DocumentCode
433731
Title
NSTX TF joint failure and re-design
Author
Neumeyer, C. ; Brooks, A. ; Chrzanowski, J. ; Dudek, L. ; Heitzenroeder, P. ; Kalish, M. ; Williams, M. ; Zatz, I.
Author_Institution
Princeton Plasma Phys. Lab., NJ, USA
fYear
2003
fDate
14-17 Oct. 2003
Firstpage
35
Lastpage
38
Abstract
The toroidal field (TF) coil of the National Spherical Torus Experiment (NSTX) suffered a failure on February 14, 2003, after approximately 3 years of service and 7200 pulses. The failure occurred at an electrical joint connecting one of the radial flags to the inner leg bundle. Damage was extensive such that the coil could not be repaired. Analysis of the failure revealed structural design problems which have been addressed in the re-design effort described herein. Construction of a new TF coil is now underway.
Keywords
Tokamak devices; coils; electromagnets; fusion reactor design; fusion reactor materials; plasma toroidal confinement; NSTX; National Spherical Torus Experiment; electrical joint; inner leg bundle; radial flags; structural design problems; toroidal field coil design; Assembly; Coils; Conductors; Failure analysis; Joining processes; Laboratories; Leg; Physics; Plasmas; Torque;
fLanguage
English
Publisher
ieee
Conference_Titel
Fusion Engineering, 2003. 20th IEEE/NPSS Symposium on
Print_ISBN
0-7803-7908-X
Type
conf
DOI
10.1109/FUSION.2003.1425872
Filename
1425872
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