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Title: Compatibility of lithium plasma-facing surfaces with high edge temperatures in the Lithium Tokamak Experiment

We measured high edge electron temperatures (200 eV or greater) at the wall-limited plasma boundary in the Lithium Tokamak Experiment (LTX). Flat electron temperature profiles are a long-predicted consequence of low recycling boundary conditions. Plasma density in the outer scrape-off layer is very low, 2-3 x 10(17) m(-3), consistent with a low recycling metallic lithium boundary. In spite of the high edge temperature, the core impurity content is low. Z(eff) is estimated to be similar to 1.2, with a very modest contribution (< 0.1) from lithium. Experiments are transient. Gas puffing is used to increase the plasma density. After gas injection stops, the discharge density is allowed to drop, and the edge is pumped by the low recycling lithium wall. An upgrade to LTX-LTX-beta, which includes a 35A, 20 kV neutral beam injector (on loan to LTX from Tri-Alpha Energy) to provide core fueling to maintain constant density, as well as auxiliary heating, is underway. LTX-beta is briefly described.
Authors:
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  1. Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
  2. Univ. of Illinois, Urbana-Champaign, IL (United States)
  3. Columbia Univ., New York, NY (United States)
  4. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  5. Princeton Univ., NJ (United States)
  6. College of New Jersey, Ewing, NJ (United States)
  7. Univ. of Washington, Seattle, WA (United States)
  8. Univ. of California, Los Angeles, CA (United States)
  9. Johns Hopkins Univ., Baltimore, MD (United States)
Publication Date:
Report Number(s):
PPPL-5325
Journal ID: ISSN 1070-664X; PHPAEN
Grant/Contract Number:
AC02-09CH11466; AC05-00OR22725
Type:
Accepted Manuscript
Journal Name:
Physics of Plasmas
Additional Journal Information:
Journal Volume: 24; Journal Issue: 5; Conference: 58th Annual Meeting of the APS-Division-of-Plasma-Physics (DPP), San Jose, CA (United States), 31 Oct - 4 Nov 2016; Related Information: The digital data for this paper can be found at http://arks.princeton.edu/ark:/88435/dsp01x920g025r.; Journal ID: ISSN 1070-664X
Publisher:
American Institute of Physics (AIP)
Research Org:
Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
Sponsoring Org:
USDOE Office of Science (SC), Fusion Energy Sciences (FES) (SC-24)
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
OSTI Identifier:
1367354
Alternate Identifier(s):
OSTI ID: 1348032

Majeski, R., Bell, R. E., Boyle, D. P., Kaita, R., Kozub, T., LeBlanc, B. P., Lucia, M., Maingi, R., Merino, E., Raitses, Y., Schmitt, J. C., Allain, J. P., Bedoya, F., Bialek, J., Biewer, T. M., Canik, J. M., Buzi, L., Koel, B. E., Patino, M. I., Capece, A. M., Hansen, C., Jarboe, T., Kubota, S., Peebles, W. A., and Tritz, K.. Compatibility of lithium plasma-facing surfaces with high edge temperatures in the Lithium Tokamak Experiment. United States: N. p., Web. doi:10.1063/1.4977916.
Majeski, R., Bell, R. E., Boyle, D. P., Kaita, R., Kozub, T., LeBlanc, B. P., Lucia, M., Maingi, R., Merino, E., Raitses, Y., Schmitt, J. C., Allain, J. P., Bedoya, F., Bialek, J., Biewer, T. M., Canik, J. M., Buzi, L., Koel, B. E., Patino, M. I., Capece, A. M., Hansen, C., Jarboe, T., Kubota, S., Peebles, W. A., & Tritz, K.. Compatibility of lithium plasma-facing surfaces with high edge temperatures in the Lithium Tokamak Experiment. United States. doi:10.1063/1.4977916.
Majeski, R., Bell, R. E., Boyle, D. P., Kaita, R., Kozub, T., LeBlanc, B. P., Lucia, M., Maingi, R., Merino, E., Raitses, Y., Schmitt, J. C., Allain, J. P., Bedoya, F., Bialek, J., Biewer, T. M., Canik, J. M., Buzi, L., Koel, B. E., Patino, M. I., Capece, A. M., Hansen, C., Jarboe, T., Kubota, S., Peebles, W. A., and Tritz, K.. 2017. "Compatibility of lithium plasma-facing surfaces with high edge temperatures in the Lithium Tokamak Experiment". United States. doi:10.1063/1.4977916. https://www.osti.gov/servlets/purl/1367354.
@article{osti_1367354,
title = {Compatibility of lithium plasma-facing surfaces with high edge temperatures in the Lithium Tokamak Experiment},
author = {Majeski, R. and Bell, R. E. and Boyle, D. P. and Kaita, R. and Kozub, T. and LeBlanc, B. P. and Lucia, M. and Maingi, R. and Merino, E. and Raitses, Y. and Schmitt, J. C. and Allain, J. P. and Bedoya, F. and Bialek, J. and Biewer, T. M. and Canik, J. M. and Buzi, L. and Koel, B. E. and Patino, M. I. and Capece, A. M. and Hansen, C. and Jarboe, T. and Kubota, S. and Peebles, W. A. and Tritz, K.},
abstractNote = {We measured high edge electron temperatures (200 eV or greater) at the wall-limited plasma boundary in the Lithium Tokamak Experiment (LTX). Flat electron temperature profiles are a long-predicted consequence of low recycling boundary conditions. Plasma density in the outer scrape-off layer is very low, 2-3 x 10(17) m(-3), consistent with a low recycling metallic lithium boundary. In spite of the high edge temperature, the core impurity content is low. Z(eff) is estimated to be similar to 1.2, with a very modest contribution (< 0.1) from lithium. Experiments are transient. Gas puffing is used to increase the plasma density. After gas injection stops, the discharge density is allowed to drop, and the edge is pumped by the low recycling lithium wall. An upgrade to LTX-LTX-beta, which includes a 35A, 20 kV neutral beam injector (on loan to LTX from Tri-Alpha Energy) to provide core fueling to maintain constant density, as well as auxiliary heating, is underway. LTX-beta is briefly described.},
doi = {10.1063/1.4977916},
journal = {Physics of Plasmas},
number = 5,
volume = 24,
place = {United States},
year = {2017},
month = {3}
}