DocumentCode :
1949362
Title :
Thermal-hydraulic simulation of 80 kA safety discharge in the ITER Toroidal Field Model Coil (TFMC) using the 4C code
Author :
Richard, L. Savoldi ; Bonifetto, R. ; Zanino, R. ; Heller, R.
Author_Institution :
Dipt. di Energetica, Politec. di Torino, Turino, Italy
fYear :
2011
fDate :
26-30 June 2011
Firstpage :
1
Lastpage :
5
Abstract :
The Toroidal Field Model Coil (TFMC) was extensively tested in 2001-2002, up to maximum transport current of 80 kA and peak field of ~ 10 T, in the TOSKA facility at the Karlsruhe Institute of Technology, Germany. Here we apply the 4C code, which was developed for the analysis of thermal-hydraulic transients in superconducting magnets, including winding, structures and cryogenic circuit, to the analysis of the TFMC safety discharge from 80 kA. The code is able to reproduce the main experimental features, within the limitations due to no more fully available information about the details of the cryogenic circuit, which play here a much more important role than at lower currents.
Keywords :
Tokamak devices; cryogenics; fusion reactor safety; plasma toroidal confinement; superconducting coils; superconducting magnets; ITER toroidal field model coil; TFMC safety discharge; TOSKA facility; cryogenic circuit; superconducting magnets; thermal-hydraulic simulation; winding; Accuracy; Approximation methods; Manifolds; Windings; Nuclear fusion; Simulation; Superconducting magnets; TFMC; Thermal-hydraulics;
fLanguage :
English
Publisher :
ieee
Conference_Titel :
Fusion Engineering (SOFE), 2011 IEEE/NPSS 24th Symposium on
Conference_Location :
Chicago, IL
ISSN :
1078-8891
Print_ISBN :
978-1-4577-0669-1
Electronic_ISBN :
1078-8891
Type :
conf
DOI :
10.1109/SOFE.2011.6052297
Filename :
6052297
Link To Document :
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