Author: "J.F. Artaud" - Searchworks@Jio Institute Digital Library Search Results

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102 results on '"J.F. Artaud"'

1. ITER NBI operational window and power availability constraints due to shine-through losses

Author: P. Vincenzi, M. Schneider, P. Veltri, J.F. Artaud, A. Loarte, S. Nicolici, C. Poggi, A.R. Polevoi, and A. Snicker
Subjects: ITER, NBI, shine-through, power load, auxiliary power, H&CD, Nuclear and particle physics. Atomic energy. Radioactivity, QC770-798
Abstract: This paper explores the operational boundaries and power availability of the neutral beam injection (NBI) system in ITER, with a specific focus on shine-through (ST) loss prevention. ST, a phenomenon where part of the injected neutral beam remains un-ionized in the plasma and directly impacts the first wall components, poses a significant risk to the lifetime of ITER’s plasma-facing components (PFCs). The operational window for NBI is consequently constrained by these losses, which are influenced by factors such as plasma density, beam energy, and injection geometry. Leveraging advanced numerical simulations, we investigate these dependencies across various ITER plasma scenarios, particularly for the DT-1 phase, which will mark the first NBI operations. In light of recent ITER blanket design changes, our analysis refines previous estimates of the maximum acceptable ST power on PFCs. We then present a new heuristic formula which permits the calculation of the ST fraction and the minimum plasma density that permits ITER NBI operations as a function of global variables. This allows for establishing operational limits for Hydrogen and Deuterium NBI in Hydrogen, Deuterium, and Deuterium–Tritium plasmas. Additionally, we compare commonly used beam ionisation codes for ITER and tokamak simulations, evaluating their reliability in the investigated parameter space. The findings of this study are crucial for ensuring the efficient operation of the NBI system during ITER’s experimental phases. They define the conditions under which beam power can be fully utilised without compromising operational lifetime, thereby informing future plasma operation plans and contributing to the success of ITER’s scientific objectives.
Published: 2025
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2. Maximizing the ion temperature in an electron heated plasma: from WEST towards larger devices

Author: P. Manas, J.F. Artaud, C. Bourdelle, V. Ostuni, J. Morales, J. Citrin, and the WEST Team
Subjects: tokamak, plasma, turbulence, Nuclear and particle physics. Atomic energy. Radioactivity, QC770-798
Abstract: In electron heated plasmas, as the power increases, it is experimentally reported that the ion temperature ( T _i ) saturates while the electron temperature ( T _e ) increases [Beurskens NF 2022]. As on AUG, W7X and elsewhere, T _i saturates around 1.5 keV in WEST L-mode electron heated plasmas while T _e reaches 4 keV. Simulations within the integrated model METIS have been compared against a whole WEST campaign consisting mostly of L-mode plasmas with Lower Hybrid heating ranging from 1 to 5.5 MW. In METIS, the collisional equipartition is modeled as well as the turbulent heat transport using the neural network regression of the quasilinear gyrokinetic code QuaLiKiz. The observed T _i saturation is well captured by the modeling framework. The saturation correlates with a low ratio of the energy confinement time to the volume averaged electron-ion collisional heat exchange time. It is then shown that T _i saturation in electron heated plasma is due to an equipartition time higher than the energy confinement time. In larger devices, no T _i saturation is expected nor predicted by physics based integrated modeling used in this work, thanks to equipartition times sufficiently shorter than the energy confinement time.
Published: 2024
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3. Overview of the EUROfusion Tokamak Exploitation programme in support of ITER and DEMO

Author: E. Joffrin, M. Wischmeier, M. Baruzzo, A. Hakola, A. Kappatou, D. Keeling, B. Labit, E. Tsitrone, N. Vianello, the ASDEX Upgrade Team, JET Contributors, the MAST-U Team, the TCV Team, the WEST Team, the EUROfusion Tokamak Exploitation Team:, D. Abate, J. Adamek, M. Agostini, C. Albert, F.C.P. Albert Devasagayam, S. Aleiferis, E. Alessi, J. Alhage, S. Allan, J. Allcock, M. Alonzo, G. Anastasiou, E. Andersson Sunden, C. Angioni, Y. Anquetin, L. Appel, G.M. Apruzzese, M. Ariola, C. Arnas, J.F. Artaud, W. Arter, O. Asztalos, L. Aucone, M.H. Aumeunier, F. Auriemma, J. Ayllon, E. Aymerich, A. Baciero, F. Bagnato, L. Bähner, F. Bairaktaris, P. Balázs, L. Balbinot, I. Balboa, M. Balden, A. Balestri, M. Baquero Ruiz, T. Barberis, C. Barcellona, O. Bardsley, S. Benkadda, T. Bensadon, E. Bernard, M. Bernert, H. Betar, R. Bianchetti Morales, J. Bielecki, R. Bilato, P. Bilkova, W. Bin, G. Birkenmeier, R. Bisson, P. Blanchard, A. Bleasdale, V. Bobkov, A. Boboc, A. Bock, K. Bogar, P. Bohm, T. Bolzonella, F. Bombarda, N. Bonanomi, L. Boncagni, D. Bonfiglio, R. Bonifetto, M. Bonotto, D. Borodin, I. Borodkina, T.O.S.J. Bosman, C. Bourdelle, C. Bowman, S. Brezinsek, D. Brida, F. Brochard, R. Brunet, D. Brunetti, V. Bruno, R. Buchholz, J. Buermans, H. Bufferand, P. Buratti, A. Burckhart, J. Cai, R. Calado, J. Caloud, S. Cancelli, F. Cani, B. Cannas, M. Cappelli, S. Carcangiu, A. Cardinali, S. Carli, D. Carnevale, M. Carole, M. Carpita, D. Carralero, F. Caruggi, I.S. Carvalho, I. Casiraghi, A. Casolari, F.J. Casson, C. Castaldo, A. Cathey, F. Causa, J. Cavalier, M. Cavedon, J. Cazabonne, M. Cecconello, L. Ceelen, A. Celora, J. Cerovsky, C.D. Challis, R. Chandra, A. Chankin, B. Chapman, H. Chen, M. Chernyshova, A.G. Chiariello, P. Chmielewski, A. Chomiczewska, C. Cianfarani, G. Ciraolo, J. Citrin, F. Clairet, S. Coda, R. Coelho, J.W. Coenen, I.H. Coffey, C. Colandrea, L. Colas, S. Conroy, C. Contre, N.J. Conway, L. Cordaro, Y. Corre, D. Costa, S. Costea, D. Coster, X. Courtois, C. Cowley, T. Craciunescu, G. Croci, A.M. Croitoru, K. Crombe, D.J. Cruz Zabala, G. Cseh, T. Czarski, A. Da Ros, A. Dal Molin, M. Dalla Rosa, Y. Damizia, O. D’Arcangelo, P. David, M. De Angeli, E. De la Cal, E. De La Luna, G. De Tommasi, J. Decker, R. Dejarnac, D. Del Sarto, G. Derks, C. Desgranges, P. Devynck, S. Di Genova, L.E. di Grazia, A. Di Siena, M. Dicorato, M. Diez, M. Dimitrova, T. Dittmar, L. Dittrich, J.J. Domínguez Palacios Durán, P. Donnel, D. Douai, S. Dowson, S. Doyle, M. Dreval, P. Drews, L. Dubus, R. Dumont, D. Dunai, M. Dunne, A. Durif, F. Durodie, G. Durr Legoupil Nicoud, B. Duval, R. Dux, T. Eich, A. Ekedahl, S. Elmore, G. Ericsson, J. Eriksson, B. Eriksson, F. Eriksson, S. Ertmer, A. Escarguel, B. Esposito, T. Estrada, E. Fable, M. Faitsch, N. Fakhrayi Mofrad, A. Fanni, T. Farley, M. Farník, N. Fedorczak, F. Felici, X. Feng, J. Ferreira, D. Ferreira, N. Ferron, O. Fevrier, O. Ficker, A.R. Field, A. Figueiredo, N. Fil, D. Fiorucci, M. Firdaouss, R. Fischer, M. Fitzgerald, M. Flebbe, M. Fontana, J. Fontdecaba Climent, A. Frank, E. Fransson, L. Frassinetti, D. Frigione, S. Futatani, R. Futtersack, S. Gabriellini, D. Gadariya, D. Galassi, K. Galazka, J. Galdon, S. Galeani, D. Gallart, A. Gallo, C. Galperti, M. Gambrioli, S. Garavaglia, J. Garcia, M. Garcia Munoz, J. Gardarein, L. Garzotti, J. Gaspar, R. Gatto, P. Gaudio, M. Gelfusa, J. Gerardin, S.N. Gerasimov, R. Gerru Miguelanez, G. Gervasini, Z. Ghani, F.M. Ghezzi, G. Ghillardi, L. Giannone, S. Gibson, L. Gil, A. Gillgren, E. Giovannozzi, C. Giroud, G. Giruzzi, T. Gleiter, M. Gobbin, V. Goloborodko, A. González Ganzábal, T. Goodman, V. Gopakumar, G. Gorini, T. Görler, S. Gorno, G. Granucci, D. Greenhouse, G. Grenfell, M. Griener, W. Gromelski, M. Groth, O. Grover, M. Gruca, A. Gude, C. Guillemaut, R. Guirlet, J. Gunn, T. Gyergyek, L. Hagg, J. Hall, C.J. Ham, M. Hamed, T. Happel, G. Harrer, J. Harrison, D. Harting, N.C. Hawkes, P. Heinrich, S. Henderson, P. Hennequin, R. Henriques, S. Heuraux, J. Hidalgo Salaverri, J. Hillairet, J.C. Hillesheim, A. Hjalmarsson, A. Ho, J. Hobirk, E. Hodille, M. Hölzl, M. Hoppe, J. Horacek, N. Horsten, L. Horvath, M. Houry, K. Hromasova, J. Huang, Z. Huang, A. Huber, E. Huett, P. Huynh, A. Iantchenko, M. Imrisek, P. Innocente, C. Ionita Schrittwieser, H. Isliker, P. Ivanova, I. Ivanova Stanik, M. Jablczynska, S. Jachmich, A.S. Jacobsen, P. Jacquet, A. Jansen van Vuuren, A. Jardin, H. Järleblad, A. Järvinen, F. Jaulmes, T. Jensen, I. Jepu, S. Jessica, T. Johnson, A. Juven, J. Kalis, J. Karhunen, R. Karimov, A.N. Karpushov, S. Kasilov, Y. Kazakov, P.V. Kazantzidis, W. Kernbichler, HT. Kim, D.B. King, V.G. Kiptily, A. Kirjasuo, K.K. Kirov, A. Kirschner, A. Kit, T. Kiviniemi, F. Kjær, E. Klinkby, A. Knieps, U. Knoche, M. Kochan, F. Köchl, G. Kocsis, J.T.W. Koenders, L. Kogan, Y. Kolesnichenko, Y. Kominis, M. Komm, M. Kong, B. Kool, S.B. Korsholm, D. Kos, M. Koubiti, J. Kovacic, Y. Kovtun, E. Kowalska Strzeciwilk, K. Koziol, M. Kozulia, A. Krämer Flecken, A. Kreter, K. Krieger, U. Kruezi, O. Krutkin, O. Kudlacek, U. Kumar, H. Kumpulainen, M.H. Kushoro, R. Kwiatkowski, M. La Matina, M. Lacquaniti, L. Laguardia, P. Lainer, P. Lang, M. Larsen, E. Laszynska, K.D. Lawson, A. Lazaros, E. Lazzaro, M.Y.K. Lee, S. Leerink, M. Lehnen, M. Lennholm, E. Lerche, Y. Liang, A. Lier, J. Likonen, O. Linder, B. Lipschultz, A. Listopad, X. Litaudon, E. Litherland Smith, D. Liuzza, T. Loarer, P.J. Lomas, J. Lombardo, N. Lonigro, R. Lorenzini, C. Lowry, T. Luda di Cortemiglia, A. Ludvig Osipov, T. Lunt, V. Lutsenko, E. Macusova, R. Mäenpää, P. Maget, C.F. Maggi, J. Mailloux, S. Makarov, K. Malinowski, P. Manas, A. Mancini, D. Mancini, P. Mantica, M. Mantsinen, J. Manyer, M. Maraschek, G. Marceca, G. Marcer, C. Marchetto, S. Marchioni, A. Mariani, M. Marin, M. Markl, T. Markovic, D. Marocco, S. Marsden, L. Martellucci, P. Martin, C. Martin, F. Martinelli, L. Martinelli, J.R. Martin Solis, R. Martone, M. Maslov, R. Masocco, M. Mattei, G.F. Matthews, D. Matveev, E. Matveeva, M.L. Mayoral, D. Mazon, S. Mazzi, C. Mazzotta, G. McArdle, R. McDermott, K. McKay, A.G. Meigs, C. Meineri, A. Mele, V. Menkovski, S. Menmuir, A. Merle, H. Meyer, K. Mikszuta Michalik, D. Milanesio, F. Militello, A. Milocco, I.G. Miron, J. Mitchell, R. Mitteau, V. Mitterauer, J. Mlynar, V. Moiseenko, P. Molna, F. Mombelli, C. Monti, A. Montisci, J. Morales, P. Moreau, J.M. Moret, A. Moro, D. Moulton, P. Mulholland, M. Muraglia, A. Murari, A. Muraro, P. Muscente, D. Mykytchuk, F. Nabais, Y. Nakeva, F. Napoli, E. Nardon, M.F. Nave, R.D. Nem, A. Nielsen, S.K. Nielsen, M. Nocente, R. Nouailletas, S. Nowak, H. Nyström, R. Ochoukov, N. Offeddu, S. Olasz, C. Olde, F. Oliva, D. Oliveira, H.J.C. Oliver, P. Ollus, J. Ongena, F.P. Orsitto, N. Osborne, R. Otin, P. Oyola Dominguez, D.I. Palade, S. Palomba, O. Pan, N. Panadero, E. Panontin, A. Papadopoulos, P. Papagiannis, G. Papp, V.V. Parail, C. Pardanaud, J. Parisi, A. Parrott, K. Paschalidis, M. Passoni, F. Pastore, A. Patel, B. Patel, A. Pau, G. Pautasso, R. Pavlichenko, E. Pawelec, B. Pegourie, G. Pelka, E. Peluso, A. Perek, E. Perelli Cippo, C. Perez Von Thun, P. Petersson, G. Petravich, Y. Peysson, V. Piergotti, L. Pigatto, C. Piron, L. Piron, A. Pironti, F. Pisano, U. Plank, B. Ploeckl, V. Plyusnin, A. Podolnik, Y. Poels, G. Pokol, J. Poley, G. Por, M. Poradzinski, F. Porcelli, L. Porte, C. Possieri, A. Poulsen, I. Predebon, G. Pucella, M. Pueschel, P. Puglia, O. Putignano, T. Pütterich, V. Quadri, A. Quercia, M. Rabinski, L. Radovanovic, R. Ragona, H. Raj, M. Rasinski, J. Rasmussen, G. Ratta, S. Ratynskaia, R. Rayaprolu, M. Rebai, A. Redl, D. Rees, D. Refy, M. Reich, H. Reimerdes, B.C.G. Reman, O. Renders, C. Reux, D. Ricci, M. Richou, S. Rienacker, D. Rigamonti, F. Rigollet, F.G. Rimini, D. Ripamonti, N. Rispoli, N. Rivals, J.F. Rivero Rodriguez, C. Roach, G. Rocchi, S. Rode, P. Rodrigues, J. Romazanov, C.F. Romero Madrid, J. Rosato, R. Rossi, G. Rubino, J. Rueda Rueda, J. Ruiz Ruiz, P. Ryan, D. Ryan, S. Saarelma, R. Sabot, M. Salewski, A. Salmi, L. Sanchis, A. Sand, J. Santos, K. Särkimäki, M. Sassano, O. Sauter, G. Schettini, S. Schmuck, P. Schneider, N. Schoonheere, R. Schramm, R. Schrittwieser, C. Schuster, N. Schwarz, F. Sciortino, M. Scotto D’Abusco, S. Scully, A. Selce, L. Senni, M. Senstius, G. Sergienko, S.E. Sharapov, R. Sharma, A. Shaw, U. Sheikh, G. Sias, B. Sieglin, S.A. Silburn, C. Silva, A. Silva, D. Silvagni, B. Simmendefeldt Schmidt, L. Simons, J. Simpson, L. Singh, S. Sipilä, Y. Siusko, S. Smith, A. Snicker, E.R. Solano, V. Solokha, M. Sos, C. Sozzi, F. Spineanu, G. Spizzo, M. Spolaore, L. Spolladore, C. Srinivasan, A. Stagni, Z. Stancar, G. Stankunas, J. Stober, P. Strand, C.I. Stuart, F. Subba, G.Y. Sun, H.J. Sun, W. Suttrop, J. Svoboda, T. Szepesi, G. Szepesi, B. Tal, T. Tala, P. Tamain, G. Tardini, M. Tardocchi, D. Taylor, G. Telesca, A. Tenaglia, A. Terra, D. Terranova, D. Testa, C. Theiler, E. Tholerus, B. Thomas, E. Thoren, A. Thornton, A. Thrysoe, Q. TICHIT, W. Tierens, A. Titarenko, P. Tolias, E. Tomasina, M. Tomes, E. Tonello, A. Tookey, M. Toscano Jiménez, C. Tsironis, C. Tsui, A. Tykhyy, M. Ugoletti, M. Usoltseva, D.F. Valcarcel, A. Valentini, M. Valisa, M. Vallar, M. Valovic, SI. Valvis, M. van Berkel, D. Van Eester, S. Van Mulders, M. van Rossem, R. Vann, B. Vanovac, J. Varela Rodriguez, J. Varje, S. Vartanian, M. Vecsei, L. Velarde Gallardo, M. Veranda, T. Verdier, G. Verdoolaege, K. Verhaegh, L. Vermare, G. Verona Rinati, J. Vicente, E. Viezzer, L. Vignitchouk, F. Villone, B. Vincent, P. Vincenzi, M.O. Vlad, G. Vogel, I. Voitsekhovitch, I. Voldiner, P. Vondracek, N.M.T. VU, T. Vuoriheimo, C. Wade, E. Wang, T. Wauters, M. Weiland, H. Weisen, N. Wendler, D. Weston, A. Widdowson, S. Wiesen, M. Wiesenberger, T. Wijkamp, M. Willensdorfer, T. Wilson, A. Wojenski, C. Wuethrich, I. Wyss, L. Xiang, S. Xu, D. Yadykin, Y. Yakovenko, H. Yang, V. Yanovskiy, R. Yi, B. Zaar, G. Zadvitskiy, L. Zakharov, P. Zanca, D. Zarzoso, Y. Zayachuk, J. Zebrowski, M. Zerbini, P. Zestanakis, C. F. B. Zimmermann, M. Zlobinski, A. Zohar, V.K. Zotta, X. Zou, M. Zuin, M. Zurita, and I. Zychor
Subjects: JET, ASDEX Upgrade, MAST-U, TCV, WEST, Tokamak Exploitation Task Force, Nuclear and particle physics. Atomic energy. Radioactivity, QC770-798
Abstract: Within the 9th European Framework programme, since 2021 EUROfusion is operating five tokamaks under the auspices of a single Task Force called ‘Tokamak Exploitation’. The goal is to benefit from the complementary capabilities of each machine in a coordinated way and help in developing a scientific output scalable to future largre machines. The programme of this Task Force ensures that ASDEX Upgrade, MAST-U, TCV, WEST and JET (since 2022) work together to achieve the objectives of Missions 1 and 2 of the EUROfusion Roadmap: i) demonstrate plasma scenarios that increase the success margin of ITER and satisfy the requirements of DEMO and, ii) demonstrate an integrated approach that can handle the large power leaving ITER and DEMO plasmas. The Tokamak Exploitation task force has therefore organized experiments on these two missions with the goal to strengthen the physics and operational basis for the ITER baseline scenario and for exploiting the recent plasma exhaust enhancements in all four devices (PEX: Plasma EXhaust) for exploring the solution for handling heat and particle exhaust in ITER and develop the conceptual solutions for DEMO. The ITER Baseline scenario has been developed in a similar way in ASDEX Upgrade, TCV and JET. Key risks for ITER such as disruptions and run-aways have been also investigated in TCV, ASDEX Upgrade and JET. Experiments have explored successfully different divertor configurations (standard, super-X, snowflakes) in MAST-U and TCV and studied tungsten melting in WEST and ASDEX Upgrade. The input from the smaller devices to JET has also been proven successful to set-up novel control schemes on disruption avoidance and detachment.
Published: 2024
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4. WEST full tungsten operation with an ITER grade divertor

