The JET hybrid scenario in Deuterium, Tritium and Deuterium-Tritium

• Published in: Nuclear fusion Vol. 63; no. 11; pp. 112001 - 112027
• Main Authors: Hobirk, J., Challis, C.D., Lerche, E., Keeling, D., King, D., Aleiferis, S., Alessi, E., Angioni, C., Auriemma, F., Baruzzo, M., Belonohy, É., Boboc, A., Carvalho, I.S., Carvalho, P., Casson, F.J., Chomiczewska, A., Citrin, J., Coffey, I.H., Conway, N.J., Douai, D., Delabie, E., Eriksson, B., Eriksson, J., Ficker, O., Field, A.R., Fontana, M., Fontdecaba, J.M., Frassinetti, L., Frigione, D., Gallart, D., Garcia, J., Gelfusa, M., Giacomelli, L., Giovannozzi, E., Goniche, M., Gromelski, W., Hacquin, S., Ham, C., Hawkes, N.C., Henriques, R.B., Hillesheim, J.C., Ho, A., Horvath, L., Ivanova-Stanik, I., Jacquet, P., Jaulmes, F., Joffrin, E., Kim, H.T., Kiptily, V., Kirov, K., Kos, D., Kowalska-Strzeciwilk, E., Kumpulainen, H., Lawson, K., Litaudon, X., Litherland-Smith, E., Lomas, P.J., de la Luna, E., Maggi, C.F., Mailloux, J., Mantsinen, M.J., Maslov, M., Matthews, G., McClements, K.G., Meigs, A.G., Menmuir, S., Milocco, A., Miron, I.G., Moradi, S., Morales, R.B., Nowak, S., Orsitto, F., Patel, A., Piron, L., Prince, C., Peluso, E., Perez von Thun, C., Rachlew, E., Rimini, F., Saarelma, S., Schneider, P. A, Scully, S., Sertoli, M., Sharapov, S., Shaw, A., Silburn, S., Sips, A., Siren, P., Sozzi, C., Solano, E.R., Stancar, Z., Stankunas, G., Stuart, C., Szepesi, G., Valcarcel, D., Valisa, M., Verdoolaege, G., Viola, B., Wendler, N., Zerbini, M.
• Format: Journal Article
• Language: English
• Published: United States IOP Publishing 2023; IOP Science
• Subjects: 70 PLASMA PHYSICS AND FUSION TECHNOLOGY; D-T; hybrid scenario; isotope effects; magnetic fusion; Tritium
• ISSN: 0029-5515; 1741-4326; 1741-4326
• DOI: 10.1088/1741-4326/acde8d

Abstract
The JET hybrid scenario has been developed from low plasma current carbon wall discharges to the record-breaking Deuterium-Tritium plasmas obtained in 2021 with the ITER-like Be/W wall. The development started in pure Deuterium with refinement of the plasma current, and toroidal magnetic field choices and succeeded in solving the heat load challenges arising from 37 MW of injected power in the ITER like wall environment, keeping the radiation in the edge and core controlled, avoiding MHD instabilities and reaching high neutron rates. The Deuterium hybrid plasmas have been re-run in Tritium and methods have been found to keep the radiation controlled but not at high fusion performance probably due to time constraints. For the first time this scenario has been run in Deuterium-Tritium (50:50). These plasmas were re-optimised to have a radiation-stable H-mode entry phase, good impurity control through edge
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gradient screening and optimised performance with fusion power exceeding 10 MW for longer than three alpha particle slow down times, 8.3 MW averaged over 5 s and fusion energy of 45.8 MJ.