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MAST Upgrade Divertor Facility: A Test Bed for Novel Divertor Solutions

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  • A. W. Morris
  • J. R. Harrison
  • A. Kirk
  • B. Lipschultz
  • F. Militello
  • D. Moulton
  • N. R. Walkden


Publication details

JournalIEEE transactions on plasma science
DateAccepted/In press - 16 Feb 2018
DateE-pub ahead of print - 17 Apr 2018
DatePublished (current) - 8 May 2018
Issue number5
Number of pages10
Pages (from-to)1217-1226
Early online date17/04/18
Original languageEnglish


The challenge of integrated exhaust consistent with the other requirements in DEMO and power plant class tokamaks (ITER-like and alternative DEMOs, Fusion Nuclear Science Facility approaches) is well-known and the exhaust solution is likely to be fundamental to the design and operating scenarios chosen. Strategies have been proposed such as high main plasma radiation, but improved solutions are sought and will require revised research methodologies. While no facility can address all the challenges, the new MAST Upgrade tokamak enables exploration of a wide range of divertor plasma aspects in a single device and their relation with the core plasma (e.g., access to H-mode) and in particular the development of fundamental understanding and new ideas. It has a unique combination of closed divertor, capability of a wide range of configurations from conventional to long leg (including Super-X), and fully symmetric double null (plasma and divertor structures). To extrapolate to DEMO and power plant scale devices where full integrated tests in advance are not feasible yet different physics mechanisms may dominate, theory-based models are likely to be essential for confident performance prediction, optimization, and a ``qualification' of the concept. Development and validation of such models is at the heart of the program around MAST Upgrade. Amongst the many areas to be explored, there will be a strong focus on the closely coupled topics of plasma detachment and cross-field transport mechanisms (e.g., plasma filaments), key ingredients of effective and reliable protection of the plasma-facing components at DEMO scale.

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© 2018 Crown Copyright. This is an author-produced version of the published paper. Uploaded in accordance with the publisher’s self-archiving policy. Further copying may not be permitted; contact the publisher for details.

    Research areas

  • Impurities, Legged locomotion, Magnetic cores, Optimization, Physics, Plasmas, Power generation, Divertor, fusion reactor design, plasma exhaust, plasma filaments, super-x, tokamak devices., tokamak devices

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