DocumentCode
973193
Title
Simulations of the ITER Toroidal Field Coil Operation With the VINCENTA Code
Author
Bessette, D. ; Shatil, N. ; Zapretilina, E.
Author_Institution
ITER Int. Team, Garching
Volume
16
Issue
2
fYear
2006
fDate
6/1/2006 12:00:00 AM
Firstpage
795
Lastpage
798
Abstract
Time-dependent thermal-hydraulic analyses of the ITER Toroidal Field (TF) Coils have been performed with a quasi-3D model based on the VINCENTA code. Two primary cooling loops are considered for the case and the winding pack respectively, each of them including a circulation pump and a heat exchanger. The conductor pancakes are cooled in parallel in the winding pack loop, as are the cooling channels in the case loop. Temperature, pressure and velocity of the helium coolant are computed in these channels by the VINCENTA code. This provides boundary conditions for the thermal coupling to 2D heat diffusion carried out in the coil sections. A range of plasma scenarios including plasma disruptions has been simulated. The deposited heat due to ac losses in the conductor, eddy current losses in the structure, thermal radiation, thermal conduction, and nuclear heating, are given as input data. The model has been updated according to recent design changes. It also includes new features such as the calculation of the local electric field along the conductor when operating in the current sharing regime. The main analysis results are presented showing the impact of design and operating parameters. The analysis has been applied to confirm that the range of strand losses and cable coupling losses are acceptable for the conductor
Keywords
diffusion; fusion reactor design; fusion reactor safety; fusion reactor theory; heat conduction; heat exchangers; plasma instability; superconducting cables; superconducting coils; 2D heat diffusion; AC losses; ITER toroidal field coil operation; VINCENTA code; boundary conditions; cable coupling losses; cable-in-conduit; circulation pump; conductor pancakes; current sharing regime; eddy current losses; heat exchanger; helium coolant; local electric field; nuclear heating; plasma disruptions; pressure; primary cooling loops; quasi3D model; strand losses; superconductor; temperature; thermal conduction; thermal coupling; thermal radiation; time-dependent thermal-hydraulic analyses; velocity; winding pack; Coils; Conductors; Coolants; Cooling; Heat pumps; Helium; Performance analysis; Plasma simulation; Plasma temperature; Thermal conductivity; Cable-in-conduit; ITER; superconductor; thermohydraulics;
fLanguage
English
Journal_Title
Applied Superconductivity, IEEE Transactions on
Publisher
ieee
ISSN
1051-8223
Type
jour
DOI
10.1109/TASC.2006.873258
Filename
1642967
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