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Liquid metal test divertor in tokamak COMPASS (SPPT 2018, Prague)

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    0491927 - ÚFP 2019 RIV CZ eng O - Others
    Horáček, Jan - Entler, Slavomír - Weinzettl, Vladimír - Dejarnac, Renaud - Vondráček, Petr - Hromádka, Jakub - Šesták, David - Adámek, Jiří - Kovařík, Karel - Hron, Martin
    Liquid metal test divertor in tokamak COMPASS (SPPT 2018, Prague).
    R&D Projects: GA ČR(CZ) GA16-14228S
    EU Projects: European Commission(XE) 633053 - EUROfusion
    Institutional support: RVO:61389021
    Keywords : tokamak * COMPASS
    OECD category: Fluids and plasma physics (including surface physics)

    Předneseno na: SPPT 2018 -Plasma Physics and Technology in Prague ,
    Soid metal plasma-facing components in divertors of thermonuclear reactors will marginally survive in ITER, whilst new approaches are required for the more powerful DEMOnstration power plant. We therefore install in tokamak COMPASS divertor a test target based on liquid lithium/tin. We will exposed it to ITER-relevant surface heat flux (20 MW/m2). Based on precisely measured heat fluxes, our simulations predict its easy survival, the surface temperature rises up to 800°C within 120 ms of the standard ELMy H-mode heat flux with ELM filaments reaching hundreds MW/m2. Consequent strong lithium vaporization will be the major operational limit, observed by spectroscopy, fast visible and infrared cameras. The scientific program will focus on operational issues (redeposition of the evaporated metal, ejection of droplets, fast enough liquid refill) as well as on the effect on the plasma physics (improvement of plasma confinement, L-H power threshold

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