Divertor shaping with neutral baffling as a solution to the tokamak power exhaust challenge

dc.contributorAalto-yliopistofi
dc.contributorAalto Universityen
dc.contributor.authorMoulton, D.
dc.contributor.authorHakola, A.
dc.contributor.authorYang, H.
dc.contributor.authorVarje, J.
dc.contributor.authorSun, H. J.
dc.contributor.authorSolokha, V.
dc.contributor.authorSnicker, A.
dc.contributor.authorSmith, S.
dc.contributor.authorSipilä, S.
dc.contributor.authorSimpson, J.
dc.contributor.authorSilva, C.
dc.contributor.authorSharma, R.
dc.contributor.authorSchneider, P.
dc.contributor.authorSärkimäki, K.
dc.contributor.authorSantos, J.
dc.contributor.authorSand, A.
dc.contributor.authorSanchis, L.
dc.contributor.authorSalmi, A.
dc.contributor.authorRyan, P.
dc.contributor.authorRossi, R.
dc.contributor.authorRees, D.
dc.contributor.authorOllus, P.
dc.contributor.authorNielsen, S. K.
dc.contributor.authorMarin, M.
dc.contributor.authorLiang, Y.
dc.contributor.authorLeerink, S.
dc.contributor.authorKumpulainen, H.
dc.contributor.authorKumar, U.
dc.contributor.authorKiviniemi, T.
dc.contributor.authorKirjasuo, A.
dc.contributor.authorKing, D.
dc.contributor.authorKim, H. T.
dc.contributor.authorKarhunen, J.
dc.contributor.authorJärvinen, A.
dc.contributor.authorHuang, Z.
dc.contributor.authorHuang, J.
dc.contributor.authorHorsten, N.
dc.contributor.authorGroth, M.
dc.contributor.authorFeng, X.
dc.contributor.authorFakhrayi Mofrad, N.
dc.contributor.authorEriksson, J.
dc.contributor.authorChen, H.
dc.contributor.authorChandra, R.
dc.contributor.authorCai, J.
dc.contributor.authorAlbert Devasagayam, F. C.P.
dc.contributor.authorRose, E.
dc.contributor.authorMartin, R.
dc.contributor.authorLomanowski, B. A.
dc.contributor.authorLiu, Y. Q.
dc.contributor.authorChen, Z. P.
dc.contributor.authorAhmed, S.
dc.contributor.author, EUROfusion Tokamak Exploitation Team
dc.contributor.author, MAST Team
dc.contributor.departmentDepartment of Applied Physicsen
dc.contributor.groupauthorFusion and Plasma Physicsen
dc.contributor.groupauthorNuclear Materials and Engineeringen
dc.contributor.organizationCulham Science Centre
dc.contributor.organizationVTT Technical Research Centre of Finland
dc.contributor.organizationFrench Alternative Energies and Atomic Energy Commission
dc.contributor.organizationUniversidade de Lisboa
dc.contributor.organizationMax-Planck-Institut für Plasmaphysik
dc.contributor.organizationDepartment of Applied Physics
dc.contributor.organizationUniversity of Rome Tor Vergata
dc.contributor.organizationDanmarks Tekniske Universitet
dc.contributor.organizationSwiss Federal Institute of Technology Lausanne
dc.contributor.organizationForschungszentrum Jülich
dc.contributor.organizationKU Leuven
dc.contributor.organizationDurham University
dc.contributor.organizationUppsala University
dc.contributor.organizationUniversity of Seville
dc.contributor.organizationOak Ridge National Laboratory
dc.contributor.organizationGeneral Atomics
dc.contributor.organizationUniversity of Texas at Austin
dc.contributor.organizationUiT The Arctic University of Norway
dc.contributor.organizationMax Planck Institute for Plasma Physics
dc.date.accessioned2025-12-29T18:44:29Z
dc.date.available2025-12-29T18:44:29Z
dc.date.issued2025-05
