DocumentCode :
785544
Title :
Model of heat deposition during fast discharge tests of the ITER toroidal field model coil
Author :
Hertout, P. ; Bleyer, A. ; Duchateau, J.L. ; Martinez, A. ; Nicollet, S.
Author_Institution :
Euratom-CEA Assoc., St. Paul-Lez-Durance, France
Volume :
12
Issue :
1
fYear :
2002
fDate :
3/1/2002 12:00:00 AM
Firstpage :
1426
Lastpage :
1429
Abstract :
In the framework of the ITER (International Thermonuclear Experimental Reactor) project, the TFMC (Toroidal Field Model Coil) has been manufactured by European industry, using about 800 m of a 80 kA Nb3Sn cable-in-conduit conductor to wind the 98 turns of the coil. These turns are wound in 10 pancakes which are inserted inside machined stainless steel radial plates, and the whole winding pack is enclosed in a thick stainless steel casing. These passive conductive structures are expected to experience severe induced eddy currents and associated Joule heating during the last testing phase of the TFMC, when fast discharges are triggered to study the electromagnetic and thermal-hydraulic transient behavior of the coil. Diffusing through insulation, the Joule heating induced in the radial plates will add to the AC losses induced in the superconducting cable. The AC losses along the TFMC winding pack are deduced from accurate magnetic field computations performed by the 3-D magneto-static code TRAPS, the eddy currents are calculated with an analytical model using circuit equations, and the Joule heating diffusion is studied with a 1-D thermal analysis model. Using these heat loads as input data, the helium temperature and pressure increases in the conductor are computed with the finite element code GANDALF. The possibility of a quench of the whole magnet is discussed.
Keywords :
eddy currents; finite element analysis; fusion reactor design; fusion reactor materials; niobium alloys; nuclear engineering computing; superconducting coils; superconducting magnets; tin alloys; type II superconductors; 3D magnetostatic code; 80 kA; 800 m; AC losses; GANDALF; ITER toroidal field model coil; International Thermonuclear Experimental Reactor; Joule heating; Nb3Sn; TFMC; TRAPS; Toroidal Field Model Coil; cable-in-conduit conductor; eddy currents; fast discharge tests; finite element code; fusion reactor; heat deposition; magnet quenching; passive conductive structures; stainless steel radial plates; superconducting magnets; Coils; Conductors; Eddy currents; Heating; Inductors; Steel; Superconducting magnets; Testing; Toroidal magnetic fields; Virtual manufacturing;
fLanguage :
English
Journal_Title :
Applied Superconductivity, IEEE Transactions on
Publisher :
ieee
ISSN :
1051-8223
Type :
jour
DOI :
10.1109/TASC.2002.1018670
Filename :
1018670
Link To Document :
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