NSTX-U research advancing the physics of spherical tokamaks

J. W. Berkery, P. O. Adebayo-Ige, H. Al Khawaldeh, G. Avdeeva, S. G. Baek, S. Banerjee, K. Barada, D. J. Battaglia, R. E. Bell, E. Belli, E. V. Belova, N. Bertelli, N. Bisai, P. T. Bonoli, M. D. Boyer, J. Butt, J. Candy, C. S. Chang, C. F. Clauser, L. D. Corona RiveraM. Curie, P. C. de Vries, R. Diab, A. Diallo, J. Dominski, V. N. Duarte, E. D. Emdee, N. M. Ferraro, R. Fitzpatrick, E. L. Foley, E. Fredrickson, M. E. Galante, K. F. Gan, S. Gerhardt, R. Goldston, W. Guttenfelder, R. Hager, M. O. Hanson, S. C. Jardin, T. G. Jenkins, S. M. Kaye, A. Khodak, J. Kinsey, A. Kleiner, E. Kolemen, S. Ku, M. Lampert, B. Leard, B. P. LeBlanc, J. B. Lestz, F. M. Levinton, C. Liu, T. Looby, R. Lunsford, T. Macwan, R. Maingi, J. McClenaghan, J. E. Menard, S. Munaretto, M. Ono, A. Pajares, J. Parisi, J. K. Park, M. S. Parsons, B. S. Patel, Y. V. Petrov, M. Podestà, F. Poli, M. Porcelli, T. Rafiq, S. A. Sabbagh, I. Sánchez Villar, E. Schuster, J. Schwartz, A. Sharma, S. Shiraiwa, P. Sinha, D. Smith, S. Smith, V. A. Soukhanovskii, G. Staebler, E. Startsev, B. Stratton, K. E. Thome, W. Tierens, M. Tobin, I. U. Uzun-Kaymak, B. Van Compernolle, J. Wai, W. Wang, W. Wehner, A. Welander, J. Yang, V. Zamkovska, X. Zhang, X. L. Zhu, S. Zweben

Research output: Contribution to journalArticlepeer-review

10 Scopus citations

Abstract

The objectives of NSTX-U research are to reinforce the advantages of STs while addressing the challenges. To extend confinement physics of low-A, high beta plasmas to lower collisionality levels, understanding of the transport mechanisms that set confinement performance and pedestal profiles is being advanced through gyrokinetic simulations, reduced model development, and comparison to NSTX experiment, as well as improved simulation of RF heating. To develop stable non-inductive scenarios needed for steady-state operation, various performance-limiting modes of instability were studied, including MHD, tearing modes, and energetic particle instabilities. Predictive tools were developed, covering disruptions, runaway electrons, equilibrium reconstruction, and control tools. To develop power and particle handling techniques to optimize plasma exhaust in high performance scenarios, innovative lithium-based solutions are being developed to handle the very high heat flux levels that the increased heating power and compact geometry of NSTX-U will produce, and will be seen in future STs. Predictive capabilities accounting for plasma phenomena, like edge harmonic oscillations, ELMs, and blobs, are being tested and improved. In these ways, NSTX-U researchers are advancing the physics understanding of ST plasmas to maximize the benefit that will be gained from further NSTX-U experiments and to increase confidence in projections to future devices.

Original languageEnglish
Article number112004
JournalNuclear Fusion
Volume64
Issue number11
DOIs
StatePublished - Nov 2024

Funding

This work was supported by the U.S. Department of Energy under contract numbers DE-AC02-09CH11466 (PPPL), DE-SC0008309 (UT, Knoxville), DE-SC0013977 (Lehigh), DE-SC0021385 (Lehigh), DE-SC0021113 (GA), DE-FG02-95ER54309 (GA), DE-FG02-91ER54109 (MIT), DE-SC0021156 (UT, Austin), DE-SC0021625 (Nova Photonics), DE-SC0021311 (Columbia), and DE-AC52-07NA27344 (LLNL). Additionally: EP/R034737/1 (UKAEA). A part of this research used resources of the National Energy Research Scientific Computing Center (NERSC), which is supported by the Office of Science of the U.S. Department of Energy under Contract No. DE-AC02-05CH11231. A part of this work was supported by the Department of Energy early career research program. Part of the data analysis was performed using the OMFIT integrated modeling framework [].

FundersFunder number
UK Atomic Energy Authority
Office of Science
Massachusetts Institute of TechnologyDE-SC0021156, DE-SC0021625, DE-AC52-07NA27344, DE-SC0021311
U.S. Department of EnergyDE-AC02-05CH11231, DE-AC02-09CH11466
Princeton Plasma Physics LaboratoryDE-SC0013977, DE-SC0021385, DE-SC0008309, DE-FG02-91ER54109, DE-FG02-95ER54309, DE-SC0021113
Lawrence Livermore National LaboratoryEP/R034737/1

    Keywords

    • NSTX
    • NSTX-U
    • magnetic confinement fusion
    • spherical tokamak

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