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Measurements of Impurity Emission and Preliminary Modeling of Edge Plasmas in the Lithium Tokamak Experiment (LTX)

Author: Travis K Gray
Requested Type: Poster Only
Submitted: 2012-12-07 15:08:42

Co-authors: JM Canik, EM Grandstedt, J Hare2, TM Biewer, DP Boyle, CM Jacobson, R Kaita, BP LeBlanc, M Lucia, R Maingi, RP Majeski, JC Schmitt

Contact Info:
ORNL
PO Box 451
Princeton, NJ   08543-0
USA

Abstract Text:
The Lithium Tokamak Experiment (LTX)[1] is designed to provide approximately 90% of the plasma facing surfaces with very low recycling wall utilizing liquid lithium. However, as has been demonstrated on NSTX, the presence of impurities, namely oxygen, can greatly effect the deuterium pumping capacity of lithium[2]. Therefore, measurements of impurity behavior in the edge plasma are necessary to understand the pumping behavior of the liquid lithium surface. On LTX this is accomplished with compact spectrometers (380—590 nm)[3] and filterscopes[4] viewing the center stack as well as the inner and outer limiters. Preliminary modeling of edge plasmas in LTX will be accomplished using the SOLPS (B2.5/EIRENE) code and constraining the simulation with experimental measurements similar to the analysis that was performed on NSTX[5]. Preliminary modeling will be presented and compared with results obtained on NSTX with evaporative lithium coatings.

This work is supported by US DOE contracts DE-AC05-00OR22725 and DE-AC02- 09CH11466.
[1] R Majeski, et al., Nucl. Fusion. 49 (2009) 055014
[2] JP Allain and CN Taylor, Phys. Plasmas. 19(5) (2012) 056126
[3] TK Gray, et al., to be submitted to Rev. Sci. Instrum. (2013)
[4] RJ Colchin, et al., Rev. Sci. Instrum. 74(3) (2003) 2068-2070
[5] JM Canik, et al., Phys. Plasmas. 18(5) (2011) 056118

Characterization: 3.0

Comments:
Placement next to TM Biewer's poster and any other LTX posters