Skip to main navigation Skip to search Skip to main content

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

  • United Kingdom Atomic Energy Authority (UKAEA)
  • Eindhoven University of Technology (TU/e)
  • University of York
  • University of Liverpool
  • Ecole Polytechnique Fédérale de Lausanne (EPFL)
  • Dutch Institute for Fundamental Energy Research (DIFFER)
  • Max-Planck-Institut für Plasmaphysik (IPP)
  • Dublin City University
  • Oak Ridge National Laboratory (ORNL)
  • National Research Council (CNR)
  • National Centre for Nuclear Research (NCBJ)
  • Commissariat a l'Energie Atomique et aux Energies Alternatives (CEA)
  • Sapienza University of Rome
  • Jožef Stefan Institute
  • Forschungszentrum Jülich GmbH (FZJ)
  • National Technical University of Athens
  • National Agency for New Technologies, Energy and Sustainable Economic Development (ENEA)
  • French National Center for Scientific Research (CNRS)
  • Aalto University
  • University of Helsinki
  • General Atomics

Research output: Contribution to journalArticleScientificpeer-review

Abstract

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.)

Original languageEnglish
Article number215
JournalCommunications Physics
Volume8
Issue number1
DOIs
Publication statusPublished - Dec 2025
MoE publication typeA1 Journal article-refereed

Funding

This work has received support from EPSRC Grants EP/T012250/1, EP/N023846/1 and EP/W006839/1. This work is supported by US Department of Energy, Office of Fusion Energy Sciences under the Spherical Tokamak programme, contract DE-AC05-00OR22725. This work has been carried out within the framework of the EUROfusion Consortium, partially funded by the European Union via the Euratom Research and Training Programme (Grant Agreement No 101052200 – EUROfusion). The Swiss contribution to this work has been funded by the Swiss State Secretariat for Education, Research and Innovation (SERI). Views and opinions expressed are however those of the author(s) only and do not necessarily reflect those of the European Union, the European Commission or SERI. Neither the European Union nor the European Commission nor SERI can be held responsible for them.

UN SDGs

This output contributes to the following UN Sustainable Development Goals (SDGs)

  1. SDG 7 - Affordable and Clean Energy
    SDG 7 Affordable and Clean Energy

Fingerprint

Dive into the research topics of 'Divertor shaping with neutral baffling as a solution to the tokamak power exhaust challenge'. Together they form a unique fingerprint.

Cite this