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
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;
Conference_Titel :
Fusion Engineering, 2003. 20th IEEE/NPSS Symposium on
Print_ISBN :
0-7803-7908-X
DOI :
10.1109/FUSION.2003.1425872
