Transverse heat transfer coefficient in the dual channel ITER TF CICCs: Part I: Analysis of steady state temperature profiles resulting from annular heating

Two ITER TF dual channel Cable-in-Conduit Conductors (CICCs) have been tested in the SULTAN test facility. The samples were heated either by foil heaters mounted on the outside of the conductor jacket or by induced AC losses. The steady-state temperature response of several thermometers installed on the jacket surface as well as inside the cable were analyzed using the two-channel analytical model proposed by Renard et al. to obtain the equivalent transverse heat transfer coefficient between the bundle and central channel as a function of the mass flow rate. In addition, on the basis of the measured pressure drop and helium flow velocities, the friction factors for helium flow in the bundle and in the central channel were determined. The obtained results may serve as a reference for these cables.

► Thermal–hydraulic behavior of two ITER TF dual channel CICCs analyzed.
► Correlations for the bundle and central channel friction factors discussed.
► Transverse heat transfer coefficient as a function of mass flow rate assessed.
► Radial temperature gradients within the bundle discussed.
► The results may serve as a reference for these cables.