Physics basis for a spherical torus power plant

S. C. Jardin, C. E. Kessel, J. Menard, T. K. Mau, R. Miller, F. Najmabadi, V. S. Chan, L. L. Lao, Y. R. Linliu, R. L. Miller, T. Petrie, P. A. Politzer, A. D. Turnbull

Research output: Contribution to journalArticlepeer-review

29 Scopus citations

Abstract

The spherical torus, or low-aspect-ratio tokamak, is considered as the basis for a fusion power plant. A special class of wall-stabilized high-β high-bootstrap fraction low-aspect-ratio tokamak equilibrium are analyzed with respect to MHD stability, bootstrap current and external current drive, poloidal field system requirements, power and particle exhaust and plasma operating regime. Overall systems optimization leads to a choice of aspect ratio A=1.6, plasma elongation κ=3.4, and triangularity δ=0.64. The design value for the plasma toroidal β is 50%, corresponding to βN=7.4, (based on the toroidal β, not the total β) which is 10% below the ideal stability limit. The bootstrap fraction of 99% greatly alleviates the current drive requirements, with tangential neutral beam injection mainly for profile control and rotation drive. The design is such that 45% of the thermal power is radiated in the plasma by Bremstrahlung and trace Krypton, with Neon in the scrapeoff layer radiating the remainder. The scarcity of spherical torus experimental data caused the design to be based largely on theoretical predictions, some of which may turn out to be overly optimistic. This highlights the need for a strong experimental research program in this area.

Original languageEnglish (US)
Pages (from-to)165-197
Number of pages33
JournalFusion Engineering and Design
Volume65
Issue number2
DOIs
StatePublished - Feb 2003

All Science Journal Classification (ASJC) codes

  • Civil and Structural Engineering
  • Nuclear Energy and Engineering
  • General Materials Science
  • Mechanical Engineering

Keywords

  • Fusion power plant
  • Low-aspect-ratio tokamak
  • Plasma operating regime

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