Discharge Control and Evolution in TFTR

  • D. Mueller
  • M. Bell
  • F. Boody
  • C. Bush
  • J. L. Cecchi
  • S. Davis
  • H. F. Dylla
  • P. C. Efthimion
  • R. J. Hawryluk
  • K. W. Hill
  • S. Kilpatrick
  • P. H. LaMarche
  • D. Manos
  • D. McCune
  • S. S. Medley
  • S. Milora
  • M. Murakami
  • D. K. Owens
  • J. Schivell
  • G. Schmidt
  • S. Sesnic
  • B. Stratton
  • G. Tait
  • M. Ulrickson
  • K. L. Wong
  • R. D. Woolley
  • M. C. Zarnstorff
Part of the Ettore Majorana International Science Series book series (EMISS)

Abstract

The Tokamak Fusion Test Reactor (TFTR) was designed to explore plasma confinement and heating at reactor-like parameters. Since the first plasma in December 1982, considerable progress has been made in this endeavor. During the run period ending April 13, 1985, operation of both the toroidal field and plasma current at full design parameters was achieved. The plasma parameters achieved are summarized in Table 1.

Keywords

Plasma Current Ohmic Heating Vacuum Vessel Minor Radius Neutral Beam Injection 
These keywords were added by machine and not by the authors. This process is experimental and the keywords may be updated as the learning algorithm improves.

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Copyright information

© Springer Science+Business Media New York 1986

Authors and Affiliations

  • D. Mueller
    • 1
  • M. Bell
    • 1
  • F. Boody
    • 1
  • C. Bush
    • 1
  • J. L. Cecchi
    • 1
  • S. Davis
    • 1
  • H. F. Dylla
    • 1
  • P. C. Efthimion
    • 1
  • R. J. Hawryluk
    • 1
  • K. W. Hill
    • 1
  • S. Kilpatrick
    • 1
  • P. H. LaMarche
    • 1
  • D. Manos
    • 1
  • D. McCune
    • 1
  • S. S. Medley
    • 1
  • S. Milora
    • 1
  • M. Murakami
    • 1
  • D. K. Owens
    • 1
  • J. Schivell
    • 1
  • G. Schmidt
    • 1
  • S. Sesnic
    • 1
  • B. Stratton
    • 1
  • G. Tait
    • 1
  • M. Ulrickson
    • 1
  • K. L. Wong
    • 1
  • R. D. Woolley
    • 1
  • M. C. Zarnstorff
    • 1
  1. 1.Princeton Plasma Physics LaboratoryPrinceton UniversityPrincetonUSA

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