Author: J. Bucalossi, A. Ekedahl, and the WEST Team, J. Achard, K. Afonin, O. Agullo, T. Alarcon, L. Allegretti, F. Almuhisen, H. Ancher, G. Antar, Y. Anquetin, S. Antusch, V. Anzallo, C. Arnas, J.F. Artaud, M.H. Aumeunier, S.G. Baek, X.Y. Bai, M. Balden, C. Balorin, T. Barbui, A. Barbuti, J. Barlerin, J. Barra, V. Basiuk, T. Batal, O. Baulaigue, A. Bec, M. Becoulet, E. Benoit, E. Bernard, J.M. Bernard, M. Bernert, N. Bertelli, E. Bertrand, P. Beyer, J. Bielecki, P. Bienvenu, R. Bisson, B. Bliewert, G. Bodner, S. Bose, C. Bottereau, C. Bouchand, Y. Boumendjel, F. Bouquey, C. Bourdelle, J. Bourg, S. Brezinsek, F. Brochard, C. Brun, V. Bruno, H. Bufferand, A. Bureau, S. Burles, Y. Camenen, B. Cantone, E. Caprin, M. Carole, S. Carpentier-Chouchana, G. Caulier, F. Causa, N. Cazanave, N. Chanet, O. Chellai, Y. Chen, M. Chernyshova, P. Chmielewski, W. Choe, A. Chomiczewska, G. Ciraolo, F. Clairet, J. Coenen, L. Colas, G. Colledani, J. Colnel, P. Coquillat, E. Corbel, Y. Corre, X. Courtois, T. Czarski, A. Da Ros, R. Daniel, J. Daumas, M. De Combarieu, P. De Vries, C. Dechelle, F. Deguara, R. Dejarnac, J.M. Delaplanche, L.F. Delgado-Aparicio, E. Delmas, L. Delpech, C. Desgranges, P. Devynck, J. Denis, S. Di Genova, R. Diab, A. Diallo, M. Diez, G. Dif-Pradalier, M. Dimitrova, R. Ding, T. Dittmar, L. Doceul, M. Domenes, D. Donovan, D. Douai, L. Dubus, N. Dumas, R. Dumont, F. Durand, A. Durif, F. Durodié, D. Elbeze, S. Ertmer, A. Escarguel, F. Escourbiac, B. Esposito, K. Ezato, F. Faisse, J.L. Farjon, N. Faure, N. Fedorczak, P. Fejoz, F. Felici, C. Fenzi-Bonizec, F. Ferlay, L. Ferrand, L. Fevre, M. Firdaouss, L. Fleury, D. Flouquet, T. Fonghetti, A. Gallo, X. Garbet, J. Garcia, J.L. Gardarein, L. Gargiulo, P. Garibaldi, S. Garitta, J. Gaspar, E. Gauthier, S. Gazzotti, F. Gely, J. Gerardin, G. Gervasini, E. Geulin, M. Geynet, P. Ghendrih, I. Giacalone, C. Gil, S. Ginoux, S. Girard, E. Giroux, G. Giruzzi, M. Goniche, V. Gorse, T. Gray, E. Grelier, C. Grisolia, A. Grosjean, A. Grosman, O. Grover, D. Guibert, D. Guilhem, C. Guillemaut, B. Guillermin, R. Guirlet, J.P. Gunn, Y. Gunsu, T. Gyergyek, S. Hacquin, A. Hakola, J. Harris, J.C. Hatchressian, W. Helou, P. Hennequin, C. Hernandez, L. Hijazi, J. Hillairet, T. Hirai, G.T. Hoang, C. Honoré, M. Houry, A. Huart, G. Huijsmans, P. Huynh, M. Iafrati, F. Imbeaux, N. Imbert, I. Ivanova-Stanik, P. Ivanova, R. Jalageas, A. Jamann, C. Jammes, A. Jardin, L. Jaubert, G. Jiolat, E. Joffrin, C. Johnson, A. Jonas, A. Kirschner, C.C. Klepper, M. Komm, M. Koubiti, S. Kosslow, J. Kovacic, M. Kozeiha, K. Krieger, K. Krol, I. Kudashev, B. Lacroix, L. Laguardia, V. Lamaison, V. Lapleigne, H. Laqua, C. Lau, Y. Lausenaz, R. Lé, M. Le Bohec, N. Lefevre, N. Lemoine, E. Lerche, Y. Lesourd, L. Letellier, M. Lewerentz, Y. Li, A. Liang, P. Linczuk, C. Linsmeier, M. Lipa, X. Litaudon, X. Liu, J. Llorens, T. Loarer, A. Loarte, T. Loewenhoff, G. Lombard, J. Lore, P. Lorenzetto, B. Lu, A. Lumsdaine, R. Lunsford, T. Lunt, G. Luo, P. Magaud, P. Maget, J.F. Mahieu, P. Maini, P. Malard, K. Malinowski, P. Manas, L. Manenc, V. Maquet, Y. Marandet, C. Martin, E.J. Martin, P. Martino, M. Mayer, D. Mazon, S. Mazzi, P. Messina, L. Meunier, D. Midou, G. Miglionico, Y. Mineo, M. Missirlian, R. Mitteau, B. Mitu, D. Moiraf, P. Mollard, G. Momparler, V. Moncada, T. Mondiere, C. Monti, J. Morales, M. Moreau, Ph. Moreau, Y. Moudden, G. Moureau, D. Mouyon, M. Muraglia, T. Nakano, E. Nardon, A. Neff, F. Nespoli, J. Nichols, L. Nicolas, S. Nicollet, R. Nouailletas, M. Ono, V. Ostuni, O. Paillat, C. Parish, H. Park, H. Parrat, J.Y. Pascal, B. Pegourie, F.P. Pellissier, Y. Peneliau, M. Peret, E. Pignoly, G. Pintsuk, R. Pitts, C. Pocheau, A. Podolnik, C. Portafaix, M. Poulos, P. Prochet, A. Puig Sitjes, R. Ragona, M. Rasinski, S. Ratynskaia, G. Raup, X. Regal-Mezin, C. Reux, J. Rice, M. Richou, F. Rigollet, N. Rivals, H. Roche, S. Rodrigues, J. Romazanov, G. Ronchi, C. Ruset, R. Sabot, A. Saille, R. Sakamoto, B. Salamon, F. Samaille, A. Santagiustina, B. Santraine, Y. Sarazin, O. Sauter, Y. Savoie-Peysson, L. Schiesko, M. Scholz, J.L. Schwob, E. Serre, H. Shin, S. Shiraiwa, Ja. Signoret, O. Skalli-Fettachi, P. Sogorb, Y. Song, A. Spring, P. Spuig, S. Sridhar, B. Stratton, C. Talatizi, P. Tamain, R. Tatali, Q. Tichit, A. Torre, L. Toulouse, W. Treutterer, E. Tsitrone, E.A. Unterberg, G. Urbanczyk, G. Van Rooij, N. Varadarajan, S. Vartanian, E. Velly, J.M. Verger, L. Vermare, D. Vezinet, N. Vignal, B. Vincent, S. Vives, D. Volpe, G. Wallace, E. Wang, L. Wang, Y. Wang, Y.S. Wang, T. Wauters, D. Weldon, B. Wirth, M. Wirtz, A. Wojenski, M. Xu, Q.X. Yang, H. Yang, B. Zago, R. Zagorski, B. Zhang, X.J. Zhang, X.L. Zou, and the EUROfusion Tokamak Exploitation Team
Subjects: nuclear fusion, magnetic confinement, tokamak, divertor, WEST, ITER, Nuclear and particle physics. Atomic energy. Radioactivity, QC770-798
Abstract: The mission of WEST (tungsten-W Environment in Steady-state Tokamak) is to explore long pulse operation in a full tungsten (W) environment for preparing next-step fusion devices (ITER and DEMO) with a focus on testing the ITER actively cooled W divertor in tokamak conditions. Following the successful completion of phase 1 (2016-2021), phase 2 started in December 2022 with the lower divertor made entirely of actively cooled ITER-grade tungsten mono-blocks. A boronization prior the first plasma attempt allowed for a smooth startup with the new divertor. Despite the reduced operating window due to tungsten, rapid progress has been made in long pulse operation, resulting in discharges with a pulse length of 100 s and an injected energy of around 300 MJ per discharge. Plasma startup studies were carried out with equatorial boron nitride limiters to compare them with tungsten limiters, while Ion Cyclotron Resonance Heating assisted startup was attempted. High fluence operation in attached regime, which was the main thrust of the first campaigns, already showed the progressive build up of deposits and appearance of dust, impacting the plasma operation as the plasma fluence increased. In total, the cumulated injected energy during the first campaigns reached 43 GJ and the cumulated plasma time exceeded 5 h. Demonstration of controlled X-Point Radiator regime is also reported, opening a promising route for investigating plasma exhaust and plasma-wall interaction issues in more detached regime. This paper summarises the lessons learned from the manufacturing and the first operation of the ITER-grade divertor, describing the progress achieved in optimising operation in a full W environment with a focus on long pulse operation and plasma wall interaction.
Published: 2024
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5. Model-predictive kinetic control with data-driven models on EAST

Author: D. Moreau, S. Wang, J.P. Qian, Q. Yuan, Y. Huang, Y. Li, S. Ding, H. Du, X. Gong, M. Li, H. Liu, Z. Luo, L. Zeng, E. Olofsson, B. Sammuli, J.F. Artaud, A. Ekedahl, and E. Witrant
Subjects: tokamaks, plasma control, kinetic control, profile control, model-predictive control, two-time-scale control, Nuclear and particle physics. Atomic energy. Radioactivity, QC770-798
Abstract: In this work, model-predictive control (MPC) was combined for the first time with singular perturbation theory, and an original plasma kinetic control method based on extremely simple data-driven models and a two-time-scale MPC algorithm has been developed. A comprehensive review is presented in this paper. Slow and fast semi-empirical models are identified from data, by considering the fast kinetic plasma dynamics as a singular perturbation of a quasi-static equilibrium, which itself is governed, on the slow time scale, by the flux diffusion equation. This control technique takes advantage of the large ratio between the time scales involved in magnetic and kinetic plasma transport. It is applied here to the simultaneous control of the safety factor profile, q (𝑥), and of several kinetic variables, such as the poloidal beta parameter, β _p , and the internal inductance parameter, l _i , on the EAST tokamak. In the experiments, the available control actuators were lower hybrid current drive (LHCD) and co-current neutral beam injection (NBI) from different sources. Ion cyclotron resonant heating (ICRH) and electron cyclotron resonant heating (ECRH) are used as additional actuators in control simulations. In the controller design, an observer provides, in real time, an estimate of the system states and of the mismatch between measured and predicted outputs, which ensures robustness to model errors and offset-free control. Based on the observer information, the controller predicts the behavior of the system over a given time horizon and computes the optimal actuation by solving a quadratic programming optimization problem that takes the actuator constraints into account. A number of control applications are described in the paper, either in nonlinear simulations with EAST-like parameters or in real experiments on EAST. The simulations were performed with a fast plasma simulator (METIS) using either two control actuators (LHCD and ICRH) in a low density scenario, or up to four actuators at higher density: LHCD, ECRH, and two NBI systems driven in a on/off pulse-width-modulation (PWM) mode, with different injection angles. The control models are identified with the prediction-error method, using datasets obtained from open loop simulations in which the actuators are modulated with pseudo-random binary sequences. The simulations with two actuators show that various q (𝑥) profiles and β _p waveforms can be tracked without offset, within times that are consistent with the resistive and thermal diffusion time scales, respectively. In simulations with four actuators, simultaneous tracking of time-dependent targets is shown for q (𝑥) at two normalized radii, 𝑥 = 0 and 𝑥 = 0.4, and for β _p . Due to the inherent mismatch between the optimal NBI power request and the delivered PWM power, the kinetic controller performs with reduced accuracy compared with simulations that do not use the NBI/PWM actuators. The first experimental tests using this new control algorithm were performed on EAST when the only available actuator was the LHCD system at 4.6 GHz. The algorithm was thus used in its simplest single-input-single-output version to track time-dependent targets for the central safety factor, q _0 , or for β _p . In the closed loop control experiments, the q _0 targets were tracked in about one second, consistently with the plasma resistive time constant. Excellent tracking of a piecewise linear β _p target waveform was also achieved. When the NBI system became controllable in real time by the EAST plasma control system, new experiments were dedicated to multiple-input-multiple-output MPC control with three actuators: LHCD and two NBI actuators using the PWM algorithm. Given that the minimum time allowed between NBI on/off switching was 0.1 s, i.e. larger than the characteristic time of the fast plasma dynamics, a reduced version of the MPC controller based only on the slow model was used. Various controller configurations were tested during a single experimental session, with up to three controlled variables chosen among q _0 = q ( 𝑥 = 0), q _1 = q ( 𝑥 = 0.5), β _p and l _i . The main difficulty encountered during this session was the unavailability of the full baseline ICRH and ECRH powers that were used in the reference scenario, and from which the plasma model was identified. This often led to the saturation of one or several actuators, which prevented some targets selected in advance from being accessible. Nevertheless, in cases that were free from actuator saturation, q _0 and q _1 targets were successfully reached, in a time that is consistent with the resistive diffusion time of the model and with small oscillations that are characteristic of the PWM operation of the neutral beams. During the simultaneous control of q _0 and β _p , the ICRH power was too low and, in addition, the plasma density was much larger than the reference one. The q _0 targets were not accessible in this high-density/low-power case, but β _p control was successful. Finally, the simultaneous control of q _0 and l _i was satisfactory and, during the simultaneous control of, q _0 , β _p and l _i , the tracking of β _p and l _i was satisfactory but q _0 was too large due to the lack of ICRH power and to NBI saturation. In conclusion, the extensive nonlinear simulations described in this paper have demonstrated the relevance of combining MPC, data-driven models and singular perturbation methods for plasma kinetic control. This technique was also assessed experimentally on EAST, although some tests were perturbed by undesired parameter changes with respect to the reference scenario.
Published: 2024
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6. Separatrix parameters and core performances across the WEST L-mode database

Author: C. Bourdelle, J. Morales, J.F. Artaud, O. Grover, T. Radenac, J. Bucalossi, Y. Camenen, G. Ciraolo, F. Clairet, R. Dumont, N. Fedorczak, J. Gaspar, C. Gil, M. Goniche, C. Guillemaut, J. Gunn, P. Maget, P. Manas, V. Ostuni, B. Pégourié, Y. Peysson, P. Tamain, L. Vermare, D. Vézinet, and the WEST Team
Subjects: plasma, tokamak, database, confinement, separatrix, Nuclear and particle physics. Atomic energy. Radioactivity, QC770-798
Abstract: WEST database analysis shows a correlation of the recycled neutral source around the separatrix with core performances. This observation questions the causality chain between particle source and turbulent transport up to the core in L-mode, high recycling plasmas, an unavoidable phase of all scenarios. The best core performances correlate with the lowest values of the density at the separatrix, ${n_{{\text{sep}}}}$ , similarly to ASDEX Upgrade (AUG) tokamak and Joint European Torus (JET) tokamak in H-mode (Verdoolaege et al 2021 Nucl. Fusion 61 076006). Reflectometry in the midplane provides ${n_{{\text{sep}}}}$ , while the temperature at the separatrix, ${T_{{\text{sep}}}}$ is inferred by the ‘two-point model’ using Langmuir probe data on divertor targets. Lower separatrix resistivity does not correlate with better core performances, unlike H-mode observations (Eich et al 2020 Nucl. Fusion 60 056016). As expected in the presence of an efficient neutral source due to recycling fluxes, ${n_{{\text{sep}}}}$ correlates with the D recycled particle flux at the divertor measured by visible spectroscopy. Coherently, at a given controlled central line integrated density $\bar n$ , lower ${n_{{\text{sep}}}}$ correlates with a larger density gradient around the separatrix as well as a larger global density peaking, $\bar n/\langle n\rangle $ , measured by interferometry. The latter correlates as well with lower collisionality in the core, similarly to JET and AUG H-modes (Angioni et al 2007 Nucl. Fusion 47 1326). The correlations reported allow phrasing the subsequent causality question: what is the interplay chain between low neutral recycling at the divertor plates, low density at the separatrix, high density peaking at the separatrix, high global density peaking, higher central temperature and better core energy confinement quality? Understanding the causality chain is essential to prepare ITER operation and design DEMO scenarios where the ratio of the divertor leg to the ionization length will be larger and where the pumped flux with respect to the plasma volume will be lower than presently operating tokamaks.
Published: 2023
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7. Estimate of 3D power wall loads due to Neutral Beam Injection in EU DEMO ramp-up phase

Author: P. Vincenzi, J. Varje, P. Agostinetti, J.F. Artaud, T. Bolzonella, T. Kurki-Suonio, M. Mattei, P. Sonato, and M. Vallar
Subjects: Nuclear engineering. Atomic power, TK9001-9401
Abstract: Heating and current drive systems such as high energy Neutral Beam Injection (NBI) are being considered for pulsed EU DEMO (“DEMO1”) pre-conceptual design. Their aim is to provide auxiliary power, not only during flat-top, but also during transient phases (i.e. plasma current ramp-up and ramp-down).In this work, NBI fast particle power loads on DEMO1 first wall, due to shine-through and orbit losses, are calculated for the diverted plasma ramp-up phase. Numerical simulations are performed using BBNBI and ASCOT Monte Carlo codes. The simulations have been done using a complete 3D wall geometry, and implementing the latest DEMO NBI design, which foresees NBI at 800 keV particle energy. Location and power density of NBI-related power loads at different ramp-up time steps are evaluated and compared with the maximum tolerable heat flux taken from ITER case. Since NBI shine-through losses (dominant during low density phases) depend mainly on the beam energy, plasma density and volume, DEMO has a more favourable situation than ITER, enlarging NBI operational window. Using ITER criteria, DEMO NBI at full energy and power could be switched on during ramp-up at ~ 1.3 × 1019 m-3. This increases the appeal of neutral beam injectors as auxiliary power systems for DEMO.
Published: 2019
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8. Separatrix parameters and core performances across WEST L-mode database

Author: C. Bourdelle, J. Morales, J.F. Artaud, O. Grover, T. Radenac, J. Bucalossi, Y. Camenen, G. Ciraolo, F. Clairet, R. Dumont, N. Fedorczak, J. Gaspar, C. Gil, M. Goniche, C. Guillemaut, J. Gunn, P. Maget, P. Manas, V. Ostuni, B. Pégourié, Y. Peysson, P. Tamain, L. Vermare, D. Vézinet, Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), Commissariat à l'énergie atomique et aux énergies alternatives (CEA), Max-Planck-Institut, Physique des interactions ioniques et moléculaires (PIIM), Aix Marseille Université (AMU)-Centre National de la Recherche Scientifique (CNRS), Aix Marseille Université (AMU), European Project: 101052200,Implementation of activities described in the Roadmap to Fusion during Horizon Europe through a joint programme of the members of the EUROfusion consortium,EUROfusion, European Project: 633053,H2020,EURATOM-Adhoc-2014-20,EUROfusion(2014), and WEST Team
Subjects: [PHYS]Physics [physics], Nuclear and High Energy Physics, [PHYS.PHYS.PHYS-PLASM-PH]Physics [physics]/Physics [physics]/Plasma Physics [physics.plasm-ph], Condensed Matter Physics
Abstract: WEST database analysis shows a correlation of the recycled neutral source around the separatrix with core performances. This observation questions the causality chain between particle source and turbulent transport up to the core in L-mode, high recycling plasmas, an unavoidable phase of all scenarios. The best core performances correlate with the lowest values of the density at the separatrix, n sep , similarly to ASDEX Upgrade (AUG) tokamak and Joint European Torus (JET) tokamak in H-mode (Verdoolaege et al 2021 Nucl. Fusion 61 076006). Reflectometry in the midplane provides n sep , while the temperature at the separatrix, T sep is inferred by the ‘two-point model’ using Langmuir probe data on divertor targets. Lower separatrix resistivity does not correlate with better core performances, unlike H-mode observations (Eich et al 2020 Nucl. Fusion 60 056016). As expected in the presence of an efficient neutral source due to recycling fluxes, n sep correlates with the D recycled particle flux at the divertor measured by visible spectroscopy. Coherently, at a given controlled central line integrated density n ˉ , lower n sep correlates with a larger density gradient around the separatrix as well as a larger global density peaking, n ˉ / ⟨ n ⟩ , measured by interferometry. The latter correlates as well with lower collisionality in the core, similarly to JET and AUG H-modes (Angioni et al 2007 Nucl. Fusion 47 1326). The correlations reported allow phrasing the subsequent causality question: what is the interplay chain between low neutral recycling at the divertor plates, low density at the separatrix, high density peaking at the separatrix, high global density peaking, higher central temperature and better core energy confinement quality? Understanding the causality chain is essential to prepare ITER operation and design DEMO scenarios where the ratio of the divertor leg to the ionization length will be larger and where the pumped flux with respect to the plasma volume will be lower than presently operating tokamaks.
Published: 2023
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9. The Commissioning of the WEST Tokamak: Experience and Lessons Learned

