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Liquid metal test divertor in tokamak COMPASS (SPPT 2018, Prague)
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SYSNO ASEP 0491927 Document Type O - Others R&D Document Type Others Title Liquid metal test divertor in tokamak COMPASS (SPPT 2018, Prague) Author(s) Horáček, Jan (UFP-V) RID, ORCID
Entler, Slavomír (UFP-V) ORCID
Weinzettl, Vladimír (UFP-V) RID, ORCID
Dejarnac, Renaud (UFP-V) RID, ORCID
Vondráček, Petr (UFP-V) RID, ORCID
Hromádka, Jakub (UFP-V)
Šesták, David (UFP-V) RID
Adámek, Jiří (UFP-V) RID, ORCID
Kovařík, Karel (UFP-V) RID, ORCID
Hron, Martin (UFP-V) RID, ORCIDYear of issue 2018 Language eng - English Country CZ - Czech Republic Keywords tokamak ; COMPASS Subject RIV BL - Plasma and Gas Discharge Physics OECD category Fluids and plasma physics (including surface physics) R&D Projects GA16-14228S GA ČR - Czech Science Foundation (CSF) Institutional support UFP-V - RVO:61389021 Annotation 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
Workplace Institute of Plasma Physics Contact Vladimíra Kebza, kebza@ipp.cas.cz, Tel.: 266 052 975 Year of Publishing 2019
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