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Title: Observation of Flat Electron Temperature Profiles in the Lithium Tokamak Experiment

It has been predicted for over a decade that low-recycling plasma-facing components in fusion devices would allow high edge temperatures and flat or nearly flat temperature profiles. In recent experiments with lithium wall coatings in the Lithium Tokamak Experiment (LTX), a hot edge ( > 200 eV ) and flat electron temperature profiles have been measured following the termination of external fueling. In this work, reduced recycling was demonstrated by retention of ~ 60% of the injected hydrogen in the walls following the discharge. Electron energy confinement followed typical Ohmic confinement scaling during fueling, but did not decrease with density after fueling terminated, ultimately exceeding the scaling by ~ 200% . Lastly, achievement of the low-recycling, hot edge regime has been an important goal of LTX and lithium plasma-facing component research in general, as it has potentially significant implications for the operation, design, and cost of fusion devices.
Authors:
 [1] ;  [1] ;  [2] ;  [3] ;  [1] ;  [4] ;  [1] ;  [5]
  1. Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
  2. Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States); Auburn Univ., AL (United States). Physics Department
  3. Univ. of Washington, Seattle, WA (United States). Department of Aeronautics and Astronautics
  4. Univ. of California, Los Angeles, CA (United States). Institute of Plasma and Fusion Research
  5. Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
Publication Date:
Report Number(s):
PPPL-5392; LLNL-JRNL-738437
Journal ID: ISSN 0031-9007; PRLTAO; TRN: US1702842
Grant/Contract Number:
AC02-09CH11466; AC05-00OR22725; SC0016256; FG02-99ER54527; AC52-07NA27344
Type:
Accepted Manuscript
Journal Name:
Physical Review Letters
Additional Journal Information:
Journal Volume: 119; Journal Issue: 1; Journal ID: ISSN 0031-9007
Publisher:
American Physical Society (APS)
Research Org:
Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States); Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
Sponsoring Org:
USDOE National Nuclear Security Administration (NNSA)
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; Physics - Plasma physics
OSTI Identifier:
1395249
Alternate Identifier(s):
OSTI ID: 1368427; OSTI ID: 1463825

Boyle, D. P., Majeski, R., Schmitt, J. C., Hansen, C., Kaita, R., Kubota, S., Lucia, M., and Rognlien, T. D.. Observation of Flat Electron Temperature Profiles in the Lithium Tokamak Experiment. United States: N. p., Web. doi:10.1103/PhysRevLett.119.015001.
Boyle, D. P., Majeski, R., Schmitt, J. C., Hansen, C., Kaita, R., Kubota, S., Lucia, M., & Rognlien, T. D.. Observation of Flat Electron Temperature Profiles in the Lithium Tokamak Experiment. United States. doi:10.1103/PhysRevLett.119.015001.
Boyle, D. P., Majeski, R., Schmitt, J. C., Hansen, C., Kaita, R., Kubota, S., Lucia, M., and Rognlien, T. D.. 2017. "Observation of Flat Electron Temperature Profiles in the Lithium Tokamak Experiment". United States. doi:10.1103/PhysRevLett.119.015001. https://www.osti.gov/servlets/purl/1395249.
@article{osti_1395249,
title = {Observation of Flat Electron Temperature Profiles in the Lithium Tokamak Experiment},
author = {Boyle, D. P. and Majeski, R. and Schmitt, J. C. and Hansen, C. and Kaita, R. and Kubota, S. and Lucia, M. and Rognlien, T. D.},
abstractNote = {It has been predicted for over a decade that low-recycling plasma-facing components in fusion devices would allow high edge temperatures and flat or nearly flat temperature profiles. In recent experiments with lithium wall coatings in the Lithium Tokamak Experiment (LTX), a hot edge ( > 200 eV ) and flat electron temperature profiles have been measured following the termination of external fueling. In this work, reduced recycling was demonstrated by retention of ~ 60% of the injected hydrogen in the walls following the discharge. Electron energy confinement followed typical Ohmic confinement scaling during fueling, but did not decrease with density after fueling terminated, ultimately exceeding the scaling by ~ 200% . Lastly, achievement of the low-recycling, hot edge regime has been an important goal of LTX and lithium plasma-facing component research in general, as it has potentially significant implications for the operation, design, and cost of fusion devices.},
doi = {10.1103/PhysRevLett.119.015001},
journal = {Physical Review Letters},
number = 1,
volume = 119,
place = {United States},
year = {2017},
month = {7}
}