@article{oai:repo.qst.go.jp:00085834,
 author = {Guttenfelder, W. and Battaglia, D.J. and Belova, E. and Bertelli, N. and Boyer, M.D. and Chang, C.S. and Diallo, A. and Duarte, V.N. and Ebrahimi, F. and Emdee, E.D. and Ferraro, N. and Fredrickson, E. and Gorelenkov, N.N. and Heidbrink, W. and Ilhan, Z. and Kaye, S.M. and E.-H., Kim and Kleiner, A. and Laggner, F. and Lampert, M. and Lestz, J.B. and C. Liu and Liu, D. and Looby, T. and Mandell, N. and Maingi, R. and Myra, J.R. and Munaretto, S. and Podesta, M. and Rafiq, T. and Raman, R. and Reinke, M. and Ren, Y. and Ruiz Ruiz, J. and Scotti, F. and Shiraiwa, S. and Soukhanovskii, V. and Vail, P. and Wang, Z.R. and Wehner, W. and White, A.E. and White, R.B. and Woods, B.J.Q. and J. Yang and Zweben, S.J. and Banerjee, S. and Barchfeld, R. and Bell, R.E. and Berkery, J.W. and Bhattacharjee, A. and Bierwage, Andreas and Canal, G.P. and Chen, X. and Clauser, C. and Crocker, N. and Domier, C. and Evans, T. and Francisquez, M. and Gan, K. and Gerhardt, S. and Goldston, R.J. and Gray, T. and Hakim, A. and Hammett, G. and Jardin, S. and Kaita, R. and Koel, B. and Kolemen, E. and S.-H., Ku and Kubota, S. and LeBlanc, B.P. and Levinton, F. and Lore, J.D. and Luhmann, N. and Lunsford, R. and Maqueda, R. and Menard, J.E. and Nichols, J.H. and Ono, M. and J.-K., Park and Poli, F. and Rhodes, T. and Riquezes, J. and Russel, D. and Sabbagh, S.A. and Schuster, E. and Smith, D.R. and Stotler, D. and Stratton, B. and Tritz, K. and Wang, W. and Wirth, B. and Bierwage, Andreas},
 issue = {4},
 journal = {Nuclear Fusion},
 month = {Mar},
 note = {The mission of the low aspect ratio spherical tokamak NSTX-U is to advance the physics basis and technical solutions required for optimizing the configuration of next-step steady-state tokamak fusion devices. NSTX-U will ultimately operate at up to 2 MA of plasma current and 1 T toroidal field on axis for 5 s, and has available up to 15 MW of neutral beam injection power at different tangency radii and 6 MW of high harmonic fast wave heating. With these capabilities NSTX-U will develop the physics understanding and control tools to ramp-up and sustain high performance fully non-inductive plasmas with large bootstrap fraction and enhanced confinement enabled via the low aspect ratio, high beta configuration. With its unique capabilities, NSTX-U research also supports ITER and other critical fusion development needs. Super-Alfvenic ions in beam-heated NSTX-U plasmas access energetic particle (EP) parameter space that is relevant for both α-heated conventional and low aspect ratio burning plasmas. NSTX-U can also generate very large target heat fluxes to test conventional and innovative plasma exhaust and plasma facing component solutions. This paper summarizes recent analysis, theory and modelling progress to advance the tokamak physics basis in the areas of macrostability and 3D fields, EP stability and fast ion transport, thermal transport and pedestal structure, boundary and plasma material interaction, RF heating, scenario optimization and real-time control.},
 pages = {042023-1--042023-17},
 title = {NSTX-U theory, modeling and analysis results},
 volume = {62},
 year = {2022}
}