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  • DEMO design using the SYCOM...
    Reux, C.; Kahn, S.; Zani, L.; Pégourié, B.; Piot, N.; Owsiak, M.; Aiello, G.; Artaud, J.-F.; Boutry, A.; Dardour, S.; Di Gallo, L.; Duchateau, J.-L.; Galassi, D.; Imbeaux, F.; Jaboulay, J.-C.; Magaud, P.; Said, J.; Saoutic, B.; Sardain, P.

    Fusion engineering and design, November 2018, 2018-11-00, 2018-11, Letnik: 136
    Journal Article

    •Advanced technology modules were added to the Sycomore fusion reactor system code.•Increased maximum toroidal field coil steel stresses yield large reactor size reduction.•Increase of the tritium burn-up requires large reactors.•Water-cooled and helium-cooled divertors are equivalent for DEMO1-class pulsed designs. The next step for fusion energy after the ITER tokamak is the demonstration power plant DEMO. In this framework, system codes are used to address high-level key design issues for the DEMO pre-conceptual phase. They aim at capturing the interactions between the subsystems of a fusion reactor. SYCOMORE is a modular system code which includes physics and technology models coupled to an optimizer in order to explore a large design parameter space. In the present paper, trade-off studies focused on technology modules are reported including the influence of some design-driving assumptions on the reactor performances and size, starting from a European DEMO1-like design (more than 500 MW net electric power and 2 h burn duration). The increase of the mechanical stress limits in TF and CS magnets can help reducing the reactor size, slightly more when high temperature superconductors are used in the TF coil. The tritium breeding ratio can be improved to more than 1.10 by a moderate increase of the size, but the tritium burn-up ratio needs one additional meter of major radius for every percent increase. Divertor coolant options are also compared, showing some differences between helium, hot and cold water scenarios at various incident divertor heat fluxes.