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NSTX-U theory, modeling and analysis results
https://repo.qst.go.jp/records/85834
https://repo.qst.go.jp/records/85834949b7fe3-4a5b-4c39-b237-b1fe1387237a
Item type | 学術雑誌論文 / Journal Article(1) | |||||
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公開日 | 2022-03-31 | |||||
タイトル | ||||||
タイトル | NSTX-U theory, modeling and analysis results | |||||
言語 | ||||||
言語 | eng | |||||
資源タイプ | ||||||
資源タイプ識別子 | http://purl.org/coar/resource_type/c_6501 | |||||
資源タイプ | journal article | |||||
アクセス権 | ||||||
アクセス権 | metadata only access | |||||
アクセス権URI | http://purl.org/coar/access_right/c_14cb | |||||
著者 |
Guttenfelder, W.
× Guttenfelder, W.× Battaglia, D.J.× Belova, E.× Bertelli, N.× Boyer, M.D.× Chang, C.S.× Diallo, A.× Duarte, V.N.× Ebrahimi, F.× Emdee, E.D.× Ferraro, N.× Fredrickson, E.× Gorelenkov, N.N.× Heidbrink, W.× Ilhan, Z.× Kaye, S.M.× E.-H., Kim× Kleiner, A.× Laggner, F.× Lampert, M.× Lestz, J.B.× C. Liu× Liu, D.× Looby, T.× Mandell, N.× Maingi, R.× Myra, J.R.× Munaretto, S.× Podesta, M.× Rafiq, T.× Raman, R.× Reinke, M.× Ren, Y.× Ruiz Ruiz, J.× Scotti, F.× Shiraiwa, S.× Soukhanovskii, V.× Vail, P.× Wang, Z.R.× Wehner, W.× White, A.E.× White, R.B.× Woods, B.J.Q.× J. Yang× Zweben, S.J.× Banerjee, S.× Barchfeld, R.× Bell, R.E.× Berkery, J.W.× Bhattacharjee, A.× Bierwage, Andreas× Canal, G.P.× Chen, X.× Clauser, C.× Crocker, N.× Domier, C.× Evans, T.× Francisquez, M.× Gan, K.× Gerhardt, S.× Goldston, R.J.× Gray, T.× Hakim, A.× Hammett, G.× Jardin, S.× Kaita, R.× Koel, B.× Kolemen, E.× S.-H., Ku× Kubota, S.× LeBlanc, B.P.× Levinton, F.× Lore, J.D.× Luhmann, N.× Lunsford, R.× Maqueda, R.× Menard, J.E.× Nichols, J.H.× Ono, M.× J.-K., Park× Poli, F.× Rhodes, T.× Riquezes, J.× Russel, D.× Sabbagh, S.A.× Schuster, E.× Smith, D.R.× Stotler, D.× Stratton, B.× Tritz, K.× Wang, W.× Wirth, B.× Bierwage, Andreas |
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抄録 | ||||||
内容記述タイプ | Abstract | |||||
内容記述 | 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. | |||||
書誌情報 |
Nuclear Fusion 巻 62, 号 4, p. 042023-1-042023-17, 発行日 2022-03 |
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出版者 | ||||||
出版者 | IOP Publishing | |||||
ISSN | ||||||
収録物識別子タイプ | ISSN | |||||
収録物識別子 | 0029-5515 | |||||
DOI | ||||||
識別子タイプ | DOI | |||||
関連識別子 | 10.1088/1741-4326/ac5448 | |||||
関連サイト | ||||||
識別子タイプ | DOI | |||||
関連識別子 | https://doi.org/10.1088/1741-4326/ac5448 |