Spherical tokamaks: Present status and role in the development of fusion power

A. W. Morris, R. J. Akers, G. F. Counsell, T. C. Hender, B. Lloyd, A. Sykes, G. M. Voss, H. R. Wilson

Research output: Contribution to journalArticlepeer-review

21 Scopus citations

Abstract

The spherical tokamak (ST) has triggered a fast-growing activity world-wide on account of its promising potential and its strong physics overlap with conventional tokamaks, including ITER. There has long been a view that it could have a key role as a component test facility, to complement ITER, IFMIF, and DEMO, and there are also interesting possibilities as an option for the fusion power source of an electricity plant. The experimental base is now considerably advanced from the time when these ideas were first raised, with the advent of the MA scale machines MAST and NSTX, and a growing theoretical and modelling base. Here, we describe the status of development on the key engineering and physics issues of the ST, considering in particular application to a component test facility and input to an accelerated programme towards deployed fusion power plants, the so-called "fast track".

Original languageEnglish
Pages (from-to)67-75
Number of pages9
JournalFusion Engineering and Design
Volume74
Issue number1-4
DOIs
StatePublished - Nov 2005
Externally publishedYes

Funding

This work was jointly funded by the United Kingdom Engineering and Physical Sciences Research Council and by EURATOM.

Keywords

  • Component test facility
  • Fast track
  • MAST
  • Spherical tokamak

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