Author: E. Tsitrone, F. Saint-Laurent, P. Moreau, Eric Nardon, Jérôme Bucalossi, C. Reux, Patrick Tamain, Rémy Nouailletas, Clarisse Bourdelle, D. Douai, J.F. Artaud, Sylvain Brémond, T. Loarer, and Nicolas Fedorczak
Subjects: Nuclear and High Energy Physics, Materials science, Toroid, Tokamak, Project commissioning, Nuclear engineering, Divertor, Plasma, Superconducting magnet, Condensed Matter Physics, 01 natural sciences, 010305 fluids & plasmas, law.invention, law, Magnet, 0103 physical sciences, Cooling down
Abstract: The integrated commissioning of the tungsten (W) environment in steady-state tokamak (WEST) was started with the superconducting magnet cool-down and completed one year after by the injection of 2.5 MW of additional power. It consisted of several steps: local system commissioning, integrated commissioning without plasma, and first plasma operation. This article reviews these WEST commissioning phases and highlights the experiences and the lessons learned. The magnet cooling down operation was initiated in late September 2016. The vacuum vessel was pumped out three weeks before the first plasma. The impregnation and curing of the two in-vessel divertor coils was performed at 180 °C during two days contributing to the baking of the vacuum vessel. In the meanwhile, rehearsal sessions for testing the CODAC systems were organized every month. The toroidal, poloidal, and divertor field coils were energized and their performance was tested successfully allowing moving to the first plasma operation phase. After a few attempts, plasma breakdown was achieved confirming that all systems were properly running and synchronized. Due to several micro air leaks on fiber optic feedthroughs and issues with the design of the in-vessel stabilizing plates, plasma current ramp-up could not be achieved in a first step. Once these issues have been fixed, confined plasmas could be obtained. Diverted plasmas were then achieved and the plasma current was increased up to 800 kA for more than 10 s. Up to 2.5 MW of additional power was eventually successfully coupled to the plasma.
Published: 2020
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10. Core-edge 2D fluid modeling of full tokamak discharge with varying magnetic equilibrium: from WEST start-up to ramp-down

Author: M. Scotto d’Abusco, G. Giorgiani, J.F. Artaud, H. Bufferand, G. Ciraolo, P. Ghendrih, E. Serre, P. Tamain, Laboratoire de Mécanique, Modélisation et Procédés Propres (M2P2), Aix Marseille Université (AMU)-École Centrale de Marseille (ECM)-Centre National de la Recherche Scientifique (CNRS), Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), Commissariat à l'énergie atomique et aux énergies alternatives (CEA), ANR-19-CE46-0005,SISTEM,Simulations par schémas d'ordre élevé du transport et de la turbulence dans un tokamak(2019), ANR-11-IDEX-0001,Amidex,INITIATIVE D'EXCELLENCE AIX MARSEILLE UNIVERSITE(2011), and Centre National de la Recherche Scientifique (CNRS)-École Centrale de Marseille (ECM)-Aix Marseille Université (AMU)
Subjects: [PHYS]Physics [physics], Nuclear and High Energy Physics, [SPI]Engineering Sciences [physics], Physics::Plasma Physics, [SPI.FLUID]Engineering Sciences [physics]/Reactive fluid environment, 0103 physical sciences, [SPI.PLASMA]Engineering Sciences [physics]/Plasmas, 010306 general physics, Condensed Matter Physics, 01 natural sciences, [INFO.INFO-MO]Computer Science [cs]/Modeling and Simulation, 010305 fluids & plasmas
Abstract: In the present work we investigate for the first time the 2D fluid transport of the plasma in WEST during an entire discharge from the start-up to the ramp-down (shot #54487). The evolution of density profile, electron and ion temperatures together with the experimental magnetic equilibrium, total current and gas-puff rate is investigated. Comparisons with the interferometry diagnostic show a remarkable overall qualitative agreement during the discharge that can be quantitative at some locations in the plasma core. If at the onset of the X-points during the ramp-up the electron heat flux is dominant at the target, present results show that the ion heat flux becomes dominant during the stationary phase of the discharge. Using a simple model for erosion, present results assess the tungsten sputtering due to deuterium ions during the start-up and ramp-up phases of the discharge and confirm the need to consider full discharge simulation to accurately treat the W source of contamination. This work also demonstrates the interest of developing magnetic equilibrium free solver including efficient time integration to step toward predictive capabilities in the future for fusion operation.
Published: 2022
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11. Neutral beam injection for DEMO alternative scenarios

Author: J.F. Artaud, H. Zohm, P. Vincenzi, E. Fable, G. Giruzzi, and Mattia Siccinio
Subjects: Optimal design, Computer science, Mechanical Engineering, Nuclear engineering, Plasma, Fusion power, 7. Clean energy, 01 natural sciences, Neutral beam injection, 010305 fluids & plasmas, Nuclear Energy and Engineering, 0103 physical sciences, Systems design, Torque, General Materials Science, 010306 general physics, Energy (signal processing), Civil and Structural Engineering, Parametric statistics
Abstract: Within the current EU pre-conceptual design activities, the reference demonstrative fusion power plant concept relies on ITER-like, pulsed H-mode plasmas (“DEMO1”). Simultaneously, alternative design options are being considered. An example is “Flexi-DEMO”, which is designed for steady-state plasma discharges, but can also be run pulsed at the same fusion power with the same auxiliary heating systems if the plasma confinement time turns out to be not sufficient for non-inductive operations. Preliminary investigations have started also for ELM-free regimes, such as I-mode or QH-mode, due to the issues encountered in ELMs active control at reactor scales. Neutral beam injection (NBI) is one of the candidates for a DEMO heating and current-drive system. Depending on the system design, NBI can be optimized for e.g. central heating (as for DEMO1), current-drive (as for Flexi-DEMO) or even to provide torque to the plasma (which may favour the access to ELM-free QH-mode regime). In the present contribution we describe the main NBI features in terms of design parameters (NBI energy, injection geometry) that would optimize these alternative DEMO plasma scenarios, in particular regarding Flexi-DEMO and QH-mode regime. Wide-range parametric scans through METIS numerical simulations of DEMO plasmas indicate the optimal design windows for NBI system in each plasma configuration. These results need however further validations against technical constraints, available technology limits and detailed plasma transport simulations.
Published: 2021

12. Optimization-oriented modelling of neutral beam injection for EU pulsed DEMO

Author: Jari Varje, M. Vallar, P. Vincenzi, Massimiliano Mattei, Piero Agostinetti, Tommaso Bolzonella, Taina Kurki-Suonio, J.F. Artaud, Vincenzi, P., Agostinetti, P., Artaud, J. F., Bolzonella, T., Kurki-Suonio, T., Mattei, M., Vallar, M., Varje, J., National Research Council of Italy, CEA, Fusion and Plasma Physics, University of Naples Federico II, Department of Applied Physics, Aalto-yliopisto, and Aalto University
Subjects: Materials science, ASCOT, NBI, Plasma, Condensed Matter Physics, plasmas, 7. Clean energy, 01 natural sciences, Neutral beam injection, 010305 fluids & plasmas, Nuclear Energy and Engineering, Deuterium, 0103 physical sciences, fast ion, fast ions, Atomic physics, 010306 general physics, DEMO, deuterium, ramp-up
Abstract: openaire: EC/H2020/633053/EU//EUROfusion Neutral beam injection (NBI) is one of the auxiliary power systems considered for the EU DEMO pulsed plasma ('DEMO1'). In this paper, we discuss the characteristics of optimized NBI in terms of the DEMO1 requirements, relating physics and engineering contexts in a novel parameter range compared to current NBI systems and in a larger plasma volume than ITER. Different injection options are investigated to account for various concepts discussed in the literature. The investigation is carried out using a wide range of sensitivity studies by means of the METIS 0.5D transport code and ASCOT Monte Carlo simulations of injected neutral-beam particles. This investigation has generated a series of recommendations for the NBI design, contributing to the system optimization process. We show how tangential injection aimed at the plasma core, with an energy greater than or similar to 800 keV, is recommended to maintain high fusion power performance and fulfill the requirements for bulk heating. Compliance with engineeringconstraints on the NBI design, e.g., the least interference with breeding blanket modules or compatibility with solutions for the beamline components, imposes some restrictions when discussing the beam geometry. The minimum density at which an NBI can be safely operated without harmful shine-through losses is investigated for different injection energies and compared to the ITER case. The NBI operational window for DEMO is shown to be significantly extended to transient, low-density phases, also highlighting the importance of NBI systems designed for modular energy and power output. NBI can therefore sustain the plasma during a considerable portion of the transient phases, i.e., the current ramp-up and ramp-down phases. The final decision on the DEMO heating mix will be made on the basis of system operability and performance: the optimized NBI is shown to be a suitable and effective option for the EU DEMO inductive scenario.
Published: 2021
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13. DEMO design using the SYCOMORE system code: Influence of technological constraints on the reactor performances

Author: Michal Owsiak, J.F. Artaud, N. Piot, Frederic Imbeaux, Jean-Charles Jaboulay, B. Saoutic, S. Dardour, L. Di Gallo, J.L. Duchateau, L. Zani, S. Kahn, J. Said, B. Pégourié, Davide Galassi, Giacomo Aiello, Philippe Magaud, C. Reux, A. Boutry, P. Sardain, Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), Commissariat à l'énergie atomique et aux énergies alternatives (CEA), Poznan Supercomputing and Networking Center (PSNC), CEA-Direction des Energies (ex-Direction de l'Energie Nucléaire) (CEA-DES (ex-DEN)), Laboratoire de Mécanique, Modélisation et Procédés Propres (M2P2), Aix Marseille Université (AMU)-École Centrale de Marseille (ECM)-Centre National de la Recherche Scientifique (CNRS), and Centre National de la Recherche Scientifique (CNRS)-École Centrale de Marseille (ECM)-Aix Marseille Université (AMU)
Subjects: Power station, Superconducting magnet, Tritium, 01 natural sciences, 7. Clean energy, 010305 fluids & plasmas, Fusion reactor, Power Balance, System code, Superconducting magnets, 0103 physical sciences, [SPI.GPROC]Engineering Sciences [physics]/Chemical and Process Engineering, General Materials Science, 010306 general physics, Process engineering, DEMO, Power balance, Civil and Structural Engineering, business.industry, Mechanical Engineering, Divertor, Fusion power, Coolant, Nuclear Energy and Engineering, Electromagnetic coil, Electric power, Breeding blankets, business
Abstract: International audience; The next step for fusion energy after the ITER tokamak is the demonstration power plant DEMO. In this framework , system codes are used to address high-level key design issues for the DEMO pre-conceptual phase. They aim at capturing the interactions between the subsystems of a fusion reactor. SYCOMORE is a modular system code which includes physics and technology models coupled to an optimizer in order to explore a large design parameter space. In the present paper, trade-off studies focused on technology modules are reported including the influence of some design-driving assumptions on the reactor performances and size, starting from a European DEMO1-like design (more than 500 MW net electric power and 2 h burn duration). The increase of the mechanical stress limits in TF and CS magnets can help reducing the reactor size, slightly more when high temperature superconductors are used in the TF coil. The tritium breeding ratio can be improved to more than 1.10 by a moderate increase of the size, but the tritium burn-up ratio needs one additional meter of major radius for every percent increase. Divertor coolant options are also compared, showing some differences between helium, hot and cold water scenarios at various incident divertor heat fluxes.
Published: 2018
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14. Progress of HL-2A experiments and HL-2M program

Author: X.R. Duan, M. Xu, W.L. Zhong, Y. Liu, X.M. Song, D.Q. Liu, Y.Q. Wang, B. Lu, Z.B. Shi, G.Y. Zheng, Yong Liu, Q.W. Yang, W.C. Mao, Q. Li, L.J. Cai, X.Q. Ji, X.L. Liu, L.C. Li, B. Li, J.Q. Dong, X.T. Ding, L.W. Yan, J.F. Artaud, X.Y. Bai, J.Y. Cao, Z. Cao, L. Chen, W. Chen, L. Delpech, H.L. Du, A. Ekedahl, Z. Gao, J. Garcia, M.K. Han, G.Z. Hao, H.M. He, G.T. Hoang, M. Huang, M. Isobe, M. Jiang, A.S. Liang, Y.Q. Liu, D. Li, H.J. Li, J.Q. Li, J.X. Li, Qing Li, Yongge Li, T. Long, D. Mazon, G.R. Mckee, Z.Y. Qiu, J.F. Peng, Y. Peysson, J. Rao, X. Song, T.F. Sun, Z.X. Wang, H.L. Wei, J. Wen, N. Wu, Y.H. Xu, G.L. Xiao, X.P. Xiao, L. Xue, Z. Yan, Z.Y. Yang, D.L. Yu, L.M. Yu, Y. Yu, L.G. Zang, J.H. Zhang, N. Zhang, Y.P. Zhang, F. Zonca, and X.L. Zou
Subjects: Nuclear and High Energy Physics, Condensed Matter Physics
Abstract: Since the last IAEA Fusion Energy Conference in 2018, significant progress of the experimental program of HL-2A has been achieved on developing advanced plasma physics, edge localized mode (ELM) control physics and technology. Optimization of plasma confinement has been performed. In particular, high-β N H-mode plasmas exhibiting an internal transport barrier have been obtained (normalized plasma pressure β N reached up to 3). Injection of impurity improved the plasma confinement. ELM control using resonance magnetic perturbation or impurity injection has been achieved in a wide parameter regime, including types I and III. In addition, impurity seeding with supersonic molecular beam injection or laser blow-off techniques has been successfully applied to actively control the plasma confinement and instabilities, as well as plasma disruption with the aid of disruption prediction. Disruption prediction algorithms based on deep learning are developed. A prediction accuracy of 96.8% can be reached by assembling a convolutional neural network. Furthermore, transport resulting from a wide variety of phenomena such as energetic particles and magnetic islands has been investigated. In parallel with the HL-2A experiments, the HL-2M mega-ampere class tokamak was commissioned in 2020 with its first plasma. Key features and capabilities of HL-2M are briefly presented.
Published: 2022
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15. First lower hybrid current drive experiments on the WEST tokamak

Author: West Team, A. Ekedahl, D. Vezinet, M. Goniche, J. P. Gunn, Jorge Morales, X. Regal-Mezin, Nicolas Fedorczak, C. Desgranges, F. Saint-Laurent, C. Reux, C. Christopher Klepper, Jérôme Bucalossi, Clarisse Bourdelle, R. J. Dumont, J.F. Artaud, Lena Delpech, P. Moreau, O. Meyer, Didier Mazon, Patrick Maget, C. Gil, P. Devynck, J. Garcia, Rémy Nouailletas, and Y. Peysson
Subjects: Tokamak, Materials science, Divertor, chemistry.chemical_element, Electron, Tungsten, law.invention, chemistry, law, Electron temperature, Current (fluid), Atomic physics, Reflection coefficient, Voltage
Abstract: The first lower hybrid current drive experiments in the full tungsten WEST tokamak are reported. Good wave coupling is found at rather low plasma current (q95∼4.3) and medium density (ne∼3×1019m-3). Reflection coefficient is in agreement with the expectation from the linear theory of coupling. With low reflection coefficients, 5MW was coupled for 2 seconds. High central electron temperature, up to 5keV, is achieved at ne = 3-4×1019m-3. Flat and even hollow profiles of tungsten density are derived from the bolometry diagnostic. The stored thermal energy follows the H96-P scaling law with very slight degradation with density. The current drive efficiency has been assessed in low loop voltage (VL∼0.15V) discharges. Low plasma current operation and rather high effective charge (Zeff∼3) lead to modest current drive efficiency (ƞ = 0.5-0.65 × 1019 A.W−1m-2). Long pulse operation (∼30s) with high LHCD power (PLH=2.7MW) is achieved with stationary parameters, in particular electron and impurity densities, with the upper water-cooled tungsten divertor.
Published: 2020
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16. Sensitivity analysis of fusion power plant designs using the SYCOMORE system code

Author: S. Dardour, Michal Owsiak, Jérôme Bucalossi, R. Radhakrishnan, J.F. Artaud, L. Di Gallo, Frederic Imbeaux, Jean-Charles Jaboulay, N. Piot, L. Zani, J. B. Blanchard, Giacomo Aiello, C. Reux, S. Kahn, Davide Galassi, Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), Commissariat à l'énergie atomique et aux énergies alternatives (CEA), Service d’Études des Réacteurs et de Mathématiques Appliquées (SERMA), Département de Modélisation des Systèmes et Structures (DM2S), CEA-Direction des Energies (ex-Direction de l'Energie Nucléaire) (CEA-DES (ex-DEN)), Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Université Paris-Saclay-CEA-Direction des Energies (ex-Direction de l'Energie Nucléaire) (CEA-DES (ex-DEN)), Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Université Paris-Saclay, Service de Thermo-hydraulique et de Mécanique des Fluides (STMF), International Atomic Energy Agency [Vienna] (IAEA), Laboratoire de Mécanique, Modélisation et Procédés Propres (M2P2), Aix Marseille Université (AMU)-École Centrale de Marseille (ECM)-Centre National de la Recherche Scientifique (CNRS), Poznan Supercomputing and Networking Center, URANIE team, European Project: 633053,H2020,EURATOM-Adhoc-2014-20,EUROfusion(2014), Service des Réacteurs et de Mathématiques Appliquées (SERMA), and Centre National de la Recherche Scientifique (CNRS)-École Centrale de Marseille (ECM)-Aix Marseille Université (AMU)
Subjects: [PHYS]Physics [physics], Nuclear and High Energy Physics, Propagation of uncertainty, Safety factor, Power station, Computer science, Fusion power, Condensed Matter Physics, 01 natural sciences, 7. Clean energy, 010305 fluids & plasmas, Power (physics), Reliability engineering, Electricity generation, 0103 physical sciences, Sensitivity (control systems), Electric power, 010306 general physics
Abstract: International audience; The next step after ITER is the demonstration of stable electricity production with a fusion reactor. Key design performances will have to be met by the corresponding power plant demonstrator (DEMO), fulfilling a large number of constraints. System codes such as SYCOMORE, by simulating all the fusion power plant subsystems , address those questions. To be able to perform design optimizations, simplified models relying on physical and technological assumptions have to be used, resulting in a large number of input parameters. As these parameters are not always exactly known, the impact of their associated uncertainties on final design performances has to be evaluated. Sensitivity methods, by measuring the relative influence of inputs on the figures of merit of the design, allow to select the dominant parameters. This information helps the search for optimal working points, guides the priority for technical improvements and finally allows selecting meaningful inputs for uncertainty propagation. A full set of sensitivity methods and their application on a ITER and a DEMO design will be presented, discussing both the statistical methods behaviors and the physical results. Plasma shape parameters (minor radius and plasma elongations) share half of the net electricity power sensitivity for the DEMO 2015 design while the toroidal magnetic field and the 95 % safety factor are responsible for 23% and 17% of the electric power sensitivity, respectively. The plasma minor radius is responsible for 45% of the pulse duration sensitivity for the DEMO 2015 design, while plasma physics parameters drive ∼ 37% of the pulse duration sensitivity.
Published: 2019
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17. First Application of Ion Cyclotron Resonant Frequency Waves on WEST Plasma Scenarios

Author: L. Colas, V. Basiuk, M. Goniche, J. P. Gunn, R. J. Dumont, G. Urbanczyk, Gilles Lombard, Julien Hillairet, V. Bobkov, C. Desgranges, Patrick Mollard, B. Pégourié, J.M. Bernard, Walid Helou, F. Durodié, Clarisse Bourdelle, O. Meyer, E. Lerche, J.F. Artaud, West Team, Nicolas Fedorczak, Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), Commissariat à l'énergie atomique et aux énergies alternatives (CEA), Laboratory for Plasma Physics (LPP), Ecole Royale Militaire / Koninklijke Militaire School (ERM KMS), Max-Planck-Institut für Plasmaphysik [Garching] (IPP), The WEST Team see also: http://west.cea.fr/WESTteam, icard, valerie, and WEST Team
Subjects: Physics, Ripple, Cyclotron, Baffle, Plasma, Medium density, Power (physics), Computational physics, law.invention, Ion, Core (optical fiber), law, [PHYS.PHYS.PHYS-PLASM-PH]Physics [physics]/Physics [physics]/Plasma Physics [physics.plasm-ph], [PHYS.PHYS.PHYS-PLASM-PH] Physics [physics]/Physics [physics]/Plasma Physics [physics.plasm-ph]
Abstract: International audience; In 2018, Ion Cyclotron Resonant Frequency (ICRF) waves were for the first time applied to the WEST plasmascenarios. In ICRF-only plasmas at medium density, or on top of a low level of Lower Hybrid (LH) power, the coupledICRF power increases the plasma energy content. However in discharges with large LH power at high core density, nearlyall the applied ICRF power gets radiated, mainly in the plasma bulk. Both the energy content and conducted power decrease.Two peculiarities of WEST, that may combine, are presently invoked to explain this phenomenology:1) Fast ion ripplelosses, evidenced between TF coils on the baffle, likely degrade the ICRF heating efficiency. 2) RF-enhanced W sources,evidenced on several Plasma-Facing Components (PFCs), likely over-contaminate the high-power plasmas.
Published: 2019

