Title :
Vacuum compatability of welded joints for NSTX-U
Author :
Denault, M. ; Arose, D.
Author_Institution :
Princeton Plasma Phys. Lab., Princeton, NJ, USA
Abstract :
The high vacuum environment of the National Spherical Torus Experiment (NSTX) cannot tolerate a leak rate of greater than 1 × 10-5 Torr-liters per second or an out-gassing rate of more than 2 × 10-12 Torr-liters per second per cm2. This is maintained with an austenitic 316 stainless steel vacuum vessel. The NSTX Upgrade (NSTX-U) will require large weldments attached to the current vacuum vessel that will become the new vacuum boundary. Due to the lack of superstructure, all loads are passed through the vacuum vessel. This means the welds must carry a substantial load as well as provide vacuum integrity. Distortion of the vessel must also be minimized in order to accommodate precisely-aligned diagnostics as well as to mate to the new second neutral beam. The ideal candidate for these welds is Flux Cored Arc Welding (FCAW). FCAW can deposit a great amount of weld material quickly with minimal heat input. This paper will discuss the vacuum compatibility of FCAW and compare it to other standard welding processes used on NSTX.
Keywords :
Tokamak devices; arc welding; fusion reactor design; fusion reactor materials; heat treatment; stainless steel; vacuum techniques; welds; NSTX upgrade; NSTX-U; National Spherical Torus Experiment; current vacuum vessel; flux cored arc welding; high vacuum environment; leak rate; minimal heat input; neutral beam; out-gassing rate; stainless steel vacuum vessel; standard welding processes; vacuum boundary; vacuum compatibility; vacuum integrity; weld material; welded joints; Welding; Wires;
Conference_Titel :
Fusion Engineering (SOFE), 2011 IEEE/NPSS 24th Symposium on
Conference_Location :
Chicago, IL
Print_ISBN :
978-1-4577-0669-1
Electronic_ISBN :
1078-8891
DOI :
10.1109/SOFE.2011.6052266