Results and future plans of the Lithium Tokamak eXperiment (LTX)

  • J. C. Schmitt
  • , T. Abrams
  • , L. R. Baylor
  • , L. Berzak Hopkins
  • , T. Biewer
  • , D. Bohler
  • , D. Boyle
  • , E. Granstedt
  • , T. Gray
  • , J. Hare
  • , C. M. Jacobson
  • , M. Jaworski
  • , R. Kaita
  • , T. Kozub
  • , B. LeBlanc
  • , D. P. Lundberg
  • , M. Lucia
  • , R. Maingi
  • , R. Majeski
  • , E. Merino
  • A. Ryou, E. Shi, J. Squire, D. Stotler, C. E. Thomas, K. Tritz, L. Zakharov

Research output: Contribution to journalArticlepeer-review

21 Scopus citations

Abstract

The Lithium Tokamak eXperiment (LTX) is a spherical tokamak with the unique capability of studying the low-recycling regime by coating nearly 90% of the first wall with lithium in either solid or liquid form. Several grams of lithium are evaporated onto the plasma-facing side of the first wall. Without lithium coatings, the plasma discharge is limited to less than 5 ms and only 10 kA of plasma current, and the first wall acts as a particle source. With cold lithium coatings, plasma discharges last up to 20 ms with plasma currents up to 70 kA. The lithium coating provides a low-recycling first wall condition for the plasma and higher fueling rates are required to realize plasma densities similar to that of pre-lithium walls. Traditional puff fueling, supersonic gas injection, and molecular cluster injection (MCI) are used. Liquid lithium experiments will begin in 2012.

Original languageEnglish
Pages (from-to)S1096-S1099
JournalJournal of Nuclear Materials
Volume438
Issue numberSUPPL
DOIs
StatePublished - 2013

Funding

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

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