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gray___ornl_ltx_collaboration___proceedings.pdf2011-08-29 13:53:44Travis Gray
gray___icc_2011_poster.pdf2011-08-19 12:16:58Travis Gray

Preliminary measurements of edge impurity fluxes in the lithium tokamak experiment

Author: Travis K Gray
Requested Type: Poster Only
Submitted: 2011-06-10 15:03:44

Co-authors: D.P. Boyle, E.M. Granstedt, T.M. Biewer, R. Kaita, A.G. McLean, R. Maingi, R. Majeski

Contact Info:
ORNL/ORISE
PO BOX 451
Princeton, NJ   08543-0
USA

Abstract Text:
Previous research on CDX-U and NSTX has demonstrated that liquid lithium and lithium wall conditioning in general can substantially alter the edge plasma in tokamaks. By providing a low recycling plasma facing surface, global plasma properties such as particle and energy confinement are increased [1, 2]. Following the successful use of liquid lithium in CDX-U, the Lithium Tokamak Experiment (LTX)[3] is designed to provide approximately 90% of the plasma facing surface with a near zero recycling wall. Near-term research involves measurement of impurity fluxes and transport from the close-fitting, lithium coated shell of LTX. This is accomplished with a set of fast (100 kHz) filterscopes, 2 optical spectrometers (380—590 nm) viewing the center-stack and the lower shell respectively with 1 ms time resolution, vacuum ultra-violet spectroscopy and filtered, fast camera images of the shell. Preliminary measurements and analysis of the optical and UV spectra will be presented as a function of lithium wall conditioning.

This work is supported by US DOE contracts DE-AC05-00OR22725 and DE-AC02- 09CH11466.

[1] R Majeski, et al., Phys. Rev. Lett. 97 (2006) 075002
[2] MG Bell, et al., Plasma Phys. Control. Fusion. 51 (2009) 124054
[3] R Majeski, et al., Nucl. Fusion. 49 (2009) 055014

Characterization: A6

Comments:

University of Washington

Workshop on Innovation in Fusion Science (ICC2011) and
US-Japan Workshop on Compact Torus Plasma
August 16-19, 2011
Seattle, Washington

ICC 2011