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Front face shaping of the inner wall tiles in the COMPASS Upgrade tokamak
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SYSNO ASEP 0578059 Druh ASEP J - Článek v odborném periodiku Zařazení RIV J - Článek v odborném periodiku Poddruh J Článek ve WOS Název Front 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, ORCIDCelkový počet autorů 8 Číslo článku 113731 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. slova power deposition ; divertor ; design ; Plasma facing components ; Field line tracing ; Charged particles heat flux ; Shaping ; Shortwave misalignment Vědní obor RIV BL - Fyzika plazmatu a výboje v plynech Obor OECD Fluids and plasma physics (including surface physics) CEP EF16_019/0000768 GA MŠMT - Ministerstvo školství, mládeže a tělovýchovy Způsob publikování Open access Institucionální podpora UFP-V - RVO:61389021 UT WOS 000983825900001 EID SCOPUS 85152238234 DOI https://doi.org/10.1016/j.fusengdes.2023.113731 Anotace The 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. Pracoviště Ústav fyziky plazmatu Kontakt Vladimíra Kebza, kebza@ipp.cas.cz, Tel.: 266 052 975 Rok sběru 2024 Elektronická adresa https://www.sciencedirect.com/science/article/pii/S0920379623003149?via%3Dihub
Počet záznamů: 1