dc.description.abstractExhausting power from the hot fusion core to the plasma-facing components is one fusion energy’s biggest challenges. The MAST Upgrade tokamak uniquely integrates strong containment of neutrals within the exhaust area (divertor) with extreme divertor shaping capability. By systematically altering the divertor shape, this study shows the strongest evidence to date to our knowledge that long-legged divertors with a high magnetic field gradient (total flux expansion) deliver key power exhaust benefits without adversely impacting the hot fusion core. These benefits are already achieved with relatively modest geometry adjustments that are more feasible to integrate in reactor designs. Benefits include reduced target heat loads and improved access to, and stability of, a neutral gas buffer that ‘shields’ the target and enhances power exhaust (detachment). Analysis and model comparisons shows these benefits are obtained by combining multiple shaping aspects: long-legged divertors have expanded plasma-neutral interaction volume that drive reductions in particle and power loads, while total flux expansion enhances detachment access and stability. Containing the neutrals in the exhaust area with physical structures further augments these shaping benefits. These results demonstrate strategic variation in the divertor geometry and magnetic topology is a potential solution to one of fusion’s power exhaust challenge. (Figure presented.)en
dc.description.versionPeer revieweden
dc.format.extent15
dc.format.mimetypeapplication/pdf
dc.identifier.citationMoulton, D, Hakola, A, Yang, H, Varje, J, Sun, H J, Solokha, V, Snicker, A, Smith, S, Sipilä, S, Simpson, J, Silva, C, Sharma, R, Schneider, P, Särkimäki, K, Santos, J, Sand, A, Sanchis, L, Salmi, A, Ryan, P, Rossi, R, Rees, D, Ollus, P, Nielsen, S K, Moulton, D, Marin, M, Liang, Y, Leerink, S, Kumpulainen, H, Kumar, U, Kiviniemi, T, Kirjasuo, A, King, D, Kim, H T, Karhunen, J, Järvinen, A, Huang, Z, Huang, J, Horsten, N, Hakola, A, Groth, M, Feng, X, Fakhrayi Mofrad, N, Eriksson, J, Chen, H, Chandra, R, Cai, J, Albert Devasagayam, F C P, Rose, E, Martin, R, Lomanowski, B A, Liu, Y Q, King, D, Chen, Z P, Ahmed, S, EUROfusion Tokamak Exploitation Team & MAST Team 2025, 'Divertor shaping with neutral baffling as a solution to the tokamak power exhaust challenge', Communications Physics, vol. 8, 215, pp. 1-15. https://doi.org/10.1038/s42005-025-02121-1en
dc.identifier.doi10.1038/s42005-025-02121-1
dc.identifier.issn2399-3650
dc.identifier.otherPURE UUID: 54d5ae88-b8c2-4ab2-8d08-0eac1d8518ea
dc.identifier.otherPURE ITEMURL: https://research.aalto.fi/en/publications/54d5ae88-b8c2-4ab2-8d08-0eac1d8518ea
dc.identifier.otherPURE FILEURL: https://research.aalto.fi/files/204164509/Divertor_shaping_with_neutral_baffling_as_a_solution_to_the_tokamak_power_exhaust_challenge.pdf
dc.identifier.urihttps://aaltodoc.aalto.fi/handle/123456789/141495
dc.identifier.urnURN:NBN:fi:aalto-202512299603
dc.language.isoenen
dc.publisherNature Publishing Group
dc.relation.ispartofseriesCommunications Physicsen
dc.relation.ispartofseriesVolume 8, pp. 1-15en
dc.rightsopenAccessen
dc.rightsCC BY-NC-ND
dc.rights.urihttps://creativecommons.org/licenses/by-nc-nd/4.0/
dc.titleDivertor shaping with neutral baffling as a solution to the tokamak power exhaust challengeen
dc.typeA1 Alkuperäisartikkeli tieteellisessä aikakauslehdessäfi
dc.type.versionpublishedVersion

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