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1. Overview of T and D–T results in JET with ITER-like wall

Author

C.F. Maggi, D. Abate, N. Abid, P. Abreu, O. Adabonyan, M. Afzal, I. Ahmad, M. Akhtar, R. Albanese, S. Aleiferis, E. Alessi, P. Aleynikov, J. Alguacil, J. Alhage, M. Ali, H. Allen, M. Allinson, M. Alonzo, E. Alves, R. Ambrosino, E. Andersson Sundén, P. Andrew, M. Angelone, C. Angioni, I. Antoniou, L. Appel, C. Appelbee, C. Aramunde, M. Ariola, G. Arnoux, G. Artaserse, J.-F. Artaud, W. Arter, V. Artigues, F.J. Artola, A. Ash, O. Asztalos, D. Auld, F. Auriemma, Y. Austin, L. Avotina, J. Ayllón, E. Aymerich, A. Baciero, L. Bähner, F. Bairaktaris, I. Balboa, M. Balden, N. Balshaw, V.K. Bandaru, J. Banks, A. Banon Navarro, C. Barcellona, O. Bardsley, M. Barnes, R. Barnsley, M. Baruzzo, M. Bassan, A. Batista, P. Batistoni, L. Baumane, B. Bauvir, L. Baylor, C. Bearcroft, P. Beaumont, D. Beckett, A. Begolli, M. Beidler, N. Bekris, M. Beldishevski, E. Belli, F. Belli, S. Benkadda, J. Bentley, E. Bernard, J. Bernardo, M. Bernert, M. Berry, L. Bertalot, H. Betar, M. Beurskens, P.G. Bhat, S. Bickerton, J. Bielecki, T. Biewer, R. Bilato, P. Bílková, G. Birkenmeier, R. Bisson, J.P.S. Bizarro, P. Blatchford, A. Bleasdale, V. Bobkov, A. Boboc, A. Bock, G. Bodnar, P. Bohm, L. Bonalumi, N. Bonanomi, D. Bonfiglio, X. Bonnin, P. Bonofiglo, J. Booth, D. Borba, D. Borodin, I. Borodkina, T.O.S.J. Bosman, C. Bourdelle, M. Bowden, I. Božičević Mihalić, S.C. Bradnam, B. Breizman, S. Brezinsek, D. Brida, M. Brix, P. Brown, D. Brunetti, M. Buckley, J. Buermans, H. Bufferand, P. Buratti, A. Burckhart, A. Burgess, A. Buscarino, A. Busse, D. Butcher, G. Calabrò, L. Calacci, R. Calado, R. Canavan, B. Cannas, M. Cannon, M. Cappelli, S. Carcangiu, P. Card, A. Cardinali, S. Carli, P. Carman, D. Carnevale, B. Carvalho, I.S. Carvalho, P. Carvalho, I. Casiraghi, F.J. Casson, C. Castaldo, J.P. Catalan, N. Catarino, F. Causa, M. Cavedon, M. Cecconello, L. Ceelen, C.D. Challis, B. Chamberlain, R. Chandra, C.S. Chang, A. Chankin, B. Chapman, P. Chauhan, M. Chernyshova, A. Chiariello, G.-C. Chira, P. Chmielewski, A. Chomiczewska, L. Chone, J. Cieslik, G. Ciraolo, D. Ciric, J. Citrin, Ł. Ciupinski, R. Clarkson, M. Cleverly, P. Coates, V. Coccorese, R. Coelho, J.W. Coenen, I.H. Coffey, A. Colangeli, L. Colas, J. Collins, S. Conroy, C. Contré, N.J. Conway, D. Coombs, P. Cooper, S. Cooper, L. Cordaro, C. Corradino, Y. Corre, G. Corrigan, D. Coster, T. Craciunescu, S. Cramp, D. Craven, R. Craven, G. Croci, D. Croft, K. Crombé, T. Cronin, N. Cruz, A. Cufar, A. Cullen, A. Dal Molin, S. Dalley, P. David, A. Davies, J. Davies, S. Davies, G. Davis, K. Dawson, S. Dawson, I. Day, G. De Tommasi, J. Deane, M. Dearing, M. De Bock, J. Decker, R. Dejarnac, E. Delabie, E. de la Cal, E. de la Luna, D. Del Sarto, A. Dempsey, W. Deng, A. Dennett, G.L. Derks, G. De Temmerman, F. Devasagayam, P. de Vries, P. Devynck, A. di Siena, D. Dickinson, T. Dickson, M. Diez, P. Dinca, T. Dittmar, L. Dittrich, J. Dobrashian, T. Dochnal, A.J.H. Donné, W. Dorland, S. Dorling, S. Dormido-Canto, R. Dotse, D. Douai, S. Dowson, R. Doyle, M. Dreval, P. Drews, G. Drummond, Ph. Duckworth, H.G. Dudding, R. Dumont, P. Dumortier, D. Dunai, T. Dunatov, M. Dunne, I. Ďuran, F. Durodié, R. Dux, T. Eade, E. Eardley, J. Edwards, T. Eich, A. Eksaeva, H. El-Haroun, R.D. Ellis, G. Ellwood, C. Elsmore, S. Emery, G. Ericsson, B. Eriksson, F. Eriksson, J. Eriksson, L.G. Eriksson, S. Ertmer, G. Evans, S. Evans, E. Fable, D. Fagan, M. Faitsch, D. Fajardo Jimenez, M. Falessi, A. Fanni, T. Farmer, I. Farquhar, B. Faugeras, S. Fazinić, N. Fedorczak, K. Felker, R. Felton, H. Fernandes, D.R. Ferreira, J. Ferreira, G. Ferrò, J. Fessey, O. Février, O. Ficker, A.R. Field, A. Figueiredo, J. Figueiredo, A. Fil, N. Fil, P. Finburg, U. Fischer, G. Fishpool, L. Fittill, M. Fitzgerald, D. Flammini, J. Flanagan, S. Foley, N. Fonnesu, M. Fontana, J.M. Fontdecaba, L. Fortuna, E. Fortuna-Zalesna, M. Fortune, C. Fowler, P. Fox, O. Franklin, E. Fransson, L. Frassinetti, R. Fresa, D. Frigione, T. Fülöp, M. Furseman, S. Gabriellini, D. Gadariya, S. Gadgil, K. Gál, S. Galeani, A. Galkowski, D. Gallart, M. Gambrioli, T. Gans, J. Garcia, M. García-Muñoz, L. Garzotti, J. Gaspar, R. Gatto, P. Gaudio, D. Gear, T. Gebhart, S. Gee, M. Gelfusa, R. George, S.N. Gerasimov, R. Gerru, G. Gervasini, M. Gethins, Z. Ghani, M. Gherendi, P.-I. Gherghina, F. Ghezzi, L. Giacomelli, C. Gibson, L. Gil, M.R. Gilbert, A. Gillgren, E. Giovannozzi, C. Giroud, G. Giruzzi, J. Goff, V. Goloborodko, R. Gomes, J.-F. Gomez, B. Gonçalves, M. Goniche, J. Gonzalez-Martin, A. Goodyear, S. Gore, G. Gorini, T. Görler, N. Gotts, E. Gow, J.P. Graves, J. Green, H. Greuner, E. Grigore, F. Griph, W. Gromelski, M. Groth, C. Grove, R. Grove, N. Gupta, S. Hacquin, L. Hägg, A. Hakola, M. Halitovs, J. Hall, C.J. Ham, M. Hamed, M.R. Hardman, Y. Haresawa, G. Harrer, J.R. Harrison, D. Harting, D.R. Hatch, T. Haupt, J. Hawes, N.C. Hawkes, J. Hawkins, S. Hazael, J. Hearmon, P. Heesterman, P. Heinrich, M. Held, W. Helou, O. Hemming, S.S. Henderson, R. Henriques, R.B. Henriques, D. Hepple, J. Herfindal, G. Hermon, J.C. Hillesheim, K. Hizanidis, A. Hjalmarsson, A. Ho, J. Hobirk, O. Hoenen, C. Hogben, A. Hollingsworth, S. Hollis, E. Hollmann, M. Hölzl, M. Hook, M. Hoppe, J. Horáček, N. Horsten, A. Horton, L.D. Horton, L. Horvath, S. Hotchin, Z. Hu, Z. Huang, E. Hubenov, A. Huber, V. Huber, T. Huddleston, G.T.A. Huijsmans, Y. Husain, P. Huynh, A. Hynes, D. Iglesias, M.V. Iliasova, M. Imríšek, J. Ingleby, P. Innocente, V. Ioannou-Sougleridis, N. Isernia, I. Ivanova-Stanik, E. Ivings, S. Jachmich, T. Jackson, A.S. Jacobsen, P. Jacquet, H. Järleblad, A. Järvinen, F. Jaulmes, N. Jayasekera, F. Jenko, I. Jepu, E. Joffrin, T. Johnson, J. Johnston, C. Jones, E. Jones, G. Jones, L. Jones, T.T.C. Jones, A. Joyce, M. Juvonen, A. Kallenbach, P. Kalnina, D. Kalupin, P. Kanth, A. Kantor, A. Kappatou, O. Kardaun, J. Karhunen, E. Karsakos, Ye.O. Kazakov, V. Kazantzidis, D.L. Keeling, W. Kelly, M. Kempenaars, D. Kennedy, K. Khan, E. Khilkevich, C. Kiefer, H.-T. Kim, J. Kim, S.H. Kim, D.B. King, D.J. Kinna, V.G. Kiptily, A. Kirjasuo, K.K. Kirov, A. Kirschner, T. Kiviniemi, G. Kizane, C. Klepper, A. Klix, G. Kneale, M. Knight, P. Knight, R. Knights, S. Knipe, U. Knoche, M. Knolker, M. Kocan, F. Köchl, G. Kocsis, J.T.W. Koenders, Y. Kolesnichenko, Y. Kominis, M. Kong, B. Kool, V. Korovin, S.B. Korsholm, B. Kos, D. Kos, M. Koubiti, Y. Kovtun, E. Kowalska-Strzęciwilk, K. Koziol, Y. Krasikov, A. Krasilnikov, V. Krasilnikov, M. Kresina, A. Kreter, K. Krieger, A. Krivska, U. Kruezi, I. Książek, H. Kumpulainen, B. Kurzan, S. Kwak, O.J. Kwon, B. Labit, M. Lacquaniti, A. Lagoyannis, L. Laguardia, A. Laing, V. Laksharam, N. Lam, H.T. Lambertz, B. Lane, M. Langley, E. Lascas Neto, E. Łaszyńska, K.D. Lawson, A. Lazaros, E. Lazzaro, G. Learoyd, C. Lee, K. Lee, S. Leerink, T. Leeson, X. Lefebvre, H.J. Leggate, J. Lehmann, M. Lehnen, D. Leichtle, F. Leipold, I. Lengar, M. Lennholm, E. Leon Gutierrez, L.A. Leppin, E. Lerche, A. Lescinskis, S. Lesnoj, L. Lewin, J. Lewis, J. Likonen, Ch. Linsmeier, X. Litaudon, E. Litherland-Smith, F. Liu, T. Loarer, A. Loarte, R. Lobel, B. Lomanowski, P.J. Lomas, J. Lombardo, R. Lorenzini, S. Loreti, V.P. Loschiavo, M. Loughlin, T. Lowe, C. Lowry, T. Luce, R. Lucock, T. Luda Di Cortemiglia, M. Lungaroni, C.P. Lungu, T. Lunt, V. Lutsenko, B. Lyons, J. Macdonald, E. Macusova, R. Mäenpää, H. Maier, J. Mailloux, S. Makarov, P. Manas, A. Manning, P. Mantica, M.J. Mantsinen, J. Manyer, A. Manzanares, Ph. Maquet, M. Maraschek, G. Marceca, G. Marcer, C. Marchetto, O. Marchuk, A. Mariani, G. Mariano, M. Marin, A. Marin Roldan, M. Marinelli, T. Markovič, L. Marot, C. Marren, S. Marsden, S. Marsen, J. Marsh, R. Marshall, L. Martellucci, A.J. Martin, C. Martin, R. Martone, S. Maruyama, M. Maslov, M. Mattei, G.F. Matthews, D. Matveev, E. Matveeva, A. Mauriya, F. Maviglia, M. Mayer, M.-L. Mayoral, S. Mazzi, C. Mazzotta, R. McAdams, P.J. McCarthy, P. McCullen, R. McDermott, D.C. McDonald, D. McGuckin, V. McKay, L. McNamee, A. McShee, D. Mederick, M. Medland, S. Medley, K. Meghani, A.G. Meigs, S. Meitner, S. Menmuir, K. Mergia, S. Mianowski, P. Middleton, J. Mietelski, K. Mikszuta-Michalik, D. Milanesio, E. Milani, E. Militello-Asp, F. Militello, J. Milnes, A. Milocco, S. Minucci, I. Miron, J. Mitchell, J. Mlynář, V. Moiseenko, P. Monaghan, I. Monakhov, A. Montisci, S. Moon, R. Mooney, S. Moradi, R.B. Morales, L. Morgan, F. Moro, J. Morris, T. Mrowetz, L. Msero, S. Munot, A. Muñoz-Perez, M. Muraglia, A. Murari, A. Muraro, B. N’Konga, Y.S. Na, F. Nabais, R. Naish, F. Napoli, E. Nardon, V. Naulin, M.F.F. Nave, R. Neu, S. Ng, M. Nicassio, D. Nicolai, A.H. Nielsen, S.K. Nielsen, D. Nina, C. Noble, C.R. Nobs, M. Nocente, H. Nordman, S. Nowak, H. Nyström, J. O’Callaghan, M. O’Mullane, C. O’Neill, C. Olde, H.J.C. Oliver, R. Olney, J. Ongena, G.P. Orsitto, A. Osipov, R. Otin, N. Pace, L.W. Packer, E. Pajuste, D. Palade, J. Palgrave, O. Pan, N. Panadero, T. Pandya, E. Panontin, A. Papadopoulos, G. Papadopoulos, G. Papp, V.V. Parail, A. Parsloe, K. Paschalidis, M. Passeri, A. Patel, A. Pau, G. Pautasso, R. Pavlichenko, A. Pavone, E. Pawelec, C. Paz-Soldan, A. Peacock, M. Pearce, I.J. Pearson, E. Peluso, C. Penot, K. Pepperell, A. Perdas, T. Pereira, E. Perelli Cippo, C. Perez von Thun, D. Perry, P. Petersson, G. Petravich, N. Petrella, M. Peyman, L. Pigatto, M. Pillon, S. Pinches, G. Pintsuk, C. Piron, A. Pironti, F. Pisano, R. Pitts, U. Planck, N. Platt, V. Plyusnin, M. Podesta, G. Pokol, F.M. Poli, O.G. Pompilian, M. Poradzinski, M. Porkolab, C. Porosnicu, G. Poulipoulis, A.S. Poulsen, I. Predebon, A. Previti, D. Primetzhofer, G. Provatas, G. Pucella, P. Puglia, K. Purahoo, O. Putignano, T. Pütterich, A. Quercia, G. Radulescu, V. Radulovic, R. Ragona, M. Rainford, P. Raj, M. Rasinski, D. Rasmussen, J. Rasmussen, J.J. Rasmussen, A. Raso, G. Rattá, S. Ratynskaia, R. Rayaprolu, M. Rebai, A. Redl, D. Rees, D. Réfy, R. Reichle, H. Reimerdes, B.C.G. Reman, C. Reux, S. Reynolds, D. Rigamonti, E. Righi, F.G. Rimini, J. Risner, J.F. Rivero-Rodriguez, C.M. Roach, J. Roberts, R. Robins, S. Robinson, D. Robson, S. Rode, P. Rodrigues, P. Rodriguez-Fernandez, S. Romanelli, J. Romazanov, E. Rose, C. Rose-Innes, R. Rossi, S. Rowe, D. Rowlands, C. Rowley, M. Rubel, G. Rubinacci, G. Rubino, M. Rud, J. Ruiz Ruiz, F. Ryter, S. Saarelma, A. Sahlberg, M. Salewski, A. Salmi, R. Salmon, F. Salzedas, F. Sanchez, I. Sanders, D. Sandiford, F. Sanni, O. Sauter, P. Sauvan, G. Schettini, A. Shevelev, A.A. Schekochihin, K. Schmid, B.S. Schmidt, S. Schmuck, M. Schneider, P.A. Schneider, N. Schoonheere, R. Schramm, D. Scoon, S. Scully, M. Segato, J. Seidl, L. Senni, J. Seo, G. Sergienko, M. Sertoli, S.E. Sharapov, R. Sharma, A. Shaw, R. Shaw, H. Sheikh, U. Sheikh, N. Shi, P. Shigin, D. Shiraki, G. Sias, M. Siccinio, B. Sieglin, S.A. Silburn, A. Silva, C. Silva, J. Silva, D. Silvagni, D. Simfukwe, J. Simpson, P. Sirén, A. Sirinelli, H. Sjöstrand, N. Skinner, J. Slater, T. Smart, R.D. Smirnov, N. Smith, P. Smith, T. Smith, J. Snell, L. Snoj, E.R. Solano, V. Solokha, C. Sommariva, K. Soni, M. Sos, J. Sousa, C. Sozzi, T. Spelzini, F. Spineanu, L. Spolladore, D. Spong, C. Srinivasan, G. Staebler, A. Stagni, I. Stamatelatos, M.F. Stamp, Ž. Štancar, P.A. Staniec, G. Stankūnas, M. Stead, B. Stein-Lubrano, A. Stephen, J. Stephens, P. Stevenson, C. Steventon, M. Stojanov, D.A. St-Onge, P. Strand, S. Strikwerda, C.I. Stuart, S. Sturgeon, H.J. Sun, S. Surendran, W. Suttrop, J. Svensson, J. Svoboda, R. Sweeney, G. Szepesi, M. Szoke, T. Tadić, B. Tal, T. Tala, P. Tamain, K. Tanaka, W. Tang, G. Tardini, M. Tardocchi, D. Taylor, A.S. Teimane, G. Telesca, A. Teplukhina, A. Terra, D. Terranova, N. Terranova, D. Testa, B. Thomas, V.K. Thompson, A. Thorman, A.S. Thrysoe, W. Tierens, R.A. Tinguely, A. Tipton, H. Todd, M. Tomeš, A. Tookey, P. Tsavalas, D. Tskhakaya, L.-P. Turică, A. Turner, I. Turner, M. Turner, M.M. Turner, G. Tvalashvili, A. Tykhyy, S. Tyrrell, A. Uccello, V. Udintsev, A. Vadgama, D.F. Valcarcel, A. Valentini, M. Valisa, M. Vallar, M. Valovic, M. Van Berkel, K.L. van de Plassche, M. van Rossem, D. Van Eester, J. Varela, J. Varje, T. Vasilopoulou, G. Vayakis, M. Vecsei, J. Vega, M. Veis, P. Veis, S. Ventre, M. Veranda, G. Verdoolaege, C. Verona, G. Verona Rinati, E. Veshchev, N. Vianello, E. Viezzer, L. Vignitchouk, R. Vila, R. Villari, F. Villone, P. Vincenzi, A. Vitins, Z. Vizvary, M. Vlad, I. Voldiner, U. Von Toussaint, P. Vondráček, B. Wakeling, M. Walker, R. Walker, M. Walsh, R. Walton, E. Wang, F. Warren, R. Warren, J. Waterhouse, C. Watts, T. Webster, M. Weiland, H. Weisen, M. Weiszflog, N. Wendler, A. West, M. Wheatley, S. Whetham, A. Whitehead, D. Whittaker, A. Widdowson, S. Wiesen, M. Willensdorfer, J. Williams, I. Wilson, T. Wilson, M. Wischmeier, A. Withycombe, D. Witts, A. Wojcik-Gargula, E. Wolfrum, R. Wood, R. Woodley, R. Worrall, I. Wyss, T. Xu, D. Yadykin, Y. Yakovenko, Y. Yang, V. Yanovskiy, R. Yi, I. Young, R. Young, B. Zaar, R.J. Zabolockis, L. Zakharov, P. Zanca, A. Zarins, D. Zarzoso Fernandez, K.-D. Zastrow, Y. Zayachuk, M. Zerbini, W. Zhang, B. Zimmermann, M. Zlobinski, A. Zocco, V.K. Zotta, M. Zuin, W. Zwingmann, and I. Zychor

