DocumentCode
1314003
Title
Predicted thermohydraulic performance of the ITER Central Solenoid Model Coil conductors
Author
Takigami, H. ; Mitchell, Neil ; Okuno, K. ; Zapretilina, E. ; Abramovich, S. ; Bessette, D.
Author_Institution
ITER Joint Central Team, Ibaraki, Japan
Volume
10
Issue
1
fYear
2000
fDate
3/1/2000 12:00:00 AM
Firstpage
1070
Lastpage
1073
Abstract
The Central Solenoid Model Coil (CSMC) of the International Thermonuclear Experimental Reactor (ITER) will be installed and tested in 1999-2000 in a test facility at the Japan Atomic Energy Research Institute (JAERI) in Japan. The expected cable performance is predicted based on the strand data on RRR, n-value, critical current density, hysteresis loss measured for each production batch, as well as AC loss characterization on full size conductor samples. Simulation of the high field layer conductor performance has been performed for operation at 4.5 K by a 1-D thermohydraulic flow analysis code which also includes elements of the cryoplant facility. The simulation results show that the temperature of the conductor after the operation rises up to 6.0 K from the initial temperature of 4.5 K due to ac losses of the conductor, and the pressure rises up to 0.64 MPa from the initial pressure of 0.3 MPa. Thus, the simulation can correlate the strand and conductor data base with the thermohydraulic behavior of the Model Coil, and the experiments in turn can validate the simulation.
Keywords
flow simulation; fusion reactor design; superconducting coils; superconducting magnets; 0.3 MPa; 1D thermohydraulic flow simulation; 4.5 K; AC loss; ITER Central Solenoid Model Coil conductor; cryoplant facility; superconducting cable; Atomic layer deposition; Atomic measurements; Coils; Communication cables; Conductors; Inductors; Solenoids; Temperature; Test facilities; Testing;
fLanguage
English
Journal_Title
Applied Superconductivity, IEEE Transactions on
Publisher
ieee
ISSN
1051-8223
Type
jour
DOI
10.1109/77.828417
Filename
828417
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