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Predicted thermohydraulic performance of the ITER Central Solenoid Model Coil conductors

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6 Author(s)
Takigami, H. ; ITER Joint Central Team, Ibaraki, Japan ; Mitchell, N. ; Okuno, K. ; Zapretilina, E.
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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.

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Applied Superconductivity, IEEE Transactions on  (Volume:10 ,  Issue: 1 )