Subjects
magnetic fusion, JET-ILW, D–T, tritium, alpha particles, fusion prediction, Nuclear and particle physics. Atomic energy. Radioactivity, QC770-798
Abstract

In 2021 JET exploited its unique capabilities to operate with T and D–T fuel with an ITER-like Be/W wall (JET-ILW). This second major JET D–T campaign (DTE2), after DTE1 in 1997, represented the culmination of a series of JET enhancements—new fusion diagnostics, new T injection capabilities, refurbishment of the T plant, increased auxiliary heating, in-vessel calibration of 14 MeV neutron yield monitors—as well as significant advances in plasma theory and modelling in the fusion community. DTE2 was complemented by a sequence of isotope physics campaigns encompassing operation in pure tritium at high T-NBI power. Carefully conducted for safe operation with tritium, the new T and D–T experiments used 1 kg of T (vs 100 g in DTE1), yielding the most fusion reactor relevant D–T plasmas to date and expanding our understanding of isotopes and D–T mixture physics. Furthermore, since the JET T and DTE2 campaigns occurred almost 25 years after the last major D–T tokamak experiment, it was also a strategic goal of the European fusion programme to refresh operational experience of a nuclear tokamak to prepare staff for ITER operation. The key physics results of the JET T and DTE2 experiments, carried out within the EUROfusion JET1 work package, are reported in this paper. Progress in the technological exploitation of JET D–T operations, development and validation of nuclear codes, neutronic tools and techniques for ITER operations carried out by EUROfusion (started within the Horizon 2020 Framework Programme and continuing under the Horizon Europe FP) are reported in (Litaudon et al Nucl. Fusion accepted), while JET experience on T and D–T operations is presented in (King et al Nucl. Fusion submitted).

Published
2024
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2. The influence of D2 pressure on D retention and release from Be co-deposits

Author

M.J. Baldwin, A. Založnik, M.J. Simmonds, G. De Temmerman, and R.P. Doerner

Subjects
Beryllium, Co-deposits, Retention, Thermal desorption, Pisces, Nuclear engineering. Atomic power, TK9001-9401
Abstract

Beryllium co-deposit thermal desorption studies are reported that focus on the effect of D2pressure during layer formation, as pressure has been linked in prior work to the formation of a high-retention-capacity sharp-release-feature. A pressure range from 0.3 to 13.3 Pa is explored. Additional insight into what drives the formation of T0is established through co-deposit formation parameter variations including deposition temperature spanning 373 K to 608 K, and ion impact energy in the range 10–100 eV. It is found that the formation of the sharp release feature exhibits a multi-parameter dependence, but is predominately favoured by low deposition temperature, higher D2pressure, and to a small degree, increased ion impact energy, during deposition. TESSIM simulations of the D2thermal release at the ITER bake temperatures of Tb1(513 K) and Tb2(623 K), show that the best efficacy for D removal (defined as the ratio of post to pre bake inventory) is found when the sharp release feature is present. However, when this feature is present, the total retained D inventory tends to be significantly increased.

Published
2021
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3. Very high-resolution infrared imagery of misaligned tungsten monoblock edge heating in the WEST tokamak

Author

A. Grosjean, Y. Corre, J. Gaspar, J.P. Gunn, S. Carpentier, X. Courtois, R. Dejarnac, E. Delmas, G. De Temmerman, M. Diez, L. Dubus, L. Dupont, F. Escourbiac, M. Firdaouss, J. Gerardin, M. Houry, R. Pitts, C. Pocheau, and E. Tsitrone

Subjects
Tungsten, Monoblock, WEST, Infrared, Heat flux, Emissivity, Nuclear engineering. Atomic power, TK9001-9401
Abstract

Fourteen ITER-like plasma-facing units (PFUs) made of bulk tungsten were installed in the WEST tokamak divertor. Five of which were misaligned with their poloidal leading edges (LEs) exposed to the plasma heat flux: two sharp-edge PFUs and three chamfered PFUs (vertical misalignment h = 0.30 ± 0.1 mm). The parallel heat flux is measured on the outer strike point with a very high-resolution (VHR) infrared camera, featuring a sub-millimeter spatial resolution (~0.1 mm/pixel). A Medium Wavelength IR filter (MWIR) was used to lower the temperature detection threshold (Tthreshold,BB ≈ 250 °C) and extend the IR analysis to the full toroidal Monoblock (MB) length on both outer (OSP) and inner (ISP) strike points. The parallel heat flux derived from the VHR data (~70 MW/m2) is consistent with previous analysis and other measurements (Thermocouple and Fiber Bragg Grating) at the maximum heat flux location (OSP). This corresponds to real temperatures of about 1000 °C on the LE. Values obtained on the LE of the ISP are typically lower than of the OSP by a factor of two. However, a significant discrepancy between modeling and measurement is observed along with the toroidal temperature profile, with a temperature drop in the first 5 mm after the LEs. Visual and microscopic analysis performed on the component show clear evidence of surface state modification caused by plasma exposure: the presence of cracks on the LE, polished surface in its vicinity, and rougher surfaces further away from the LE.

Published
2021
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4. A growth/annealing equilibrium model for helium-induced nanostructure with application to ITER

Author

G. De Temmerman, R.P. Doerner, and R.A. Pitts

Subjects
Nuclear engineering. Atomic power, TK9001-9401
Abstract

It is now well-known that under exposure to a helium (He) plasma at elevated temperatures, a tungsten (W) surface is modified by the growth of a fibreform nano-structure referred to as “fuzz”. Formation of W fuzz occurs when a specific set of conditions are met and raises concerns for the behaviour of the ITER W divertor targets. The key open question remains, however, of whether or not fuzz will actually form in ITER.An analysis of existing data shows that the fuzz annealing kinetics can be described by a diffusive-like kinetics law. A growth/annealing equilibrium model is then proposed to take into account Edge Localized Mode (ELM)-induced erosion and the effect of the transient temperature excursion on fuzz growth and annealing. In addition, both the decrease of fuzz erosion rate and thermal conductivity with increasing thickness are treated consistently. The main finding is that as fuzz grows thicker, its thermal conductivity decreases and peak temperature attained during an ELM increases. Given the competition between growth and annealing rates, an equilibrium thickness exists above which fuzz annealing dominates for a given ELM energy density. In the absence of ELMs, the fuzz thickness would increase with the typical t0.5 time dependence. PACS: PSI-23, Keywords: Helium, Tungsten, ITER, Nanostructure, Fuzz

Published
2019
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5. Numerical simulation by finite element modelling of diffusion and transient hydrogen trapping processes in plasma facing components

Author

S. Benannoune, Y. Charles, J. Mougenot, M. Gaspérini, and G. De Temmerman

Subjects
Nuclear engineering. Atomic power, TK9001-9401
Abstract

In order to simulate hydrogen charging and discharging cycles of mechanically loaded structures full 3D Macroscopic Rate Equation (MRE) modelling is proposed based on a finite element method (FEM). The model, implemented in the 3DS Abaqus software, uses a generalized transport equation, which accounts for mechanical fields, hydrogen transport and trapping, and their evolution with time. The influence of a-priori known thermal field has also been included. To ensure the solution convergence and the numerical stability, the trapping kinetic is introduced by using an approximation of the analytical solution the McNabb and Foster equation. Comparisons with a relevant 1D MRE code and with thermal programmed desorption (TPD) experimental results are performed on a 1D configuration to validate the model. Next, the model is used to simulate the tritium diffusion and trapping in a 2D geometry of interest in the upper plug of ITER tokamak, and results of tritium inventory are compared with an equivalent 1D calculation. Keywords: Hydrogen, Kinetic trapping, Modelling, Finite elements, Abaqus, User subroutine, Macroscopic Rate Equations

Published
2019
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6. Laser-Induced Desorption of co-deposited Deuterium in Beryllium Layers on Tungsten

Author

M. Zlobinski, G. Sergienko, Y. Martynova, D. Matveev, B. Unterberg, S. Brezinsek, B. Spilker, D. Nicolai, M. Rasinski, S. Möller, Ch. Linsmeier, C.P. Lungu, C. Porosnicu, P. Dinca, and G. De Temmerman

Subjects
Nuclear engineering. Atomic power, TK9001-9401
Abstract

For the development of the tritium monitoring system in ITER the hydrogen isotope release by Laser-Induced Desorption (LID) from Be layers is studied to determine the laser parameters for a high desorption efficiency while minimising dust production and surface modifications is also pursued. Be layers of 1 µm thickness with 25–30 at% D and 3 × 1022 D/m2 comparable to JET-ILW areal concentrations [1] have been produced by High Power Impulse Magnetron Sputtering (HiPIMS) on ITER grade W. Laser pulses of 1, 5 and 10 ms duration heat the layer in vacuum in the Fuel REtention DIagnostic Setup (FREDIS) and release the retained D thermally. By mass spectrometry in FREDIS and subsequent Nuclear Reaction Analysis (NRA) inside the laser spot the desorbed and remaining D is quantified. While a pulse duration of 1 ms cannot fully desorb the deuterium, it is found that a single 5 or 10 ms laser pulse with an absorbed energy density of ca. 1.5 MJ/m2 corresponding to a heat flux factor around 20 MW√s/m2 leads to nearly complete desorption of the retained D. This encourages the development of a useful tritium monitoring system, although the present layers produce some dust due to local delamination of the layer on at least 11% of the heated surface (at 1.4 MJ/m2 absorbed energy within 5 ms) and lead to unavoidable crack formation. Keywords: Fuel retention, Beryllium, Tritium monitoring, Laser, Desorption, FREDIS

Published
2019
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7. Beryllium layer response to ITER-like ELM plasma pulses in QSPA-Be

Author

N.S. Klimov, V.L. Podkovyrov, I.B. Kupriyanov, J. Linke, R.A. Pitts, V.M. Safronov, D.V. Kovalenko, Th. Loewenhoff, C.P. Lungu, G. Pintsuk, G. De Temmerman, A.D. Muzichenko, A.A. Markin, P.N. Taratorkin, N.E. Zabirova, and A.M. Zhitlukhin

Subjects
Nuclear engineering. Atomic power, TK9001-9401
Abstract

Material migration in ITER is expected to move beryllium (Be) eroded from the first wall primarily to the tungsten (W) divertor region and to magnetically shadowed areas of the wall itself. This paper is concerned with experimental study of Be layer response to ELM-like plasma pulses using the new QSPA-Be plasma gun (SRC RF TRINITI). The Be layers (1→50µm thick) are deposited on special castellated Be and W targets supplied by the ITER Organization using the Thermionic Vacuum Arc technique. Transient deuterium plasma pulses with duration ∼0.5ms were selected to provide absorbed energy densities on the plasma stream axis for a 30° target inclination of 0.2 and 0.5MJm−2, the first well below and the second near the Be melting point. This latter value is close to the prescribed maximum energy density for controlled ELMs on ITER. At 0.2MJm−2 on W, all Be layer thicknesses tested retain their integrity up to the maximum pulse number, except at local defects (flakes, holes and cracks) and on tile edges. At 0.5MJm−2 on W, Be layer melting and melt layer agglomeration are the main damage processes, they happen immediately in the first plasma impact. Melt layer movement was observed only near plasma facing edges. No significant melt splashing is observed in spite of high plasma pressure (higher than expected in ITER). Be layer of 10µm thick on Be target has higher resistance to plasma irradiation than 1 and 55µm, and retain their integrity up to the maximum pulse number at 0.2MJm−2. For 1µm and 55µm thick on Be target significant Be layer losses were observed at 0.2MJm−2. Keywords: ITER, High heat flux, Thermal shock, Beryllium, Tungsten, Coating

Published
2017
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8. Mechanical properties of tungsten following rhenium ion and helium plasma exposure

Author

C.S. Corr, S. O'Ryan, C. Tanner, M. Thompson, J.E. Bradby, G. De Temmerman, R.G. Elliman, P. Kluth, and D. Riley

Subjects
Nuclear engineering. Atomic power, TK9001-9401
Abstract

Mechanical properties of Tungsten (W) samples irradiated with 2 MeV Rhenium (Re) ions and helium (He) plasma were investigated using nanoindentation. It was found that there was an increase in hardness for all samples following separate irradiation with both Re ion and He plasma. A slight increase in hardness was obtained for combined exposures. A comparable increase in hardness was observed for a pure He plasma with a sample temperature of 473 K and 1273 K. Optical interferometry was employed to compare surface modification of the samples. Grazing incidence small angle x-ray scattering confirmed He nano-bubble formation of approximately 1 nm diameter in the higher temperature sample, which was not observed with samples at the lower temperatures.

Published
2017
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9. Physics conclusions in support of ITER W divertor monoblock shaping

Author

R.A. Pitts, S. Bardin, B. Bazylev, M.A. van den Berg, P. Bunting, S. Carpentier-Chouchana, J.W. Coenen, Y. Corre, R. Dejarnac, F. Escourbiac, J. Gaspar, J.P. Gunn, T. Hirai, S-H. Hong, J. Horacek, D. Iglesias, M. Komm, K. Krieger, C. Lasnier, G.F. Matthews, T.W. Morgan, S. Panayotis, S. Pestchanyi, A. Podolnik, R.E. Nygren, D.L. Rudakov, G. De Temmerman, P. Vondracek, and J.G. Watkins

Subjects
Nuclear engineering. Atomic power, TK9001-9401
Abstract

The key remaining physics design issue for the ITER tungsten (W) divertor is the question of monoblock (MB) front surface shaping in the high heat flux target areas of the actively cooled targets. Engineering tolerance specifications impose a challenging maximum radial step between toroidally adjacent MBs of 0.3mm. Assuming optical projection of the parallel heat loads, magnetic shadowing of these edges is required if quasi-steady state melting is to be avoided under certain conditions during burning plasma operation and transiently during edge localized mode (ELM) or disruption induced power loading. An experiment on JET in 2013 designed to investigate the consequences of transient W edge melting on ITER, found significant deficits in the edge power loads expected on the basis of simple geometric arguments, throwing doubt on the understanding of edge loading at glancing field line angles. As a result, a coordinated multi-experiment and simulation effort was initiated via the International Tokamak Physics Activity (ITPA) and through ITER contracts, aimed at improving the physics basis supporting a MB shaping decision from the point of view both of edge power loading and melt dynamics. This paper reports on the outcome of this activity, concluding first that the geometrical approximation for leading edge power loading on radially misaligned poloidal leading edges is indeed valid. On this basis, the behaviour of shaped and unshaped monoblock surfaces under stationary and transient loads, with and without melting, is compared in order to examine the consequences of melting, or power overload in context of the benefit, or not, of shaping. The paper concludes that MB top surface shaping is recommended to shadow poloidal gap edges in the high heat flux areas of the ITER divertor targets. Keywords: ITER, Tungsten, Divertor, Shaping, Melting, MEMOS

Published
2017
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10. Remobilization of tungsten dust from castellated plasma-facing components

Author

M. De Angeli, P. Tolias, S. Ratynskaia, D. Ripamonti, G. Riva, S. Bardin, T. Morgan, and G. De Temmerman

Subjects
Nuclear engineering. Atomic power, TK9001-9401
Abstract

Studies of tungsten dust remobilization from castellated plasma-facing components can shed light to whether gaps constitute a dust accumulation site with important implications for monitoring but also removal. Castellated structures of ITER relevant geometry that contained pre-adhered tungsten dust of controlled deposition profile have been exposed in the Pilot-PSI linear device. The experiments were performed under steady state and transient plasma conditions, as well as varying magnetic field topologies. The results suggest that dust remobilization from the plasma-facing monoblock surface can enhance dust trapping in the gaps and that tungsten dust is efficiently trapped inside the gaps.

