Abstract
The new HTS design concept for the DEMO toroidal field (TF) coil, based on cross-conductor (CroCo) strands, has been proposed by Karlsruhe Institute of Technology (KIT). The coil is layer wound and consists of 12 layers with different jacket radial thickness grades. Two variants of the design are considered, namely Option 8 and 9 with one-in-hand and two-in-hand winding, respectively. The present work is focused on the thermal-hydraulic analysis of the conductors’ design, which includes: (1) hydraulic analysis—calculation of the mass flow rates in each conductor at operating conditions during the dwell time; (2) heat removal analysis aimed at the assessment of the temperature margin at the expected nuclear heat load during the plasma burn; and (3) estimation of the maximum hot spot temperature in each conductor during quench. The analysis is performed using simplified models and the THEA code, and is aimed at verification if the proposed designs fulfill the design requirements for the temperature margin and for the hot spot temperature.
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