Particle control and plasma performance in the Lithium Tokamak eXperiment

  • R. Majeski
  • , T. Abrams
  • , D. Boyle
  • , E. Granstedt
  • , J. Hare
  • , C. M. Jacobson
  • , R. Kaita
  • , T. Kozub
  • , B. Leblanc
  • , D. P. Lundberg
  • , M. Lucia
  • , E. Merino
  • , J. Schmitt
  • , D. Stotler
  • , T. M. Biewer
  • , J. M. Canik
  • , T. K. Gray
  • , R. Maingi
  • , A. G. McLean
  • , S. Kubota
  • W. A. Peebles, P. Beiersdorfer, J. H.T. Clementson, K. Tritz

Research output: Contribution to journalArticlepeer-review

28 Scopus citations

Abstract

The Lithium Tokamak eXperiment is a small, low aspect ratio tokamak [Majeski, Nucl. Fusion 49, 055014 (2009)], which is fitted with a stainless steel-clad copper liner, conformal to the last closed flux surface. The liner can be heated to 350 °C. Several gas fueling systems, including supersonic gas injection and molecular cluster injection, have been studied and produce fueling efficiencies up to 35%. Discharges are strongly affected by wall conditioning. Discharges without lithium wall coatings are limited to plasma currents of order 10 kA, and discharge durations of order 5 ms. With solid lithium coatings discharge currents exceed 70 kA, and discharge durations exceed 30 ms. Heating the lithium wall coating, however, results in a prompt degradation of the discharge, at the melting point of lithium. These results suggest that the simplest approach to implementing liquid lithium walls in a tokamak - thin, evaporated, liquefied coatings of lithium - does not produce an adequately clean surface.

Original languageEnglish
Article number056103
JournalPhysics of Plasmas
Volume20
Issue number5
DOIs
StatePublished - May 2013

Funding

This work supported by USDoE Contract Nos. DE-AC02-09CH11466 and DE-AC05-00OR22725.

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