Demonstration of low recycling and NBI fueling with liquid lithium walls in the Lithium Tokamak Experiment-β (LTX-β)

ORAL

Abstract



Low-recycling liquid lithium surfaces are a potential solution to the two main obstacles for fusion - confinement and power handling. Several critical prerequisites for the low-recycling, liquid Li approach have been recently achieved in the Lithium Tokamak Experiment-β. Improved conditioning techniques in LTX-β created clean, mirror-like liquid Li surfaces that fully surround the plasma, without significant operational problems. Experiments with liquid Li walls have reproduced key results previously demonstrated with solid Li, including a hot, low-recycling edge (R~0.6) with a unique, low-collisionality scrape-off layer. A hot edge is predicted to greatly improve confinement by suppressing temperature gradients that drive turbulent losses. As gas puffing cools the edge, core fueling is essential in the low-recycling regime. LTX-β has recently achieved neutral beam fueling and heating with a ~20% increase in plasma density and high normalized confinement not seen to degrade with PNBI. Recent improvements to the neutral beam, liquid Li techniques, plasma operational systems, and diagnostics will extend the initial proof-of-principle results to higher levels of performance and steadier-state, as well as investigate new, unique aspects of the low-recycling liquid Li regime.

*Supported by US DOE contracts DE-AC02-09CH11466, DE-SC0019006, DE-AC05-00OR22725, DE-SC0024898, DE-SC0019308, DE-SC0023481, and DE-AC52-07NA27344.

Publication: 1. DP Boyle et al, Low-recycling, flat Te discharges with higher performance, NBI-heating, and liquid Li walls in LTX-β, 65th APS DPP Meeting 2023 meetings.aps.org/Meeting/DPP23/Session/BI02.5 - paper to be submitted to Physics of Plasmas before the conference

2. DP Boyle et al Improved liquid lithium surfaces in the Lithium Tokamak Experiment-β Nuclear Materials and Energy (submitted, based on Invited presentation at the 26th International Conference on Plasma Surface Interaction in Controlled Fusion Devices, May 12-17 2024, Marseille, France)

3. A Maan et al Estimates of global recycling coefficients for LTX-β discharges Physics of Plasmas 31 (2024) 022505

4. DP Boyle et al, Extending the low-recycling, flat temperature profile regime in LTX-β with ohmic and neutral beam heating 2023 Nucl. Fusion 63 056020 doi.org/10.1088/1741-4326/acc4da

Presenters

  • Dennis P Boyle

    • Princeton Plasma Physics Laboratory
    • PPPL

Authors

  • Dennis P Boyle

    • Princeton Plasma Physics Laboratory
    • PPPL
  • Anurag Maan

    • Princeton Plasma Physics Laboratory
    • PPPL
    • Princeton Plasma Physics Laboratory (PPPL)
  • Richard Majeski

    • Princeton Plasma Physics Laboratory
    • PPPL
  • Shota Abe

    • Princeton Plasma Physics Laboratory
  • Santanu Banerjee

    • Princeton Plasma Physics Laboratory
    • PPPL
  • William J Capecchi

    • University of Wisconsin - Madison
    • U. Wisconsin
  • Drew B Elliott

    • Oak Ridge National Lab
  • Manaure Francisquez

    • Princeton Plasma Physics Laboratory
    • Princeton Plasma Physics Laboratory (PPPL)
  • Christopher J Hansen

    • Columbia University
  • Euichan Jung

    • Princeton Plasma Physics Laboratory
  • Shigeyuki Kubota

    • University of California, Los Angeles
  • Rajesh Maingi

    • Princeton Plasma Physics Laboratory
    • Princeton Plasma Physics Laboratory (PPPL)
  • Adam G McLean

    • Lawrence Livermore Natl Lab
  • Evan T Ostrowski

    • Princeton University
  • Vlad A Soukhanovskii

    • Lawrence Livermore Natl Lab
    • LLNL
  • George J Wilkie

    • Princeton Plasma Physics Laboratory
  • Leonid Zakharov

    • LiWFusion; Department of Physics, University of Helsinki
    • LiWFusion