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Title: Toroidal plasma acceleration due to NBI fast ion losses in LTX-β

Abstract

The recent Lithium Tokamak Experiment-Beta (LTX-β) upgrade includes the addition of neutral beam injection (NBI) in the same direction as the plasma current (co-IP) and a new toroidal Mirnov array for MHD characterization. In initial NBI experiments, a spontaneously rotating n = 1 MHD mode is seen to accelerate during NBI in the counter-beam direction, accompanied by a rise in electron density consistent with the beam-injected inventory but without a clear increase in plasma pressure. Together with analytic and numerical modeling of beam optics and fast ion confinement, these observations indicate the prompt loss of all or nearly all beam ions. However, the same modeling also suggests that planned upgrades to the Ohmic heating system should provide the fast ion confinement necessary for beam heating and core fueling. Here, a simple analytic model relates the momentum confinement time τΦ to the observed evolution of mode rotation due to the combination of NBI momentum coupling, fast ion loss $$\vec{J}\times\vec{B}$$, and anomalous viscous torques, yielding τΦ values consistent with past measurements of electron energy confinement time τE,e.

Authors:
ORCiD logo [1];  [2]; ORCiD logo [3];  [4]; ORCiD logo [1]; ORCiD logo [5]; ORCiD logo [1];  [1];  [1];  [1]
  1. Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
  2. Univ. of Wisconsin, Madison, WI (United States)
  3. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  4. Lithium Wall Fusion, Princeton, NJ (United States)
  5. Univ. of Washington, Seattle, WA (United States)
Publication Date:
Research Org.:
Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
1807662
Grant/Contract Number:  
AC02-09CH11466; AC05-00OR22725; SC0019239
Resource Type:
Accepted Manuscript
Journal Name:
Plasma Physics and Controlled Fusion
Additional Journal Information:
Journal Volume: 63; Journal Issue: 8; Journal ID: ISSN 0741-3335
Publisher:
IOP Science
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY

Citation Formats

Hughes, P. E., Capecchi, W., Elliott, D. B., Zakharov, L. E., Bell, R. E., Hansen, C., Boyle, D. P., Gorelenkov, S. N., Majeski, R., and Kaita, R. Toroidal plasma acceleration due to NBI fast ion losses in LTX-β. United States: N. p., 2021. Web. doi:10.1088/1361-6587/ac0b9f.
Hughes, P. E., Capecchi, W., Elliott, D. B., Zakharov, L. E., Bell, R. E., Hansen, C., Boyle, D. P., Gorelenkov, S. N., Majeski, R., & Kaita, R. Toroidal plasma acceleration due to NBI fast ion losses in LTX-β. United States. https://doi.org/10.1088/1361-6587/ac0b9f
Hughes, P. E., Capecchi, W., Elliott, D. B., Zakharov, L. E., Bell, R. E., Hansen, C., Boyle, D. P., Gorelenkov, S. N., Majeski, R., and Kaita, R. Mon . "Toroidal plasma acceleration due to NBI fast ion losses in LTX-β". United States. https://doi.org/10.1088/1361-6587/ac0b9f. https://www.osti.gov/servlets/purl/1807662.
@article{osti_1807662,
title = {Toroidal plasma acceleration due to NBI fast ion losses in LTX-β},
author = {Hughes, P. E. and Capecchi, W. and Elliott, D. B. and Zakharov, L. E. and Bell, R. E. and Hansen, C. and Boyle, D. P. and Gorelenkov, S. N. and Majeski, R. and Kaita, R.},
abstractNote = {The recent Lithium Tokamak Experiment-Beta (LTX-β) upgrade includes the addition of neutral beam injection (NBI) in the same direction as the plasma current (co-IP) and a new toroidal Mirnov array for MHD characterization. In initial NBI experiments, a spontaneously rotating n = 1 MHD mode is seen to accelerate during NBI in the counter-beam direction, accompanied by a rise in electron density consistent with the beam-injected inventory but without a clear increase in plasma pressure. Together with analytic and numerical modeling of beam optics and fast ion confinement, these observations indicate the prompt loss of all or nearly all beam ions. However, the same modeling also suggests that planned upgrades to the Ohmic heating system should provide the fast ion confinement necessary for beam heating and core fueling. Here, a simple analytic model relates the momentum confinement time τΦ to the observed evolution of mode rotation due to the combination of NBI momentum coupling, fast ion loss $\vec{J}\times\vec{B}$, and anomalous viscous torques, yielding τΦ values consistent with past measurements of electron energy confinement time τE,e.},
doi = {10.1088/1361-6587/ac0b9f},
journal = {Plasma Physics and Controlled Fusion},
number = 8,
volume = 63,
place = {United States},
year = {Mon Jul 05 00:00:00 EDT 2021},
month = {Mon Jul 05 00:00:00 EDT 2021}
}

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