Published
2017
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11. Plasma pressure and particle loss studies in the Pilot-PSI high flux linear plasma generator

Author

K. Ješko, H.J. van der Meiden, J.P. Gunn, J.W.M. Vernimmen, and G. De Temmerman

Subjects
Nuclear engineering. Atomic power, TK9001-9401
Abstract

Plasma detachment in tokamak divertors reduces the particle and power fluxes to the plasma facing components and is essential for successful operation of ITER. The linear plasma generator Pilot-PSI can produce a high density (∼1021 m−3), low temperature (∼1eV) plasma which is similar to that expected at the ITER divertor strike-points during the partially detached regime [1]. Given the simple geometry of the device, Pilot-PSI allows to diagnose the plasma beam at multiple axial positions. In this study, the incoherent Thomson scattering (TS) diagnostic [2] is exploited to measure the radial plasma Te and ne profiles at two locations of the hydrogen plasma beam: near the plasma source (upstream) and 2cm from the target plate. At the target, the TS measurements are supported by an embedded Langmuir probe. These measurements prove the existence of parallel plasma pressure loss as well as particle loss, confirming that physical processes believed to cause detachment in tokamak divertors also hold in Pilot-PSI (ion-neutral friction, volume recombination). It is found that the fractional reduction of the plasma pressure varies between ∼4 and ∼5000, depending strongly on the pressure of the background neutrals. The importance of individual loss channels is discussed. Keywords: Detachment, Pilot-PSI, Langmuir probe, Thomson scattering, Divertor, Volume recombination

Published
2017
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12. Efficiency of thermal outgassing for tritium retention measurement and removal in ITER

Author

G. De Temmerman, M.J. Baldwin, D. Anthoine, K. Heinola, A. Jan, I. Jepu, J. Likonen, C.P. Lungu, C. Porosnicu, and R.A. Pitts

Subjects
Nuclear engineering. Atomic power, TK9001-9401
Abstract

As a licensed nuclear facility, ITER must limit the in-vessel tritium (T) retention to reduce the risks of potential release during accidents, the inventory limit being set at 1kg. Simulations and extrapolations from existing experiments indicate that T-retention in ITER will mainly be driven by co-deposition with beryllium (Be) eroded from the first wall, with co-deposits forming mainly in the divertor region but also possibly on the first wall itself. A pulsed Laser-Induced Desorption (LID) system, called Tritium Monitor, is being designed to locally measure the T-retention in co-deposits forming on the inner divertor baffle of ITER. Regarding tritium removal, the baseline strategy is to perform baking of the plasma-facing components, at 513K for the FW and 623K for the divertor. Both baking and laser desorption rely on the thermal desorption of tritium from the surface, the efficiency of which remains unclear for thick (and possibly impure) co-deposits. This contribution reports on the results of TMAP7 studies of this efficiency for ITER-relevant deposits. keywords: Tritium retention, ITER, Divertor, Outgassing

Published
2017
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13. Surface modification of He pre-exposed tungsten samples by He plasma impact in the divertor manipulator of ASDEX Upgrade

Author

S. Brezinsek, A. Hakola, H. Greuner, M. Balden, A. Kallenbach, M. Oberkofler, G. De Temmerman, D. Douai, A. Lahtinen, B. Böswirth, D. Brida, R. Caniello, D. Carralero, S. Elgeti, K. Krieger, H. Mayer, G. Meisl, S. Potzel, V. Rohde, B. Sieglin, A. Terra, R. Neu, and Ch. Linsmeier

Subjects
Nuclear engineering. Atomic power, TK9001-9401
Abstract

Tungsten (W) will be used as material for plasma-facing components (PFCs) in the divertor of ITER and interact with Helium (He) ions either from initial He plasma operation or from Deuterium-Tritium (DT) fusion reactions in the active operation phase. Laboratory experiments reported that in a specific operational window of impact energy, ion fluence, and surface temperature (Ein ≥ 20 eV, ϕ ≥ 1 × 1024 He+mBt=2.5T,Ip=0.8MA,Paux≃8.0MW Tsurf ≥ 1000 K) a modification of W surfaces occurs resulting in the formation of He-induced W nanostructures. Experiments in ASDEX Upgrade H-mode plasmas (Ein=37keV T, ϕ≃0.75×1024He0m−2 MA, Paux ≃ 8.0 MW) in He have been carried out to investigate in detail (a) the potential growth of W nanostructures on pre-damaged W samples incorporating He nanobubbles, and (b) the potential ELM-induced erosion of W nanostructure. Both W surface modifications were generated artificially in the GLADIS facility by He bombardment of W samples at ϕ≃1×1024He0m−2 keV (a) to ϕ ≃ 0.75 × 1024 He0mϕ≃1.6×1024He+m−2 at Tsurf ≃ 1800 K and (b) ϕ ≃ 1 × 1024 He0m−2 at Tsurf ≃ 2300 K prior to exposure in the divertor manipulator of ASDEX Upgrade. Though in part (a) conditions of W nanostructure growth with a total He ion fluence of ϕ ≃ 1.6 × 1024 He+m−2 and peak He ion impact energies above 150 eV were met, no growth could be detected. In part (b) lower density plasmas with more pronounced type I ELMs, carrying energetic He ions in the keV range, were executed with the strike-line positioned on 2 µm thick W nanostructure accumulating a fluence of ϕ ≃ 0.8 × 1024 He+m−2. Post-mortem analysis revealed that co-deposition by predominantly W, and Boron (B), eroded at the main chamber wall and transported into the divertor, took place on all W samples. Erosion of W nanostructure or its formation was hindered by the fact that the outer divertor at the location of the samples was turned under these He plasma conditions into a net deposition zone by W, B and Carbon (C) ions. The surface morphology with large roughness and effective surface area act as a catcher for the impinging impurities. Thus, apart from operation in the existence diagram of W nanostructure with respect to Tsurf, ϕ, and Ein, also the impinging impurity flux contribution needs to be considered in predictions concerning the formation of W nanostructures. Keywords: PSI, ASDEX Upgrade, ITER, W divertor, W nanostructure, Helium

Published
2017
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14. Tungsten dust remobilization under steady-state and transient plasma conditions

Author

S. Ratynskaia, P. Tolias, M. De Angeli, V. Weinzettl, J. Matejicek, I. Bykov, D.L. Rudakov, L. Vignitchouk, E. Thorén, G. Riva, D. Ripamonti, T. Morgan, R. Panek, and G. De Temmerman

Subjects
Nuclear engineering. Atomic power, TK9001-9401
Abstract

Remobilization is one of the most prominent unresolved fusion dust-relevant issues, strongly related to the lifetime of dust in plasma-wetted regions, the survivability of dust on hot plasma-facing surfaces and the formation of dust accumulation sites. A systematic cross-machine study has been initiated to investigate the remobilization of tungsten micron-size dust from tungsten surfaces implementing a newly developed technique based on controlled pre-adhesion by gas dynamics methods. It has been utilized in a number of devices and has provided new insights on remobilization under steady-state and transient conditions. The experiments are interpreted with contact mechanics theory and heat conduction models.

Published
2017
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15. Characterization and origin of large size dust particles produced in the Alcator C-Mod tokamak

Author

C. Arnas, J. Irby, S. Celli, G. De Temmerman, Y. Addab, L. Couëdel, C. Grisolia, Y. Lin, C. Martin, C. Pardanaud, and S. Pierson

Subjects
Dust formation, Molybdenum, Tungsten, Boron, Alloy, Nuclear engineering. Atomic power, TK9001-9401
Abstract

Post mortem analyses of dust collected in Alcator C-Mod have highlighted a production of large size dust particles. The quantities of such large particles are higher than in any other tokamak. They are divided in two classes as a function of their shape and consequently, their origin. Rounded dust particles such as spheres and splashes constitute the first class. These particles are the result of high heat loads on various leading edges of plasma facing components and possibly, their melting during plasma operation. The heated or already molten material can be destabilized during disruptions and droplets are emitted across the vacuum chamber. After solidification, the resulting rounded particles are either in pure elements or in alloys. Flake-like dust particles, which are mainly due to light material coating delamination, constitute the second class of dust particles.

Published
2017
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16. WallDYN simulations of material migration and fuel retention in ITER low power H plasmas and high power neon-seeded DT plasmas

Author

A. Khan, G. De Temmerman, S.W. Lisgo, X. Bonnin, H. Anand, M.A. Miller, R.A. Pitts, K. Schmid, and A.S. Kukushkin

Subjects
Nuclear engineering. Atomic power, TK9001-9401
Abstract

Deposition and fuel retention profiles in low power hydrogen L-mode plasmas and neon (Ne) seeded ITER DT burning plasmas have been investigated. Two different Ne seeded plasma backgrounds with varying sub-divertor neutral pressures but the same Ne impurity concentration are considered, representing high recycling and partially detached divertor solutions. The 2D SOLPS numerical grid does not extend all the way to the wall surfaces so that an extrapolation of the plasma background is required and is performed using a second simulation stage in which the far scrape-off layer (SOL) region is numerically gridded and plasma transport solved on the extended grid using the OSM (a 1D simplified Braginski code) approach [1]. The plasma conditions chosen for this far SOL region strongly influence the results. The hydrogenic flux is calculated from the electronic density and ion flow, the latter of which has an assumed distribution. Depending on the main-SOL plasma flow parameters and far-SOL density, fuel retention is driven by deposition on the first wall (when parallel flow through the main-SOL is switched off), or by deposition on the divertor (parallel flow through the main-SOL is switched on). When retention is dominated by deposition on the first wall, there is slightly more retention in the partially detached case compared to a high recycling scenario. In the low power cases, there is insignificant deposition and fuel retention.

Published
2019
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17. Accumulation of beryllium dust in ITER diagnostic ports after off-normal events

Author

L. Vignitchouk, S. Ratynskaia, P. Tolias, R.A. Pitts, G. De Temmerman, M. Lehnen, and D. Kiramov

Subjects
Nuclear engineering. Atomic power, TK9001-9401
Abstract

Dust transport simulations are used to predict the effect of diagnostic ports on the in-vessel inventory of solid beryllium particles produced during mitigated disruptions in ITER. Beryllium dust is assumed to originate from the re-solidification of liquid droplets, which are initially ejected during transient first-wall melting events and subsequently interact with the disrupting plasma. The trajectories of droplets launched with various initial conditions, as well as the time evolution of their temperature and mass, are simulated until either complete vaporization or immobilization upon undergoing a sticking or splashing impact with the wall is realized. The results indicate that approximately 10% of the dust mass in the vessel can be expected to reside inside ports, in particular those located in the equatorial plane or in the lower outboard first wall. Keywords: Beryllium, Dust, Droplets, Disruptions

Published
2019
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18. Physics basis for the first ITER tungsten divertor

Author

R.A. Pitts, X. Bonnin, F. Escourbiac, H. Frerichs, J.P. Gunn, T. Hirai, A.S. Kukushkin, E. Kaveeva, M.A. Miller, D. Moulton, V. Rozhansky, I. Senichenkov, E. Sytova, O. Schmitz, P.C. Stangeby, G. De Temmerman, I. Veselova, and S. Wiesen

Subjects
Nuclear engineering. Atomic power, TK9001-9401
Abstract

On the eve of component procurement, this paper discusses the present physics basis for the first ITER tungsten (W) divertor, beginning with a reminder of the key elements defining the overall design, and outlining relevant aspects of the Research Plan accompanying the new “staged approach” to ITER nuclear operations which fixes the overall divertor lifetime constraint. The principal focus is on the main design driver, steady state power fluxes in the DT phases, obtained from simulations using the 2-D SOLPS-4.3 and SOLPS-ITER plasma boundary codes, assuming the use of the low Z seeding impurities nitrogen (N) and neon (Ne). A new perspective on the simulation database is adopted, concentrating purely on the divertor physics aspects rather than on the core-edge integration, which has been studied extensively in the course of the divertor design evolution and is published elsewhere. Emphasis is placed on factors which may increase the peak steady state loads: divertor target shaping for component misalignment protection, the influence of fluid drifts, and the consequences of narrow scrape-off layer heat flux channels. All tend to push the divertor into an operating space at higher sub-divertor neutral pressure in order to remain at power flux densities acceptable for the target material. However, a revised criterion for the maximum tolerable loads based on avoidance of W recrystallization, sets an upper limit potentially ∼50% higher than the previously accepted value of ∼10 MW m−2, a consequence both of the choice of material and the finalized component design. Although the simulation database is currently restricted to the 2-D toroidally symmetric situation, considerable progress is now also being made using the EMC3-Eirene 3-D code suite for the assessment of power loading in the presence of magnetic perturbations for ELM control. Some new results for low input power corresponding to the early H-mode operation phases are reported, showing that even if realistic plasma screening is taken into account, significant asymmetric divertor heat fluxes may arise far from the unperturbed strike point. The issue of tolerable limits for transient heat pulses is an open and key question. A new scaling for ELM power deposition has shown that whilst there may be more latitude for operation at higher current without ELM control, the ultimate limit is likely to be set more by material fatigue under large numbers of sub-threshold melting events. Keywords: ITER, Tungsten, Divertor, Heat fluxes, SOLPS

Published
2019
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19. Global scaling of the heat transport in fusion plasmas

