Evaluation of Transverse Heat Transfer Coefficient in Dual Channel ITER-Like CICCs

The transverse heat transfer coefficient in dual channel cable-in-conduit conductors (CICCs) is a crucial parameter in the design of International Thermonuclear Experimental Reactor (ITER) superconducting coils, as it determines their heat removal capability and thermal stability. This article evaluates the equivalent transverse heat transfer coefficient in dual channel ITER-like CICCs, which utilizes the fractal friction factor correlation for cable bundle proposed by the authors. The good agreement between the evaluated equivalent transverse heat transfer coefficients and experimental data of toroidal field (TF) and poloidal field (PF) samples confirms the validity of model. Furthermore, the comparative analysis with established models demonstrates the wider applicability of the evaluation model presented in this article. The proposed model offers valuable insights into comprehending the transverse heat transfer in dual channel ITER-like CICCs and analyzing the effects of geometric parameters on such heat transfer.