18. Status of the ITER remote experimentation centre

Author: Gabriele Manduchi, E. Joffrin, Makoto Matsukawa, A. Mele, Y. Miyata, O. Naito, Kenjiro Yamanaka, Massimiliano Mattei, M. Namekawa, T. Oshima, A. Wakasa, Hirotaka Kubo, Hajime Urano, Norihiro Nakajima, V. Vitale, J.F. Artaud, S. Clement Lorenzo, M. Wheatley, Frederic Imbeaux, T. Ozeki, Filippo Sartori, P. Barbato, S. Ohira, J. Noe, Shunsuke Ide, G. De Tommasi, Y. Ishii, G. Giruzzi, J. Farthing, F. Robin, Nobuhiko Hayashi, O. Hemming, Annette M. Hynes, Hideya Nakanishi, T. Totsuka, A. Rigoni, Farthing, J., Ozeki, T., Clement Lorenzo, S., Nakajima, N., Sartori, F., De Tommasi, G., Manduchi, G., Barbato, P., Rigoni, A., Vitale, V., Giruzzi, G., Mattei, M., Mele, A., Imbeaux, F., Artaud, J. -F., Robin, F., Noe, J., Joffrin, E., Hynes, A., Hemming, O., Wheatley, M., O’Hira, S., Ide, S., Ishii, Y., Matsukawa, M., Kubo, H., Totsuka, T., Urano, H., Naito, O., Hayashi, N., Miyata, Y., Namekawa, M., Wakasa, A., Oshima, T., Nakanishi, H., Yamanaka, K., and O'Hira, S.
Subjects: IFERC, Computer science, Broadband networks, JT-60SA, BA, 7. Clean energy, 01 natural sciences, 010305 fluids & plasmas, Remote experimentation, CODAC, Data visualization, Software, ITER, 0103 physical sciences, Tape library, General Materials Science, 010306 general physics, Civil and Structural Engineering, business.industry, Nuclear Energy and Engineering, Materials Science (all), Mechanical Engineering, Fusion power, Supercomputer, Computer data storage, Data analysis, Systems engineering, business
Abstract: The ITER Remote Experimentation Centre (REC) project (one of the three sub-projects of the International Fusion Energy Research Centre (IFERC)) is progressing under the agreement between the Government of Japan and the European Atomic Energy Community for the joint implementation of the Broader Approach (BA) activities in the field of fusion energy research. The objectives of the REC activity are to identify the functions and solve the technical issues for the construction of the REC for ITER at Rokkasho, and to develop the remote experiment system and verify the functions required for remote experimentation by using the Satellite Tokamak (JT-60SA) facilities to facilitate the future exploitation of ITER and JT-60SA. The functions of REC will be tested, and the total system will be demonstrated using JT-60SA and existing facilities in the EU, such as JET and WEST. The hardware of the REC has been prepared in Rokkasho Japan, which has the remote experiment room with a large video wall to show the plasma and operation status, IT equipment and a storage system by the reuse of the Helios supercomputer tape library. A broadband network infrastructure of 10Gbps has been installed connected to SINET5. Using this network system, fast data transfer from ITER to REC was examined in 2016, and the transfer of the data volumes expected for the initial ITER experiments has been demonstrated. A secure remote experimentation system has been developed, using JT-60SA, that has functions for preparing and setting of shot parameters, viewing the status of control data, streaming of the plasma status, data-exchange function of shot events, and monitoring of the facility operation. Remote data analysis techniques, data visualisation software, a documentation management and experiment planning system and numerical simulation codes for the preparation and performance estimation of discharges have also been developed.
Published: 2018
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19. Integrated plasma scenario analysis for the HL-2M tokamak

Author: X.Q. Ji, S. Wang, M. Huang, X.L. Zou, J.F. Artaud, J.X. Li, W.Y. Huang, X. Song, M. Xue, G. Giruzzi, X.Y. Bai, L. Xue, J.H. Zhang, Xuru Duan, J. Garcia, G.Y. Zheng, G.T. Hoang, H.L. Wei, W. Pan, and X.M. Song
Subjects: Physics, Nuclear and High Energy Physics, Tokamak, law, Nuclear engineering, Plasma, Scenario analysis, Condensed Matter Physics, law.invention
Abstract: HL-2M is a new medium-sized tokamak under construction at the Southwestern Institute of Physics, dedicated to supporting the critical physics and engineering issues of ITER and CFETR. Analyzing integrated plasma scenarios is essential for assessing performance metrics and foreseeing physics as well as the envisaged experiments of HL-2M. This paper comprehensively presents the kind of expected discharge regimes (conventional inductive (baseline), hybrid and steady-state) of HL-2M based on the integrated suite of codes METIS. The simulation results show that the central electron temperature of the baseline regime can achieve more than 10 keV by injecting 27 MW of heating power with a plasma current of I p = 3 MA and Greenwald fraction f G = 0.65, with the thermal energy and β N reaching 5 MJ and 2.5, respectively. The hybrid regime with f ni = 80%–90% can be realized at I p = 1–1.4 MA with f G around 0.5, where β N is 2.3–2.5 with H 98(y ,2) = 1.1. Because of the effect of the on-axis NBCD, the hybrid steady state, at I p = 1.0 and 1.2, can be achieved more easily than the steady state regimes with reversed shear, corresponding to β N = 2.6 and 3.4. Such studies show that HL-2M is a flexible tokamak with a significant capacity for generating a broad variety of plasmas as a consequence of the different heating and current drive systems installed.
Published: 2019
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20. Modelling one-third field operation in the ITER pre-fusion power operation phase

Author: Integrated Operation Scenarios, D. Boilson, D. Van Eester, S. D. Pinches, A. M. Messiaen, Y. Gribov, S.H. Kim, F. Köchl, J.F. Artaud, M. A. Henderson, Pierre Dumortier, V.E. Lukash, B. Beaumont, P. U. Lamalle, D. Farina, K. Särkimäki, Lorenzo Figini, Antti Snicker, A. Kuyanov, A. Loarte, A. A. Kavin, Taina Kurki-Suonio, E. Lerche, R. Bilato, V.V. Parail, David Campbell, R.R. Khayrutdinov, E. Militello-ASP, A. R. Polevoi, M. Schneider, and ITPA Topical Groups on Energetic Particle Physics and Integrated Operation & Scenarios
Subjects: Physics, Nuclear and High Energy Physics, Tokamak, Field (physics), Nuclear engineering, NBI, Fusion power, Condensed Matter Physics, one-third field operation, ICRH, 7. Clean energy, 01 natural sciences, Phase (combat), ECRH, 010305 fluids & plasmas, law.invention, law, ITER, 0103 physical sciences, heating and current drive, 010306 general physics, tokamak
Abstract: In the four-stage approach of the new ITER Research Plan, the first pre-fusion power operation (PFPO) phase will only have limited power available from external heating and current drive (H&CD) systems: 20-30 MW provided by the electron cyclotron resonance heating (ECRH) system. Accessing the H-mode confinement regime at such low auxiliary power requires operating at low magnetic field, plasma current and density, i.e. 1.8 T and 5 MA for a density between 40% and 50% of the Greenwald density. II-mode plasmas at 5 MA/1.8 T will also be investigated in the second PFPO phase when ITER will have its full complement of H&CD capabilities installed, i.e. 20-30 MW of ECRH, 20 MW of ion cyclotron resonance heating and 33 MW of neutral beam injection. This paper describes the operational constraints and the II&CD capabilities for such scenarios in hydrogen and helium plasmas, to assess their viability and the issues it will be possible to address with them. The modelling results show that 5 MA/1.8 T scenarios are viable and will allow the exploration of the H-mode physics and control issues foreseen in the ITER Research Programme in the PFPO phases.
Published: 2019
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21. Multi-Inputs/Multi-Outputs control of plasma current and loop voltage on Tore Supra

Author: P. Moreau, A. Ekedahl, J.F. Artaud, Oliviero Barana, Rémy Nouailletas, F. Saint-Laurent, and S. Bremond
Subjects: Physics, Coupling, Tokamak, Mechanical Engineering, Solenoid, Tore Supra, Power (physics), law.invention, Loop (topology), Nuclear Energy and Engineering, Physics::Plasma Physics, Control theory, law, General Materials Science, Civil and Structural Engineering, Voltage
Abstract: During a tokamak discharge, several control modes may have to be run in sequence in order to perform the control of the different discharge phases. The transitions between these control modes are not always easy to handle because in most cases the coupling between the controlled plasma quantities is not taken into account in each control mode design process. This paper presents a new Multi-Inputs/Multi-Outputs (MIMO) controller applied on Tore Supra to control both plasma current and flux variations through the central solenoid voltage and the lower hybrid current drive (LHCD) system power. It deals with the transition from a loop voltage floating mode to a loop voltage control mode. The controller, synthesized and tuned using a model-based approach, has been validated in simulation before its successful implementation on Tore Supra experiments.
Published: 2013
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22. Conceptual design for the superconducting magnet system of a pulsed DEMO reactor

Author: P. Sardain, G. Giruzzi, Philippe Magaud, B. Saoutic, J.-M. Ané, J.L. Duchateau, P. Hertout, Jérôme Bucalossi, J.F. Artaud, A. Li-Puma, Frederic Imbeaux, and J. Johner
Subjects: Materials science, Tokamak, Mechanical Engineering, Nuclear engineering, Solenoid, Superconducting magnet, Fusion power, Conductor, law.invention, Magnetic field, Nuclear magnetic resonance, Nuclear Energy and Engineering, Conceptual design, law, Magnet, General Materials Science, Civil and Structural Engineering
Abstract: A methodology has been developed to consistently investigate, taking into account main reactor components, possible magnet solutions for a pulsed fusion reactor aiming at a large solenoid flux swing duration within the 2–3 h range. In a conceptual approach, investigations are carried out in the equatorial plane, taking into account the radial extension of the blanket-shielding zone, of the toroidal field magnet system inner leg and of the central solenoid for estimation of the pulsed swing. Design criteria are presented for the radial extension of the superconducting magnets, which is mostly driven by the structures (casings and conductor jacket). Typical available cable current densities are presented as a function of the magnetic field and of the temperature margin. The magnet design criteria have been integrated into SYCOMORE, a code for reactor modeling presently in development at CEA/IRFM in Cadarache, using the tools of the EFDA Integrated Tokamak Modeling task force. Possible solutions are investigated for a 2 GW fusion power reactor with different aspect ratios. The final adjustment of the DEMO pulsed reactor parameters will have to be consistently done, considering all reactor components, when the final goals of the machine will be completely clarified.
Published: 2013
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23. EU DEMO transient phases: Main constraints and heating mix studies for ramp-up and ramp-down

Author: G. Giruzzi, L. Garzotti, F. Köchl, J.F. Artaud, Ronald Wenninger, R. Ambrosino, P. Vincenzi, Tommaso Bolzonella, Massimiliano Mattei, Minh Quang Tran, Gustavo Granucci, Vincenzi, P., Ambrosino, R., Artaud, J. F., Bolzonella, T., Garzotti, L., Giruzzi, G., Granucci, G., Kochl, F., Mattei, M., Tran, M. Q., Wenninger, R., Vincenzi, P, Köchl, F., and Mattei, Massimiliano
Subjects: Tokamak, Computer science, Nuclear engineering, 01 natural sciences, 7. Clean energy, 010305 fluids & plasmas, law.invention, Heating and current drive, Materials Science(all), Physics::Plasma Physics, law, 0103 physical sciences, General Materials Science, 010306 general physics, DEMO, Civil and Structural Engineering, Radiation, Mechanical Engineering, Ramp-up, Plasma, Fusion power, Plasma control, Ramp-down, Controllability, Nuclear Energy and Engineering, 13. Climate action, Auxiliary power unit, Electromagnetic coil, ____, Physics::Accelerator Physics, Transient (oscillation), Materials Science (all), Engineering design process
Abstract: Content: EU DEMO studies for pulsed (DEMO1) and steady-state (DEMO2) concepts are currently in the pre-conceptual phase [1]. DEMO1 aims at producing about 2GW of fusion power with a burn time of approximately 2 hours. Within EUROfusion Power Plant Physics and Technology department, DEMO scenario modelling is carried out as part of the validation of feasibility and performance of DEMO designs. One of the most challenging activities deals with numerical investigations of DEMO1 transient phases including ramp-up and ramp-down, which exhibit peculiar issues with respect to existing devices. Studies on ramp-up have been carried out to highlight the effects of different ramp-up options in terms of robustness of the access to the desired flattop scenario. A heating power during ramp-up, additional to the one required during flattop, appears to be necessary for plasma burn initiation and access to H-mode, with Paux,RU50MW depending on the uncertainties on L-H transition scaling. Current ramp-rate and heating power influence also plasma position controllability, and results are presented in terms of the achieved li(3) and bp. Additional power requirements and integration of different systems which are relevant for DEMO heating mix assessment are here discussed. Ramp-down phase in DEMO poses specific issues on vertical stability given the distance of control actuators from the plasma. Ramp-down trajectories with controllable plasma boundaries have been coupled to transport studies showing the necessity of additional ramp-down heating power to avoid radiative plasma collapses. Off-axis power deposition helps plasma controllability, together with a current ramp-rate100kA/s. Plasma radiation also dominates the H-L transition, which is investigated and appears to be a critical step in terms of plasma control. DEMO performance is strongly linked to the maximum plasma elongation, which has to be assessed comparing different ramp-down trajectories. [1] G. Federici et. al, Fus. Eng. Des. 89, 882-889 (2014)
Published: 2017
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24. Physics and operation oriented activities in preparation of the JT-60SA tokamak exploitation

Author: H. Sasao, T. Bolzonella, D. C. McDonald, Lorenzo Figini, Peter Lang, A. Boboc, G. Pautasso, R. Neu, V. Vitale, J.F. Artaud, G. De Tommasi, C. Gil, A. Kojima, Akihiko Isayama, S. Saarelma, Patrick Maget, Yasunori Kawano, Y. Miyata, L. Pigatto, Carlo Sozzi, Timothy Goodman, Paolo Bettini, David Terranova, M. Romanelli, B. Pégourié, E. de la Luna, Manabu Takechi, K. Galazka, Maiko Yoshida, F. Orsitto, A. Mele, J. Garcia, J. Galdon, Ryota Imazawa, Paola Platania, S. Clement-Lorenzo, Hajime Urano, Go Matsunaga, W. Stepniewski, M. Enoeda, Hisato Kawashima, L. Garzotti, Masakatsu Fukumoto, M. Toma, Daniela Farina, Kazuo Hoshino, S. Soare, M. Scannapiego, Yutaka Kamada, S. Sakurai, Paolo Innocente, K. Shinohara, M. Dibon, H. Kubo, R. Zagórski, S. Mastrostefano, O. Asztalos, D. Ricci, K. Itami, Stefano Coda, T. Kobayashi, Gergö Pokol, Daniel Dunai, Kenji Tanaka, A. Moro, Giuseppe Marchiori, C. Gleason-González, S. Nowak, Tamás Szepesi, Chr. Day, N. Hayashi, Filippo Sartori, Ph. Lauber, Jesús Vega, D. Douai, T. Nakano, K. Shimizu, E. Barbato, Nuno Cruz, G. Giruzzi, Shunsuke Ide, M. Wischmeier, Alfredo Pironti, Fabio Villone, Shinichi Moriyama, Kensaku Kamiya, M. Garcia-Munoz, Massimiliano Mattei, E. Joffrin, J. Shiraishi, T. Suzuki, Gustavo Granucci, T. Wakatsuki, Andreas Bierwage, Y. Suzuki, Giruzzi, G., Yoshida, M., Artaud, J. F., Asztalos, Ö., Barbato, E., Bettini, P., Bierwage, A., Boboc, A., Bolzonella, T., Clement Lorenzo, S., Coda, S., Cruz, N., Day, C. h. r., DE TOMMASI, Gianmaria, Dibon, M., Douai, D., Dunai, D., Enoeda, M., Farina, D., Figini, L., Fukumoto, M., Galazka, K., Galdon, J., Garcia, J., Garcia Muñoz, M., Garzotti, L., Gil, C., Gleason Gonzalez, C., Goodman, T., Granucci, G., Hayashi, N., Hoshino, K., Ide, S., Imazawa, R., Innocente, P., Isayama, A., Itami, K., Joffrin, E., Kamada, Y., Kamiya, K., Kawano, Y., Kawashima, H., Kobayashi, T., Kojima, A., Kubo, H., Lang, P., Lauber, P. h., de la Luna, E., Maget, P., Marchiori, G., Mastrostefano, S., Matsunaga, G., Mattei, M., Mcdonald, D. C., Mele, Adriano, Miyata, Y., Moriyama, S., Moro, A., Nakano, T., Neu, R., Nowak, S., Orsitto, F. P., Pautasso, G., Pégourié, B., Pigatto, L., Pironti, Alfredo, Platania, P., Pokol, G. I., Ricci, D., Romanelli, M., Saarelma, S., Sakurai, S., Sartori, F., Sasao, H., Scannapiego, M., Shimizu, K., Shinohara, K., Shiraishi, J., Soare, S., Sozzi, C., Stępniewski, W., Suzuki, T., Suzuki, Y., Szepesi, T., Takechi, M., Tanaka, K., Terranova, D., Toma, M., Urano, H., Vega, J., Villone, F., Vitale, V., Wakatsuki, T., Wischmeier, M., Zagórski, R., Asztalos, O., Clement-Lorenzo, S., Day, Chr, De Tommasi, G., Garcia-Munoz, M., Gleason-Gonzalez, C., De La Luna, E., Mele, A., Pã©gouriã©, B., Pironti, A., Stè©pniewski, W., Zagã³rski, R., Universidad de Sevilla. Departamento de Física Atómica, Molecular y Nuclear, and Universidad de Sevilla. RNM138: Física Nuclear Aplicada
Subjects: Nuclear and High Energy Physics, Tokamak, diagnostic, JT-60SA, 01 natural sciences, Modelling, 010305 fluids & plasmas, law.invention, modelling, Research plan, law, 0103 physical sciences, diagnostics, ddc:530, 010306 general physics, Diagnostics, tokamak, Operation, Nuclear and High Energy Physic, Physics, modeling, operation, Condensed Matter Physics, Chemical physics, Systems engineering
Abstract: The JT-60SA tokamak, being built under the Broader Approach agreement jointly by Europe and Japan, is due to start operation in 2020 and is expected to give substantial contributions to both ITER and DEMO scenario optimisation. A broad set of preparation activities for an efficient start of the experiments on JT-60SA is being carried out, involving elaboration of the Research Plan, advanced modelling in various domains, feasibility and conception studies of diagnostics and other sub-systems in connection with the priorities of the scientific programme, development and validation of operation tools. The logic and coherence of this approach, as well as the most significant results of the main activities undertaken are presented and summarised. EURATOM 633053
Published: 2017
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25. Requirements and modelling of fast particle injection in RFX-mod tokamak plasmas

Author: J.F. Artaud, T. Bolzonella, P. Vincenzi, Hajime Sakakita, M. Valisa, and Matteo Vallar
Subjects: Tokamak, RFX-mod, Nuclear engineering, Particle injection, NBI, 01 natural sciences, 010305 fluids & plasmas, law.invention, law, 0103 physical sciences, General Materials Science, 010306 general physics, Civil and Structural Engineering, Physics, Mechanical Engineering, TPE-RX, Plasma, Injector, Neutral beam injection, Power (physics), Upgrade, Nuclear Energy and Engineering, METIS, RFX-mod ,NBI,Fast particles,METIS,TPE-RX, Fast particles, Beam (structure)
Abstract: The planned upgrade of the RFX-mod device is a good opportunity to widen the operational space of the machine, in both RFP and tokamak configurations. Installation of a power neutral beam injector is also envisaged and a NB system compatible with RFX-mod, formerly installed in TPE-RX, is already available on site. In this work, the METIS simulator is used to study the feasibility of TPE-RX injector integration in RFX-mod circular tokamak plasmas. METIS code allows the simulation of a full tokamak discharge, with the addition of the neutral beam injection (NBI) which, in METIS, is described by a decay equation applied in a simplified geometry and an analytical solution of the Fokker-Planck equation. In this work, RFX-mod scenarios with NBI have been studied, with careful attention to the beam absorption and plasma response to the additional heating. (C) 2017 Elsevier B.V. All rights reserved.
Published: 2017
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26. Thermal and mechanical analysis of ITER-relevant LHCD antenna elements