Author

Sara Moradi, Johan Anderson, Michele Romanelli, Hyun-Tae Kim, JET contributors, X. Litaudon, S. Abduallev, M. Abhangi, P. Abreu, M. Afzal, K. M. Aggarwal, T. Ahlgren, J. H. Ahn, L. Aho-Mantila, N. Aiba, M. Airila, R. Albanese, V. Aldred, D. Alegre, E. Alessi, P. Aleynikov, A. Alfier, A. Alkseev, M. Allinson, B. Alper, E. Alves, G. Ambrosino, R. Ambrosino, L. Amicucci, V. Amosov, E. Andersson Sundén, M. Angelone, M. Anghel, C. Angioni, L. Appel, C. Appelbee, P. Arena, M. Ariola, H. Arnichand, S. Arshad, A. Ash, N. Ashikawa, V. Aslanyan, O. Asunta, F. Auriemma, Y. Austin, L. Avotina, M. D. Axton, C. Ayres, M. Bacharis, A. Baciero, D. Baião, S. Bailey, A. Baker, I. Balboa, M. Balden, N. Balshaw, R. Bament, J. W. Banks, Y. F. Baranov, M. A. Barnard, D. Barnes, M. Barnes, R. Barnsley, A. Baron Wiechec, L. Barrera Orte, M. Baruzzo, V. Basiuk, M. Bassan, R. Bastow, A. Batista, P. Batistoni, R. Baughan, B. Bauvir, L. Baylor, B. Bazylev, J. Beal, P. S. Beaumont, M. Beckers, B. Beckett, A. Becoulet, N. Bekris, M. Beldishevski, K. Bell, F. Belli, M. Bellinger, É. Belonohy, N. Ben Ayed, N. A. Benterman, H. Bergsȧker, J. Bernardo, M. Bernert, M. Berry, L. Bertalot, C. Besliu, M. Beurskens, B. Bieg, J. Bielecki, T. Biewer, M. Bigi, P. Bìlkovà, F. Binda, A. Bisoffi, J. P. S. Bizarro, C. Björkas, J. Blackburn, K. Blackman, T. R. Blackman, P. Blanchard, P. Blatchford, V. Bobkov, A. Boboc, G. Bodnàr, O. Bogar, I. Bolshakova, T. Bolzonella, N. Bonanomi, F. Bonelli, J. Boom, J. Booth, D. Borba, D. Borodin, I. Borodkina, A. Botrugno, C. Bottereau, P. Boulting, C. Bourdelle, M. Bowden, C. Bower, C. Bowman, T. Boyce, C. Boyd, H. J. Boyer, J. M. A. Bradshaw, V. Braic, R. Bravanec, B. Breizman, S. Bremond, P. D. Brennan, S. Breton, A. Brett, S. Brezinsek, M. D. J. Bright, M. Brix, W. Broeckx, M. Brombin, A. Brosawski, D. P. D. Brown, M. Brown, E. Bruno, J. Bucalossi, J. Buch, J. Buchanan, M. A. Buckley, R. Budny, H. Bufferand, M. Bulman, N. Bulmer, P. Bunting, P. Buratti, A. Burckhart, A. Buscarino, A. Busse, N. K. Butler, I. Bykov, J. Byrne, P. Cahyna, G. Calabrò, I. Calvo, Y. Camenen, P. Camp, D. C. Campling, J. Cane, B. Cannas, A. J. Capel, P. J. Card, A. Cardinali, P. Carman, M. Carr, D. Carralero, L. Carraro, B. B. Carvalho, I. Carvalho, P. Carvalho, F. J. Casson, C. Castaldo, N. Catarino, J. Caumont, F. Causa, R. Cavazzana, K. Cave-Ayland, M. Cavinato, M. Cecconello, S. Ceccuzzi, E. Cecil, A. Cenedese, R. Cesario, C. D. Challis, M. Chandler, D. Chandra, C. S. Chang, A. Chankin, I. T. Chapman, S. C. Chapman, M. Chernyshova, G. Chitarin, G. Ciraolo, D. Ciric, J. Citrin, F. Clairet, E. Clark, M. Clark, R. Clarkson, D. Clatworthy, C. Clements, M. Cleverly, J. P. Coad, P. A. Coates, A. Cobalt, V. Coccorese, V. Cocilovo, S. Coda, R. Coelho, J. W. Coenen, I. Coffey, L. Colas, S. Collins, D. Conka, S. Conroy, N. Conway, D. Coombs, D. Cooper, S. R. Cooper, C. Corradino, Y. Corre, G. Corrigan, S. Cortes, D. Coster, A. S. Couchman, M. P. Cox, T. Craciunescu, S. Cramp, R. Craven, F. Crisanti, G. Croci, D. Croft, K. Crombé, R. Crowe, N. Cruz, G. Cseh, A. Cufar, A. Cullen, M. Curuia, A. Czarnecka, H. Dabirikhah, P. Dalgliesh, S. Dalley, J. Dankowski, D. Darrow, O. Davies, W. Davis, C. Day, I. E. Day, M. De Bock, A. de Castro, E. de la Cal, E. de la Luna, G. De Masi, J. L. de Pablos, G. De Temmerman, G. De Tommasi, P. de Vries, K. Deakin, J. Deane, F. Degli Agostini, R. Dejarnac, E. Delabie, N. den Harder, R. O. Dendy, J. Denis, P. Denner, S. Devaux, P. Devynck, F. Di Maio, A. Di Siena, C. Di Troia, P. Dinca, R. Dinca, B. Ding, T. Dittmar, H. Doerk, R. P. Doerner, T. Donné, S. E. Dorling, S. Dormido-Canto, S. Doswon, D. Douai, P. T. Doyle, A. Drenik, P. Drewelow, P. Drews, Ph. Duckworth, R. Dumont, P. Dumortier, D. Dunai, M. Dunne, I. Duran, F. Durodié, P. Dutta, B. P. Duval, R. Dux, K. Dylst, N. Dzysiuk, P. V. Edappala, J. Edmond, A. M. Edwards, J. Edwards, Th. Eich, A. Ekedahl, R. El-Jorf, C. G. Elsmore, M. Enachescu, G. Ericsson, F. Eriksson, J. Eriksson, L. G. Eriksson, B. Esposito, S. Esquembri, H. G. Esser, D. Esteve, B. Evans, G. E. Evans, G. Evison, G. D. Ewart, D. Fagan, M. Faitsch, D. Falie, A. Fanni, A. Fasoli, J. M. Faustin, N. Fawlk, L. Fazendeiro, N. Fedorczak, R. C. Felton, K. Fenton, A. Fernades, H. Fernandes, J. Ferreira, J. A. Fessey, O. Février, O. Ficker, A. Field, S. Fietz, A. Figueiredo, J. Figueiredo, A. Fil, P. Finburg, M. Firdaouss, U. Fischer, L. Fittill, M. Fitzgerald, D. Flammini, J. Flanagan, C. Fleming, K. Flinders, N. Fonnesu, J. M. Fontdecaba, A. Formisano, L. Forsythe, L. Fortuna, E. Fortuna-Zalesna, M. Fortune, S. Foster, T. Franke, T. Franklin, M. Frasca, L. Frassinetti, M. Freisinger, R. Fresa, D. Frigione, V. Fuchs, D. Fuller, S. Futatani, J. Fyvie, K. Gàl, D. Galassi, K. Galazka, J. Galdon-Quiroga, J. Gallagher, D. Gallart, R. Galvão, X. Gao, Y. Gao, J. Garcia, A. Garcia-Carrasco, M. Garca-Munoz, J.-L. Gardarein, L. Garzotti, P. Gaudio, E. Gauthier, D. F. Gear, S. J. Gee, B. Geiger, M. Gelfusa, S. Gerasimov, G. Gervasini, M. Gethins, Z. Ghani, M. Ghate, M. Gherendi, J. C. Giacalone, L. Giacomelli, C. S. Gibson, T. Giegerich, C. Gil, L. Gil, S. Gilligan, D. Gin, E. Giovannozzi, J. B. Girardo, C. Giroud, G. Giruzzi, S. Glöggler, J. Godwin, J. Goff, P. Gohil, V. Goloborod'ko, R. Gomes, B. Goncalves, M. Goniche, M. Goodliffe, A. Goodyear, G. Gorini, M. Gosk, R. Goulding, A. Goussarov, R. Gowland, B. Graham, M. E. Graham, J. P. Graves, N. Grazier, P. Grazier, N. R. Green, H. Greuner, B. Grierson, F. S. Griph, C. Grisolia, D. Grist, M. Groth, R. Grove, C. N. Grundy, J. Grzonka, D. Guard, C. Guérard, C. Guillemaut, R. Guirlet, C. Gurl, H. H. Utoh, L. J. Hackett, S. Hacquin, A. Hagar, R. Hager, A. Hakola, M. Halitovs, S. J. Hall, S. P. Hallworth Cook, C. Hamlyn-Harris, K. Hammond, C. Harrington, J. Harrison, D. Harting, F. Hasenbeck, Y. Hatano, D. R. Hatch, T. D. V. Haupt, J. Hawes, N. C. Hawkes, J. Hawkins, P. Hawkins, P. W. Haydon, N. Hayter, S. Hazel, P. J. L. Heesterman, K. Heinola, C. Hellesen, T. Hellsten, W. Helou, O. N. Hemming, T. C. Hender, M. Henderson, S. S. Henderson, R. Henriques, D. Hepple, G. Hermon, P. Hertout, C. Hidalgo, E. G. Highcock, M. Hill, J. Hillairet, J. Hillesheim, D. Hillis, K. Hizanidis, A. Hjalmarsson, J. Hobirk, E. Hodille, C. H. A. Hogben, G. M. D. Hogeweij, A. Hollingsworth, S. Hollis, D. A. Homfray, J. Horàcek, G. Hornung, A. R. Horton, L. D. Horton, L. Horvath, S. P. Hotchin, M. R. Hough, P. J. Howarth, A. Hubbard, A. Huber, V. Huber, T. M. Huddleston, M. Hughes, G. T. A. Huijsmans, C. L. Hunter, P. Huynh, A. M. Hynes, D. Iglesias, N. Imazawa, F. Imbeaux, M. Imrìŝek, M. Incelli, P. Innocente, M. Irishkin, I. Ivanova-Stanik, S. Jachmich, A. S. Jacobsen, P. Jacquet, J. Jansons, A. Jardin, A. Järvinen, F. Jaulmes, S. Jednoróq, I. Jenkins, C. Jeong, I. Jepu, E. Joffrin, R. Johnson, T. Johnson, Jane Johnston, L. Joita, G. Jones, T. T. C. Jones, K. K. Hoshino, A. Kallenbach, K. Kamiya, J. Kaniewski, A. Kantor, A. Kappatou, J. Karhunen, D. Karkinsky, I. Karnowska, M. Kaufman, G. Kaveney, Y. Kazakov, V. Kazantzidis, D. L. Keeling, T. Keenan, J. Keep, M. Kempenaars, C. Kennedy, D. Kenny, J. Kent, O. N. Kent, E. Khilkevich, H. T. Kim, H. S. Kim, A. Kinch, C. King, D. King, R. F. King, D. J. Kinna, V. Kiptily, A. Kirk, K. Kirov, A. Kirschner, G. Kizane, C. Klepper, A. Klix, P. Knight, S. J. Knipe, S. Knott, T. Kobuchi, F. Köchl, G. Kocsis, I. Kodeli, L. Kogan, D. Kogut, S. Koivuranta, Y. Kominis, M. Köppen, B. Kos, T. Koskela, H. R. Koslowski, M. Koubiti, M. Kovari, E. Kowalska-Strzeciwilk, A. Krasilnikov, V. Krasilnikov, N. Krawczyk, M. Kresina, K. Krieger, A. Krivska, U. Kruezi, I. Ksiazek, A. Kukushkin, A. Kundu, T. Kurki-Suonio, S. Kwak, R. Kwiatkowski, O. J. Kwon, L. Laguardia, A. Lahtinen, A. Laing, N. Lam, H. T. Lambertz, C. Lane, P. T. Lang, S. Lanthaler, J. Lapins, A. Lasa, J. R. Last, E. Laszynska, R. Lawless, A. Lawson, K. D. Lawson, A. Lazaros, E. Lazzaro, J. Leddy, S. Lee, X. Lefebvre, H. J. Leggate, J. Lehmann, M. Lehnen, D. Leichtle, P. Leichuer, F. Leipold, I. Lengar, M. Lennholm, E. Lerche, A. Lescinskis, S. Lesnoj, E. Letellier, M. Leyland, W. Leysen, L. Li, Y. Liang, J. Likonen, J. Linke, Ch. Linsmeier, B. Lipschultz, G. Liu, Y. Liu, V. P. Lo Schiavo, T. Loarer, A. Loarte, R. C. Lobel, B. Lomanowski, P. J. Lomas, J. Lönnroth, J. M. López, J. López-Razola, R. Lorenzini, U. Losada, J. J. Lovell, A. B. Loving, C. Lowry, T. Luce, R. M. A. Lucock, A. Lukin, C. Luna, M. Lungaroni, C. P. Lungu, M. Lungu, A. Lunniss, I. Lupelli, A. Lyssoivan, N. Macdonald, P. Macheta, K. Maczewa, B. Magesh, P. Maget, C. Maggi, H. Maier, J. Mailloux, T. Makkonen, R. Makwana, A. Malaquias, A. Malizia, P. Manas, A. Manning, M. E. Manso, P. Mantica, M. Mantsinen, A. Manzanares, Ph. Maquet, Y. Marandet, N. Marcenko, C. Marchetto, O. Marchuk, M. Marinelli, M. Marinucci, T. Markovic, D. Marocco, L. Marot, C. A. Marren, R. Marshal, A. Martin, Y. Martin, A. Martín de Aguilera, F. J. Martínez, J. R. Martín-Solís, Y. Martynova, S. Maruyama, A. Masiello, M. Maslov, S. Matejcik, M. Mattei, G. F. Matthews, F. Maviglia, M. Mayer, M. L. Mayoral, T. May-Smith, D. Mazon, C. Mazzotta, R. McAdams, P. J. McCarthy, K. G. McClements, O. McCormack, P. A. McCullen, D. McDonald, S. McIntosh, R. McKean, J. McKehon, R. C. Meadows, A. Meakins, F. Medina, M. Medland, S. Medley, S. Meigh, A. G. Meigs, G. Meisl, S. Meitner, L. Meneses, S. Menmuir, K. Mergia, I. R. Merrigan, Ph. Mertens, S. Meshchaninov, A. Messiaen, H. Meyer, S. Mianowski, R. Michling, D. Middleton-Gear, J. Miettunen, F. Militello, E. Militello-Asp, G. Miloshevsky, F. Mink, S. Minucci, Y. Miyoshi, J. Mlynàr, D. Molina, I. Monakhov, M. Moneti, R. Mooney, S. Moradi, S. Mordijck, L. Moreira, R. Moreno, F. Moro, A. W. Morris, J. Morris, L. Moser, S. Mosher, D. Moulton, A. Murari, A. Muraro, S. Murphy, N. N. Asakura, Y. S. Na, F. Nabais, R. Naish, T. Nakano, E. Nardon, V. Naulin, M. F. F. Nave, I. Nedzelski, G. Nemtsev, F. Nespoli, A. Neto, R. Neu, V. S. Neverov, M. Newman, K. J. Nicholls, T. Nicolas, A. H. Nielsen, P. Nielsen, E. Nilsson, D. Nishijima, C. Noble, M. Nocente, D. Nodwell, K. Nordlund, H. Nordman, R. Nouailletas, I. Nunes, M. Oberkofler, T. Odupitan, M. T. Ogawa, T. O'Gorman, M. Okabayashi, R. Olney, O. Omolayo, M. O'Mullane, J. Ongena, F. Orsitto, J. Orszagh, B. I. Oswuigwe, R. Otin, A. Owen, R. Paccagnella, N. Pace, D. Pacella, L. W. Packer, A. Page, E. Pajuste, S. Palazzo, S. Pamela, S. Panja, P. Papp, R. Paprok, V. Parail, M. Park, F. Parra Diaz, M. Parsons, R. Pasqualotto, A. Patel, S. Pathak, D. Paton, H. Patten, A. Pau, E. Pawelec, C. Paz Soldan, A. Peackoc, I. J. Pearson, S.-P. Pehkonen, E. Peluso, C. Penot, A. Pereira, R. Pereira, P. P. Pereira Puglia, C. Perez von Thun, S. Peruzzo, S. Peschanyi, M. Peterka, P. Petersson, G. Petravich, A. Petre, N. Petrella, V. Petrzilka, Y. Peysson, D. Pfefferlé, V. Philipps, M. Pillon, G. Pintsuk, P. Piovesan, A. Pires dos Reis, L. Piron, A. Pironti, F. Pisano, R. Pitts, F. Pizzo, V. Plyusnin, N. Pomaro, O. G. Pompilian, P. J. Pool, S. Popovichev, M. T. Porfiri, C. Porosnicu, M. Porton, G. Possnert, S. Potzel, T. Powell, J. Pozzi, V. Prajapati, R. Prakash, G. Prestopino, D. Price, M. Price, R. Price, P. Prior, R. Proudfoot, G. Pucella, P. Puglia, M. E. Puiatti, D. Pulley, K. Purahoo, Th. Pütterich, E. Rachlew, M. Rack, R. Ragona, M. S. J. Rainford, A. Rakha, G. Ramogida, S. Ranjan, C. J. Rapson, J. J. Rasmussen, K. Rathod, G. Rattà, S. Ratynskaia, G. Ravera, C. Rayner, M. Rebai, D. Reece, A. Reed, D. Réfy, B. Regan, J. Regana, M. Reich, N. Reid, F. Reimold, M. Reinhart, M. Reinke, D. Reiser, D. Rendell, C. Reux, S. D. A. Reyes Cortes, S. Reynolds, V. Riccardo, N. Richardson, K. Riddle, D. Rigamonti, F. G. Rimini, J. Risner, M. Riva, C. Roach, R. J. Robins, S. A. Robinson, T. Robinson, D. W. Robson, R. Roccella, R. Rodionov, P. Rodrigues, J. Rodriguez, V. Rohde, F. Romanelli, M. Romanelli, S. Romanelli, J. Romazanov, S. Rowe, M. Rubel, G. Rubinacci, G. Rubino, L. Ruchko, M. Ruiz, C. Ruset, J. Rzadkiewicz, S. Saarelma, R. Sabot, E. Safi, P. Sagar, G. Saibene, F. Saint-Laurent, M. Salewski, A. Salmi, R. Salmon, F. Salzedas, D. Samaddar, U. Samm, D. Sandiford, P. Santa, M. I. K. Santala, B. Santos, A. Santucci, F. Sartori, R. Sartori, O. Sauter, R. Scannell, T. Schlummer, K. Schmid, V. Schmidt, S. Schmuck, M. Schneider, K. Schöpf, D. Schwörer, S. D. Scott, G. Sergienko, M. Sertoli, A. Shabbir, S. E. Sharapov, A. Shaw, R. Shaw, H. Sheikh, A. Shepherd, A. Shevelev, A. Shumack, G. Sias, M. Sibbald, B. Sieglin, S. Silburn, A. Silva, C. Silva, P. A. Simmons, J. Simpson, J. Simpson-Hutchinson, A. Sinha, S. K. Sipilä, A. C. C. Sips, P. Sirén, A. Sirinelli, H. Sjöstrand, M. Skiba, R. Skilton, K. Slabkowska, B. Slade, N. Smith, P. G. Smith, R. Smith, T. J. Smith, M. Smithies, L. Snoj, S. Soare, E. R. Solano, A. Somers, C. Sommariva, P. Sonato, A. Sopplesa, J. Sousa, C. Sozzi, S. Spagnolo, T. Spelzini, F. Spineanu, G. Stables, I. Stamatelatos, M. F. Stamp, P. Staniec, G. Stankunas, C. Stan-Sion, M. J. Stead, E. Stefanikova, I. Stepanov, A. V. Stephen, M. Stephen, A. Stevens, B. D. Stevens, J. Strachan, P. Strand, H. R. Strauss, P. Ström, G. Stubbs, W. Studholme, F. Subba, H. P. Summers, J. Svensson, L. Swiderski, T. Szabolics, M. Szawlowski, G. Szepesi, T. T. Suzuki, B. Tàl, T. Tala, A. R. Talbot, S. Talebzadeh, C. Taliercio, P. Tamain, C. Tame, W. Tang, M. Tardocchi, L. Taroni, D. Taylor, K. A. Taylor, D. Tegnered, G. Telesca, N. Teplova, D. Terranova, D. Testa, E. Tholerus, J. Thomas, J. D. Thomas, P. Thomas, A. Thompson, C.-A. Thompson, V. K. Thompson, L. Thorne, A. Thornton, A. S. Thrysoe, P. A. Tigwell, N. Tipton, I. Tiseanu, H. Tojo, M. Tokitani, P. Tolias, M. Tomes, P. Tonner, M. Towndrow, P. Trimble, M. Tripsky, M. Tsalas, P. Tsavalas, D. Tskhakaya jun, I. Turner, M. M. Turner, M. Turnyanskiy, G. Tvalashvili, S. G. J. Tyrrell, A. Uccello, Z. Ul-Abidin, J. Uljanovs, D. Ulyatt, H. Urano, I. Uytdenhouwen, A. P. Vadgama, D. Valcarcel, M. Valentinuzzi, M. Valisa, P. Vallejos Olivares, M. Valovic, M. Van De Mortel, D. Van Eester, W. Van Renterghem, G. J. van Rooij, J. Varje, S. Varoutis, S. Vartanian, K. Vasava, T. Vasilopoulou, J. Vega, G. Verdoolaege, R. Verhoeven, C. Verona, G. Verona Rinati, E. Veshchev, N. Vianello, J. Vicente, E. Viezzer, S. Villari, F. Villone, P. Vincenzi, I. Vinyar, B. Viola, A. Vitins, Z. Vizvary, M. Vlad, I. Voitsekhovitch, P. Vondràcek, N. Vora, T. Vu, W. W. Pires de Sa, B. Wakeling, C. W. F. Waldon, N. Walkden, M. Walker, R. Walker, M. Walsh, E. Wang, N. Wang, S. Warder, R. J. Warren, J. Waterhouse, N. W. Watkins, C. Watts, T. Wauters, A. Weckmann, J. Weiland, H. Weisen, M. Weiszflog, C. Wellstood, A. T. West, M. R. Wheatley, S. Whetham, A. M. Whitehead, B. D. Whitehead, A. M. Widdowson, S. Wiesen, J. Wilkinson, J. Williams, M. Williams, A. R. Wilson, D. J. Wilson, H. R. Wilson, J. Wilson, M. Wischmeier, G. Withenshaw, A. Withycombe, D. M. Witts, D. Wood, R. Wood, C. Woodley, S. Wray, J. Wright, J. C. Wright, J. Wu, S. Wukitch, A. Wynn, T. Xu, D. Yadikin, W. Yanling, L. Yao, V. Yavorskij, M. G. Yoo, C. Young, D. Young, I. D. Young, R. Young, J. Zacks, R. Zagorski, F. S. Zaitsev, R. Zanino, A. Zarins, K. D. Zastrow, M. Zerbini, W. Zhang, Y. Zhou, E. Zilli, V. Zoita, S. Zoletnik, and I. Zychor

Subjects
Physics, QC1-999
Abstract

A global heat flux model based on a fractional derivative of plasma pressure is proposed for the heat transport in fusion plasmas. The degree of the fractional derivative of the heat flux, α, is defined through the power balance analysis of the steady state. The model was used to obtain the experimental values of α for a large database of the Joint European Torus (JET) carbon-wall as well as ITER like-wall plasmas. The fractional degrees of the electron heat flux are found to be α

Published
2020
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20. Investigation of plasma wall interactions between tungsten plasma facing components and helium plasmas in the WEST tokamak

Author

E. Tsitrone, B. Pegourie, J.P. Gunn, E. Bernard, V. Bruno, Y. Corre, L. Delpech, M. Diez, D. Douai, A. Ekedahl, N. Fedorczak, A. Gallo, T. Loarer, S. Vartanian, J. Gaspar, M. Le Bohec, F. Rigollet, R. Bisson, S. Brezinsek, T. Dittmar, G. De Temmerman, A. Hakola, T. Wauters, M. Balden, M. Mayer, null WEST Team, CEA Cadarache, Commissariat à l'énergie atomique et aux énergies alternatives (CEA), Institut universitaire des systèmes thermiques industriels (IUSTI), Aix Marseille Université (AMU)-Centre National de la Recherche Scientifique (CNRS), Physique des interactions ioniques et moléculaires (PIIM), Forschungszentrum Jülich GmbH, Institut des Hautes Etudes pour l’Innovation et l’Entrepreneuriat (IHEIE) (IHEIE), Mines Paris - PSL (École nationale supérieure des mines de Paris), Université Paris sciences et lettres (PSL)-Université Paris sciences et lettres (PSL), Laboratory for Plasma Physics (LPP), Ecole Royale Militaire / Koninklijke Militaire School (ERM KMS), Max-Planck-Institut für Plasmaphysik [Garching] (IPP), European Project: 633053,H2020,EURATOM-Adhoc-2014-20,EUROfusion(2014), and WEST Team

Subjects
[PHYS]Physics [physics], Nuclear and High Energy Physics, Tokamak, Materials science, ITER tungsten divertor, chemistry.chemical_element, Plasma, Tungsten, Condensed Matter Physics, law.invention, chemistry, tungsten plasma facing components, WEST tokamak, law, helium tungsten interactions, Atomic physics, ddc:620, Helium
Abstract

ITER will operate with a tungsten divertor, a material featuring surface morphology changes when exposed to helium plasmas, in particular the formation of the so called tungsten fuzz under specific conditions. Investigating interactions between tungsten plasma facing components and helium plasmas in a tokamak environment is therefore a key point to consolidate predictions for the ITER divertor performance and lifetime. To this end, a dedicated helium campaign was performed in the full tungsten WEST tokamak, cumulating ∼2000 s of repetitive L mode discharges. It is shown that conditions for tungsten fuzz formation, as derived from linear devices experiments (incident helium energy E inc > 20 eV, helium fluence >1024 He/m2, surface temperature T surf > 700 °C), were met in the outer strike point (OSP) area of the inertially cooled tungsten divertor elements of WEST. Preliminary inspection of the components after the campaign did not show visible signs of surface modification, but points to significant net erosion in the OSP area. An extensive post mortem analysis is now ongoing to confirm these first indications. These results underline that the complex balance between erosion/redeposition (in particular linked to impurities) and tungsten fuzz formation needs to be taken into account in tokamak conditions.

