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ICC 2011 and CT Workshops Abstracts Abstract Details
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| gray___ornl_ltx_collaboration___proceedings.pdf | 2011-08-29 13:53:44 | Travis Gray |
| gray___icc_2011_poster.pdf | 2011-08-19 12:16:58 | Travis 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:
