Title :
Thermal Hydraulic Analysis of the ITER PF and Correction Coils in 15 MA Scenario Operation Using the SuperMagnet Suite of Codes
Author :
Gauthier, Francois ; Bessette, D. ; Dong-Keun Oh
Author_Institution :
Tokamak Dept., ITER Organ., St. Paul-lez-Durance, France
Abstract :
The poloidal field (PF) coils and correction coils (CCs) constitute one of the four hydraulic loops of the ITER magnet system. They are cooled in parallel by the same heat exchanger. The PF coils consist of 6 different pulsed coils while the CCs include 18 coils divided into 3 different sets: bottom, side and top. The PF coils are made of dual-channel NbTi conductors whereas the CCs consist of single-channel NbTi conductors. The SuperMagnet suite of codes can combine 1-D cooling with supercritical helium flow in the ITER conductors and the 2-D heat diffusion across the coils into a full-scale quasi 3-D model. We analyzed the in-coil NbTi conductor performance and the heat load to the cryogenic plant. We also compared the results from Vincenta and SuperMagnet.
Keywords :
conductors (electric); electric conduits; hydraulic systems; niobium compounds; superconducting coils; superconducting magnets; thermal analysis; 1D cooling; 2D heat diffusion; CCs; ITER PF magnet system; NbTi; cable-in-conduit conductor; correction coils; cryogenic plant; current 15 MA; dual-channel conductors; full-scale quasi 3D model; heat exchanger; heat load; hydraulic loops; in-coil conductor performance; poloidal field coils; single-channel conductors; supercritical helium flow; supermagnet suite of codes; thermal hydraulic analysis; Coils; Conductors; Cryogenics; Data models; Heating; Joints; Load modeling; Cable-in-conduit conductor (CICC); ITER; correction coils (CCs); poloidal field (PF) coils; thermal hydraulics;
Journal_Title :
Applied Superconductivity, IEEE Transactions on
DOI :
10.1109/TASC.2013.2283530