Published
2022

21. Sticking Probability of Ammonia Molecules on Tungsten and 316L Stainless Steel Surfaces

Author

G. De Temmerman, J.-B. Faure, Régis Bisson, Marco Minissale, A. Dunand, Thierry Angot, Physique des interactions ioniques et moléculaires (PIIM), Aix Marseille Université (AMU)-Centre National de la Recherche Scientifique (CNRS), ITER organization (ITER), FR-FCM, A*MIDEX, ANR-18-CE05-0012,WHeSCI,Etudes fondamentales sur W, H et He par une approche intégrée(2018), and ANR-11-IDEX-0001,Amidex,INITIATIVE D'EXCELLENCE AIX MARSEILLE UNIVERSITE(2011)

Subjects
Materials science, Metallurgy, Natural surface, chemistry.chemical_element, Tungsten, 7. Clean energy, Surfaces, Coatings and Films, Electronic, Optical and Magnetic Materials, Ammonia, chemistry.chemical_compound, General Energy, chemistry, Impurity, Molecule, [PHYS.PHYS.PHYS-CHEM-PH]Physics [physics]/Physics [physics]/Chemical Physics [physics.chem-ph], Physical and Theoretical Chemistry, Sticking probability
Abstract

International audience; We present measurements of the sticking probability of ammonia on two metals, tungsten and 316L stainless steel, covered with natural surface impurities as they will be used for the international nuclear fusion experimental reactor ITER. Using a collimated supersonic molecular beam at two different kinetic energies (55 and 255 meV), varying the sample temperature in the 130–425 K range, and characterizing the surface composition with Auger electron spectroscopy, we observe similar sticking features on both surfaces, consistent with a nondissociative adsorption mediated by two precursors having different trapping probabilities. First, the initial sticking probability decreases with increase in the surface temperature. Second, the sticking probability increases with the surface coverage up to near-saturation coverage, where it declines. Both features cannot be described together with the Kisliuk model (intrinsic + extrinsic precursors with identical trapping probabilities) or the modified Kisliuk model (direct adsorption + extrinsic precursor). Thus, we derive a generalized and separable Kisliuk (GSK) model that is able to reproduce quantitatively these two experimental observations thanks to intrinsic and extrinsic precursors having different trapping probabilities. The GSK model assumes a negligible transfer from the intrinsic precursor to the extrinsic precursor, which allows one to extract precursors kinetic parameters in a two-step analysis. The GSK analysis indicates that the ammonia trapping probability is lower on the bare surface (intrinsic precursor) than on the NH3-covered surface (extrinsic precursor). Furthermore, the barriers between the two precursor wells and the deep adsorption well are found below the vacuum level. Finally, we measure that the sticking probability does not decline to zero, i.e., steady-state sticking is observed with a probability up to 0.15 at a beam energy of 55 meV and a surface temperature of 220 K. This observation is consistent with NH3 multilayer adsorption. These experimental results and their fitting with the GSK model offer the starting point to a predictive determination of the fusion fuel inventory related to ammonia in the international experimental reactor ITER.

Published
2020

22. Three-dimensional modelling of sputtered materials transport in diagnostic ducts of fusion devices

Author

N.A. Babinov, A.G. Razdobarin, I.M. Bukreev, D.A. Kirilenko, Z.G. Lyullin, E.E. Mukhin, A.A. Sitnikova, L.A. Varshavchik, P.A. Zatylkin, A. Putrik, N.S. Klimov, D.V. Kovalenko, A.M. Zhitlukhin, T. Morgan, S. Brons, G. De Temmerman, I.T. Serenkov, V.I. Sakharov, S.V. Bulovich, A.E. Gorodetsky, and R.Kh. Zalavutdinov

Subjects
Nuclear and High Energy Physics, Condensed Matter Physics
Abstract

Migration of plasma erosion products in plasma facilities is studied experimentally and numerically within the framework of modeling transport of plasma-facing materials in the diagnostic ducts of fusion devices. Material transport simulation is discussed for two cases of low and high background neutral gas pressures. Monte Carlo software KITe was used to simulate transport at a neutral gas background pressure 0.1–0.5 Pa—typical during steady-state tokamak operation and during pressure pulses caused by edge localized modes (ELMs). The simulation approach was implemented to describe experiments at the MAGNUM-PSI facility. Fluid dynamic code FLUENT is used to simulate transport during pressure surges as high as 1000 Pa, which can occur in the case of severe disruptions in tokamak plasma discharges, such as vertical displacement events (VDE) or accidental events. The hydrodynamic approach was verified in simulation of target sputtering in the QSPA plasma gun facility.

Published
2022

23. Power deposition behavior of high-density transient hydrogen plasma on tungsten in Magnum-PSI

Author

Y. Li, J.W. Genuit, J. van den Berg-Stolp, J.A.W. van Dommelen, G. De Temmerman, Johan P.M. Hoefnagels, Thomas Morgan, Kim Verbeken, Marc G.D. Geers, Group Hoefnagels, Group Van Dommelen, Group Geers, Mechanics of Materials, Science and Technology of Nuclear Fusion, and EAISI Foundational

Subjects
Materials science, sheath physics, Plasma parameters, Thomson scattering, edge-localized modes, neutrals recycling, chemistry.chemical_element, Plasma, Fusion power, Tungsten, Condensed Matter Physics, Nuclear Energy and Engineering, chemistry, Sputtering, Physics::Plasma Physics, Ionization, Physics::Space Physics, plasma flow, Nuclear fusion, Atomic physics, nuclear fusion
Abstract

The lifetime of plasma-facing components (PFCs) will have a strong influence on the efficiency and viability of future fusion power plants. However, the PFCs suffer from thermal stresses and physical sputtering induced by edge-localized modes (ELMs). ELMs in future fusion devices are expected to occur with a high plasma density compared to current day devices such that coupling of recycling neutrals and plasma ions will be strong. Because of the scale hierarchy of future fusion devices compared to the present ones, the influence of this coupling is difficult to predict. Here, we investigate the ELM-like hydrogen plasma induced heat loads on tungsten in the linear device Magnum-PSI, producing similar to 1 ms plasma pulses with electron densities up to 3.5 x 10(21) m(-3). A combination of time-resolved Thomson scattering and coherent Thomson scattering was used to acquire plasma parameters in front of the target. Moreover, a fast infrared camera coupled to finite element thermal analyses allowed to determine the deposited heat loads on the target. We found a significant inconsistency between the plasma power calculated with a conventional collisionless sheath model and the absorbed power by the target. Moreover, plasma stagnation upstream and plasma cooling downstream were observed during the pulses. The observations are explained based on ionization and elastic collisions between the recycling neutrals and plasma ions. The results highlight the impact of plasma-neutral interaction on the power deposition behavior of ELM-like hydrogen plasma on tungsten.

Published
2021

24. Numerical simulation by finite element modelling of diffusion and transient hydrogen trapping processes in plasma facing components

Author

Yann Charles, Jonathan Mougenot, Monique Gaspérini, Sofiane Benannoune, G. De Temmerman, Laboratoire des Sciences des Procédés et des Matériaux (LSPM), Université Paris 13 (UP13)-Institut Galilée-Université Sorbonne Paris Cité (USPC)-Centre National de la Recherche Scientifique (CNRS), ITER organization (ITER), ANR-11-IDEX-0001,Amidex,INITIATIVE D'EXCELLENCE AIX MARSEILLE UNIVERSITE(2011), and European Project: 633053,H2020,EURATOM-Adhoc-2014-20,EUROfusion(2014)

Subjects
Nuclear and High Energy Physics, Materials science, Field (physics), Hydrogen, Computer simulation, Materials Science (miscellaneous), chemistry.chemical_element, 02 engineering and technology, Mechanics, Rate equation, [PHYS.MECA.MSMECA]Physics [physics]/Mechanics [physics]/Materials and structures in mechanics [physics.class-ph], 021001 nanoscience & nanotechnology, 01 natural sciences, lcsh:TK9001-9401, Finite element method, 010305 fluids & plasmas, Nuclear Energy and Engineering, chemistry, 0103 physical sciences, lcsh:Nuclear engineering. Atomic power, [PHYS.PHYS.PHYS-CHEM-PH]Physics [physics]/Physics [physics]/Chemical Physics [physics.chem-ph], Diffusion (business), 0210 nano-technology, Convection–diffusion equation, Numerical stability
Abstract

In order to simulate hydrogen charging and discharging cycles of mechanically loaded structures full 3D Macroscopic Rate Equation (MRE) modelling is proposed based on a finite element method (FEM). The model, implemented in the 3DS Abaqus software, uses a generalized transport equation, which accounts for mechanical fields, hydrogen transport and trapping, and their evolution with time. The influence of a-priori known thermal field has also been included. To ensure the solution convergence and the numerical stability, the trapping kinetic is introduced by using an approximation of the analytical solution the McNabb and Foster equation. Comparisons with a relevant 1D MRE code and with thermal programmed desorption (TPD) experimental results are performed on a 1D configuration to validate the model. Next, the model is used to simulate the tritium diffusion and trapping in a 2D geometry of interest in the upper plug of ITER tokamak, and results of tritium inventory are compared with an equivalent 1D calculation. Keywords: Hydrogen, Kinetic trapping, Modelling, Finite elements, Abaqus, User subroutine, Macroscopic Rate Equations

Published
2019

25. Recrystallization-mediated crack initiation in tungsten under simultaneous high-flux hydrogen plasma loads and high-cycle transient heating

Author

Thomas Morgan, Th. Loewenhoff, J.A.W. van Dommelen, Kim Verbeken, Marius Wirtz, Tijmen Vermeij, Johan P.M. Hoefnagels, Y. Li, G. De Temmerman, Marc G.D. Geers, J.W.M. Vernimmen, Group Hoefnagels, Group Van Dommelen, Group Geers, Mechanics of Materials, and EAISI Foundational

Subjects
Nuclear and High Energy Physics, Recrystallization (geology), Materials science, thermal fatigue, EBSD, chemistry.chemical_element, 02 engineering and technology, Tungsten, edge localized modes (ELMs), 01 natural sciences, 010305 fluids & plasmas, 0103 physical sciences, Composite material, Divertor, 021001 nanoscience & nanotechnology, Condensed Matter Physics, equipment and supplies, tungsten recrystallization, Heat flux, chemistry, hydrogen plasma, PFCs, Grain boundary, Deformation (engineering), Dislocation, 0210 nano-technology, Electron backscatter diffraction
Abstract

Tungsten and tungsten-based alloys are the leading material choices for the divertor plasma facing components (PFCs) in future fusion reactors. Recrystallization may occur when they undergo high heat loads, drastically modifying the predesigned grain structures and the associated desired mechanical properties. However, the influence of recrystallization on the thermal fatigue behavior of tungsten PFCs still remains unclear. In this study, ITER-grade tungsten was simultaneously exposed to a high-flux hydrogen plasma (∼5 × 1024 m−2 s−1) and high-cycle (104–105) transient heat loads in the linear plasma device Magnum-PSI. By correlating the surface temperature distribution, obtained by analyzing temperature-, wavelength-, and surface-dependent emissivity, and the surface modifications of the plasma exposed specimens, the crack initiation heat flux factor threshold was found to be ∼2 MW m−2 s0.5 (equivalently, ∼0.07 MJ m−2 for a 1 ms pulse). Based on electron backscatter diffraction analyses of cross-sections near the crack initiation sites, faster recrystallization kinetics near the surface compared to literature was observed and the surface cracks preferentially initiated at high angle grains boundaries (HAGBs). Upon recrystallization, the yield strength decreases which entails increasing cyclic plastic strains. The HAGBs fraction is increased, which constrains the transfer of plastic strains at grain boundaries. The recrystallization decreases the dislocation density, which promotes heterogeneous deformation. All these mechanisms explain the reduced crack initiation threshold of recrystallized tungsten compared to its as-received counterpart. The results provide new insights into the structural failure mechanisms in tungsten PFCs exposed to extreme fusion plasmas.

Published
2021

26. Analytical approach for description of deuterium content in deuterium-beryllium co-deposited layers

Author

A. Prishvitsyn, G. De Temmerman, Yu. M. Gasparyan, A. A. Pisarev, S. A. Krat, and Ya. A. Vasina

Subjects
010302 applied physics, Nuclear and High Energy Physics, Materials science, Materials Science (miscellaneous), Relative standard deviation, Recombination rate, Co-deposition, Modeling, chemistry.chemical_element, THIN films, Fuel accumulation, 01 natural sciences, lcsh:TK9001-9401, 010305 fluids & plasmas, Nuclear Energy and Engineering, chemistry, Deuterium, 0103 physical sciences, Content (measure theory), Hydrogen accumulation, lcsh:Nuclear engineering. Atomic power, Beryllium, Atomic physics, Scaling
Abstract

Available literature data for beryllium content in D-Be co-deposited layers was modeled using newly developed model. It was shown that the model adequately describes the experimental results. An empirical scaling for the available trap concentrations as a function of deuteron energy was introduced in order to improve the agreement between the experimental data and model predictions. The limited recombination rate describes the co-deposition better than the unlimited one. Assuming two types of traps in the film with detrapping energies of 0.8–0.9 and 1.2–1.3 eV and trap concentrations of 10 at. % and 1 at. %, respectively, and the deuterium implantation energy of 15.6 eV, the average relative deviation between experimental and predicted D/Be values of 1.9 was observed, which is better than the empirical D/Be scalings.

Published
2021

27. Combined high fluence and high cycle number transient loading of ITER-like monoblocks in Magnum-PSI

Author

Y. Li, M. Balden, S. Brezinsek, Thomas Morgan, G. De Temmerman, and Science and Technology of Nuclear Fusion

Subjects
010302 applied physics, Nuclear and High Energy Physics, Materials science, Divertor, chemistry.chemical_element, Plasma, Tungsten, Condensed Matter Physics, Microstructure, 01 natural sciences, Fluence, 010305 fluids & plasmas, chemistry, Heat flux, 13. Climate action, 0103 physical sciences, Surface roughness, Seeding, Composite material
Abstract

It is highly desirable to understand the long term evolution of the divertor material under the extreme steady-state and transient heat and particle loads expected during ITER operation. Here the impact of ELM-like transient loading under combined high-flux plasma and transient ELM-like heat loading in Magnum-PSI was explored to determine how plasma affects the fatigue cracking threshold of tungsten due to ELMs. Mock-ups consisting of five ITER-like monoblocks in a chain were simultaneously exposed to high flux plasma and a high power pulsed laser which closely simulated the ELM impact in terms of heat flux and duration. Loading conditions were chosen to enable comparison to existing data from electron-beam loading, while the influence of surface base temperature (750 °C, 1150 °C or 1500 °C) and impurity seeding (addition of 6.5 ion% He+ and/or 8 ion% Ne+) were also investigated. The plasma loading leads to differences in surface morphology and indicates synergistic effects on the extent of the surface damage. Base temperatures at or above 1150 °C are found to lead to a significant reduction in the fatigue cracking threshold by a factor of two or more compared to at 750 °C. Cracked surfaces are found to be more than ten times rougher than the original microstructure, and additionally when seeding impurities are added surface roughness can be significantly increased by up closely factor of two compared to roughening using pure H plasma. Overall the results indicate that avoiding fatigue cracking in ITER will be very challenging, and that understanding the level to which this can therefore be tolerated is vital for anticipating divertor lifetime and reliability.

