DocumentCode :
2759052
Title :
Analysis of NSTX TF Joint Voltage Measurements
Author :
Woolley, R.
Author_Institution :
Princeton Plasma Phys. Lab., NJ
fYear :
2005
fDate :
Sept. 2005
Firstpage :
1
Lastpage :
6
Abstract :
This report presents findings of analyses of recorded current and voltage data associated with 72 electrical joints operating at high current and high mechanical stress. The analysis goal was to characterize the mechanical behavior of each joint and thus evaluate its mechanical supports. The joints are part of the toroidal field (TF) magnet system of the National Spherical Torus Experiment (NSTX) pulsed plasma device operating at the Princeton Plasma Physics Laboratory (PPPL). Since there is not sufficient space near the joints for much traditional mechanical instrumentation, small voltage probes were installed on each joint and their voltage monitoring waveforms have been recorded on sampling digitizers during each NSTX "shot". Strong mechanical forces arise during pulsed operations, far stronger than the joint conductors could long survive without the restraining assistance of a mechanical support system. A joint\´s apparent electrical resistance changes dynamically if sufficiently strong net lateral force on the conductors causes a reduction in the joint\´s area of high pressure contact. Since the electromagnetic forces are well known, this circumstance would arise if the mechanical supports were not working properly. Analyzing the nonlinear relations between pulsed magnetic forces and joint electrical resistances can thus identify and even diagnose mechanically overstressed joints. The present design of the joints and their supports was operated in two successive run periods, February-July 2004 and April-September 2005. Because of indications from analyzing the first run period\´s voltage probe data that the mechanical support system\´s fabrication was flawed, the joints and their mechanical supports were rebuilt before the second run period without changing the design. Analyses of voltage probe data from the second run period indicate improved mechanical support function
Keywords :
Tokamak devices; electromagnetic forces; fusion reactor design; fusion reactor ignition; plasma ohmic heating; plasma toroidal confinement; NSTX TF joint voltage measurements; National Spherical Torus Experiment; Princeton Plasma Physics Laboratory; electrical joints; electromagnetic forces; fusion reactors; high mechanical stress; high pressure contact; joints apparent electrical resistance; mechanical instrumentation; mechanical support system fabrication; mechanically overstressed joints; ohmic heating coils; plasma confinement scheme; plasma current; pulsed magnetic forces; pulsed operations; pulsed plasma device; sampling digitizers; strong net lateral force; tokamaks; toroidal field magnet system; voltage monitoring waveforms; Conductors; Electric resistance; Magnetic analysis; Magnetic devices; Plasma devices; Plasma waves; Probes; Stress; Toroidal magnetic fields; Voltage measurement;
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.2005.252877
Filename :
4018911
Link To Document :
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