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

  • The EUROfusion Tokamak Exploitation Team
  • , the MAST Upgrade Team
  • Culham Science Centre
  • Technical University of Eindhoven
  • University of York
  • University of Liverpool
  • ENAC-IIC-GEL
  • FOM Institute DIFFER 'Dutch Institute for Fundamental Energy Research'
  • Max-Planck-Institut für Plasmaphysik
  • Dublin City University
  • Oak Ridge National Laboratory
  • VTT Technical Research Centre of Finland Ltd
  • Consorzio Rfx
  • Ev-K2-CNR Committee
  • National Centre for Nuclear Research
  • CEA Cadarache
  • University of Rome
  • Department of Biochemistry and Molecular and Structural Biology
  • Research Centre Julich
  • National Technical University of Athens
  • ENEA Centro Ricerche Frascati
  • Aix-Marseille Université
  • University of Helsinki
  • Institute of Plasma Physics AS CR
  • KTH Royal Institute of Technology
  • Institute of Nuclear Research, National Academy of Sciences in Ukraine
  • Chalmers University of Technology
  • University of Rome “Tor Vergata”
  • Warsaw University of Technology
  • Technical University of Denmark
  • Institute of Plasma Physics and Laser Microfusion
  • Kharkov National University
  • ITER
  • Durham University
  • Laboratorio Nacional de Fusión
  • Plasma and Radiation Physics (INFLPR)
  • Consorzio CREATE
  • University of Seville
  • Instituto Superior Técnico
  • Ghent University
  • Centre for Energy Research
  • Aalto University
  • Universidad Carlos III de Madrid
  • Plasma Science and Fusion Center
  • Koninklijke Militaire School - Ecole Royale Militaire
  • Center for Energy Research
  • Politecnico di Milano
  • Politecnico di Torino
  • Lithuanian Energy Institute
  • Kharkov Institute of Physics and Technology
  • Universitá di Cagliari
  • University of Innsbruck
  • University Roma Tre
  • University of Oxford
  • Heinrich Heine University Düsseldorf
  • Eurofusion PMU
  • IUSTI
  • KU Leuven
  • Tuscia University
  • Vienna University of Technology
  • University of Milano-Bicocca
  • Long Beach VA and University of California
  • Graz University of Technology
  • Earth Sciences
  • Loughborough University
  • Institute for Nuclear Physics
  • Institute of Electronics Bulgarian Academy of Sciences
  • Aristotle University of Thessaloniki
  • Uppsala University
  • Univ.́ Henri Poincaré
  • ASTAR
  • Aix Marseille Université
  • Queen's University of Belfast
  • Università degli Studi di Catania
  • Columbia University
  • University of California, Los Angeles
  • General Atomics
  • University of Strathclyde
  • Lawrence Livermore National Laboratory
  • College of William and Mary
  • University of Warwick
  • The University of Texas at Austin
  • University of Manchester
  • Florida International University
  • Princeton Plasma Physics Laboratory
  • Astrodel LLC
  • Imperial College London
  • University of Tromsø - The Arctic University of Norway

Résultats de recherche: Contribution à un journalArticleRevue par des pairs

Résumé

Exhausting 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.)

langue originaleAnglais
Numéro d'article215
journalCommunications Physics
Volume8
Numéro de publication1
Les DOIs
étatPublié - 1 déc. 2025

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