Abstract
The coolant in the ITER cable‐in‐conduit conductors (CICC) flows at significant higher speed in the central channel than in the strand bundle region due to the large difference of hydraulic impedance. When energy is deposited in the bundle region, e.g. by ac loss or radiation, the heat removal in vertically oriented dual channel CICC with the coolant flowing downward is affected by the reduced density of helium (buoyancy) in the bundle region, which is arising from the temperature gradient due to poor heat exchange between the two channels. At large deposited power, flow stagnation and back‐flow can cause in the strand bundle area a slow temperature runaway eventually leading to quench.A new test campaign of the thermal‐hydraulic behavior was carried out in the SULTAN facility on an instrumented section of the ITER Poloidal Field Conductor Insert (PFIS). The buoyancy‐gravity effect was investigated using ac loss heating, with ac loss in the cable calibrated in separate runs. The extent of upstream tempera...
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