell inner surfaces; shell surfaces; temperature 500 degC; vacuum vessel; vessel pressure; Heating; Liquid lithium; Lithium; Plasma facing surface;
fLanguage :
English
Publisher :
ieee
Conference_Titel :
Fusion Engineering (SOFE), 2011 IEEE/NPSS 24th Symposium on
Conference_Location :
Chicago, IL
ISSN :
1078-8891
Print_ISBN :
978-1-4577-0669-1
Electronic_ISBN :
1078-8891
Type :
conf
DOI :
10.1109/SOFE.2011.6052293
Filename :
6052293
Link To Document :
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