Doorgaan naar hoofdnavigatie Doorgaan naar zoeken Ga verder naar hoofdinhoud

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

  • The EUROfusion Tokamak Exploitation Team
  • , the MAST Upgrade Team
  • EURATOM-UKAEA Association Culham Science Centre
  • Eindhoven University of Technology
  • University of York
  • University of Liverpool
  • École Polytechnique Fédérale de Lausanne
  • FOM Institute DIFFER
  • Max Planck Institute for Plasma Physics
  • Dublin City University
  • Oak Ridge National Laboratory
  • VTT Technical Research Centre of Finland
  • Consorzio Rfx
  • CNR
  • Narodowe Centrum Badań Jadrowych
  • Commissariat à l'Énergie Atomique et aux Énergies Alternatives
  • Sapienza University of Rome
  • Jozef Stefan Institute
  • FORSCHUNGSZENTRUM JULICH GMBH
  • National Technical University of Athens
  • ENEA Centro Ricerche Frascati
  • Université Aix Marseille
  • University of Helsinki
  • Institute of Plasma Physics, Academy of Sciences of the Czech Republic
  • ITER
  • University of Ghent
  • Technical University of Denmark
  • KU Leuven
  • KTH Royal Institute of Technology
  • Institute for Nuclear Research
  • Chalmers University of Technology
  • University of Rome Tor Vergata
  • Warsaw University of Technology
  • Institute of Plasma Physics and Laser Microfusion
  • V.N. Karazin Kharkiv National University
  • Durham University
  • Laboratorio Nacional de Fusión
  • National Institute for Laser, Plasma and Radiation Physics
  • Consorzio CREATE
  • University of Seville
  • Instituto Superior Técnico
  • Ecole Polytechnique
  • Centre for Energy Research
  • Aalto University
  • Universidad Carlos III de Madrid
  • MIT Plasma Science and Fusion Center
  • Center for Energy Research
  • Politecnico di Milano
  • Politecnico di Torino
  • Lithuanian Energy Institute
  • National Science Center Kharkiv Institute of Physics and Technology
  • University of Cagliari
  • Universitat Innsbruck
  • Roma Tre University
  • University of Oxford
  • Heinrich-Heine University Düsseldorf
  • EUROfusion
  • University of Tuscia
  • Vienna University of Technology
  • University of Milano-Bicocca
  • University of California, Irvine
  • Technische Universität Graz
  • Barcelona Supercomputing Center
  • Loughborough University
  • Institute of Nuclear Physics PAN
  • Institute of Electronics, Bulgarian Academy of Sciences
  • Aristotle University of Thessaloniki
  • Uppsala Universitet
  • Institut Jean Lamour
  • Technology and Research (A∗STAR)
  • Queens University
  • 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
  • University of Texas at Austin
  • University of Manchester
  • Fiu
  • Princeton Plasma Physics Laboratory
  • Astrodel LLC
  • Imperial College London
  • UiT the Arctic University of Norway

Onderzoeksoutput: Bijdrage aan een tijdschriftArtikelpeer review

13 Citaten (Scopus)

Samenvatting

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.)

Originele taal-2Engels
Artikelnummer215
TijdschriftCommunications Physics
Volume8
Nummer van het tijdschrift1
DOI's
StatusGepubliceerd - dec 2025

Vingerafdruk

Duik in de onderzoeksthema's van 'Divertor shaping with neutral baffling as a solution to the tokamak power exhaust challenge'. Samen vormen ze een unieke vingerafdruk.

Citeer dit