Lithium as a plasma facing component to optimize the edge plasma

R. Maingi, R. Majeski, J. E. Menard, M. A. Jaworski, R. Kaita

Research output: Chapter in Book/Report/Conference proceedingConference contribution

1 Scopus citations

Abstract

The use of lithium to coat plasma-facing components (PFCs) or serve directly as liquid PFCs has resulted in energy confinement improvement in several devices. Coupled with the demonstrated ability of liquid Li to exhaust high power fluxes, the use of Li could resolve the two leading problems of high-Z PFCs. The effect of Li in NSTX, EAST, and DIII-D is compared, and common features are identified. A compact spherical tokamak-based Fusion Nuclear Science Facility design could deliver an attractive neutral wall loading for materials testing, with Li PFCs enabling access to the required high confinement scenarios.

Original languageEnglish (US)
Title of host publication2015 IEEE 26th Symposium on Fusion Engineering, SOFE 2015
PublisherInstitute of Electrical and Electronics Engineers Inc.
ISBN (Electronic)9781479982646
DOIs
StatePublished - May 31 2016
Event26th IEEE Symposium on Fusion Engineering, SOFE 2015 - Austin, United States
Duration: May 31 2015Jun 4 2015

Publication series

NameProceedings - Symposium on Fusion Engineering
Volume2016-May

Other

Other26th IEEE Symposium on Fusion Engineering, SOFE 2015
Country/TerritoryUnited States
CityAustin
Period5/31/156/4/15

All Science Journal Classification (ASJC) codes

  • Nuclear and High Energy Physics
  • Nuclear Energy and Engineering

Keywords

  • energy confinement
  • impurities
  • lithium
  • plasma facing components
  • power exhaust

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