Development of a 1D thermofluid code for divertor target plate modeling

Abstract

The Oxford Divertor Thermo-Fluid Code (OxDTFC) is a numerical model to assess and compare the steady state thermo-fluid performance of the cooling systems present in the divertor target plate region of a fusion tokamak. Two water-cooled divertor target plate concepts have been used to demonstrate the model: an ITER-like monoblock system and the High Pressure Jet Cascade (HPJC) modular concept, developed by the University of Oxford. Validation of the model was carried out by comparing results for the ITER-like monoblock system with experimental and numerical data in the literature. This comparison showed that the model could quickly and accurately replicate divertor target plate thermo-fluid results across various coolant flow rates, incident heat fluxes, and geometric parameters. OxDTFC is used to compare the performance of the ITER-like monoblock and HPJC systems under equivalent target plate power loading. In this analysis, for equivalent peak heat sink temperatures and thermal loading conditions, the HPJC cooling system was found to have pumping power requirements of ∼65% and coolant flow rates of ∼50% less than a comparable ITER-like monoblock system.