Published
2021

28. Recrystallization at high temperature of two tungsten materials complying with the ITER specifications

Author

M. Lenci, M. Mondon, Guillaume Kermouche, A. Durif, Marco Minissale, G. De Temmerman, Marianne Richou, Laurent Gallais, Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), Commissariat à l'énergie atomique et aux énergies alternatives (CEA), École des Mines de Saint-Étienne (Mines Saint-Étienne MSE), Institut Mines-Télécom [Paris] (IMT), Physique des interactions ioniques et moléculaires (PIIM), Centre National de la Recherche Scientifique (CNRS)-Aix Marseille Université (AMU), Institut FRESNEL (FRESNEL), Centre National de la Recherche Scientifique (CNRS)-École Centrale de Marseille (ECM)-Aix Marseille Université (AMU), ITER organization (ITER), Aix Marseille Université (AMU)-Centre National de la Recherche Scientifique (CNRS), Aix Marseille Université (AMU)-École Centrale de Marseille (ECM)-Centre National de la Recherche Scientifique (CNRS), Laboratoire Georges Friedel (LGF-ENSMSE), Institut Mines-Télécom [Paris] (IMT)-Institut Mines-Télécom [Paris] (IMT)-Université de Lyon-Centre National de la Recherche Scientifique (CNRS), Centre Science des Matériaux et des Structures (SMS-ENSMSE), Institut Mines-Télécom [Paris] (IMT)-Institut Mines-Télécom [Paris] (IMT), CEA, IRFM, Aix Marseille Univ, CNRS, PIIM, and ITER Organization

Subjects
Nuclear and High Energy Physics, Materials science, Annealing (metallurgy), Kinetics, chemistry.chemical_element, 02 engineering and technology, Tungsten, 01 natural sciences, 7. Clean energy, 010305 fluids & plasmas, [SPI.MAT]Engineering Sciences [physics]/Materials, 0103 physical sciences, Thermal, General Materials Science, ComputingMilieux_MISCELLANEOUS, [PHYS]Physics [physics], Divertor, Metallurgy, Recrystallization (metallurgy), Recrystallization, 021001 nanoscience & nanotechnology, Microstructure, Heating system, Nuclear Energy and Engineering, chemistry, 0210 nano-technology, Thermal loading at high temperatures
Abstract

International audience; Estimating the lifetime of W-armoured divertor components is of great importance for ITER. During heat loading, one of the mechanisms inducing tungsten microstructure modification is recrystallization. As tungsten recrystallization induces a decrease of the mechanical properties, the knowledge of the recrystallization kinetics of the ITER tungsten material is necessary over the entire divertor PFU operational temperature window (up to 2000 °C). Some data exist for temperature loading lower than 1350 °C. For higher temperatures, some constraints due to the heating system and its impact on recrystallization process limit the possibility of high temperature studies. For this reason, in this study, a laser heating device and related diagnostics are used for the determination of the recrystallization kinetics. The Johnson Mehl-Avrami Kolmogorov (JMAK) equation is used to model the recrystallization process. Recrystallization kinetics for annealing temperatures higher than 1400 °C are provided for two tungsten materials produced according to the ITER specifications. At 1600 °C (resp. 1800 °C), recrystallization fraction of 50% is obtained after 200 s (resp. 10 s) thermal loading for one batch and after 500 s (resp. 50 s) for the other one.

Published
2020

29. Long discharges in a steady state with D 2 and N 2 on the actively cooled tungsten upper divertor in WEST

Author

S. Brezinsek, Jérôme Bucalossi, P. Moreau, Clarisse Bourdelle, Patrick Maget, Lena Delpech, Yann Corre, Nicolas Fedorczak, A. Ekedahl, E. Tsitrone, A. Gallo, Régis Bisson, T. Dittmar, M. Houry, J. P. Gunn, T. Loarer, Jonathan Gaspar, D. Douai, West Team, G. De Temmerman, R. Mitteau, C. Desgranges, Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), Commissariat à l'énergie atomique et aux énergies alternatives (CEA), Forschungszentrum Jülich GmbH | Centre de recherche de Juliers, Helmholtz-Gemeinschaft = Helmholtz Association, Physique des interactions ioniques et moléculaires (PIIM), Aix Marseille Université (AMU)-Centre National de la Recherche Scientifique (CNRS), ITER organization (ITER), Institut universitaire des systèmes thermiques industriels (IUSTI), European Project: 63253, and Centre National de la Recherche Scientifique (CNRS)-Aix Marseille Université (AMU)

Subjects
Nuclear and High Energy Physics, Jet (fluid), Materials science, Tokamak, Hydrogen, [PHYS.PHYS]Physics [physics]/Physics [physics], Divertor, Joint European Torus, chemistry.chemical_element, Plasma, Tungsten, Condensed Matter Physics, 01 natural sciences, 010305 fluids & plasmas, law.invention, Outgassing, chemistry, law, 0103 physical sciences, Atomic physics, ddc:620, 010306 general physics
Abstract

International audience; Nitrogen (N2) will be used in ITER to enhance the radiative fraction to ~90%, thereby cooling the edge plasma and preventing damage to the plasma-facing components. However, the reactivity of N2 with hydrogen isotopes can lead to the formation of tritiated ammonia (NT3). This should be considered in terms of the in-vessel tritium inventory, the regeneration of the cryo pumps, and the processes in the ITER de-tritiation plant. In the 'W' Environment in Steady-state Tokamak (WEST), a series of long L-mode discharges (~50 s), with a constant N2 seeding from the outer strike point region has been performed on the upper actively cooled divertor. In the absence of active pumping, the N2 balance shows steady-state retention during plasma discharge, and is partially (~35%) released in between discharges. Although a significant amount of N2( 18.65 Pa m3) has been injected, the wall still exhibited N2 pumping capabilities. Under these conditions, as long as this N2 reservoir is not saturated, there is not enough N available for the detectable threshold of ND3 formation to be reached. In these WEST experiments, no ammonia is detected during the pulse or after the pulse in the outgassing phase. These results are consistent with and complementary to the N2 seeded experiments performed in the Joint European Torus (JET) with its ITER-like wall and in the Axially Symmetric Divertor Experiment (ASDEX) upgrade.

Published
2020

31. First analysis of the misaligned leading edges of ITER-like Plasma Facing Units using a very high resolution infrared camera in WEST

Author

M. Firdaouss, Yann Corre, M. Houry, J. P. Gunn, Jonathan Gaspar, A. Durocher, J. Gerardin, G. De Temmerman, S. Carpentier-Chouchana, C. Pocheau, R. Dejarnac, R.A. Pitts, E. Delmas, L. Dubus, X. Courtois, M. Diez, A. Grosjean, Frederic Escourbiac, E. Tsitrone, Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), Commissariat à l'énergie atomique et aux énergies alternatives (CEA), Czech Academy of Sciences [Prague] (CAS), Institut universitaire des systèmes thermiques industriels (IUSTI), Centre National de la Recherche Scientifique (CNRS)-Aix Marseille Université (AMU), ITER organization (ITER), ANR-11-IDEX-0001,Amidex,INITIATIVE D'EXCELLENCE AIX MARSEILLE UNIVERSITE(2011), European Project, Aix Marseille Université (AMU)-Centre National de la Recherche Scientifique (CNRS), GASPAR, Jonathan, INITIATIVE D'EXCELLENCE AIX MARSEILLE UNIVERSITE - - Amidex2011 - ANR-11-IDEX-0001 - IDEX - VALID, and EUROfusion - Implementation of activities described in the Roadmap to Fusion during Horizon 2020 through a Joint programme of the members of the EUROfusion consortiumNuméro CORDIS : 633053 - INCOMING

Subjects
[PHYS]Physics [physics], Nuclear and High Energy Physics, Leading edge, Toroid, Tokamak, Materials science, business.industry, Divertor, Plasma, Condensed Matter Physics, 01 natural sciences, [PHYS] Physics [physics], 010305 fluids & plasmas, law.invention, Optics, Heat flux, Fiber Bragg grating, law, 0103 physical sciences, Emissivity, 010306 general physics, business
Abstract

International audience; Twelve ITER-like plasma-facing units made of tungsten were exposed in the WEST tokamak divertor, with three PFUs significantly overexposed to plasma heat flux: one sharp-edged PFU (vertical misalignment h = 0.8 mm) and two chamfered PFUs (h = 0.6 mm and 0.3 mm, respectively). This paper describes the first temperature analysis obtained with a very high spatial resolution infrared camera (pixel size ~ 0.1 mm) on the misaligned PFU edges and shows the consistency obtained on the parallel heat flux derived from these measurements. The analysis is focused on the hottest areas of the PFU misaligned leading edges, since the temperature detection threshold of the VHR camera is high (Tthreshold,BB ≈ 370°C). The heat flux parallel to the magnetic field lines is assessed by matching the toroidal temperature profile in the vicinity of the leading edge with 3D finite element modelling. The tungsten emissivity assumed in this study is 0.6, consistent with laboratory measurements for damaged PFUs. For the three PFUs studied (with different vertical misalignments, incident angles, geometries), the derived parallel heat flux is similar, and consistent with independent measurements by a Fiber Bragg grating embedded in a graphite PFU at another toroidal location, giving confidence in future experiments using the same settings.

Published
2020

32. Impact of H-mode plasma operation on predamaged tungsten divertor tiles in ASDEX Upgrade

Author

B. Böswirth, G. De Temmerman, Marius Wirtz, J. Likonen, P. de Marne, K. Krieger, J. W. Coenen, H. Greuner, R. Dux, Antti Hakola, Th. Löwenhoff, A. Lahtinen, M. Balden, V. Rohde, B. Göths, Gerald Pintsuk, and ASDEX Upgrade Team, Max Planck Institute for Plasma Physics, Max Planck Society

Subjects
Materials science, tungsten, Divertor, Nuclear engineering, edge-localized modes, Mode (statistics), chemistry.chemical_element, plasma-facing components, Plasma, Tungsten, Condensed Matter Physics, 01 natural sciences, Atomic and Molecular Physics, and Optics, 010305 fluids & plasmas, components, chemistry, ASDEX Upgrade, 0103 physical sciences, divertor, ddc:530, 010306 general physics, Mathematical Physics
Abstract

The effect of continued plasma exposure on two divertor target tiles intentionally damaged before installation was studied for ASDEX Upgrade H-mode discharge conditions. On one tile, made of molybdenum alloy (TZM), superficial melt damage was created in the GLADIS high heat flux test facility. To measure the influence of the resulting surface corrugations on erosion, the tile surface was subsequently covered with a 20 nm tungsten marker layer. A second tile, made of tungsten, was pre-damaged by exposure to 2 × 105 consecutive ELM-like heat pulses in the electron beam test facility JUDITH, which resulted in formation of an extended crack network. Both tiles were placed at the outer divertor target of ASDEX Upgrade using the DIM-II divertor manipulator and exposed to a series of 15 identical H-mode discharges. The surface state of both tiles was documented pre- and post-exposure using electron scanning microscopy. SEM analysis of the crack network's microscopic structure did not reveal any additional damage created by plasma exposure but showed deposition of migrated wall materials inside shadowed areas. The erosion pattern of the W-marker layer revealed regions of net erosion as well as of net deposition in the corrugated melt zone. Net erosion up to complete removal of the W marker layer was found at elevated parts of the surface oriented towards the incident plasma flux whereas net deposition was found in corresponding shadowed areas. In contrast, the undamaged surface parts showed a uniform erosion pattern determined by incident plasma ion flux and temperature.

Published
2020

33. Long-term neurosensory disturbances after modified sagittal split osteotomy

Author

Ivo Lambrichts, O. da Costa Senior, Eman Shaheen, Jimoh Olubanwo Agbaje, F. Van der Cruyssen, Constantinus Politis, G. De Temmerman, B. Gemels, Lambrichts, Ivo/0000-0001-7520-0021, Van der Cruyssen, Frederic/0000-0002-6888-9219, da Costa Senior, O., Sr., Gemels, B., Van der Cruyssen, F., Agbaje, J. O., De Temmerman, G., Shaheen, E., LAMBRICHTS, Ivo, and POLITIS, Constantinus

Subjects
medicine.medical_specialty, Chin, Mandibular Nerve, Lower lip, Osteotomy, Sagittal Split Ramus, Sagittal split osteotomy, Mandible, Inferior alveolar nerve, Genioplasty, Iliac crest, Hypesthesia, medicine, Humans, inferior alveolar nerve, Aged, Univariate analysis, business.industry, Neurosensory disturbances, nerve detachment, Surgery, Osteotomy, medicine.anatomical_structure, Otorhinolaryngology, hypoaesthesia, Trigeminal Nerve Injuries, Oral Surgery, business, Synthetic bone graft, sagittal split osteotomy
Abstract

We have investigated the long-term incidence of neurosensory disturbances after modified bilateral sagittal split osteotomy, and identified associated risk factors. We prospectively studied 376 patients, and their self-reported neurosensory disturbances were evaluated six months, and one, two, and three years postoperatively. The correlations between the following risk factors and neurosensory disturbances were investigated using univariate analysis and stepwise multivariate analysis: age at operation, sex, type of movement (advancement, setback, or rotation), concurrent genioplasty, type of detachment, iliac crest bone graft, and use of dicalcium phosphate synthetic bone graft. Probabilities of less than 0.05 were accepted as significant. Three years postoperatively, 57 patients (15%) reported altered sensation of the lower lip or chin. Older age correlated significantly with neurosensory disturbances (p < 0.0001). Greater mandibular advancement correlated with postoperative "positive" neurosensory phenomena (right side p = 0.08; left side p = 0.03). Intraoperative surgical manipulation of the left inferior alveolar nerve was significantly associated with postoperative hypoaesthesia (p = 0.014). Older age at surgery, extensive mandibular advancement, and surgical manipulation of the left inferior alveolar nerve, were associated with long-term neurosensory disturbances after modified bilateral sagittal split osteotomy. The modified operation seems to safeguard the inferior alveolar nerve from transection, without causing damage to other nerves. (C) 2020 The Author(s). Published by Elsevier Ltd on behalf of The British Association of Oral and Maxillofacial Surgeons. da Costa, O (corresponding author), Dept Oral & Maxillofacial Surg, Kapucijnenvoer 33,E91, B-3000 Leuven, Belgium. Oliver.dacosta@uzleuven.be

Published
2020

34. Scanning electron microscopy analyses of an ITER plasma-facing unit mockup exposed to extreme ion fluences in Magnum-PSI

Author

Thomas Morgan, S. Elgeti, M. Balden, S. Brezinsek, and G. De Temmerman

Subjects
Materials science, Hydrogen, Scanning electron microscope, Analytical chemistry, chemistry.chemical_element, Plasma, Tungsten, Condensed Matter Physics, 01 natural sciences, Atomic and Molecular Physics, and Optics, 010305 fluids & plasmas, Ion, chemistry, Mockup, 0103 physical sciences, Electron temperature, ddc:530, 010306 general physics, Mathematical Physics, Helium
Abstract

A small-scale tungsten monoblock mockup was exposed to continuous Magnum-PSI plasma beams under six different conditions, including pure hydrogen, deuterium and helium (He) plasmas as well as mixed D/He plasmas with low electron temperature (1.5–5 eV), with maximum surface temperatures up to 1600 °C, and with ion fluences up to 10 30 m−2. The recrystallization in the centre of the hottest exposure spots, the absence of cracking on all monoblocks, the formation of a nanostructured fuzz layer several microns thick by pure He exposure, and the presence of various impurities from the exposure in Magnum-PSI on the surface were observed and analysed with a dedicated scanning electron microscope able to handle the entire mockup without any prior cutting.

Published
2020

35. CRDS modelling of deuterium release from co-deposited beryllium layers in temperature programmed and laser induced desorption experiments

Author

M. Zlobinski, Dmitry Matveev, B. Unterberg, G. De Temmerman, and Ch. Linsmeier

Subjects
Materials science, Analytical chemistry, chemistry.chemical_element, Condensed Matter Physics, Laser, 01 natural sciences, Atomic and Molecular Physics, and Optics, 010305 fluids & plasmas, law.invention, chemistry, Deuterium, Physics::Plasma Physics, law, Desorption, 0103 physical sciences, ddc:530, Beryllium, 010306 general physics, Mathematical Physics
Abstract

Deuterium release from Be/D layers co-deposited using high power impulse magnetron sputtering (HiPIMS) is modelled with rate equations using the CRDS code under conditions of temperature programmed (TPD) and laser induced (LID) Desorption experiments. TPD results are simulated to fit D trapping parameters that are in turn applied to simulate the LID. TPD results are compared to equivalent results from JET-ILW and UCSD samples. HiPIMS samples show a different release behavior compared to UCSD and JET samples, release peaks at comparable heating rates are narrower and cannot be modelled using the same set of parameters. With a particular choice of diffusion-trapping parameters that reproduce the TPD peak positions, modelling of the LID efficiency results in a qualitative agreement with experimental observations. In particular, it is shown that a complete outgassing of low D content samples is not possible during laser heating unless the surface temperature exceeds the Be melting threshold.

Published
2020
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36. ITER monoblock performance under lifetime loading conditions in Magnum-PSI

Author

Y. Li, Thomas Morgan, G. De Temmerman, S. Brezinsek, Thomas Schwarz-Selinger, Th. Loewenhoff, Marius Wirtz, and M. Balden

Subjects
Materials science, Nuclear engineering, Divertor, chemistry.chemical_element, Recrystallization (metallurgy), Plasma, Tungsten, Fusion power, Condensed Matter Physics, 7. Clean energy, 01 natural sciences, Fluence, Atomic and Molecular Physics, and Optics, 010305 fluids & plasmas, chemistry, Nuclear reaction analysis, 0103 physical sciences, Vickers hardness test, 010306 general physics, Mathematical Physics
Abstract

The ITER divertor will be exposed to extremely high plasma fluences over its lifetime, and it is known that plasma exposure can lead to a variety of particle-induced surface-morphology and microstructure changes in tungsten. However, no data exists at fluences comparable to those expected over extended ITER operations (10 30−31 m−2) and so it is uncertain how these changes will evolve and affect the divertor performance over such long timescales. Six monoblocks were exposed to high flux plasma comparable to partially-detached plasma conditions in the ITER divertor in Magnum-PSI. Different exposures used different plasma species (H, He, D or D + He) and aimed to replicate conditions similar to those during different phases of the ITER staged approach. The highest fluence achieved was 10 30 D m−2, comparable to around one year of ITER Fusion Power Operation. Post-mortem analysis by Nuclear Reaction Analysis revealed very low deuterium retention throughout the blocks, while surface analysis showed no cracking or damage, but did observe helium fuzz growth at low ion energies of 8–18 eV, below typically assumed ion energy requirements for such growth to occur. Metallographic sectioning revealed recrystallization up to 2.2 mm below the surface of monoblocks exposed at peak surface temperatures of up to 1580 °C for different durations up to ~20 h. Finite Element Method analysis coupled to metallographic and Vickers Hardness identification of the boundary of the recrystallized region identified a faster recrystallization process compared to literature expectations, reinforcing that recrystallization dynamics is an important criterion for tungsten grade selection for the ITER divertor. Overall, no major damage or failure was identified, indicating that the design is capable of fulfilling its steady-state performance requirements under high flux, high fluence plasma loading conditions in the ITER divertor.

