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. Model validation was carried out by comparing results for the ITER-like monoblock system with experimental and numerical data in the literature. This comparison showed OxDTFC could 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 thermal boundary conditions. This analysis shows the HPJC system has pumping power requirements of ∼65% and coolant flow rates of ∼50% less than a comparable ITER-like monoblock system.