In DEMO, the divertor must endure steady state loads of 10 MW m−2 and transient thermal cycling up to 20 MW m−2. A novel divertor target, termed the Spiral Plate Module (SPM) and designed to meet these loads, was initially optimized by a one-dimensional, steady-state model. The best design was a trade-off between the wall overheat (τ s )—a figure of merit for cooling performanceand the pumping ratio (η P )—a comparison of the pressure drop and the incident heat flux on a target surface. A three-dimensional, steady-state, conjugate heat transfer study showed significant correlation to the one-dimensional model. Compared to other divertor target concepts, the SPM achieved the lowest wall overheat of any target design. The hydraulic performance was also on par with comparable designs, demonstrating a very low pumping ratio. This novel, modular divertor target could be used in future fusion power plants to effectively cool the plasma facing components with low pressure drop.
The Mulberry Harbours were used during the Second World War as part of Operation Overlord, the invasion of northern Europe by the Allies in June 1944. This commenced with the D-Day landings on the Normandy beaches on 6th June. The harbours played an important role in the history of ocean engineering leading to the development of novel technology and new theory. A severe storm occurred soon after the harbours were deployed leading to the destruction of the American harbour and severe damage to the British one. In this paper, we analyse this storm using hindcast data from ECMWF and SWAN modelling. We find that the waves were significantly more severe at the American harbour than at the British one, which may partially explain why the latter experienced less damage. We also find that the usually quoted figure for the storm severity of 1 in 40 years is a reasonable estimate for a summer storm at these locations.
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.
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