Published
2020

37. Design optimization of the ITER tungsten divertor vertical targets

Author

M. Garcia-Martinez, L. Ferrand, R.A. Pitts, S. Carpentier-Chouchana, Frederic Escourbiac, S. Panayotis, Mario Merola, J. P. Gunn, V. Komarov, G. De Temmerman, T. Hirai, and A. Durocher

Subjects
Materials science, Armour, Mechanical Engineering, Divertor, Nuclear engineering, chemistry.chemical_element, Tungsten, 01 natural sciences, Finite element calculations, Calculation methods, Finite element method, 010305 fluids & plasmas, Nuclear Energy and Engineering, chemistry, Heat flux, 0103 physical sciences, General Materials Science, 010306 general physics, Design Validation, Civil and Structural Engineering
Abstract

The shaping of the ITER divertor vertical targets has been refined as a consequence of manufacturing and engineering considerations during the prototype manufacturing activities. In this paper, the optimized ITER divertor design is presented together with design validation by 3D field line tracing calculation and thermo-mechanical analysis by finite element calculations. Furthermore, the reduction of W monoblock armour thickness to 6 mm is also discussed.

Published
2018

38. Studies on synthesis of plasma fusion relevant tungsten dust particles and measurement of their hydrogen absorption properties

Author

Biswarup Satpati, Sidananda Sarma, N. Aomoa, Uday Deshpande, Sanjiv Kumar, Divesh N. Srivastava, G. De Temmerman, M. Kakati, and Trinayan Sarmah

Subjects
Materials science, Hydrogen, Mechanical Engineering, Divertor, Refractory metals, Nanoparticle, chemistry.chemical_element, 02 engineering and technology, Tungsten, 021001 nanoscience & nanotechnology, 01 natural sciences, 010305 fluids & plasmas, Micrometre, Nuclear Energy and Engineering, chemistry, Chemical physics, Nuclear reaction analysis, Phase (matter), 0103 physical sciences, General Materials Science, 0210 nano-technology, Civil and Structural Engineering
Abstract

In this communication, we identify some thermal-plasma assisted synthesis techniques for the alternative production of fusion relevant tungsten dust particles in bulk amounts, to allow for the statistically meaningful study of their hydrogen absorption properties. Fast, single step synthesis of fine particles in the α-tungsten phase was demonstrated, using a high heat flux device for sizes in the micrometer region and an experimental nanoparticle reactor for dust with nanometer sizes. Production of both equilibrium polyhedral and nonequilibrium spherulitic crystal shapes was demonstrated, dust morphologies similar to which were identified before in existing tokamaks and divertor simulator systems. Their hydrogen retention characteristics were measured by the Nuclear Resonance Reaction Analysis technique, which was found to be orders of magnitude higher compared to the same metal in the bulk form. The mesoporous crystals generated during high power, high pressure synthesis conditions were assumed to be responsible for the unusually high gas retention of the nanoparticle sample. It was concluded that non-equilibrium tungsten dust morphologies would be dominant in the high power fusion machines in the future, which may aggravate the hydrogen isotope retention issues further.

Published
2018

39. Nitrogen retention and ammonia production on tungsten

Author

Marco Minissale, G. De Temmerman, F Ghiorghiu, T. Aissou, Régis Bisson, Thierry Angot, Physique des interactions ioniques et moléculaires (PIIM), Aix Marseille Université (AMU)-Centre National de la Recherche Scientifique (CNRS), ITER organization (ITER), Zenon Research, European Project: 633053,H2020,EURATOM-Adhoc-2014-20,EUROfusion(2014), and ANR-11-IDEX-0001,Amidex,INITIATIVE D'EXCELLENCE AIX MARSEILLE UNIVERSITE(2011)

Subjects
Nuclear and High Energy Physics, Inorganic chemistry, chemistry.chemical_element, Tungsten, Condensed Matter Physics, 01 natural sciences, Nitrogen, 010305 fluids & plasmas, Ammonia production, chemistry, [PHYS.PHYS.PHYS-PLASM-PH]Physics [physics]/Physics [physics]/Plasma Physics [physics.plasm-ph], 0103 physical sciences, [PHYS.PHYS.PHYS-CHEM-PH]Physics [physics]/Physics [physics]/Chemical Physics [physics.chem-ph], 010306 general physics
Abstract

We report a systematic study that quantifies nitrogen retention and ammonia production on tungsten and that sheds light on the mechanism for ammonia formation on ITER’s divertor material. Saturation of the nitrogen-implanted layer in polycrystalline tungsten is observed at room temperature for a nitrogen ion fluence in the low 1021 N+ m−2 range. Nitrogen desorption from this N-implanted layer occurs in the 800–1100 K temperature range and exhibits a zero-order kinetics with an activation energy of 1.45 eV and a prefactor of 5 × 1024 m−2 s−1. Following nitrogen and deuterium co-implantation, deuterated ammonia production is observed during temperature programmed desorption between 350 K and 650 K in conjunction with deuterium desorption. In contrast, nitrogen desorption still occurs above 800 K. Significant production of ammonia is obtained only when the nitrogen layer created by ion implantation is approaching saturation and the amount of nitrogen lost to ammonia production is only in the percent range. This result is understood by repeating cycles of deuterium implantation and thermo-desorption below the desorption temperature of the nitrogen layer. The exponential decay of the amount of produced ammonia with cycle number demonstrates that nitrogen diffusion to the surface is negligible in the ammonia production temperature range and that ammonia formation occurs at the outermost surface layer. The maximum quantity of ammonia produced from the present N implanted layer is below 2 × 1018 ND3 m−2, which is limited by the nitrogen atom surface density. Surface vibrational spectroscopy demonstrates the presence of ammonia precursors on the nitrogen-implanted tungsten surface upon deuterium implantation. These ammonia precursors can be created also at room temperature through the dissociative chemisorption of thermal D2 catalysed by nitrogen present at the tungsten surface and, more efficiently, by adsorption of deuterium atoms.

Published
2021

40. Plasma expansion synthesis of tungsten nanopowder

Author

Biswajit Bora, M. Kakati, Trinayan Sarmah, Sidananda Sarma, G. De Temmerman, N. Aomoa, Gourab Bhattacharjee, Heman Bhuyan, and Divesh N. Srivastava

Subjects
Tungsten Compounds, Materials science, 020502 materials, Mechanical Engineering, Metals and Alloys, chemistry.chemical_element, Nanotechnology, 02 engineering and technology, Tungsten, 021001 nanoscience & nanotechnology, 0205 materials engineering, chemistry, Chemical engineering, Mechanics of Materials, Transmission electron microscopy, Materials Chemistry, Particle, Particle size, Crystallite, Sample collection, 0210 nano-technology, High-resolution transmission electron microscopy
Abstract

This article reports the synthesis of tungsten nanoparticles predominantly in α-W phase by a single step plasma expansion technique. The oxidation of the metal and contribution from the β-W phase in the nanomaterial samples was observed to decrease with the increase of both the pressure in the sample collection chamber and the plasma power. We had observed production of faceted, lightly sintered particles with up to 300 nm individual sizes during high plasma current/high pressure synthesis conditions, which were measured to have the highest specific surface area of 35 m 2 /g. Condensation of this high temperature material at low saturation ratio and the high collisional regime had led to the synthesis of relatively bigger particle sizes in this experiment. Cauliflower like particle morphologies was observed during low pressure synthesis conditions, which is considered to have formed through spherulitic growth processes. Transmission Electron Microscopy (TEM) micrographs show very small crystallites remaining dispersed in an amorphous moss like the background, which was confirmed to be a mixture of tungsten and its oxides.

Published
2017

41. The influence of D2 pressure on D retention and release from Be co-deposits

Author

R.P. Doerner, M.J. Baldwin, M. J. Simmonds, G. De Temmerman, and A. Založnik

Subjects
Nuclear and High Energy Physics, Work (thermodynamics), Range (particle radiation), Materials science, Materials Science (miscellaneous), Thermal desorption, Analytical chemistry, chemistry.chemical_element, Degree (temperature), Ion, Nuclear Energy and Engineering, chemistry, Beryllium, Deposition (chemistry), Layer (electronics)
Abstract

Beryllium co-deposit thermal desorption studies are reported that focus on the effect of D 2 pressure during layer formation, as pressure has been linked in prior work to the formation of a high-retention-capacity sharp-release-feature. A pressure range from 0.3 to 13.3 Pa is explored. Additional insight into what drives the formation of T 0 is established through co-deposit formation parameter variations including deposition temperature spanning 373 K to 608 K, and ion impact energy in the range 10–100 eV. It is found that the formation of the sharp release feature exhibits a multi-parameter dependence, but is predominately favoured by low deposition temperature, higher D 2 pressure, and to a small degree, increased ion impact energy, during deposition. TESSIM simulations of the D 2 thermal release at the ITER bake temperatures of T b 1 (513 K) and T b 2 (623 K), show that the best efficacy for D removal (defined as the ratio of post to pre bake inventory) is found when the sharp release feature is present. However, when this feature is present, the total retained D inventory tends to be significantly increased.

Published
2021

42. Beryllium layer response to ITER-like ELM plasma pulses in QSPA-Be

Author

C. P. Lungu, I.B. Kupriyanov, R.A. Pitts, Gerald Pintsuk, P.N. Taratorkin, A.M. Zhitlukhin, G. De Temmerman, V.M. Safronov, A. D. Muzichenko, D. V. Kovalenko, V.L. Podkovyrov, Th. Loewenhoff, Jochen Linke, A.A. Markin, N. S. Klimov, and N.E. Zabirova

Subjects
010302 applied physics, Nuclear and High Energy Physics, Dense plasma focus, Materials science, Materials Science (miscellaneous), Divertor, chemistry.chemical_element, Thermionic emission, Vacuum arc, Plasma, Tungsten, 01 natural sciences, lcsh:TK9001-9401, 010305 fluids & plasmas, Nuclear Energy and Engineering, chemistry, 0103 physical sciences, Forensic engineering, ddc:333.7, lcsh:Nuclear engineering. Atomic power, Beryllium, Composite material, Layer (electronics)
Abstract

Material migration in ITER is expected to move beryllium (Be) eroded from the first wall primarily to the tungsten (W) divertor region and to magnetically shadowed areas of the wall itself. This paper is concerned with experimental study of Be layer response to ELM-like plasma pulses using the new QSPA-Be plasma gun (SRC RF TRINITI). The Be layers (1→50µm thick) are deposited on special castellated Be and W targets supplied by the ITER Organization using the Thermionic Vacuum Arc technique. Transient deuterium plasma pulses with duration ∼0.5ms were selected to provide absorbed energy densities on the plasma stream axis for a 30° target inclination of 0.2 and 0.5MJm−2, the first well below and the second near the Be melting point. This latter value is close to the prescribed maximum energy density for controlled ELMs on ITER. At 0.2MJm−2 on W, all Be layer thicknesses tested retain their integrity up to the maximum pulse number, except at local defects (flakes, holes and cracks) and on tile edges. At 0.5MJm−2 on W, Be layer melting and melt layer agglomeration are the main damage processes, they happen immediately in the first plasma impact. Melt layer movement was observed only near plasma facing edges. No significant melt splashing is observed in spite of high plasma pressure (higher than expected in ITER). Be layer of 10µm thick on Be target has higher resistance to plasma irradiation than 1 and 55µm, and retain their integrity up to the maximum pulse number at 0.2MJm−2. For 1µm and 55µm thick on Be target significant Be layer losses were observed at 0.2MJm−2. Keywords: ITER, High heat flux, Thermal shock, Beryllium, Tungsten, Coating

Published
2017

43. Mechanical properties of tungsten following rhenium ion and helium plasma exposure

Author

Cormac Corr, Jodie Bradby, Christopher A. Tanner, Matt Thompson, G. De Temmerman, Daniel P. Riley, Robert Elliman, Sean O'Ryan, and Patrick Kluth

Subjects
010302 applied physics, Nuclear and High Energy Physics, Materials science, Materials Science (miscellaneous), Analytical chemistry, chemistry.chemical_element, Plasma, Rhenium, Tungsten, Nanoindentation, lcsh:TK9001-9401, 01 natural sciences, 010305 fluids & plasmas, Ion, Nuclear Energy and Engineering, chemistry, Physics::Plasma Physics, 0103 physical sciences, lcsh:Nuclear engineering. Atomic power, Surface modification, Irradiation, Helium
Abstract

Mechanical properties of Tungsten (W) samples irradiated with 2 MeV Rhenium (Re) ions and helium (He) plasma were investigated using nanoindentation. It was found that there was an increase in hardness for all samples following separate irradiation with both Re ion and He plasma. A slight increase in hardness was obtained for combined exposures. A comparable increase in hardness was observed for a pure He plasma with a sample temperature of 473 K and 1273 K. Optical interferometry was employed to compare surface modification of the samples. Grazing incidence small angle x-ray scattering confirmed He nano-bubble formation of approximately 1 nm diameter in the higher temperature sample, which was not observed with samples at the lower temperatures.

Published
2017

44. Physics conclusions in support of ITER W divertor monoblock shaping

Author

P. Bunting, B. Bazylev, R. Dejarnac, T. Hirai, Richard E. Nygren, C.J. Lasnier, Yann Corre, D. Iglesias, M.A. van den Berg, R.A. Pitts, J. W. Coenen, S. Bardin, Petr Vondracek, Frederic Escourbiac, K. Krieger, James Paul Gunn, S. Panayotis, G. De Temmerman, S-H. Hong, S. Carpentier-Chouchana, Jonathan Gaspar, Dmitry Rudakov, J. Horacek, Matthias Komm, G. F. Matthews, S. Pestchanyi, A. Podolnik, Thomas Morgan, and J.G. Watkins

Subjects
Technology, Nuclear and High Energy Physics, Leading edge, Tokamak, Field line, Materials Science (miscellaneous), Nuclear engineering, Context (language use), Edge (geometry), 01 natural sciences, Tungsten, 010305 fluids & plasmas, law.invention, Divertor, law, ITER, 0103 physical sciences, Forensic engineering, 010306 general physics, Edge-localized mode, Physics, Melting, lcsh:TK9001-9401, Shaping, Nuclear Energy and Engineering, lcsh:Nuclear engineering. Atomic power, Transient (oscillation), MEMOS, ddc:600
Abstract

The key remaining physics design issue for the ITER tungsten (W) divertor is the question of monoblock (MB) front surface shaping in the high heat flux target areas of the actively cooled targets. Engineering tolerance specifications impose a challenging maximum radial step between toroidally adjacent MBs of 0.3mm. Assuming optical projection of the parallel heat loads, magnetic shadowing of these edges is required if quasi-steady state melting is to be avoided under certain conditions during burning plasma operation and transiently during edge localized mode (ELM) or disruption induced power loading. An experiment on JET in 2013 designed to investigate the consequences of transient W edge melting on ITER, found significant deficits in the edge power loads expected on the basis of simple geometric arguments, throwing doubt on the understanding of edge loading at glancing field line angles. As a result, a coordinated multi-experiment and simulation effort was initiated via the International Tokamak Physics Activity (ITPA) and through ITER contracts, aimed at improving the physics basis supporting a MB shaping decision from the point of view both of edge power loading and melt dynamics. This paper reports on the outcome of this activity, concluding first that the geometrical approximation for leading edge power loading on radially misaligned poloidal leading edges is indeed valid. On this basis, the behaviour of shaped and unshaped monoblock surfaces under stationary and transient loads, with and without melting, is compared in order to examine the consequences of melting, or power overload in context of the benefit, or not, of shaping. The paper concludes that MB top surface shaping is recommended to shadow poloidal gap edges in the high heat flux areas of the ITER divertor targets. Keywords: ITER, Tungsten, Divertor, Shaping, Melting, MEMOS

Published
2017

45. Efficiency of thermal outgassing for tritium retention measurement and removal in ITER

Author

Corneliu Porosnicu, I. Jepu, Kalle Heinola, M.J. Baldwin, A. Jan, C. P. Lungu, D. Anthoine, R.A. Pitts, G. De Temmerman, Jari Likonen, and Department of Physics

Subjects
Nuclear and High Energy Physics, Materials Science (miscellaneous), Nuclear engineering, Thermal desorption, chemistry.chemical_element, Baffle, 114 Physical sciences, 01 natural sciences, 010305 fluids & plasmas, Divertor, Tritium retention, ITER, Divertor, Outgassing, ITER, Desorption, 0103 physical sciences, Thermal, divertor, 010306 general physics, ta214, Outgassing, Radiochemistry, lcsh:TK9001-9401, Tritium retention, Nuclear Energy and Engineering, chemistry, outgassing, lcsh:Nuclear engineering. Atomic power, Tritium, Beryllium
Abstract

Proceedings of the 22nd International Conference on Plasma Surface Interactions 2016, 22nd PSI As a licensed nuclear facility, ITER must limit the in-vessel tritium (T) retention to reduce the risks of potential release during accidents, the inventory limit being set at 1kg. Simulations and extrapolations from existing experiments indicate that T-retention in ITER will mainly be driven by co-deposition with beryllium (Be) eroded from the first wall, with co-deposits forming mainly in the divertor region but also possibly on the first wall itself. A pulsed Laser-Induced Desorption (LID) system, called Tritium Monitor, is being designed to locally measure the T-retention in co-deposits forming on the inner divertor baffle of ITER. Regarding tritium removal, the baseline strategy is to perform baking of the plasma-facing components, at 513K for the FW and 623K for the divertor. Both baking and laser desorption rely on the thermal desorption of tritium from the surface, the efficiency of which remains unclear for thick (and possibly impure) co-deposits. This contribution reports on the results of TMAP7 studies of this efficiency for ITER-relevant deposits.