Author: Y.S. Bae, J. Garcia, M. Goniche, Q. Zeng, Jia Hua, L. Panaccione, R. Magne, C. Hamlyn-Harris, S.H. Kim, A. Saille, O. Tudisco, J. Belo, Gilles Berger-By, Karl Vulliez, M. Schneider, Lara Pajewski, C. Castaldo, Giuseppe Schettini, Julien Hillairet, J.F. Artaud, D. Guilhem, Riccardo Maggiora, Frederic Imbeaux, Ph. Cara, F. Kazarian, A. Ekedahl, Daniele Milanesio, J. Decker, Q.Y. Huang, P. Garibaldi, Lena Delpech, S. Meschino, Angelo A. Tuccillo, Y. Peysson, J.M. Bernard, Silvio Ceccuzzi, A. Cardinali, G. Vecchi, R. Cesario, Francesco Mirizzi, G. T. Hoang, P.K. Sharma, Won Namkung, Y. Wu, L. Marfisi, R. Villari, Y. Lausenaz, Marfisi, L., Goniche, M., Hamlyn Harris, C., Hillairet, J., Artaud, J. F., Bae, Y. S., Belo, J., Berger By, G., Bernard, J. M., Cara, Ph, Cardinali, A., Castaldo, C., Ceccuzzi, Silvio, Cesario, R., Decker, J., Delpech, L., Ekedahl, A., Garcia, J., Garibaldi, P., Guilhem, D., Hoang, G. T., Jia, H., Huang, Q. V., Imbeaux, F., Kazarian, F., Kim, S. H., Lausenaz, Y., Maggiora, R., Magne, R., Meschino, S., Milanesio, D., Mirizzi, F., Namkung, W., Pajewski, Lara, Panaccione, L., Peysson, Y., Saille, A., Schettini, Giuseppe, Schneider, M., Sharma, P. K., Tuccillo, A. A., Tudisco, O., Vecchi, G., Villari, R., Vulliez, K., Wu, Y., and Zeng, Q.
Subjects: Materials science, Nuclear Fusion, RF heating, Nuclear engineering, chemistry.chemical_element, engineering.material, Radio-Frequency Heating, Coating, ITER, Dielectric heating, Thermal, Nuclear fusion, General Materials Science, Lower hybrid, Civil and Structural Engineering, Front face, Mechanical Engineering, Plasma, Passive-active, RF windows, Line (electrical engineering), Nuclear Energy and Engineering, chemistry, engineering, Antenna (radio), Beryllium
Abstract: A 20 MW Lower Hybrid Current Drive system using an antenna based on the Passive-Active Multijunction (PAM) concept is envisaged on ITER. This paper gives an overview of the mechanical analysis, modeling and design carried out on two major elements of the antenna: the grill front face, and the RF feed-through or windows. The front face will have to withstand high heat and fast neutrons fluxes directly from the plasma. It will be actively cooled and present a beryllium coating upon ITER requirement. The RF window being a critical safety importance class component (SIC) because of its tritium confinement function, two of them will be put in series on each line to achieve a double barrier. A design of a water cooled 5 GHz CW RF “pillbox” window capable of sustaining 500 kW of transmitted power is proposed. Both studies allow to move forward, and focus on critical issues, such as manufacturing processes and R&D associated programs including tests of mock-ups.
Published: 2011
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27. Requirements specification for the Neutral Beam Injector on FAST

Author: T. Bolzonella, M. Schneider, W. Rigato, A. Cardinali, J.F. Artaud, Diego Marcuzzi, G. Calabrò, P. Mantica, F. Crisanti, M. Baruzzo, Frederic Imbeaux, Fulvio Zonca, P. Zaccaria, V. Basiuk, M. Valisa, A. Cucchiaro, M. Marinucci, Piergiorgio Sonato, and L. Lauro Taroni
Subjects: Coupling, Tokamak, Mechanical Engineering, NBI, Software requirements specification, Injector, Integrated approach, Neutral beam injection, law.invention, Nuclear Energy and Engineering, Conceptual design, Neutral beam injector, law, FAST, Systems engineering, General Materials Science, Fusion, Civil and Structural Engineering
Abstract: This paper discusses the scientific and technical requirements for a Neutral Beam Injection system on the FAST tokamak and describes a preliminary conceptual design of a suitable injector. FAST is being proposed as a European experiment in support to the operations on ITER and to the design of DEMO. The specific mission of this device is an integrated approach to a number of outstanding burning plasmas physics and operational issues with an emphasis on the impact of fast particles on turbulent transport. Such scientific requirements set a series of technical challenges regarding the injector and the coupling of the injector to the FAST main chamber that are addressed in the paper. A preliminary conceptual design of the injector is proposed which attempts to meet the stated requirements.
Published: 2011
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28. Development of a flight simulator for the control of plasma discharges

Author: P. Moreau, J.F. Artaud, N. Ravenel, Sylvain Brémond, P. Huynh, J. Signoret, and B. Guillerminet
Subjects: Functional specification, Tokamak, Computer science, Mechanical Engineering, Interface (computing), Control (management), Fusion power, Reuse, Flight simulator, law.invention, Development (topology), Nuclear Energy and Engineering, law, General Materials Science, Simulation, Civil and Structural Engineering
Abstract: The feedback control of fusion experiments in tokamak devices is entering a new area driven by the increase of control requirements for obtaining burning plasmas under safe operation conditions. A project aiming at setting up a flight simulator for the development of advanced controllers has started last year at CEA. This simulator will reuse most of the components of the European Integrated Tokamak Modelling (ITM) simulation platform. Thus, it will benefit from the development made by the task force and it will be able to offer a development platform for the new controllers of present day European tokamaks and future machines. This paper provides an overview of the architecture of the simulator. The functional specifications of the simulator have been defined and the needs in interface implementation are analysed as well.
Published: 2010
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29. Simulations of ITER H-mode scenarios using the new generation of quasi-linear models

Author: B. Baiocchi (1, P. Mantica (1, J.F. Artaud (2, V. Basiuk (2, C. Bourdelle (2, J. Citrin (2,3, J. Garcia (2, F. Imbeaux (2, F. Koechl (4,5, A. Loarte (6, and M. Schneider (2
Subjects: __
Abstract: __
Published: 2016

30. Physics and operation oriented activities in preparation of the JT-60SA tokamak exploitation

Author: Giruzzi G., M. Yoshida, J.F. Artaud, E. Barbato, P. Bettini, A. Bierwage, A. Boboc, T. Bolzonella, S. Clement-Lorenzo, S. Coda, N. Cruz, Chr. Day, G. De Tommasi, M. Dibon, D. Douai, D. Dunai, M. Enoeda, L. Figini, M. Fukumoto, K. Galazka, J. Galdon, J. Garcia, M. Garcia-Muñoz, L. Garzotti, C. Gleason-Gonzalez, T. Goodman, G. Granucci, N. Hayashi, K. Hoshino, S. Ide, P. Innocente, A. Isayama, E. Joffrin, Y. Kamada, K. Kamiya, H. Kawashima, T. Kobayashi, A. Kojima, H. Kubo, P. Lang, Ph. Lauber, E. de la Luna, P. Maget, S. Mastrostefano, G. Matsunaga, M. Mattei, D.C. McDonald, A. Mele, Y. Miyata, S. Moriyama, A. Moro, T. Nakano, R. Neu, S. Nowak, F.P. Orsitto, G. Pautasso, B. Pégourié, L. Pigatto, A. Pironti, P. Platania, D. Ricci, M. Romanelli, S. Saarelma, S. Sakurai, F. Sartori, M. Scannapiego, K. Shimizu, K. Shinohara, J. Shiraishi, S. Soare, C. Sozzi, W. Stepniewski, T. Suzuki, Y. Suzuki, T. Szepesi, M. Takechi, K. Tanaka, D. Terranova, M. Toma, H. Urano, J. Vega, F. Villone, V. Vitale, T. Wakatsuki, M. Wischmeier, and R. Zagórski
Abstract: The JT-60SA tokamak, being built under the Broader Approach agreement jointly by Europe and Japan, is due to start operation in 2019 and is expected to give substantial contributions to both ITER and DEMO scenario optimization. A broad set of preparation activities for an efficient start of the experiments on JT-60SA is being carried out, involving the elaboration of the Research Plan, advanced modelling in various domains, feasibility and conception studies of diagnostics and other sub-systems in connection with the priorities of the scientific programme, development and validation of operation tools. The logic and coherence of this approach, as well as the main activities undertaken are presented and summarized.
Published: 2016

31. Integrated plasma controls for steady state scenarios

Author: M. Goniche, A. Ekedahl, Francesca Turco, Patrick Maget, Jérôme Bucalossi, F. Clairet, L. Laborde, Sylvain Brémond, Didier Mazon, Clarisse Bourdelle, F. Kazarian, J.F. Artaud, V. Basiuk, Oliviero Barana, G. Giruzzi, Frederic Imbeaux, Y. Peysson, F.G. Rimini, Yann Corre, P. Monier-Garbet, Brigitte Pegourie, P. Moreau, R. J. Dumont, L. Colas, E. Tsitrone, F. Saint-Laurent, and E. Joffrin
Subjects: Physics, Nuclear and High Energy Physics, Steady state, Nuclear magnetic resonance, Control theory, Limiter, Magnetic confinement fusion, Solenoid, Tore Supra, Condensed Matter Physics, Actuator, Power (physics), Voltage
Abstract: In recent campaigns, Tore Supra has focused its efforts on the physics optimisation and operation of stationary scenarios with high input power (up to 8 MW), duration of more than 60 s and vanishing loop voltage (up to 80% of non-inductive current). For physics integration, Tore Supra has been equipped with a large number of new real time sensors. The control of the lower hybrid (LH) wave deposition profile width measured by the hard x-ray camera has been achieved with the parallel refractive index n|| varying from 1.7 to 2.3 and the LH-wave power using different types of control techniques. In addition, the control of the current profile with the parallel refractive index of the LH-launched spectrum has also been combined with loop voltage control using the central solenoid voltage as actuator. The effect of electron cyclotron heating as an actuator has been examined for control of temperature bifurcation phenomena such as internal transport barrier. On the basis of the experimental power flux analyses, the seven infrared cameras monitoring the five antennas and the toroidal pumped limiter have been used for implementing new power load limit avoidance control schemes which have been successfully combined with the LH-deposition profile and loop voltage control.
Published: 2007
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32. Turbulent particle transport in Tore Supra

Author: J.F. Artaud, Frederic Imbeaux, Xavier Garbet, J.-M. Travere, R. Guirlet, E. Tsitrone, C. Gil, B. Schunke, J. L. Segui, Clarisse Bourdelle, C. Fenzi-Bonizec, Jérôme Bucalossi, C.G. Lowry, F. Clairet, Brigitte Pegourie, G.T. Hoang, L.-G. Eriksson, V. Basiuk, J. Lasalle, and Laure Vermare
Subjects: Physics, Nuclear and High Energy Physics, Magnetic confinement fusion, Radius, Plasma, Electron, Tore Supra, Condensed Matter Physics, Physics::Fluid Dynamics, Physics::Plasma Physics, Pinch, Electron temperature, Plasma diagnostics, Atomic physics
Abstract: Steady state fully non-inductive current plasmas in Tore Supra offer an opportunity to study the turbulent particle pinch. The local parametric dependence of the particle pinch velocity allows us to discriminate between different theories. The existence of an anomalous pinch is unambiguously demonstrated. The results support the turbulent theories based on ion temperature gradient and trapped electron modes. An anomalous inward pinch related to the safety factor (q) profile is found to be dominant in the gradient region (normalized radius 0.3 ≤ r/a ≤ 0.6). In contrast, the direction of the anomalous pinch in the plasma core (r/a ≤ 0.3) is more sensitive to the electron temperature (Te) profile.
Published: 2006
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33. Integrated modelling of the current profile in steady-state and hybrid ITER scenarios

Author: W.A Houlberg, C Gormezano, J.F Artaud, E Barbato, V Basiuk, A Becoulet, P Bonoli, R.V Budny, L.G Eriksson, D Farina, Yu Gribov, R.W Harvey, J Hobirk, F Imbeaux, C.E Kessel, V Leonov, M Murakami, A Polevoi, E Poli, R Prater, H. St John, F Volpe, E Westerhof, A Zvonkov, ITPA Steady State Operation Topical Group, and ITPA Confinement Database and Model Group
Subjects: Nuclear and High Energy Physics, Steady state (electronics), Computer science, Nuclear engineering, Cyclotron, Iter tokamak, Magnetic confinement fusion, Condensed Matter Physics, law.invention, Nuclear magnetic resonance, ___, law, Benchmark (surveying), Enhanced Data Rates for GSM Evolution, Current (fluid), Stationary state
Abstract: We present integrated modelling of steady-state and hybrid scenarios for ITER parameters using several predictive transport codes. These employ models for non-inductive current drive sources in conjunction with various theory-based and semi-empirical transport models. In conjunction with the simulation effort, the current drive models are being evaluated in a series of cross-code and code-experiment comparisons under ITER-relevant conditions. New benchmark evaluations of current drive from injection of neutral beams (NBCD), electron cyclotron waves (ECCD) and lower hybrid waves (LHCD) are reported. Simulations using several transport modelling codes self-consistently calculate the heating and current drive sources using ITER design parameters. Operating constraints are also taken into account, although the calculations reported here still require further refinement. The modelling addresses both the final stationary state and dynamic access to it. The simulations indicate that generation and control of internal and edge barriers to access and maintain high confinement will be a major undertaking for future simulations, as well as a challenge for the ITER steady-state and hybrid experimental programme.
Published: 2005
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34. Simulations of steady-state scenarios for Tore Supra using the CRONOS code

Author: X. Litaudon, J.F. Artaud, G. T. A. Huysmans, Y. Peysson, Frederic Imbeaux, D. Moreau, V. Basiuk, G.T. Hoang, L.-G. Eriksson, Didier Mazon, and A. Bécoulet
Subjects: Physics, Nuclear and High Energy Physics, Steady state, Nuclear engineering, Magnetic confinement fusion, Plasma, Tore Supra, Condensed Matter Physics, Bootstrap current, Power (physics), Nuclear physics, Ion cyclotron resonance heating, Physics::Plasma Physics, Current (fluid)
Abstract: Scenarios of steady-state, fully non-inductive current in Tore Supra are predicted using a package of simulation codes (CRONOS). The plasma equilibrium and transport are consistently calculated with the deposition of power. The achievement of high injected energy discharges up to 1 GJ is shown. Two main scenarios are considered: a low density regime with 90% non-inductive current driven by lower hybrid waves-lower hybrid current drive (LHCD)-and a high density regime combining LHCD and ion cyclotron resonance heating with a bootstrap current fraction up to 25%. The predictive simulations of existing discharges are also reported.
Published: 2003
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35. A rapid fast ion Fokker–Planck solver for integrated modelling of tokamaks

Author: R. Futtersack, J.F. Artaud, Thomas Johnson, L.-G. Eriksson, B. Wolle, R. J. Dumont, M. Schneider, and Itm-Tf Contributors
Subjects: Physics, Nuclear and High Energy Physics, Tokamak, Context (language use), Eigenfunction, Solver, Condensed Matter Physics, 01 natural sciences, 010305 fluids & plasmas, Computational physics, law.invention, Distribution function, Physics::Plasma Physics, law, 0103 physical sciences, Orbit (dynamics), Fokker–Planck equation, Atomic physics, 010306 general physics, Beam (structure)
Abstract: The RISK (rapid ion solver for tokamaks) code for simulating the evolution of the distribution function of neutral beam injected ions (NBI) in tokamak plasmas is described. The code has been especially developed for use in integrated modelling frameworks. Within this context, a code needs to be modular, machine independent and fast. RISK fulfils all these conditions. The RISK code solves the bounce averaged Fokker–Planck equation for the species of the injected ions by expanding the distribution function in the eigenfunctions of the collisional pitch angle scattering operator. The velocity dependent coefficient functions are calculated with a finite element solver. Finite orbit width effects are handled by an ad hoc broadening algorithm of the NBI ionization source. In order to assess the validity of the approximations employed in RISK, a comparison with a full orbit following Monte Carlo code is presented. RISK is integrated into the CRONOS transport suite of codes (Artaud et al 2010 Nucl. Fusion 50 043001) and the European integrated modelling (EU-IM) framework (Falchetto et al 2014 Nucl. Fusion 54 043018). The RISK implementation in this platform is discussed and exemplified to show the strength of running simulation codes in a modular and machine independent environment for simulation of fusion plasmas.
Published: 2015
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36. Investigations of LHCD induced plasma rotation in Tore Supra

Author: J. Decker, B. Baiocchi, Clarisse Bourdelle, B. Chouli, M. Irishkin, C. Fenzi, M. Schneider, T. Aniel, J. E. Rice, P. Cottier, J.F. Artaud, Frederic Imbeaux, Didier Mazon, Yanick Sarazin, V. Basiuk, and Xavier Garbet
Subjects: Physics, Toroid, Reynolds number, Reynolds stress, Plasma, Tore Supra, Condensed Matter Physics, Rotation, Momentum, symbols.namesake, Nuclear Energy and Engineering, Physics::Plasma Physics, symbols, Diamagnetism, Atomic physics
Abstract: Theoretical investigations are performed in order to explain the plasma rotation increments induced by lower hybrid current drive (LHCD) in Tore Supra and the results are compared to the experimental observations. The intrinsic toroidal rotation is governed by several mechanisms in concert. The impact of the LHCD on each involved mechanism is analyzed. The neoclassical toroidal rotation is always in the counter-current direction. The toroidal diamagnetic velocity is of the order of the experimental toroidal velocity. At high plasma current the rotation evolution in the lower hybrid (LH) phase is controlled by the neoclassical friction force due to the trapped ions in banana trajectories through the toroidal diamagnetic velocity. This force results in the counter-current increment as observed in the experimental measurement of toroidal rotation. At low plasma current the rotation is dominated by momentum turbulent transport when the LH waves are applied. The Reynolds stress grows strongly compared to the high plasma current case and acts as a co-current force through its residual stress contribution. Momentum transport simulations are also performed with CRONOS (Artaud et al 2010) in order to assess the rotation increments induced by LHCD.
Published: 2015
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37. WEST Physics Basis

Author: Marc Missirlian, Pascale Hennequin, M. Yoshida, T. Loarer, A. Ekedahl, J. Decker, Patrick Maget, M. Firdaouss, Sylvain Brémond, Irena Ivanova-Stanik, E. Tsitrone, C. Grisolia, Lena Delpech, Marina Becoulet, C. Gil, X. Courtois, A. Kallenbach, Philippe Ghendrih, R. Zagórski, L. Colas, C. Fenzi, J.F. Artaud, T. Hoang, Roland Sabot, Guido Ciraolo, James Paul Gunn, Julien Hillairet, Frederic Imbeaux, P. Lotte, G. Giruzzi, P. Devynck, J. Garcia, P. Moreau, Patrick Mollard, Laure Vermare, M. Goniche, O. Meyer, Eric Nardon, Jérôme Bucalossi, B. Pégourié, R. J. Dumont, M. Schneider, P. Monier-Garbet, D. Douai, S. Vartanian, Yannick Marandet, Jochen Linke, Y. Peysson, Jet Contributors, J.-M. Travere, Clarisse Bourdelle, D. Guilhem, Hugo Bufferand, V. Basiuk, Yann Corre, R.P. Doerner, Guilhem Dif-Pradalier, F. Saint-Laurent, M.-L. Mayoral, Nicolas Fedorczak, A. Grosman, R. Guirlet, E. Joffrin, Universidad de Sevilla. Departamento de Física Atómica, Molecular y Nuclear, Laboratoire de Physique des Plasmas (LPP), Université Paris-Sud - Paris 11 (UP11)-Université Pierre et Marie Curie - Paris 6 (UPMC)-Observatoire de Paris, Université Paris sciences et lettres (PSL)-Université Paris sciences et lettres (PSL)-École polytechnique (X)-Université Paris-Saclay-Centre National de la Recherche Scientifique (CNRS), Université Paris sciences et lettres (PSL)-Université Paris sciences et lettres (PSL)-École polytechnique (X)-Sorbonne Université (SU)-Université Paris-Saclay-Centre National de la Recherche Scientifique (CNRS), IRFM-CEA, École Polytechnique Fedérale de Lausanne, VTT Technical Research Centre of Finland, Department of Applied Physics, Princeton University, Culham Science Centre, Uppsala University, European Commission, Chinese Academy of Sciences, National Fusion Research Institute, ITER, Universidad Politécnica de Madrid, School services,SCI, Sorbonne Université, Institute for Plasma Research, Universidade de Lisboa, Research Center Julich, University of Electronic Science and Technology of China, Aalto-yliopisto, Aalto University, and JET Contributors
Subjects: Nuclear and High Energy Physics, Long pulse, Tokamak, Nuclear engineering, TOKAMAKS, POWER, Tore Supra, PROFILE, 7. Clean energy, law.invention, Plasma physics, Pedestal, Divertor, law, [PHYS.PHYS.PHYS-PLASM-PH]Physics [physics]/Physics [physics]/Plasma Physics [physics.plasm-ph], divertor, User Facility, ddc:530, tokamak, LOSSES, Plasma facing components, Physics, TUNGSTEN, plasma physics, EXTRAPOLATION, Plasma, Condensed Matter Physics, plasma facing components, DENSITY PEAKING, TRANSPORT, Heat flux, BEHAVIOR
Abstract: International audience; With WEST (Tungsten Environment in Steady State Tokamak) (Bucalossi et al 2014 Fusion Eng. Des. 89 [http://dx.doi.org/10.1016/j.fusengdes.2014.01.062] 907?12 ), the Tore Supra facility and team expertise (Dumont et al 2014 Plasma Phys. Control. Fusion 56 [http://dx.doi.org/10.1088/0741-3335/56/7/075020] 075020 ) is used to pave the way towards ITER divertor procurement and operation. It consists in implementing a divertor configuration and installing ITER-like actively cooled tungsten monoblocks in the Tore Supra tokamak, taking full benefit of its unique long-pulse capability. WEST is a user facility platform, open to all ITER partners. This paper describes the physics basis of WEST: the estimated heat flux on the divertor target, the planned heating schemes, the expected behaviour of the L?H threshold and of the pedestal and the potential W sources. A series of operating scenarios has been modelled, showing that ITER-relevant heat fluxes on the divertor can be achieved in WEST long pulse H-mode plasmas.
Published: 2015
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38. MHD stability of lower hybrid enhanced performance discharges on the Tore Supra tokamak

