DocumentCode
3460409
Title
NSTX OH Coil Design Improvements
Author
Kalish, M. ; Chrzanowski, J. ; Neumeyer, C. ; Paul, Biju ; Woolley, R. ; Jun, C.
Author_Institution
Princeton Plasma Phys. Lab., Princeton
fYear
2007
fDate
17-21 June 2007
Firstpage
1
Lastpage
4
Abstract
The National Spherical Torus Experiment (NSTX) has been operating successfully since February of 1999. A unique element of NSTX is the center solenoid or OH coil that from the start has been a design challenged by the low aspect ratio/geometry of the device. To achieve this low aspect ratio the OH coil´s outer diameter is constrained to a narrow profile creating the need for creative design solutions concerning cooling connections, lead orientation, and insulation schemes. The original design has succeeded overall, but NSTX run time has been lost due to coil reliability issues. It was decided in the last year that it would be prudent to fabricate a new OH coil and have it available as an upgrade to the experiment. The experience of operating and maintaining the OH coil has provided the basis for an improved OH coil design. A collaboration was arranged with ASIPP in China to fabricate a spare coil for NSTX. The new OH coil will incorporate both design improvements intended to increase reliability as well as upgrades that will provide flexibility during future operation by allowing for an expanded operational profile. This paper summarizes and reviews these design and reliability improvements.
Keywords
fusion reactor design; fusion reactor materials; fusion reactor operation; reliability; solenoids; ASIPP; NSTX OH coil design improvements; National Spherical Torus Experiment; center solenoid; coil reliability issues; cooling connections; creative design solutions; expanded operational profile; flexibility; insulation schemes; lead orientation; Coils; Conductors; Contamination; Cooling; Copper; Fitting; Insulation; Physics; Plasmas; Solenoids; Fusion; NSTX; OH Coil; Princeton Plasma Physics Laboratory; Solenoid Insulation;
fLanguage
English
Publisher
ieee
Conference_Titel
Fusion Engineering, 2007. SOFE 2007. 2007 IEEE 22nd Symposium on
Conference_Location
Albuquerque, NM
Print_ISBN
978-1-4244-1193-1
Electronic_ISBN
978-1-4244-1194-8
Type
conf
DOI
10.1109/FUSION.2007.4337876
Filename
4337876
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