Počet záznamů: 1  

Front face shaping of the inner wall tiles in the COMPASS Upgrade tokamak

  1. 1.
    SYSNO ASEP0578059
    Druh ASEPJ - Článek v odborném periodiku
    Zařazení RIVJ - Článek v odborném periodiku
    Poddruh JČlánek ve WOS
    NázevFront face shaping of the inner wall tiles in the COMPASS Upgrade tokamak
    Tvůrce(i) Gerardin, Jonathan (UFP-V) ORCID
    Balner, Vojtěch (UFP-V)
    Dejarnac, Renaud (UFP-V) RID, ORCID
    Imríšek, Martin (UFP-V) RID
    Jaulmes, Fabien (UFP-V) ORCID
    Komm, Michael (UFP-V) RID, ORCID
    Peterka, Matěj (UFP-V) RID, ORCID
    Vondráček, Petr (UFP-V) RID, ORCID
    Celkový počet autorů8
    Číslo článku113731
    Zdroj.dok.Fusion Engineering and Design. - : Elsevier - ISSN 0920-3796
    Roč. 194, September (2023)
    Poč.str.9 s.
    Jazyk dok.eng - angličtina
    Země vyd.NL - Nizozemsko
    Klíč. slovapower deposition ; divertor ; design ; Plasma facing components ; Field line tracing ; Charged particles heat flux ; Shaping ; Shortwave misalignment
    Vědní obor RIVBL - Fyzika plazmatu a výboje v plynech
    Obor OECDFluids and plasma physics (including surface physics)
    CEPEF16_019/0000768 GA MŠMT - Ministerstvo školství, mládeže a tělovýchovy
    Způsob publikováníOpen access
    Institucionální podporaUFP-V - RVO:61389021
    UT WOS000983825900001
    EID SCOPUS85152238234
    DOI https://doi.org/10.1016/j.fusengdes.2023.113731
    AnotaceThe central column of the COMPASS Upgrade tokamak, where the plasma discharges will be started and shut down, is covered by a continuous first wall composed of 8 bulk tungsten guard limiters with recessed Inconel tiles in between. In diverted configurations, the plasma will be limited for a short duration (similar to 0.2 s-0.4 s) during the plasma current ramp-up and ramp-down phases but high heat fluxes due to short power decay lengths are foreseen. An adapted shaping is therefore needed to spread the heat loads over a maximum area. A novel method taking into account the different magnetic equilibria and the incident angle of the field lines was used to design a roof shape able to ensure a constant heat flux on the toroidal direction, accounting for the lambda(gnear-SOL) and lambda(gfar-SOL) Due to the diversity of plasma scenarios considered on COMPASS-U, the optimized shape of the inner wall tiles strongly differs from one scenario to another, thus a compromise has to be found among all foreseen scenarios. The tile shaping also needs to take into account possible short wave misalignments. Calculations with the 3D magnetic field line tracing code PFCFlux validates the design, confirming the constant toroidal profile of deposited heat flux for the COMPASS-U workhorse scenarios, or slightly decreasing or increasing heat flux profiles (from the center to the sides of the tile) for scenarios with smaller or higher lambda(gnear-SOL) respectively, within the expected large range (1.7 mm<lambda(gnear-SOL)<5 mm), but still providing acceptable loads. Estimated heat fluxes are in the range of 5 MW/m(2) to 35 MW/m(2) on the 8 guard limiters, receiving 70%-80% of the power deposited to the inner wall. In case of shortwave misalignments up to 0.5 mm in the radial direction, calculations show that leading edges are still protected, confirming the robustness of the design.
    PracovištěÚstav fyziky plazmatu
    KontaktVladimíra Kebza, kebza@ipp.cas.cz, Tel.: 266 052 975
    Rok sběru2024
    Elektronická adresahttps://www.sciencedirect.com/science/article/pii/S0920379623003149?via%3Dihub
Počet záznamů: 1  

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