Title :
Solder development and fabrication techniques for coolant tube bonding in toroidal field conductors for the National Spherical Torus experiment
Author :
Jurczynski, S.Z. ; Anderson, M.L. ; Benchoff, J.E. ; Schneider, H. ; Westover, D.M. ; White, W.W.
Author_Institution :
Princeton Plasma Phys. Lab., Princeton, NJ, USA
Abstract :
The National Spherical Torus Experiment (NSTX) is being enhanced to significantly expand the operational space for plasma conditions that are essential for next step Spherical Torus (ST) engineering and scientific development. Improvements to this leading, high performance ST include doubling the magnetic toroidal field (TF) and plasma current with a tenfold increase to the plasma discharge flat top duration. This requires a Center Stack Upgrade (CSU) with almost double the current capability of the TF inner conductors. Bonding water cooling tubes in these new TF Conductors required developing nonionic solder flux and a controlled, repeatable heating technique.
Keywords :
Tokamak devices; discharges (electric); plasma flow; plasma heating; plasma toroidal confinement; Center Stack Upgrade; National Spherical Torus Experiment; TF inner conductors; bonding water cooling tubes; coolant tube bonding; fabrication techniques; magnetic toroidal field; nonionic solder flux; plasma conditions; plasma current; plasma discharge; repeatable heating technique; solder development; spherical torus engineering; toroidal field conductors; Clamps; Conductors; Electron tubes; Heating; Soldering; Temperature measurement; Ettingshausen-Nernst effect; Rockwell B Hardness; SnAg solder; conductive heating; cooling tube; copper conductor; data acquisition; heater control; heating ramp rate; nonionic flux; reducing flame; thermal conduction; thermal expansion; thermocouple probes;
Conference_Titel :
Fusion Engineering (SOFE), 2013 IEEE 25th Symposium on
Conference_Location :
San Francisco, CA
Print_ISBN :
978-1-4799-0169-2
DOI :
10.1109/SOFE.2013.6635322