Author: Yves Peysson, G. T. A. Huysmans, M. Zabiego, J.F. Artaud, Frederic Imbeaux, and X. Litaudon
Subjects: Physics, Tokamak, Cyclotron, Electron, Tore Supra, Condensed Matter Physics, law.invention, Computational physics, Shear (sheet metal), Nuclear Energy and Engineering, law, Tearing, Electron temperature, Atomic physics, Magnetohydrodynamics
Abstract: Lower hybrid enhanced performance (LHEP) discharges have been successfully operated on Tore Supra, with a significant improvement in electron core-confinement and remarkable steady-state features. However, recent attempts to operate such discharges with better confinement performance were hindered by the systematic onset of large MHD activity, preventing any good performance recovery. The associated MHD limit is found to result from reaching the tearing mode limit as the current profile is driven from centrally peaked towards off-axis peaked by the lower hybrid (LH) wave. The specific feature of the considered discharges is that they achieve a weak magnetic shear over a broader core region than past LHEP discharges, then leading to systematic fast MHD onset (m/n = 2/1 tearing mode) when qmin approaches 2. The present paper reports on experimental observations and modelling which support this finding and analyses the perspectives of improving the LHEP scenario by combining the current profile control through the LH wave with a significant increase in pressure through ion cyclotron wave coupling.
Published: 2001
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39. EFD-P(13)01 Numerical Analysis of JET Discharges with the European Transport Simulator

Author: D. Kalupin, I. Ivanova-Stanik, I. Voitsekhovitch, J. Ferreira, D. Coster, L.L. Alves, Th. Aniel, J.F Artaud, V. Basiuk, J.P.S. Bizarro, R. Coelho, A. Czarnecka, Ph. Huynh, A. Figueiredo, J. Garcia, L. Garzotti, F. Imbeaux, F. Köchl, M.F. Nave, G. Pereverzev, O. Sauter, B.D. Scott, R. Stankiewicz, P. Str, ITM-TF contributors, and JET EFDA contributors
Abstract: D. Kalupin, I. Ivanova-Stanik, I. Voitsekhovitch, J. Ferreira, D. Coster, L.L. Alves, Th. Aniel, J.F Artaud, V. Basiuk, J.P.S. Bizarro, R. Coelho, A. Czarnecka, Ph. Huynh, A. Figueiredo, J. Garcia, L. Garzotti, F. Imbeaux, F. Köchl, M.F. Nave, G. Pereverzev, O. Sauter, B.D. Scott, R. Stankiewicz, P. Strand, ITM-TF contributors and JET EFDA contributors The "European Transport Simulator" (ETS) is the new modular package for 1-D discharge evolution developed within the EFDA Integrated Tokamak Modelling (ITM) Task Force. It consists of precompiled physics modules combined into a workflow through standardized input/ output data-structures. Ultimately, the ETS will allow for an entire discharge simulation from the start up until the current termination phase, including controllers and sub-systems. The paper presents the current status of the ETS towards this ultimate goal. It discusses the design of the workflow, and presents the first physics applications of the ETS for the analysis of JET tokamak discharges.
Published: 2013
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40. Numerical analysis of JET discharges with the European Transport Simulator

Author: Olivier Sauter, F. Köchl, Irena Ivanova-Stanik, Jorge Ferreira, Itm-Tf Contributors, Bruce D. Scott, Luís L Alves, R. Stankiewicz, L. Garzotti, A. Czarnecka, J.F. Artaud, A. Figueiredo, Ph. Huynh, Pär Strand, Jet-Efda Contributors, João P. S. Bizarro, Frederic Imbeaux, V. Basiuk, R. Coelho, T. Aniel, I. Voitsekhovitch, Denis Kalupin, G. V. Pereverzev, D. P. Coster, M. F. F. Nave, J. Garcia, ITM-TF Contributors, and JET-EFDA Contributors
Subjects: Coupling, Nuclear and High Energy Physics, Jet (fluid), Tokamak, business.industry, Numerical analysis, Solver, Modular design, Condensed Matter Physics, Data structure, law.invention, Workflow, law, business, Simulation
Abstract: The 'European Transport Simulator' (ETS) (Coster et al 2010 IEEE Trans. Plasma Sci. 38 2085-92, Kalupin et al 2011 Proc. 38th EPS Conf. on Plasma Physics (Strasbourg, France, 2011) vol 35G (ECA) P. 4.111) is the new modular package for 1D discharge evolution developed within the EFDA Integrated Tokamak Modelling (ITM) Task Force. It consists of precompiled physics modules combined into a workflow through standardized input/output data structures. Ultimately, the ETS will allow for an entire discharge simulation from the start up until the current termination phase, including controllers and sub-systems. The paper presents the current status of the ETS towards this ultimate goal. It discusses the design of the workflow, the validation and verification of its components on the example of impurity solver and demonstrates a proof-of-principles coupling of a local gyrofluid model for turbulent transport to the ETS. It also presents the first results on the application of the ETS to JET tokamak discharges with the ITER like wall. It studies the correlations of the radiation from impurity to the choice of the sources and transport coefficients.
Published: 2013

41. RF modeling of the ITER-relevant lower hybrid antenna

Author: S.H. Kim, O. Tudisco, Gilles Berger-By, Pankaj Sharma, R. Magne, Daniele Milanesio, Won Namkung, Y. Wu, Y. Lausenaz, A. A. Tuccillo, L. Marfisi, Giuseppe Schettini, J. Belo, R. Villari, C. Castaldo, Julien Hillairet, L. Panaccione, G. T. Hoang, J.F. Artaud, M. Schneider, A. Cardinali, Ph. Cara, G. Vecchi, Frederic Imbeaux, P. Garibaldi, Riccardo Maggiora, J. Garcia, M. Goniche, Q.Y. Huang, Y.S. Bae, Y. Peysson, Jia Hua, J. Decker, Karl Vulliez, A. Ekedahl, Silvio Ceccuzzi, J.M. Bernard, Lara Pajewski, R. Cesario, S. Meschino, Lena Delpech, D. Guilhem, F. Kazarian, Francesco Mirizzi, Q. Zeng, A. Saille, Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), Commissariat à l'énergie atomique et aux énergies alternatives (CEA), Italian National agency for new technologies, Energy and sustainable economic development [Frascati] (ENEA), Associacao Euratom-IST, Universidade Tecnica de Lisboa, National Fusion Research Institute (NFRI), Institute of Plasma Physics, Chinese Academy of Sciences (ASIPP), Politecnico di Torino = Polytechnic of Turin (Polito), Department of Physics, Pohang University of Science and Technology, Università degli Studi di Roma 'La Sapienza' = Sapienza University [Rome], European Project: 25887,EFDA, Università degli Studi di Roma 'La Sapienza' = Sapienza University [Rome] (UNIROMA), Hillairet, J., Ceccuzzi, Silvio, Belo, J., Marfisi, L., Artaud, J. F., Bae, Y. S., Berger By, G., Bernard, J. M., Cara, Ph, Cardinali, A., Castaldo, C., Cesario, R., Decker, J., Delpech, L., Ekedahl, A., Garcia, J., Garibaldi, P., Goniche, M., Guilhem, D., Hoang, G. T., Jia, H., Huang, Q. Y., Imbeaux, F., Kazarian, F., Kim, S. H., Lausenaz, Y., Maggiora, R., Magne, R., Meschino, S., Milanesio, D., Mirizzi, F., Namkung, W., Pajewski, Lara, Panaccione, L., Peysson, Y., Saille, A., Schettini, Giuseppe, Schneider, M., Sharma, P. K., Tuccillo, A. A., Tudisco, O., Vecchi, G., Villari, R., Vulliez, K., Wu, Y., and Zeng, Q.
Subjects: Lower hybrid, Current Drive, LHCD, PAM, ITER, Nuclear Fusion, Computer science, Wave propagation, Mechanical Engineering, Nuclear engineering, Frame (networking), [SPI.PLASMA]Engineering Sciences [physics]/Plasmas, 01 natural sciences, 010305 fluids & plasmas, [SPI.ELEC]Engineering Sciences [physics]/Electromagnetism, Nuclear Energy and Engineering, [PHYS.PHYS.PHYS-PLASM-PH]Physics [physics]/Physics [physics]/Plasma Physics [physics.plasm-ph], Hybrid system, 0103 physical sciences, General Materials Science, Lower Hybrid, Antenna (radio), 010306 general physics, High heat, Civil and Structural Engineering
Abstract: "In the frame of the EFDA task HCD-08-03-01, a 5 GHz Lower Hybrid system which should be able to deliver 20 MW CW on ITER and sustain the expected high heat fluxes has been reviewed. The design and overall dimensions of the key RF elements of the launcher and its subsystem has been updated from the 2001 design in collaboration with ITER organization. Modeling of the LH wave propagation and absorption into the plasma shows that the optimal parallel index must be chosen between 1.9 and 2.0 for the ITER steady-state scenario. The present study has been made with n|| = 2.0 but can be adapted for n|| = 1.9. Individual components have been studied separately giving confidence on the global RF design of the whole antenna. © 2011 Elsevier B.V. All Rights Reserved."
Published: 2011
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42. Contribution of Tore Supra in preparation of ITER

