Bulletin of the American Physical Society
64th Annual Meeting of the APS Division of Plasma Physics
Volume 67, Number 15
Monday–Friday, October 17–21, 2022; Spokane, Washington
Session CP11: Poster Session II: In-Person, Hall A (2:00-3:30pm) and Virtual Poster Presentations (3:45-5:00pm)
MFE: Low Aspect Ratio; Superconducting
FUND: Nonneutral, Antimatter, Strong coupled Plasmas; Waves
2:00 PM - 5:00 PM
Monday, October 17, 2022
Room: Exhibit Hall A and Online
Abstract: CP11.00007 : Lithium surface conditioning and its impact on the scrape-off layer and fuel recycling in the Lithium Tokamak eXperiment-β*
Presenter:
Anurag Maan
(PPPL)
Authors:
Anurag Maan
(PPPL)
Dennis P Boyle
(Princeton Plasma Physics Laboratory)
George J Wilkie
(Princeton Plasma Physics Laboratory)
Manaure Francisquez
(Princeton Plasma Physics Laboratory)
Dick Majeski
(Princeton Plasma Physics Laboratory)
Robert Kaita
(Princeton Plasma Physics Laboratory)
Santanu Banerjee
(Princeton Plasma Physics Laboratory)
Drew B Elliott
(Oak Ridge National Lab)
William J Capecchi
(University of Wisconsin - Madison)
Christopher J Hansen
(University of Washington)
Shigeyuki Kubota
(University of California, Los Angeles)
Elizabeth Perez
(University of Illinois, Urbana-Champaign)
Filippo Scotti
(Lawrence Livermore Natl Lab)
Vlad Soukhanovskii
(Lawrence Livermore Natl Lab)
It is well established that the application of lithium to plasma facing components (PFCs) can improve plasma performance in tokamaks. Primarily, lithium PFCs improve plasma performance by reducing fuel recycling and the influx of high Z impurities sputtered from the underlying substrate. The Lithium Tokamak eXperiment (LTX) and its upgrade LTX-?? is the only tokamak in the world capable of operating with near complete coverage of lithium on its PFCs. LTX and LTX-?? have demonstrated plasma performance improvement due to both flat electron temperature profiles, attributed to lowered recycling and reduced radiative loss, attributed to lowered impurity levels. Experiments on LTX have demonstrated that high edge temperatures and low edge density, likely due to a low recycling boundary, lead to a low collisionality scrape-off layer (SOL). However, the connection between flattening electron temperature profiles and recycling, particularly as it relates to the SOL characteristics, remains to be made. To study this unique SOL and to quantify fuel recycling in LTX-?? a new, movable, low field side, off-midplane, swept single Langmuir probe is installed to measure SOL edge density and temperature. Additionally, the neutral particle influx from the high field side limiter is measured using a hydrogen Lyman-?? array. Core electron temperature and density are measured using the LTX-?? Thomson scattering system. The data from these diagnostics indicate a reduction in line integrated Lyman-?? emission intensity and an increase in edge temperature and energy confinement times after fueling termination. More complete analysis of the data using the neutral particle modeling code DEGAS2 will be presented.
*This work is supported by USDoE contracts DE-AC02-09CH11466, DE-AC52-07NA27344. Chris Hansen acknowledges support from USDoE award DE-SC0019239.
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