The Central Solenoid Model Coil (CSMC) of the International Thermonuclear E
xperimental Reactor (ITER) will be installed and tested in 1999 - 2000 in a
test facility at the Japan Atomic Energy Research Institute (JAERI) in Jap
an. 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 conducto
r samples. Simulation of the high field layer conductor performance has bee
n performed for operation at 4.5 K by a 1-D thermohydraulic flow analysis c
ode which also includes elements of the cryoplant facility. The simulation
results show that the temperature of the conductor after the operation rise
s up to 6.0K 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 dat
a base with the thermohydraulic behavior of the Model Coil, and the experim
ents in turn can validate the simulation.