Author: B. Saoutic, J. Abiteboul, L. Allegretti, S. Allfrey, J.M. Ané, T. Aniel, A. Argouarch, J.F. Artaud, M.H. Aumenier, S. Balme, V. Basiuk, O. Baulaigue, P. Bayetti, A. Bécoulet, M. Bécoulet, M.S. Benkadda, F. Benoit, G. Berger-by, J.M. Bernard, B. Bertrand, P. Beyer, A. Bigand, J. Blum, D. Boilson, G. Bonhomme, H. Bottollier-Curtet, C. Bouchand, F. Bouquey, C. Bourdelle, S. Bourmaud, C. Brault, S. Brémond, C. Brosset, J. Bucalossi, Y. Buravand, P. Cara, V. Catherine-Dumont, A. Casati, M. Chantant, M. Chatelier, G. Chevet, D. Ciazynski, G. Ciraolo, F. Clairet, M. Coatanea-Gouachet, L. Colas, L. Commin, E. Corbel, Y. Corre, X. Courtois, R. Dachicourt, M. Dapena Febrer, M. Davi Joanny, R. Daviot, H. De Esch, J. Decker, P. Decool, P. Delaporte, E. Delchambre, E. Delmas, L. Delpech, C. Desgranges, P. Devynck, T. Dittmar, L. Doceul, D. Douai, H. Dougnac, J.L. Duchateau, B. Dugué, N. Dumas, R. Dumont, A. Durocher, F.X. Duthoit, A. Ekedahl, D. Elbeze, M. El Khaldi, F. Escourbiac, F. Faisse, G. Falchetto, M. Farge, J.L. Farjon, M. Faury, N. Fedorczak, C. Fenzi-Bonizec, M. Firdaouss, Y. Frauel, X. Garbet, J. Garcia, J.L. Gardarein, L. Gargiulo, P. Garibaldi, E. Gauthier, O. Gaye, A. Géraud, M. Geynet, P. Ghendrih, I. Giacalone, S. Gibert, C. Gil, G. Giruzzi, M. Goniche, V. Grandgirard, C. Grisolia, G. Gros, A. Grosman, R. Guigon, D. Guilhem, B. Guillerminet, R. Guirlet, J. Gunn, O. Gurcan, S. Hacquin, J.C. Hatchressian, P. Hennequin, C. Hernandez, P. Hertout, S. Heuraux, J. Hillairet, G.T. Hoang, C. Honore, M. Houry, T. Hutter, P. Huynh, G. Huysmans, F. Imbeaux, E. Joffrin, J. Johner, L. Jourd'Heuil, Y.S. Katharria, D. Keller, S.H. Kim, M. Kocan, M. Kubic, B. Lacroix, V. Lamaison, G. Latu, Y. Lausenaz, C. Laviron, F. Leroux, L. Letellier, M. Lipa, X. Litaudon, T. Loarer, P. Lotte, S. Madeleine, P. Magaud, P. Maget, R. Magne, L. Manenc, Y. Marandet, G. Marbach, J.L. Maréchal, L. Marfisi, C. Martin, G. Martin, V. Martin, A. Martinez, J.P. Martins, R. Masset, D. Mazon, N. Mellet, L. Mercadier, A. Merle, D. Meshcheriakov, O. Meyer, L. Million, M. Missirlian, P. Mollard, V. Moncada, P. Monier-Garbet, D. Moreau, P. Moreau, L. Morini, M. Nannini, M. Naiim Habib, E. Nardon, H. Nehme, C. Nguyen, S. Nicollet, R. Nouilletas, T. Ohsako, M. Ottaviani, S. Pamela, H. Parrat, P. Pastor, A.L. Pecquet, B. Pégourié, Y. Peysson, I. Porchy, C. Portafaix, M. Preynas, M. Prou, J.M. Raharijaona, N. Ravenel, C. Reux, P. Reynaud, M. Richou, H. Roche, P. Roubin, R. Sabot, F. Saint-Laurent, S. Salasca, F. Samaille, A. Santagiustina, Y. Sarazin, A. Semerok, J. Schlosser, M. Schneider, M. Schubert, F. Schwander, J.L. Ségui, G. Selig, P. Sharma, J. Signoret, A. Simonin, S. Song, E. Sonnendruker, F. Sourbier, P. Spuig, P. Tamain, M. Tena, J.M. Theis, D. Thouvenin, A. Torre, J.M. Travère, E. Tsitrone, J.C. Vallet, E. Van Der Plas, A. Vatry, J.M. Verger, L. Vermare, F. Villecroze, D. Villegas, R. Volpe, K. Vulliez, J. Wagrez, T. Wauters, L. Zani, D. Zarzoso, X.L. Zou, Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), Commissariat à l'énergie atomique et aux énergies alternatives (CEA), Science et Ingénierie des Matériaux et Procédés (SIMaP), Université Joseph Fourier - Grenoble 1 (UJF)-Institut polytechnique de Grenoble - Grenoble Institute of Technology (Grenoble INP )-Institut National Polytechnique de Grenoble (INPG)-Centre National de la Recherche Scientifique (CNRS), Dept. Accelerateurs - XFEL, Laboratoire de l'Accélérateur Linéaire (LAL), Centre National de la Recherche Scientifique (CNRS)-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Université Paris-Sud - Paris 11 (UP11)-Centre National de la Recherche Scientifique (CNRS)-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Université Paris-Sud - Paris 11 (UP11), Laboratoire de Météorologie Dynamique (UMR 8539) (LMD), Département des Géosciences - ENS Paris, École normale supérieure - Paris (ENS Paris), Université Paris sciences et lettres (PSL)-Université Paris sciences et lettres (PSL)-École normale supérieure - Paris (ENS Paris), Université Paris sciences et lettres (PSL)-Université Paris sciences et lettres (PSL)-Centre National de la Recherche Scientifique (CNRS)-École des Ponts ParisTech (ENPC)-École polytechnique (X)-Institut national des sciences de l'Univers (INSU - CNRS)-Université Pierre et Marie Curie - Paris 6 (UPMC), Franche-Comté Électronique Mécanique, Thermique et Optique - Sciences et Technologies (UMR 6174) (FEMTO-ST), Université de Technologie de Belfort-Montbeliard (UTBM)-Ecole Nationale Supérieure de Mécanique et des Microtechniques (ENSMM)-Université de Franche-Comté (UFC), Université Bourgogne Franche-Comté [COMUE] (UBFC)-Université Bourgogne Franche-Comté [COMUE] (UBFC)-Centre National de la Recherche Scientifique (CNRS), Institut universitaire des systèmes thermiques industriels (IUSTI), Centre National de la Recherche Scientifique (CNRS)-Aix Marseille Université (AMU), Matériaux et Mécanique des Composants (EDF R&D MMC), EDF R&D (EDF R&D), EDF (EDF)-EDF (EDF), Association EURATOM-CEA (CEA/DSM/DRFC), Département de Recherche sur la Fusion Contrôlée (DRFC), Laboratoire d'Interaction Laser Matière (LILM), Département de Physico-Chimie (DPC), CEA-Direction des Energies (ex-Direction de l'Energie Nucléaire) (CEA-DES (ex-DEN)), Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Université Paris-Saclay-CEA-Direction des Energies (ex-Direction de l'Energie Nucléaire) (CEA-DES (ex-DEN)), Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Université Paris-Saclay, Laboratoire de Physique des Plasmas (LPP), Université Paris-Sud - Paris 11 (UP11)-Université Pierre et Marie Curie - Paris 6 (UPMC)-Observatoire de Paris, Université Paris sciences et lettres (PSL)-Université Paris sciences et lettres (PSL)-École polytechnique (X)-Sorbonne Université-Université Paris-Saclay-Centre National de la Recherche Scientifique (CNRS), Institut Jean Lamour (IJL), Université de Lorraine (UL)-Centre National de la Recherche Scientifique (CNRS), Département de Physique Nucléaire (ex SPhN) (DPHN), Institut de Recherches sur les lois Fondamentales de l'Univers (IRFU), Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Université Paris-Saclay-Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Université Paris-Saclay, Ngee Ann Polytechnic, School of Engineering, Mechanical Engineering Division, ITER organization (ITER), CEA Cadarache, Centre de Thermique de Lyon (CETHIL), Université Claude Bernard Lyon 1 (UCBL), Université de Lyon-Université de Lyon-Institut National des Sciences Appliquées de Lyon (INSA Lyon), Université de Lyon-Institut National des Sciences Appliquées (INSA)-Institut National des Sciences Appliquées (INSA)-Centre National de la Recherche Scientifique (CNRS), CEA ISIS, Commissariat à l'énergie atomique et aux énergies alternatives - Laboratoire d'Electronique et de Technologie de l'Information (CEA-LETI), Direction de Recherche Technologique (CEA) (DRT (CEA)), Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Commissariat à l'énergie atomique et aux énergies alternatives (CEA), Institut de Chimie de Clermont-Ferrand (ICCF), Université Blaise Pascal - Clermont-Ferrand 2 (UBP)-SIGMA Clermont (SIGMA Clermont)-Centre National de la Recherche Scientifique (CNRS), Institut de Recherche en Sciences et Techniques de la Ville - FR 2488 (IRSTV), Université de Nantes (UN)-École Centrale de Nantes (ECN)-EC. ARCHIT. NANTES-Université d'Angers (UA)-Université de La Rochelle (ULR)-Centre National de la Recherche Scientifique (CNRS), Eau et Environnement (IFSTTAR/GERS/EE), Institut Français des Sciences et Technologies des Transports, de l'Aménagement et des Réseaux (IFSTTAR)-PRES Université Nantes Angers Le Mans (UNAM), Physique des interactions ioniques et moléculaires (PIIM), Aix Marseille Université (AMU)-Centre National de la Recherche Scientifique (CNRS), Laboratoire d'Intégration des Systèmes et des Technologies (LIST), Institut des Sciences de l'Evolution de Montpellier (UMR ISEM), Centre de Coopération Internationale en Recherche Agronomique pour le Développement (Cirad)-École pratique des hautes études (EPHE), Université Paris sciences et lettres (PSL)-Université Paris sciences et lettres (PSL)-Université de Montpellier (UM)-Institut de recherche pour le développement [IRD] : UR226-Centre National de la Recherche Scientifique (CNRS), Centre of Molecular and Structural Biomedicine (CBME)/Institute of Biotechnology and Bioengineering (IBB), University of Algarve [Portugal], Laboratoire Lasers, Plasmas et Procédés photoniques (LP3), Centre d'Histoire 'Espaces et Cultures' (CHEC), Université Blaise Pascal - Clermont-Ferrand 2 (UBP), École des hautes études en sciences sociales (EHESS), Centre hospitalier universitaire de Nantes (CHU Nantes), Centre de Recherche en Cancérologie Nantes-Angers (CRCNA), Centre Hospitalier Universitaire d'Angers (CHU Angers), PRES Université Nantes Angers Le Mans (UNAM)-PRES Université Nantes Angers Le Mans (UNAM)-Hôtel-Dieu de Nantes-Institut National de la Santé et de la Recherche Médicale (INSERM)-Hôpital Laennec-Centre National de la Recherche Scientifique (CNRS)-Faculté de Médecine d'Angers-Centre hospitalier universitaire de Nantes (CHU Nantes), Centre d'investigation clinique en cancérologie (CI2C), IFP Energies nouvelles (IFPEN), Matériaux, ingénierie et science [Villeurbanne] (MATEIS), Ecologie Systématique et Evolution (ESE), Centre National de la Recherche Scientifique (CNRS)-AgroParisTech-Université Paris-Sud - Paris 11 (UP11), Laboratoire d'Etude des Matériaux en Milieux Agressifs (LEMMA), Université de La Rochelle (ULR), CMCR des Massues, Croix rouge française, Laboratoire Procédés et Ingénierie en Mécanique et Matériaux (PIMM), Conservatoire National des Arts et Métiers [CNAM] (CNAM)-Arts et Métiers Sciences et Technologies, HESAM Université (HESAM)-HESAM Université (HESAM), Laboratoire de Mécanique, Modélisation et Procédés Propres (M2P2), Aix Marseille Université (AMU)-École Centrale de Marseille (ECM)-Centre National de la Recherche Scientifique (CNRS), Réserve Naturelle Nationale Baie St-Brieuc, Réserves Naturelles de France-Réserves Naturelles de France, Géoazur (GEOAZUR 6526), Observatoire de la Côte d'Azur, Université Côte d'Azur (UCA)-COMUE Université Côte d'Azur (2015 - 2019) (COMUE UCA)-Université Côte d'Azur (UCA)-COMUE Université Côte d'Azur (2015 - 2019) (COMUE UCA)-Institut national des sciences de l'Univers (INSU - CNRS)-Université Nice Sophia Antipolis (... - 2019) (UNS), COMUE Université Côte d'Azur (2015 - 2019) (COMUE UCA)-Université Pierre et Marie Curie - Paris 6 (UPMC)-Institut de Recherche pour le Développement (IRD)-Centre National de la Recherche Scientifique (CNRS), Direction des Jardins botaniques et zoologiques, Muséum national d'Histoire naturelle (MNHN), Department of Information Technology (INTEC), Ghent University [Belgium] (UGENT), Dipartimento di Ingegneria dell'Ambiente e per lo Sviluppo Sostenibile (DIASS), Dipartimento Ingn Ambiente & Sviluppo Soste, Institut Charles Gerhardt Montpellier - Institut de Chimie Moléculaire et des Matériaux de Montpellier (ICGM ICMMM), Ecole Nationale Supérieure de Chimie de Montpellier (ENSCM)-Centre National de la Recherche Scientifique (CNRS)-Université de Montpellier (UM)-Université Montpellier 1 (UM1)-Université Montpellier 2 - Sciences et Techniques (UM2), Equipe Dynamique des Systemes Complexes, Université de Provence - Aix-Marseille 1, Technische Universität Braunschweig [Braunschweig], Laboratoire de physique des milieux ionisés et applications (LPMIA), Université Henri Poincaré - Nancy 1 (UHP)-Centre National de la Recherche Scientifique (CNRS), Centre de Recherche en Cancérologie de Lyon (UNICANCER/CRCL), Institut National de la Santé et de la Recherche Médicale (INSERM)-Centre National de la Recherche Scientifique (CNRS)-Université Claude Bernard Lyon 1 (UCBL), Université de Lyon-Université de Lyon-Centre Léon Bérard [Lyon], Bureau de Recherches Géologiques et Minières (BRGM) (BRGM), Service de Chimie Physique (SCP), Laboratoire des Adaptations Physiologiques aux Activités Physiques (LAPHAP), Université de Poitiers, Institut d'Electronique du Solide et des Systèmes ( InESS ), Centre National de la Recherche Scientifique ( CNRS ), Institut de Recherche sur la Fusion par confinement Magnétique ( IRFM ), Commissariat à l'énergie atomique et aux énergies alternatives ( CEA ), Science et Ingénierie des Matériaux et Procédés ( SIMaP ), Université Joseph Fourier - Grenoble 1 ( UJF ) -Institut polytechnique de Grenoble - Grenoble Institute of Technology ( Grenoble INP ) -Institut National Polytechnique de Grenoble ( INPG ) -Centre National de la Recherche Scientifique ( CNRS ) -Université Grenoble Alpes ( UGA ), Laboratoire de l'Accélérateur Linéaire ( LAL ), Université Paris-Sud - Paris 11 ( UP11 ) -Institut National de Physique Nucléaire et de Physique des Particules du CNRS ( IN2P3 ) -Centre National de la Recherche Scientifique ( CNRS ) -Université Paris-Sud - Paris 11 ( UP11 ) -Institut National de Physique Nucléaire et de Physique des Particules du CNRS ( IN2P3 ) -Centre National de la Recherche Scientifique ( CNRS ), Laboratoire de Météorologie Dynamique (UMR 8539) ( LMD ), Université Pierre et Marie Curie - Paris 6 ( UPMC ) -Institut national des sciences de l'Univers ( INSU - CNRS ) -École polytechnique ( X ) -École des Ponts ParisTech ( ENPC ) -Centre National de la Recherche Scientifique ( CNRS ) -Département des Géosciences - ENS Paris, École normale supérieure - Paris ( ENS Paris ) -École normale supérieure - Paris ( ENS Paris ), Franche-Comté Électronique Mécanique, Thermique et Optique - Sciences et Technologies ( FEMTO-ST ), Université de Technologie de Belfort-Montbeliard ( UTBM ) -Ecole Nationale Supérieure de Mécanique et des Microtechniques ( ENSMM ) -Centre National de la Recherche Scientifique ( CNRS ) -Université de Franche-Comté ( UFC ), Institut universitaire des systèmes thermiques industriels ( IUSTI ), Centre National de la Recherche Scientifique ( CNRS ) -Aix Marseille Université ( AMU ), EDF - R&D Department MMC and MAI, EDF R&D ( EDF R&D ), EDF ( EDF ) -EDF ( EDF ), Association EURATOM-CEA ( CEA/DSM/DRFC ), Département de Recherche sur la Fusion Contrôlée ( DRFC ), Laboratoire d'Interaction Laser Matière ( LILM ), Département de Physico-Chimie ( DPC ), Université Paris-Saclay-Commissariat à l'énergie atomique et aux énergies alternatives ( CEA ) -Université Paris-Saclay-Commissariat à l'énergie atomique et aux énergies alternatives ( CEA ), Laboratoire de Physique des Plasmas ( LPP ), Université Paris-Sud - Paris 11 ( UP11 ) -Université Pierre et Marie Curie - Paris 6 ( UPMC ) -Observatoire de Paris-École polytechnique ( X ) -Sorbonne Universités-PSL Research University ( PSL ) -Université Paris-Saclay-Centre National de la Recherche Scientifique ( CNRS ), Institut Jean Lamour ( IJL ), Centre National de la Recherche Scientifique ( CNRS ) -Université de Lorraine ( UL ), Département de Physique Nucléaire (ex SPhN) ( DPHN ), Institut de Recherches sur les lois Fondamentales de l'Univers ( IRFU ), Commissariat à l'énergie atomique et aux énergies alternatives ( CEA ) -Université Paris-Saclay-Commissariat à l'énergie atomique et aux énergies alternatives ( CEA ) -Université Paris-Saclay, ITER [St. Paul-lez-Durance], ITER, Centre de Thermique de Lyon ( CETHIL ), Université Claude Bernard Lyon 1 ( UCBL ), Université de Lyon-Université de Lyon-Institut National des Sciences Appliquées de Lyon ( INSA Lyon ), Université de Lyon-Institut National des Sciences Appliquées ( INSA ) -Institut National des Sciences Appliquées ( INSA ) -Centre National de la Recherche Scientifique ( CNRS ), Laboratoire d'Electronique et des Technologies de l'Information ( CEA-LETI ), Commissariat à l'énergie atomique et aux énergies alternatives ( CEA ) -Université Grenoble Alpes [Saint Martin d'Hères], Institut de Chimie de Clermont-Ferrand ( ICCF ), Université Blaise Pascal - Clermont-Ferrand 2 ( UBP ) -Sigma CLERMONT ( Sigma CLERMONT ) -Centre National de la Recherche Scientifique ( CNRS ), Institut de Recherche en Sciences et Techniques de la Ville ( IRSTV ), Université d'Angers ( UA ) -Université de Nantes ( UN ) -École Centrale de Nantes ( ECN ) -Université de La Rochelle ( ULR ) -EC. ARCHIT. NANTES-Centre National de la Recherche Scientifique ( CNRS ), Eau et Environnement ( IFSTTAR/GERS/EE ), Institut Français des Sciences et Technologies des Transports, de l'Aménagement et des Réseaux ( IFSTTAR ) -PRES Université Nantes Angers Le Mans ( UNAM ), Physique des interactions ioniques et moléculaires ( PIIM ), Aix Marseille Université ( AMU ) -Centre National de la Recherche Scientifique ( CNRS ), Laboratoire d'Intégration des Systèmes et des Technologies ( LIST ), Commissariat à l'énergie atomique et aux énergies alternatives ( CEA ) -Université Paris-Saclay, Institut des Sciences de l'Evolution de Montpellier ( ISEM ), Université de Montpellier ( UM ) -Institut de recherche pour le développement [IRD] : UR226-Centre National de la Recherche Scientifique ( CNRS ), Laboratoire Lasers, Plasmas et Procédés photoniques ( LP3 ), Centre d'Histoire 'Espaces et Cultures' ( CHEC ), Université Blaise Pascal - Clermont-Ferrand 2 ( UBP ), École des hautes études en sciences sociales ( EHESS ), Centre hospitalier universitaire de Nantes ( CHU Nantes ), Centre de Recherche en Cancérologie / Nantes - Angers ( CRCNA ), CHU Angers-Centre hospitalier universitaire de Nantes ( CHU Nantes ) -Hôtel-Dieu de Nantes-Institut National de la Santé et de la Recherche Médicale ( INSERM ) -Hôpital Laennec-Centre National de la Recherche Scientifique ( CNRS ) -Faculté de Médecine d'Angers, Centre d'investigation clinique en cancérologie ( CI2C ), IFP Energies nouvelles ( IFPEN ), Matériaux, ingénierie et science [Villeurbanne] ( MATEIS ), Université de Lyon-Université de Lyon-Centre National de la Recherche Scientifique ( CNRS ) -Institut National des Sciences Appliquées de Lyon ( INSA Lyon ), Université de Lyon-Institut National des Sciences Appliquées ( INSA ) -Institut National des Sciences Appliquées ( INSA ), Ecologie Systématique et Evolution ( ESE ), Université Paris-Sud - Paris 11 ( UP11 ) -AgroParisTech-Centre National de la Recherche Scientifique ( CNRS ), Laboratoire d'Etude des Matériaux en Milieux Agressifs ( LEMMA ), Université de La Rochelle ( ULR ), Institut des Sciences Chimiques de Rennes ( ISCR ), Université de Rennes 1 ( UR1 ), Université de Rennes ( UNIV-RENNES ) -Université de Rennes ( UNIV-RENNES ) -Ecole Nationale Supérieure de Chimie de Rennes-Institut National des Sciences Appliquées ( INSA ) -Centre National de la Recherche Scientifique ( CNRS ), Croix-rouge française, Procédés et Ingénierie en Mécanique et Matériaux [Paris] ( PIMM ), Centre National de la Recherche Scientifique ( CNRS ) -Conservatoire National des Arts et Métiers [CNAM] ( CNAM ), Institut de Microélectronique, Electromagnétisme et Photonique - Laboratoire d'Hyperfréquences et Caractérisation ( IMEP-LAHC ), Centre National de la Recherche Scientifique ( CNRS ) -Université Savoie Mont Blanc ( USMB [Université de Savoie] [Université de Chambéry] ) -Institut National Polytechnique de Grenoble ( INPG ) -Université Joseph Fourier - Grenoble 1 ( UJF ) -Institut polytechnique de Grenoble - Grenoble Institute of Technology ( Grenoble INP ) -Université Grenoble Alpes ( UGA ), Laboratoire de Mécanique, Modélisation et Procédés Propres ( M2P2 ), Aix Marseille Université ( AMU ) -Ecole Centrale de Marseille ( ECM ) -Centre National de la Recherche Scientifique ( CNRS ), Géoazur ( GEOAZUR ), Université Pierre et Marie Curie - Paris 6 ( UPMC ) -Université Nice Sophia Antipolis ( UNS ), Université Côte d'Azur ( UCA ) -Université Côte d'Azur ( UCA ) -Institut national des sciences de l'Univers ( INSU - CNRS ) -Observatoire de la Côte d'Azur, Université Côte d'Azur ( UCA ) -Centre National de la Recherche Scientifique ( CNRS ), Réserve de la Haute Touche, Muséum National d'Histoire Naturelle ( MNHN ), Department of Information Technology ( INTEC ), Ghent University [Belgium] ( UGENT ), Dipartimento di Ingegneria dell'Ambiente e per lo Sviluppo Sostenibile ( DIASS ), Institut Charles Gerhardt Montpellier - Institut de Chimie Moléculaire et des Matériaux de Montpellier ( ICGM ICMMM ), Université Montpellier 1 ( UM1 ) -Université Montpellier 2 - Sciences et Techniques ( UM2 ) -Ecole Nationale Supérieure de Chimie de Montpellier ( ENSCM ) -Université de Montpellier ( UM ) -Centre National de la Recherche Scientifique ( CNRS ), Physique des milieux ionisés et applications ( LPMIA ), Université Henri Poincaré - Nancy 1 ( UHP ) -Centre National de la Recherche Scientifique ( CNRS ), Centre de Recherche en Cancérologie de Lyon ( CRCL ), Université de Lyon-Université de Lyon-Centre Léon Bérard [Lyon]-Institut National de la Santé et de la Recherche Médicale ( INSERM ) -Centre National de la Recherche Scientifique ( CNRS ), Bureau de Recherches Géologiques et Minières (BRGM) ( BRGM ), Catalyse par les métaux, Institut de Chimie des Milieux et Matériaux de Poitiers ( IC2MP ), Université de Poitiers-Centre National de la Recherche Scientifique ( CNRS ) -Université de Poitiers-Centre National de la Recherche Scientifique ( CNRS ), Service de Chimie Physique ( SCP ), Laboratoire des Adaptations Physiologiques aux Activités Physiques ( LAPHAP ), Institut de Recherche pour le Développement (IRD)-Université Pierre et Marie Curie - Paris 6 (UPMC)-Université Nice Sophia Antipolis (... - 2019) (UNS), COMUE Université Côte d'Azur (2015 - 2019) (COMUE UCA)-COMUE Université Côte d'Azur (2015 - 2019) (COMUE UCA)-Institut national des sciences de l'Univers (INSU - CNRS)-Observatoire de la Côte d'Azur, Université Côte d'Azur (UCA)-COMUE Université Côte d'Azur (2015 - 2019) (COMUE UCA)-Université Côte d'Azur (UCA)-Centre National de la Recherche Scientifique (CNRS), Centre Léon Bérard [Lyon]-Université Claude Bernard Lyon 1 (UCBL), Université de Lyon-Université de Lyon-Institut National de la Santé et de la Recherche Médicale (INSERM)-Centre National de la Recherche Scientifique (CNRS), Centre National de la Recherche Scientifique (CNRS)-Université Joseph Fourier - Grenoble 1 (UJF)-Institut National Polytechnique de Grenoble (INPG)-Institut polytechnique de Grenoble - Grenoble Institute of Technology (Grenoble INP ), Université de Lyon-Université de Lyon-Centre National de la Recherche Scientifique (CNRS)-Institut National des Sciences Appliquées de Lyon (INSA Lyon), Université de Lyon-Institut National des Sciences Appliquées (INSA)-Institut National des Sciences Appliquées (INSA), Université d'Angers (UA)-Université de Nantes (UN)-École Centrale de Nantes (ECN)-Université de La Rochelle (ULR)-EC. ARCHIT. NANTES-Centre National de la Recherche Scientifique (CNRS), École pratique des hautes études (EPHE), Université Paris sciences et lettres (PSL)-Université Paris sciences et lettres (PSL)-Centre de Coopération Internationale en Recherche Agronomique pour le Développement (Cirad)-Centre National de la Recherche Scientifique (CNRS)-Université de Montpellier (UM)-Institut de recherche pour le développement [IRD] : UR226, Centre National de la Recherche Scientifique (CNRS)-Université Claude Bernard Lyon 1 (UCBL), and COMUE Université Côte d'Azur (2015 - 2019) (COMUE UCA)-Université Côte d'Azur (UCA)-COMUE Université Côte d'Azur (2015 - 2019) (COMUE UCA)-Université Côte d'Azur (UCA)-Institut national des sciences de l'Univers (INSU - CNRS)-Université Nice Sophia Antipolis (... - 2019) (UNS)
Subjects: Physics, [PHYS]Physics [physics], Nuclear and High Energy Physics, [ PHYS ] Physics [physics], Plasma parameters, Ripple, Plasma, Tore Supra, Collisionality, Condensed Matter Physics, 7. Clean energy, 01 natural sciences, 010305 fluids & plasmas, Computational physics, symbols.namesake, Nuclear magnetic resonance, Physics::Plasma Physics, 0103 physical sciences, symbols, Langmuir probe, Electron temperature, 010306 general physics, Power density
Abstract: International audience; Tore Supra routinely addresses the physics and technology of very long-duration plasma discharges, thus bringing precious information on critical issues of long pulse operation of ITER. A new ITER relevant lower hybrid current drive (LHCD) launcher has allowed coupling to the plasma a power level of 2.7 MW for 78 s, corresponding to a power density close to the design value foreseen for an ITER LHCD system. In accordance with the expectations, long distance (10 cm) power coupling has been obtained. Successive stationary states of the plasma current pro le have been controlled in real-time featuring (i) control of sawteeth with varying plasma parameters, (ii) obtaining and sustaining a `hot core' plasma regime, (iii) recovery from a voluntarily triggered deleterious magnetohydrodynamic regime. The scrape-off layer (SOL) parameters and power deposition have been documented during L-mode ramp-up phase, a crucial point for ITER before the X-point formation. Disruption mitigation studies have been conducted with massive gas injection, evidencing the difference between He and Ar and the possible role of the q = 2 surface in limiting the gas penetration. ICRF assisted wall conditioning in the presence of magnetic eld has been investigated, culminating in the demonstration that this conditioning scheme allows one to recover normal operation after disruptions. The effect of the magnetic eld ripple on the intrinsic plasma rotation has been studied, showing the competition between turbulent transport processes and ripple toroidal friction. During dedicated dimensionless experiments, the effect of varying the collisionality on turbulence wavenumber spectra has been documented, giving new insight into the turbulence mechanism. Turbulence measurements have also allowed quantitatively comparing experimental results with predictions by 5D gyrokinetic codes: numerical results simultaneously match the magnitude of effective heat diffusivity, rms values of density uctuations and wavenumber spectra. A clear correlation between electron temperature gradient and impurity transport in the very core of the plasma has been observed, strongly suggesting the existence of a threshold above which transport is dominated by turbulent electron modes. Dynamics of edge turbulent uctuations has been studied by correlating data from fast imaging cameras and Langmuir probes, yielding a coherent picture of transport processes involved in the SOL.
Published: 2011
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43. Benchmark of coupling codes (ALOHA, TOPLHA and GRILL3D) with ITER-relevant Lower Hybrid antenna

Author: J.F. Artaud, A. Saille, S. Meschino, Frederic Imbeaux, Q. Zeng, J. Garcia, M. Goniche, A. Cardinali, Angelo A. Tuccillo, Giuseppe Schettini, Y.S. Bae, A. Ekedahl, Ph. Cara, S.H. Kim, Daniele Milanesio, J. Decker, P. Garibaldi, Silvio Ceccuzzi, Jia Hua, Gilles Berger-By, Lara Pajewski, Francesco Mirizzi, R. Magne, M. Schneider, C. Hamlyn-Harris, Y. Lausenaz, J.M. Bernard, J. Belo, C. Castaldo, Julien Hillairet, Q.Y. Huang, D. Guilhem, Y. Peysson, L. Marfisi, R. Villari, G. T. Hoang, L. Panaccione, Won Namkung, Y. Wu, A.M.A. Barbera, P.K. Sharma, O. Tudisco, Riccardo Maggiora, Lena Delpech, Karl Vulliez, R. Cesario, Milanesio, D, Hillairet, J, Panaccione, L, Maggiora, R, Artaud J., F, Bae Y., S, Belo, J, Berger By, G, Bernard J., M, Cara, Ph, Cardinali, A, Castaldo, C, Ceccuzzi, Silvio, Cesario, R, Decker, J, Delpech, L, Ekedahl, A, Garcia, J, Garibaldi, P, Goniche, M, Guilhem, D, Hamlyn Harris, C, Hoang G., T, Hua, J, Huang Q., Y, Imbeaux, F, Kazarian, F, Kim S., H, Lausenaz, Y, Magne, R, Marfisi, L, Meschino, S, Mirizzi, F, Namkung, W, Pajewski, Lara, Peysson, Y, Saille, A, Schettini, Giuseppe, Schneider, M, Sharma P., K, Tudisco, O, Villari S., R, Vulliez, K, Wu, Y, and Zeng, Q.
Subjects: Physics, Coupling, Tokamak, Nuclear Fusion, Lower Hybrid Antenna, Mechanical Engineering, Fusion power, Topology, Power (physics), law.invention, ITER, Lower Hybrid, PAM, Nuclear Energy and Engineering, Aloha, law, Benchmark (computing), General Materials Science, Reflection coefficient, Antenna (radio), Civil and Structural Engineering
Abstract: "In order to assist the design of the future ITER Lower Hybrid launcher, coupling codes ALOHA, from CEA\/IRFM, TOPLHA, from Politecnico di Torino, and GRILL3D, developed by Dr. Mikhail Irzak (A.F. Ioffe Physico-Technical Institute, St. Petersburg, Russia) and operated by ENEA Frascati, have been compared with the updated (six modules with four active waveguides per module) Passive-Active Multi-junction (PAM) Lower Hybrid antennas. Both ALOHA and GRILL3D formulate the problem in terms of rectangular waveguides modes, while TOPLHA is based on boundary-value problem with the adoption of a triangular cell-mesh to represent the relevant waveguides surfaces. Several plasma profiles, with varying edge density and density increase, have been adopted to provide a complete description of the simulated launcher in terms of reflection coefficient, computed at the beginning of each LH module, and of power spectra. Good agreement can be observed among codes for all the simulated profiles. © 2010 Elsevier B.V. "
Published: 2011

