Heat loads in inboard limited L-mode plasmas in TCV

Autor: Nespoli, F., Labit, B., Furno, I., Canal, G.P., Fasoli, A.

Publikováno v: In Journal of Nuclear Materials August 2015 463:393-396

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NSTX-U theory, modeling and analysis results

Autor: 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.

Publikováno v: Nuclear Fusion. 62(4):042023-042023-17

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

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=jairo_______::ba53234cb113b411c1488075ddb3c4fb
https://repo.qst.go.jp/records/85834

Importance of resistivity on edge-localized mode onset in spherical tokamaks.

Autor: Kleiner, A., Ferraro, N.M., Diallo, A., Canal, G.P.

Publikováno v: Nuclear Fusion; Jun2021, Vol. 61 Issue 6, p1-6, 6p

Power distribution in the snowflake divertor in TCV

Autor: Reimerdes, H., Canal, G.P., Duval, B.P., Labit, B., Lunt, T., Vijvers, W.A. J., Coda, S., De Temmerman, G., Morgan, T.W., Nespoli, F., Tal, B., team, TCV

Publikováno v: Plasma Physics and Controlled Fusion, 55, 124027
PLASMA PHYSICS AND CONTROLLED FUSION

TCV experiments demonstrate the basic power exhaust properties of the snowflake (SF) plus and SF minus divertor configurations by measuring the heat fluxes at each of their four divertor legs. The measurements indicate an enhanced transport into the

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::370b0bd9966489be3dcc36a4fb0530ba
https://doi.org/10.1088/0741-3335/55/12/124027