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F. Scotti

Observed names: F Scotti, F, Scotti, F., Scotti, Filippo SCOTTI, Filippo Scotti, Scotti, F, Scotti, F., Scotti, Filippo
ORCID: 0000-0002-0196-9919
Observed ORCID: 0000-0002-0196-9919
OpenAlex ID: A5050132460
Liquid lithium divertor characteristics and plasma–material interactions in NSTX high-performance plasmas
2013 · M.A. Jaworski, T. Abrams, et al. · Nuclear Fusion · 96
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Diverted negative triangularity plasmas on DIII-D: the benefit of high confinement without the liability of an edge pedestal
2021 · A. Marinoni, M.E. Austin, et al. · Nuclear Fusion · 78
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Snowflake divertor configuration studies in National Spherical Torus Experiment
2012 · V. A. Soukhanovskii, R. E. Bell, et al. · Physics of Plasmas · 74
Overview of NSTX Upgrade initial results and modelling highlights
2017 · J.E. Menard, J.P. Allain, et al. · Nuclear Fusion · 72
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Overview of physics results from the conclusive operation of the National Spherical Torus Experiment
2013 · S.A. Sabbagh, J.-W. Ahn, et al. · Nuclear Fusion · 63
Robust Avoidance of Edge-Localized Modes alongside Gradient Formation in the Negative Triangularity Tokamak Edge
2023 · A. O. Nelson, L. Schmitz, et al. · Physical Review Letters · 60
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Overview of recent experimental results on the EAST Tokamak
2024 · X. Gong, on behalf of EAST Team and Collaborators, et al. · Nuclear Fusion · 46
Fast-wave power flow along SOL field lines in NSTX and the associated power deposition profile across the SOL in front of the antenna
2013 · R.J. Perkins, J.-W. Ahn, et al. · Nuclear Fusion · 44
Core transport of lithium and carbon in ELM-free discharges with lithium wall conditioning in NSTX
2013 · F. Scotti, V.A. Soukhanovskii, et al. · Nuclear Fusion · 43
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Recent progress in the NSTX/NSTX-U lithium programme and prospects for reactor-relevant liquid-lithium based divertor development
2013 · M. Ono, M.A. Jaworski, et al. · Nuclear Fusion · 42
Overview of results from the 2023 DIII-D negative triangularity campaign
2024 · K E Thome, M E Austin, et al. · Plasma Physics and Controlled Fusion · 39
Midplane neutral density profiles in the National Spherical Torus Experiment
2015 · D. P. Stotler, F. Scotti, et al. · Physics of Plasmas · 39
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DIII-D research advancing the physics basis for optimizing the tokamak approach to fusion energy
2021 · M. E. Fenstermacher, J. Abbate, et al. · Nuclear Fusion · 37
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Scenario development during commissioning operations on the National Spherical Torus Experiment Upgrade
2018 · D.J. Battaglia, M.D. Boyer, et al. · Nuclear Fusion · 36
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Plasma boundary shape control and real-time equilibrium reconstruction on NSTX-U
2018 · M.D. Boyer, D.J. Battaglia, et al. · Nuclear Fusion · 33
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Advanced divertor configurations with large flux expansion
2013 · V.A. Soukhanovskii, R.E. Bell, et al. · Journal of Nuclear Materials · 32
Simultaneous access to high normalized density, current, pressure, and confinement in strongly-shaped diverted negative triangularity plasmas
2024 · C. Paz-Soldan, C. Chrystal, et al. · Nuclear Fusion · 30
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Comparative study of recombining He plasmas below 0.1eV using laser Thomson scattering and spectroscopy in the divertor simulator MAP-II
2009 · Filippo Scotti, Shinichiro Kado · Journal of Nuclear Materials · 29
Measurements of core lithium concentration in a Li-conditioned tokamak with carbon walls
2012 · M. Podestà, R.E. Bell, et al. · Nuclear Fusion · 28
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An overview of recent physics results from NSTX
2015 · S.M. Kaye, T. Abrams, et al. · Nuclear Fusion · 27
Full toroidal imaging of non-axisymmetric plasma material interaction in the National Spherical Torus Experiment divertor
2012 · Filippo Scotti, A. L. Roquemore, et al. · Review of Scientific Instruments · 27
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Advances in boronization on NSTX-Upgrade
2017 · C. H Skinner, F. Bedoya, et al. · Nuclear Materials and Energy · 26
Plasma Facing Component Characterization and Correlation With Plasma Conditions in Lithium Tokamak Experiment-β
2020 · Anurag Maan, Evan Ostrowski, et al. · IEEE Transactions on Plasma Science · 24
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Divertor leg filaments in NSTX-U
2018 · Filippo Scotti, Stewart Zweben, et al. · Nuclear Fusion · 24
Hydrogen retention in lithium on metallic walls from “in vacuo” analysis in LTX and implications for high-Z plasma-facing components in NSTX-U
2016 · R. Kaita, M. Lucia, et al. · Fusion Engineering and Design · 24
Works count: 247
Citation count: 1,842
H-index: 24
I10-index: 55
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