DocumentCode :
298237
Title :
Design of the TFTR TF coil alternate coolant system
Author :
Walton, G.R. ; Brooks, A. ; Harnsberger, D.A. ; Murray, H. ; Satkofsky, J.
Author_Institution :
Plasma Phys. Lab., Princeton Univ., NJ, USA
Volume :
1
fYear :
1993
fDate :
11-15 Oct 1993
Firstpage :
325
Abstract :
The Tokamak Fusion Test Reactor (TFTR) toroidal field (TF) system consists of twenty coils which when operated with deionized water as the coolant has a maximum pulsed operating current and I2T of 73.3 kA and 5.4 E10 A2-s respectively. With deionized water as the primary coolant, the pulse repetition rate is 300 s, which is dependent upon the cooling system efficiency. Numerous small water leaks in several TF coils occurred which have adversely impacted machine operations. These leaks have resulted in a reduction of the TF coil´s resistance to ground. Various leak repair techniques have been successfully used. However, the leaks which cannot be exactly located have a history of reoccurring after repairs have been made. An alternative approach to coil cooling has been implemented which replaces the deionized water with a nonconductive fluid. This fluid should prevent the degradation of the coil resistance because it will retain its high dielectric strength, even if it wets the coil insulation. Perfluoroheptane was chosen from a number of dielectric fluids because of its compatibility with existing materials in the TF coil circuit, chemical and radiation stability, and environmental acceptability. This fluid has reduced thermal capacity which decreases the TF coil I2 T to 4.84 E10 A2-s with an increased repetition rate to 900 s
Keywords :
Tokamak devices; coils; cooling; fusion reactor design; fusion reactors; 73.3 kA; H2O; TFTR; Tokamak Fusion Test Reactor; coil resistance; cooling system; deionized water; dielectric fluid; leak repair; nonconductive fluid; perfluoroheptane; toroidal field coil; water leaks; Coils; Coolants; Cooling; Degradation; Dielectric breakdown; Fusion reactor design; History; Inductors; System testing; Tokamaks;
fLanguage :
English
Publisher :
ieee
Conference_Titel :
Fusion Engineering, 1993., 15th IEEE/NPSS Symposium on
Conference_Location :
Hyannis, MA
Print_ISBN :
0-7803-1412-3
Type :
conf
DOI :
10.1109/FUSION.1993.518341
Filename :
518341
Link To Document :
بازگشت