NSTX-U research advancing the physics of spherical tokamaks
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Published:2024-08-15
Issue:11
Volume:64
Page:112004
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ISSN:0029-5515
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Container-title:Nuclear Fusion
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language:
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Short-container-title:Nucl. Fusion
Author:
Berkery J.W.ORCID, Adebayo-Ige P.O.ORCID, Al Khawaldeh H.ORCID, Avdeeva G.ORCID, Baek S-G.ORCID, Banerjee S.ORCID, Barada K.ORCID, Battaglia D.J.ORCID, Bell R.E.ORCID, Belli E.ORCID, Belova E.V.ORCID, Bertelli N.ORCID, Bisai N.ORCID, Bonoli P.T.ORCID, Boyer M.D., Butt J.ORCID, Candy J.ORCID, Chang C.S.ORCID, Clauser C.F.ORCID, Corona Rivera L.D.ORCID, Curie M.ORCID, de Vries P.C.ORCID, Diab R.ORCID, Diallo A.ORCID, Dominski J.ORCID, Duarte V.N.ORCID, Emdee E.D.ORCID, Ferraro N.M.ORCID, Fitzpatrick R.ORCID, Foley E.L., Fredrickson E., Galante M.E., Gan K.F.ORCID, Gerhardt S., Goldston R.ORCID, Guttenfelder W.ORCID, Hager R.ORCID, Hanson M.O.ORCID, Jardin S.C.ORCID, Jenkins T.G.ORCID, Kaye S.M.ORCID, Khodak A.ORCID, Kinsey J.ORCID, Kleiner A.ORCID, Kolemen E.ORCID, Ku S.ORCID, Lampert M.ORCID, Leard B.ORCID, LeBlanc B.P., Lestz J.B.ORCID, Levinton F.M., Liu C.ORCID, Looby T.ORCID, Lunsford R.ORCID, Macwan T.ORCID, Maingi R.ORCID, McClenaghan J.ORCID, Menard J.E.ORCID, Munaretto S.ORCID, Ono M.ORCID, Pajares A.ORCID, Parisi J.ORCID, Park J-K., Parsons M.S.ORCID, Patel B.S.ORCID, Petrov Y.V.ORCID, Podestà M.ORCID, Poli F.ORCID, Porcelli M., Rafiq T.ORCID, Sabbagh S.A., Sánchez Villar Á.ORCID, Schuster E.ORCID, Schwartz J.ORCID, Sharma A., Shiraiwa S.ORCID, Sinha P.ORCID, Smith D., Smith S.ORCID, Soukhanovskii V.A.ORCID, Staebler G.ORCID, Startsev E., Stratton B., Thome K.E.ORCID, Tierens W.ORCID, Tobin M.ORCID, Uzun-Kaymak I.U.ORCID, Van Compernolle B.ORCID, Wai J.ORCID, Wang W.ORCID, Wehner W., Welander A., Yang J.ORCID, Zamkovska V.ORCID, Zhang X.ORCID, Zhu X.L.ORCID, Zweben S.ORCID
Abstract
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.
Funder
Fusion Energy Sciences Culham Centre for Fusion Energy
Cited by
10 articles.
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