44. Impact of heating and current drive mix on the ITER hybrid scenario

Author: Jonathan Citrin, J.F. Artaud, G. M. D. Hogeweij, Frederic Imbeaux, and J. Garcia
Subjects: Nuclear and High Energy Physics, Materials science, Nuclear engineering, Magnetic confinement fusion, Flux, Fusion power, Condensed Matter Physics, 01 natural sciences, 7. Clean energy, 010305 fluids & plasmas, Power (physics), Pedestal, 13. Climate action, 0103 physical sciences, Heat transfer, Sensitivity (control systems), Atomic physics, Current (fluid), 010306 general physics
Abstract: Hybrid scenario performance in ITER is studied with the CRONOS integrated modelling suite, using the GLF23 anomalous transport model for heat transport prediction. GLF23 predicted core confinement is optimized through tailoring the q-profile shape by a careful choice of current drive actuators, affecting the transport due to the predicted dependence of the turbulence level on the absolute q-profile values and magnetic shear. A range of various heating and current drive choices are examined, as are different assumptions on the pedestal height. The optimum q-profile shape is predicted to be one that maximizes the ratio of s/q throughout the bulk of the plasma volume. Optimizing the confinement allows a minimization of the plasma density required in order to achieve a defined target fusion power of 350 MW. A lower density then allows a lower total current (I p) at the same Greenwald fraction (f G), thus aiding in maintaining q > 1 as desired in a hybrid scenario, and in minimizing the flux consumption. The best performance is achieved with a combination of NBI and ECCD (e.g. 33/37 MW NBI/ECCD for a scenario with a pedestal height of 4 keV). The q-profile shape and plasma confinement properties are shown to be highly sensitive to the positioning of the ECCD deposition. Comparisons with the lower performing cases where some or all of the ECCD power is replaced with LHCD or ICRH are shown (e.g. 33/20/17 MW NBI/ECCD/LHCD or NBI/ECCD/ICRH). The inclusion of LHCD reduces confinement due to deleterious shaping of the q-profile, and the inclusion of ICRH, particularly in a stiff model, does not lead to significantly increased fusion power and furthermore does not contribute to the non-inductive current fraction. For the optimum NBI/ECCD current drive mix, the predictions show that a satisfactory ITER hybrid scenario (P fus ∼ 350 MW, Q ⩾ 5, q min close to 1) may be achieved with T ped ⩾ 4 keV. In addition, predicted performance sensitivity analysis was carried out for several assumed parameters, such as Z eff and density peaking.
Published: 2010

45. Particle transport in low core turbulence Tore-Supra plasmas

Author: J.F. Artaud, T. Parisot, Frederic Imbeaux, Clarisse Bourdelle, R. Guirlet, A. Sirinelli, J. L. Segui, D. Villegas, G.T. Hoang, Roland Sabot, Pascale Hennequin, Didier Mazon, Xavier Garbet, Laboratoire de Physique des Plasmas (LPP), Université Paris-Sud - Paris 11 (UP11)-Université Pierre et Marie Curie - Paris 6 (UPMC)-Observatoire de Paris, Université Paris sciences et lettres (PSL)-Université Paris sciences et lettres (PSL)-École polytechnique (X)-Sorbonne Université (SU)-Université Paris-Saclay-Centre National de la Recherche Scientifique (CNRS), and Université Paris sciences et lettres (PSL)-Université Paris sciences et lettres (PSL)-École polytechnique (X)-Université Paris-Saclay-Centre National de la Recherche Scientifique (CNRS)
Subjects: Physics, Nuclear and High Energy Physics, Electron density, Tokamak, Turbulence, Magnetic confinement fusion, Plasma, Sawtooth wave, Electron, Tore Supra, Condensed Matter Physics, 01 natural sciences, 010305 fluids & plasmas, law.invention, law, Physics::Plasma Physics, [PHYS.PHYS.PHYS-PLASM-PH]Physics [physics]/Physics [physics]/Plasma Physics [physics.plasm-ph], 0103 physical sciences, Atomic physics, 010306 general physics
Abstract: Electron and impurity transport has been studied in sawtoothing plasmas in the Tore-Supra tokamak. High time and space resolution measurements of the electron density reveal the existence of a flat profile region encompassing the q = 1 surface, on which is superimposed a density peak building up between sawtooth relaxations. For the first time in this regime, we have determined the underlying transport of both nickel and electrons independently of the effect of sawteeth in the central part of the plasma. Electron transport is consistent with the neoclassical expectations only in the close vicinity of the magnetic axis. Further out, it exceeds the neoclassical values as calculated with the NCLASS code, although the turbulence level is very low in the whole central region region. In contrast, nickel transport is in good agreement with the neoclassical calculations in the same region. The neoclassical effect on trapped particles of a persisting mode due to incomplete reconnection of the magnetic surfaces is consistent with these observations.
Published: 2010
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46. Investigation of steady-state tokamak issues by long pulse experiments on Tore Supra

Author: Nicolas Crouseilles, R. Guirlet, J. Hourtoule, W. Xiao, J. L. Gardarein, Frédéric Schwander, E. Delchambre, A. Martinez, F. Bouquey, D. Boilson, M. Richou, L. Allegretti, V. Lamaison, T. Loarer, B. Lacroix, A. Vatry, W. Zwingmann, D. Ciazynski, J. Decker, P. Hertout, A. Bécoulet, R. Abgrall, M. Chatelier, B. Guillerminet, J. Lasalle, Yannick Marandet, M. Lipa, S. Nicollet, C. Reux, F. Benoit, E. Delmas, P. Reynaud, J. Y. Journeaux, F. Jullien, H. Bottollier-Curtet, Y. Buranvand, M. Schneider, D. Moreau, Karl Vulliez, M. Tena, P. Pastor, C. Le Niliot, S. Balme, G. Falchetto, V. Martin, L. Svensson, S. H. Hong, C. Laviron, M. Houry, J. M. Theis, S. Madeleine, T. Hutter, T. Salmon, L. Manenc, C. Bouchand, M. Davi, S. Rosanvallon, N. Dolgetta, Pascale Roubin, Eric Nardon, L.-G. Eriksson, B. Pégourié, D. Douai, O. Chaibi, Patrick Mollard, Didier Mazon, J. P. Gunn, Marie Farge, M. Prou, M. Thonnat, L. Begrambekov, J. Garcia, Philippe Ghendrih, L. Colas, Jacques Blum, J. Clary, P. Spuig, C. Gil, M. Kocan, Ph. Lotte, Paolo Angelino, B. Saoutic, M. Ottaviani, P. Devynck, X. Courtois, L. Doceul, Gilles Berger-By, Patrick Tamain, Marc Missirlian, K. Schneider, Yanick Sarazin, Lena Delpech, J.M. Ané, Pascale Hennequin, A. Durocher, Patrick Maget, P. Huynh, David Henry, P. Decool, Marc Goniche, F. Clairet, Julien Hillairet, A. Geraud, J. Signoret, Stéphane Heuraux, P. Bayetti, T. Gerbaud, X. L. Zou, Y. Peysson, H. Parrat, L. Million, Jérôme Bucalossi, S. Hacquin, Clarisse Bourdelle, F. Samaille, Bernard Bertrand, E. Sonnendruker, G. Chevet, A. Simonin, Ph. Cara, J. L. Maréchal, J. Johner, M. S. Benkadda, J. C. Hatchressian, R. Magne, J. Schlosser, A. Grosman, F. Brémond, R. Masset, Estelle Gauthier, S. Song, G. Giruzzi, M. Nannini, Caroline Hernandez, H.P.L. de Esch, P. Garibaldi, R. J. Dumont, Stanislas Pamela, M. Geynet, C. Nguyen, L. Zani, A. Casati, Cyrille Honoré, G. Gros, Fabrice Rigollet, A. Argouarch, Yann Corre, A. Marcor, H. Dougnac, E. Tsitrone, C. Grisolia, D. Pacella, Guillaume Latu, Céline Martin, T. Aniel, G. Darmet, R. Daviot, J.P. Martins, J. L. Farjon, P. Magaud, A. Ekedahl, Francesca Turco, D. Elbeze, P. Beyer, S. Carpentier, Roger Reichle, F. Faisse, X. Litaudon, R. Guigon, F.G. Rimini, F. Linez, L. Gargiulo, C. Fenzi-Bonizec, G. Marbach, Alexandre Torre, P. Monier-Garbet, N. Ravenel, Laure Vermare, J.-M. Travere, Xavier Garbet, R. Mitteau, H. Roche, C. Desgranges, V. Moncada, F. Villecroze, Jean-François Luciani, G. Ciraolo, F. Kazarian, J. Roth, C. Brosset, F. Saint-Laurent, H. Nehme, T. Parisot, Nicolas Fedorczak, F. Escourbiac, D. Guilhem, J. L. Duchateau, P. Moreau, O. Meyer, D. Yu, A. L. Pecquet, V. Petrzilka, E. Trier, Roland Sabot, G. T. A. Huysmans, G. T. Hoang, E. Joffrin, L. Meunier, P. Chantant, C. Portafaix, D. Voyer, J. C. Vallet, S. Salasca, J. L. Segui, A. Santagiustina, J.F. Artaud, G. Dunand, M. Lennholm, Frederic Imbeaux, V. Grandgirard, A. Escarguel, F. Leroux, Y. Lausenaz, P. Chappuis, V. Basiuk, F. Lott, Hinrich Lütjens, Sylvain Brémond, D. Villegas, Marina Becoulet, Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), Commissariat à l'énergie atomique et aux énergies alternatives (CEA), Centre de Physique Théorique [Palaiseau] (CPHT), École polytechnique (X)-Centre National de la Recherche Scientifique (CNRS), Institut de Mathématiques de Bordeaux (IMB), Université Bordeaux Segalen - Bordeaux 2-Université Sciences et Technologies - Bordeaux 1-Université de Bordeaux (UB)-Institut Polytechnique de Bordeaux (Bordeaux INP)-Centre National de la Recherche Scientifique (CNRS), Institut Jean Lamour (IJL), Institut de Chimie du CNRS (INC)-Université de Lorraine (UL)-Centre National de la Recherche Scientifique (CNRS), Association EURATOM-CEA (CEA/DSM/DRFC), Centre National de la Recherche Scientifique (CNRS)-École polytechnique (X), and Université Bordeaux Segalen - Bordeaux 2-Université Sciences et Technologies - Bordeaux 1 (UB)-Université de Bordeaux (UB)-Institut Polytechnique de Bordeaux (Bordeaux INP)-Centre National de la Recherche Scientifique (CNRS)
Subjects: Nuclear and High Energy Physics, fusion, Tokamak, MHD, Nuclear engineering, Cyclotron, Ultra-high vacuum, Electron, Tore Supra, 01 natural sciences, 7. Clean energy, 010305 fluids & plasmas, law.invention, Nuclear physics, law, [PHYS.PHYS.PHYS-PLASM-PH]Physics [physics]/Physics [physics]/Plasma Physics [physics.plasm-ph], 0103 physical sciences, 52.35, 010306 general physics, ComputingMilieux_MISCELLANEOUS, Physics, Magnetic confinement fusion, plasma heating, Plasma, Condensed Matter Physics, Magnetohydrodynamics
Abstract: The main results of the Tore Supra experimental programme in the years 2007–2008 are reported. They document significant progress achieved in the domain of steady-state tokamak research, as well as in more general issues relevant for ITER and for fusion physics research. Three areas are covered: ITER relevant technology developments and tests in a real machine environment, tokamak operational issues for high power and long pulses, and fusion plasma physics. Results presented in this paper include test and validation of a new, load-resilient concept of ion cycotron resonance heating antenna and of an inspection robot operated under ultra-high vacuum and high temperature conditions; an extensive experimental campaign (5 h of plasma) aiming at deuterium inventory and carbon migration studies; real-time control of sawteeth by electron cyclotron current drive in the presence of fast ion tails; ECRH-assisted plasma start-up studies; dimensionless scalings of transport and turbulence; transport experiments using active perturbation methods; resistive and fast-particle driven MHD studies. The potential role of Tore Supra in the worldwide fusion programme before the start of ITER operation is also discussed.
Published: 2009
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47. INTEGRATED MODELLING OF ITER HYBRID SCENARIOS WITH ECCD

Author: G. Giruzzi, V. Basiuk, J.F. Artaud, M. Schneider, Frederic Imbeaux, and J. Garcia
Published: 2009
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48. RF-driven advanced modes of ITER operation

Author: X. Litaudon, G. Giruzzi, N. C. Hawkes, J.F. Artaud, M. Schneider, Frederic Imbeaux, J. Garcia, M. Brix, J. Mailloux, Y. Peysson, V. Basiuk, J. Decker, and Jet Efda contributors
Subjects: Physics, Jet (fluid), Tokamak, Plasma heating, law, Nuclear engineering, Dielectric heating, Electronic engineering, Iter tokamak, Radio frequency, Current (fluid), law.invention, Power (physics)
Abstract: The impact of the Radio Frequency heating and current drive systems on the ITER advanced scenarios is analyzed by means of the CRONOS suite of codes for integrated tokamak modelling. As a first step, the code is applied to analyze a high power advanced scenario discharge of JET in order to validate both the heating and current drive modules and the overall simulation procedure. Then, ITER advanced scenarios, based on Radio Frequency systems, are studied on the basis of previous results. These simulations show that both hybrid and steady‐state scenarios could be possible within the ITER specifications, using RF heating and current drive only.
Published: 2009
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49. A lower hybrid current drive system for ITER

Author: Si Park, J.F. Artaud, A. Tanga, C.E. Kessel, Frederic Imbeaux, J. Garcia, M. Goniche, C. Gormezano, S.L. Milora, G.T. Hoang, X. Litaudon, Y. Peysson, F. Kazarian, J.H. Jeong, Moo-Hyun Cho, J.B. Lister, R.R. Parker, João P. S. Bizarro, Annika Ekedahl, J. Jacquinot, R. Magne, Lena Delpech, Jong-Gu Kwak, Young-Soon Bae, E. J. Synakowski, A. A. Tuccillo, Julien Hillairet, Won Namkung, M. Schneider, D. Guilhem, Francesco Mirizzi, J. Decker, J.H. Belo, P.T. Bonoli, G. Giruzzi, A. Bécoulet, Yuanxi Wan, B. Beaumont, David A Rasmussen, Pankaj Sharma, S.H. Kim, Jean-Marie Noterdaeme, and Gilles Berger-By
Subjects: Nuclear and High Energy Physics, Launcher, Tokamak, Advisory committee, Transport, Magnetic confinement fusion, Tore-Supra, Commit, Tore Supra, Condensed Matter Physics, Task (project management), Lhcd, Procurement, Work plan, Work (electrical), Plasmas, Scenarios, Power, Progress, Systems engineering, Operation
Abstract: A 20 MW/5 GHz lower hybrid current drive (LHCD) system was initially due to be commissioned and used for the second mission of ITER, i.e. the Q = 5 steady state target. Though not part of the currently planned procurement phase, it is now under consideration for an earlier delivery. In this paper, both physics and technology conceptual designs are reviewed. Furthermore, an appropriate work plan is also developed. This work plan for design, R&D, procurement and installation of a 20 MW LHCD system on ITER follows the ITER Scientific and Technical Advisory Committee (STAC) T13-05 task instructions. It gives more details on the various scientific and technical implications of the system, without presuming on any work or procurement sharing amongst the possible ITER partnersb The LHCD system of ITER is not part of the initial cost sharing.. This document does not commit the Institutions or Domestic Agencies of the various authors in that respect.
Published: 2009

50. Advances in the physics basis for the European DEMO design

Author: Patrick Maget, E. Fable, Emanuele Poli, Massimiliano Mattei, H. Zohm, Raffaele Albanese, C. Reux, C. Angioni, G. Ramogida, Ambrogio Fasoli, M. Bernert, G. Federici, J.F. Artaud, G. Giruzzi, J. Aubert, Fabio Villone, Roberto Ambrosino, Leena Aho-Mantila, M. Wischmeier, Ronald Wenninger, J. Garcia, Frederik Arbeiter, M. Schneider, B. Sieglin, Frank Jenko, F. Maviglia, CEA-Direction des Energies (ex-Direction de l'Energie Nucléaire) (CEA-DES (ex-DEN)), Commissariat à l'énergie atomique et aux énergies alternatives (CEA), VTT Technical Research Centre of Finland (VTT), Assoc. Euratom-ENEA-CREATE, Universita Mediterranea of Reggio Calabria [Reggio Calabria], Max-Planck-Institut für Plasmaphysik [Garching] (IPP), Association EURATOM-CEA (CEA/DSM/DRFC), Università degli studi di Napoli Federico II, Laboratoire de Physique des Plasmas (LPP), Université Paris-Sud - Paris 11 (UP11)-Université Pierre et Marie Curie - Paris 6 (UPMC)-Observatoire de Paris, Université Paris sciences et lettres (PSL)-Université Paris sciences et lettres (PSL)-École polytechnique (X)-Sorbonne Université-Université Paris-Saclay-Centre National de la Recherche Scientifique (CNRS), European Project: 633053,H2020,EURATOM-Adhoc-2014-20,EUROfusion(2014), EUROfusion, Karlsruher Institut für Technologie (KIT), Institut de Physique du Globe de Paris (IPGP), Université Pierre et Marie Curie - Paris 6 (UPMC)-Institut national des sciences de l'Univers (INSU - CNRS)-IPG PARIS-Université Paris Diderot - Paris 7 (UPD7)-Université de La Réunion (UR)-Centre National de la Recherche Scientifique (CNRS), Universita degli studi di Napoli 'Parthenope' [Napoli], Centre de Recherches en Physique des Plasmas (CRPP), Ecole Polytechnique Fédérale de Lausanne (EPFL), Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), Institut de Génétique Moléculaire de Montpellier (IGMM), Centre National de la Recherche Scientifique (CNRS)-Université de Montpellier (UM), Italian National agency for new technologies, Energy and sustainable economic development [Frascati] (ENEA), Università degli studi di Cassino e del Lazio Meridionale (UNICAS), Wenninger, R., Arbeiter, F., Aubert, J., Aho Mantila, L., Albanese, R., Ambrosino, R., Angioni, C., Artaud, J. F., Bernert, M., Fable, E., Fasoli, A., Federici, G., Garcia, J., Giruzzi, G., Jenko, F., Maget, P., Mattei, Massimiliano, Maviglia, F., Poli, E., Ramogida, G., Reux, C., Schneider, M., Sieglin, B., Villone, F., Wischmeier, M., Zohm, H., Laboratoire Technologie d'Assemblage (LTA), Service d'Etudes Mécaniques et Thermiques (SEMT), Département de Modélisation des Systèmes et Structures (DM2S), Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Université Paris-Saclay-CEA-Direction des Energies (ex-Direction de l'Energie Nucléaire) (CEA-DES (ex-DEN)), Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Université Paris-Saclay-Département de Modélisation des Systèmes et Structures (DM2S), Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Université Paris-Saclay, University of Naples Federico II = Università degli studi di Napoli Federico II, Università degli Studi di Napoli 'Parthenope' = University of Naples (PARTHENOPE), Université de Montpellier (UM)-Centre National de la Recherche Scientifique (CNRS), Aho-Mantila, L., Artaud, J. -F., and Mattei, M.
Subjects: Nuclear and High Energy Physics, [PHYS.NUCL]Physics [physics]/Nuclear Theory [nucl-th], Basis (linear algebra), MHD, Condensed Matter Physic, [PHYS.NEXP]Physics [physics]/Nuclear Experiment [nucl-ex], Fusion power, Condensed Matter Physics, 7. Clean energy, disruption, scenario, fast particle, fast particles, Conceptual design, [SDU]Sciences of the Universe [physics], Iter, transport, Systems engineering, ddc:620, Current (fluid), DEMO, PWI, Engineering & allied operations
Abstract: International audience; in the European fusion roadmap, ITER is followed by a demonstration fusion power reactor (DEMO), for which a conceptual design is under development. This paper reports the first results of a coherent effort to develop the relevant physics knowledge for that (DEMO Physics Basis), carried out by European experts. The program currently includes investigations in the areas of scenario modeling, transport, MHD, heating & current drive, fast particles, plasma wall interaction and disruptions.
Published: 2015
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