Published
2017

46. Collective Thomson scattering system for determination of ion properties in a high flux plasma beam

Author

H.J. van der Meiden, Thomas Morgan, M.Y. Kantor, K. Jesko, K. Bystrov, G. De Temmerman, J.W.M. Vernimmen, and Science and Technology of Nuclear Fusion

Subjects
Physics, Electron density, Physics and Astronomy (miscellaneous), Thomson scattering, Bremsstrahlung, Plasma, Laser, 7. Clean energy, 01 natural sciences, 010305 fluids & plasmas, Ion, law.invention, law, Physics::Plasma Physics, 0103 physical sciences, Electron temperature, Plasma diagnostics, Atomic physics, 010306 general physics
Abstract

A collective Thomson scattering system has been developed for measuring ion temperature, plasma velocity and impurity concentration in the high density magnetized Magnum-PSI plasma beam, allowing for measurements at low temperature (4 × 1020 m−3, while avoiding laser plasma heating caused by inverse Bremsstrahlung. The collective Thomson scattering system is based on the fundamental mode of a seeded Nd:YAG laser and equipped with an LIVAR M506 camera (EBABS technology). The first collective Thomson scattering measurements are taken at the linear plasma generator Pilot-PSI, 40 mm downstream of the cascaded arc source. At this location, the ion temperature is about equal to the electron temperature in the bulk of the plasma beam.

Published
2016

47. WallDYN simulations of material migration and fuel retention in ITER low power H plasmas and high power neon-seeded DT plasmas

Author

M.A. Miller, Karl Schmid, R.A. Pitts, A. Khan, A.S. Kukushkin, G. De Temmerman, Xavier Bonnin, H. Anand, and S.W. Lisgo

Subjects
010302 applied physics, Nuclear and High Energy Physics, Materials science, Hydrogen, Divertor, Materials Science (miscellaneous), Extrapolation, Flux, chemistry.chemical_element, Plasma, 01 natural sciences, lcsh:TK9001-9401, 010305 fluids & plasmas, Neon, chemistry, Nuclear Energy and Engineering, 0103 physical sciences, Deposition (phase transition), lcsh:Nuclear engineering. Atomic power, Atomic physics, Electronic density
Abstract

Deposition and fuel retention profiles in low power hydrogen L-mode plasmas and neon (Ne) seeded ITER DT burning plasmas have been investigated. Two different Ne seeded plasma backgrounds with varying sub-divertor neutral pressures but the same Ne impurity concentration are considered, representing high recycling and partially detached divertor solutions. The 2D SOLPS numerical grid does not extend all the way to the wall surfaces so that an extrapolation of the plasma background is required and is performed using a second simulation stage in which the far scrape-off layer (SOL) region is numerically gridded and plasma transport solved on the extended grid using the OSM (a 1D simplified Braginski code) approach [1] . The plasma conditions chosen for this far SOL region strongly influence the results. The hydrogenic flux is calculated from the electronic density and ion flow, the latter of which has an assumed distribution. Depending on the main-SOL plasma flow parameters and far-SOL density, fuel retention is driven by deposition on the first wall (when parallel flow through the main-SOL is switched off), or by deposition on the divertor (parallel flow through the main-SOL is switched on). When retention is dominated by deposition on the first wall, there is slightly more retention in the partially detached case compared to a high recycling scenario. In the low power cases, there is insignificant deposition and fuel retention.

Published
2019

48. First principles and integrated modelling achievements towards trustful fusion power predictions for JET and ITER

Author

Garcia, J., Dumont, R. J., Joly, J., Morales, J., Garzotti, L., Bache, T. W., Baranov, Y., Casson, F. J., Challis, C., Kirov, K., Mailloux, J., Saarelma, S., Nocente, M., Banon-Navarro, A., Goerler, T., Citrin, J., Ho, A., Gallart, D., Mantsinen, M., Abduallev, (Abduallev, S, ( 8, S., 42, ), Abhangi, (Abhangi, M, ( 8, M., 54, ), Abreu, (Abreu, P, ( 8, P., 60, ), Afanasev, (Afanasev, V, V)(, 8, 61, ), Afzal, (Afzal, M, 14, ), Aggarwal, (Aggarwal, Km, ( 8, K. M., 85, ), Ahlgren, (Ahlgren, T, ( 8, T., 106, ), Aho-Mantila, (Aho-Mantila, L, ( 8, L., 113, ), Aiba, (Aiba, N, ( 8, N., 73, ), Airila, (Airila, M, Alarcon, (Alarcon, T, 15, ), Albanese, (Albanese, R, ( 8, R., 18, ), Alegre, (Alegre, D, ( 8, D., 64, ), Aleiferis, (Aleiferis, S, 75, ), Alessi, (Alessi, E, ( 8, E., 50, ), Aleynikov, (Aleynikov, P, 62, ), Alkseev, (Alkseev, A, ( 8, A., 76, ), Allinson, (Allinson, M, Alper, (Alper, B, ( 8, B., Alves, (Alves, E, Ambrosino, (Ambrosino, G, ( 8, G., (Ambrosino, R, Amosov, (Amosov, V, 95, ), Sunden, (Sunden, Ea, Andersson)( 8, E., 26, ), Andrews, (Andrews, R, Angelone, (Angelone, M, 96, ), Anghel, (Anghel, M, 92, ), Angioni, (Angioni, C, ( 8, C., 68, ), Appel, (Appel, L, Appelbee, (Appelbee, C, Arena, Paolo Pietro, (Arena, P, 34, ), Ariola, (Ariola, M, Arshad, (Arshad, S, 45, ), Artaud, (Artaud, J, ( 8, J., Arter, (Arter, W, ( 8, W., Ash, (Ash, A, Ashikawa, (Ashikawa, N, ( 8 ), N., Aslanyan, (Aslanyan, V, 70, ), Asunta, (Asunta, O, ( 8, O., Asztalos, 9, (Asztalos, O, 114, ), Auriemma, (Auriemma, F, ( 8, F., 19, ), Austin, (Austin, Y, ( 8, Y., Avotina, (Avotina, L, 109, ), Axton, (Axton, M, Ayres, (Ayres, C, Baciero, (Baciero, A, Baiao, (Baiao, D, Balboa, (Balboa, I, I)(, 8, Balden, (Balden, M, Balshaw, (Balshaw, N, Bandaru, (Bandaru, Vk, ( 8, V. K., Banks, (Banks, J, Baranov, (Baranov, Yf, ( 8, Y. F., Barcellona, (Barcellona, C, Barnard, (Barnard, T, Barnes, (Barnes, M, 84, ), Barnsley, (Barnsley, R, Wiechec, (Wiechec, Ab, Baron)( 8, A., Orte, (Orte, Lb, Barrera)( 8, L., 37, ), Baruzzo, (Baruzzo, M, Basiuk, (Basiuk, V, Bassan, (Bassan, M, Bastow, (Bastow, R, 82, ), Batista, (Batista, A, Batistoni, (Batistoni, P, Baumane, (Baumane, L, Bauvir, (Bauvir, B, Baylor, (Baylor, L, 77, ), Beaumont, (Beaumont, Ps, ( 8, P. S., Beckers, (Beckers, M, Beckett, (Beckett, B, Bekris, (Bekris, N, 38, ), Beldishevski, (Beldishevski, M, Bell, (Bell, K, ( 8, K., Belli, (Belli, F, Belonohy, (Belonohy, E, ( 8 ), E., Benayas, (Benayas, J, Bergsaker, (Bergsaker, H, ( 8, H., 46, ), Bernardo, (Bernardo, J, Bernert, (Bernert, M, Berry, (Berry, M, Bertalot, (Bertalot, L, Besiliu, (Besiliu, C, Betar, (Betar, H, 51, ), Beurskens, (Beurskens, M, 69, ), Bielecki, (Bielecki, J, 55, ), Biewer, (Biewer, T, Bilato, (Bilato, R, Biletskyi, (Biletskyi, O, 53, ), Bilkova, (Bilkova, P, 58, ), Binda, (Binda, F, Birkenmeier, (Birkenmeier, G, Bizarro, Jps, (Bizarro, ( 8, J. P. S., Bjorkas, (Bjorkas, C, Blackburn, (Blackburn, J, Blackman, (Blackman, Tr, ( 8, T. R., Blanchard, (Blanchard, P, 36, ), Blatchford, (Blatchford, P, Bobkov, (Bobkov, V, Boboc, (Boboc, A, Bogar, (Bogar, O, 24, ), Bohm, (Bohm, P, (Bohm, T, 112, ), Bolshakova, (Bolshakova, I, 67, ), Bolzonella, (Bolzonella, T, Bonanomi, (Bonanomi, N, 104, ), Boncagni, (Boncagni, L, Bonfiglio, (Bonfiglio, D, Bonnin, (Bonnin, X, ( 8, X., Boom, (Boom, J, Borba, (Borba, D, Borodin, (Borodin, D, Borodkina, (Borodkina, I, Boulbe, (Boulbe, C, 102, ), Bourdelle, (Bourdelle, C, Bowden, (Bowden, M, Bowman, (Bowman, C, 115, ), Boyce, (Boyce, T, Boyer, (Boyer, H, Bradnam, (Bradnam, Sc, ( 8, S. C., Braic, (Braic, V, 94, ), Bravanec, (Bravanec, R, 44, ), Breizman, (Breizman, B, 52, ), Brennan, (Brennan, D, Breton, (Breton, S, Brett, (Brett, A, Brezinsek, (Brezinsek, S, Bright, (Bright, M, Brix, (Brix, M, Broeckx, (Broeckx, W, 86, ), Brombin, (Brombin, M, Broslawski, (Broslawski, A, 71, ), Brown, (Brown, B, Brunetti, (Brunetti, D, Bruno, (Bruno, E, Buch, (Buch, J, Buchanan, (Buchanan, J, Buckingham, (Buckingham, R, Buckley, (Buckley, M, Bucolo, MAIDE ANGELA RITA, (Bucolo, M, Budny, (Budny, R, 80, ), Bufferand, (Bufferand, H, Buller, (Buller, S, 28, ), Bunting, (Bunting, P, Buratti, (Buratti, P, Burckhart, (Burckhart, A, Burroughes, (Burroughes, G, Buscarino, Arturo, (Buscarino, A, Busse, (Busse, A, Butcher, (Butcher, D, Butler, (Butler, B, Bykov, (Bykov, I, Cahyna, (Cahyna, P, Calabro, (Calabro, G, 111, ), Calacci, (Calacci, L, 100, ), Callaghan, (Callaghan, D, (Callaghan, J, Calvo, (Calvo, I, Camenen, (Camenen, Y, 11, ), Camp, (Camp, P, Campling, (Campling, Dc, ( 8, D. 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T., (Chapman, B, 32, ), (Chapman, Sc, Chernyshova, (Chernyshova, M, 57, ), Chiariello, (Chiariello, A, Chitarin, (Chitarin, G, Chmielewski, (Chmielewski, P, Chone, (Chone, L, Ciraolo, 9, (Ciraolo, G, Ciric, (Ciric, D, Citrin, (Citrin, J, 41, ), Clairet, (Clairet, F, Clark, (Clark, M, (Clark, E, Clarkson, (Clarkson, R, Clay, (Clay, R, Clements, (Clements, C, Coad, (Coad, Jp, ( 8, J. P., Coates, (Coates, P, Cobalt, (Cobalt, A, Coccorese, (Coccorese, V, Cocilovo, (Cocilovo, V, Coelho, (Coelho, R, Coenen, (Coenen, Jw, ( 8, J. W., Coffey, (Coffey, I, Colas, (Colas, L, Colling, (Colling, B, Collins, (Collins, S, Conka, (Conka, D, Conroy, (Conroy, S, Conway, (Conway, N, Coombs, (Coombs, D, Cooper, (Cooper, Sr, ( 8, S. 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Esquembri, S, Esquisabel, Al, Esser, Hg, Ewart, G, Fable, E, Fagan, D, Faitsch, M, Falie, D, Fanni, A, Farahani, A, Fasoli, A, Faugeras, B, Fazinic, S, Felici, F, Felton, Rc, Feng, S, Fernades, A, Fernandes, H, Ferreira, J, Ferreira, Dr, Ferro, G, Fessey, Ja, Ficker, O, Field, A, Fietz, S, Figini, L, Figueiredo, J, Figueiredo, A, Fil, N, Finburg, P, Fischer, U, Fittill, L, Fitzgerald, M, Flammini, D, Flanagan, J, Flinders, K, Foley, S, Fonnesu, N, Fontdecaba, Jm, Formisano, A, Forsythe, L, Fortuna, L, Fransson, E, Frasca, M, Frassinetti, L, Freisinger, M, Fresa, R, Fridstrom, R, Frigione, D, Fuchs, V, Fusco, V, Futatani, S, Gal, K, Galassi, D, Galazka, K, Galeani, S, Galvao, R, Gao, Y, Garcia-Carrasco, A, Garcia-Munoz, M, Gardener, M, Gaspar, J, Gaudio, P, Gear, D, Gebhart, T, Gee, S, Geiger, B, Gelfusa, M, George, R, Gerasimov, S, Gervasini, G, Gethins, M, Ghani, Z, Ghate, M, Gherendi, M, Ghezzi, F, Giacalone, Jc, Giacomelli, L, Giacometti, G, Gibson, K, Giegerich, T, Gil, L, Gilbert, 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Kobuchi, T, Kochl, F, Kocsis, G, Kodeli, I, Koechl, F, Kogut, D, Koivuranta, S, Kolesnichenko, Y, Kollo, Z, Kominis, Y, Koppen, M, Korolczuk, S, Kos, B, Koslowski, Hr, Kotschenreuther, M, Koubiti, M, Kovaldins, R, Kovanda, O, Kowalska-Strzeciwilk, E, Krasilnikov, A, Krasilnikov, V, Krawczyk, N, Kresina, M, Krieger, K, Krivska, A, Kruezi, U, Ksiazek, I, Kukushkin, A, Kundu, A, Kurki-Suonio, T, Kwak, S, Kwon, Oj, Laguardia, L, Lahtinen, A, Laing, A, Lalousis, P, Lam, N, Lamb, C, Lambertz, Ht, Lang, Pt, Lanthaler, S, Neto, El, Laszynska, E, Lawless, R, Lawson, Kd, Lazaros, A, Lazzaro, E, Leach, R, Learoyd, G, Leerink, S, Lefebvre, X, Leggate, Hj, Lehmann, J, Lehnen, M, Leichauer, P, Leichtle, D, Leipold, F, Lengar, I, Lennholm, M, Lepiavko, B, Leppanen, J, Lerche, E, Lescinskis, A, Lescinskis, B, Lesnoj, S, Leyland, M, Leysen, W, Li, Y, Li, L, Liang, Y, Likonen, J, Linke, J, Linsmeier, C, Lipschultz, B, Litaudon, X, Liu, G, Lloyd, B, Lo Schiavo, Vp, Loarer, T, Loarte, A, Lomanowski, B, Lomas, Pj, Lonnroth, J, Lopez, Jm, Lorenzini, R, Losada, U, Loughlin, M, Lowry, C, Luce, T, Lucock, R, Lukin, A, Luna, C, Lungaroni, M, Lungu, Cp, Lungu, M, Lunniss, A, Lunt, T, Lupelli, I, Lutsenko, V, Lyssoivan, A, Macheta, P, Macusova, E, Magesh, B, Maggi, C, Maggiora, R, Mahesan, S, Maier, H, Maingi, R, Makwana, R, Malaquias, A, Malinowski, K, Malizia, A, Manas, P, Manduchi, G, Manso, Me, Mantica, P, Manzanares, A, Maquet, P, Marandet, Y, Marcenko, N, Marchetto, C, Marchuk, O, Marconato, N, Marin, M, Marinelli, M, Marinucci, M, Markovic, T, Marocco, D, Marot, L, Marsh, J, Martin, A, de Aguilera, Am, Martin-Solis, Jr, Martone, R, Martynova, Y, Maruyama, S, Maslov, M, Matejcik, S, Mattei, M, Matthews, Gf, Matveev, D, Matveeva, E, Mauriya, A, Maviglia, F, May-Smith, T, Mayer, M, Mayoral, Ml, Mazon, D, Mazzotta, C, Mcadams, R, Mccarthy, Pj, Mcclements, Kg, Mccormack, O, Mccullen, Pa, Mcdonald, D, Mchardy, M, Mckean, R, Mckehon, J, Mcnamee, L, Meadowcroft, C, Meakins, A, Medley, S, Meigh, S, Meigs, Ag, Meisl, G, Meiter, S, Meitner, S, Meneses, L, Menmuir, S, Mergia, K, Merle, A, Merriman, P, Mertens, P, Meshchaninov, S, Messiaen, A, Meyer, H, Michling, R, Milanesio, D, Militello, F, Militello-Asp, E, Milocco, A, Miloshevsky, G, Mink, F, Minucci, S, Miron, I, Mistry, S, Miyoshi, Y, Mlynar, J, Moiseenko, V, Monaghan, P, Monakhov, I, Moon, S, Mooney, R, Moradi, S, Moran, J, Mordijck, S, Moreira, L, Moro, F, Morris, J, Moser, L, Mosher, S, Moulton, D, Mrowetz, T, Muir, A, Muraglia, M, Murari, A, Muraro, A, Murphy, S, Muscat, P, Muthusonai, N, Myers, C, Asakura, Nn, N'Konga, B, Nabais, F, Naish, R, Naish, J, Nakano, T, Napoli, F, Nardon, E, Naulin, V, Nave, Mff, Nedzelskiy, I, Nemtsev, G, Nesenevich, V, Nespoli, F, Neto, A, Neu, R, Neverov, V, Newman, M, Ng, S, Nicassio, M, Nielsen, Ah, Nina, D, Nishijima, D, Noble, C, Nobs, Cr, Nodwell, D, Nordlund, K, Nordman, H, Normanton, R, Noterdaeme, Jm, Nowak, S, Nunes, I, O'Gorman, T, O'Mullane, M, Oberkofler, M, Oberparleiter, M, Odupitan, T, Ogawa, Mt, Okabayashi, M, Oliver, H, Olney, R, Omoregie, L, Ongena, J, Orsitto, F, Orszagh, J, Osborne, T, Otin, R, Owen, A, Owen, T, Paccagnella, R, Packer, Lw, Pajuste, E, Pamela, S, Panja, S, Papp, P, Papp, G, Parail, V, Pardanaud, C, Diaz, Fp, Parsloe, A, Parsons, N, Parsons, M, Pasqualotto, R, Passeri, M, Patel, A, Pathak, S, Patten, H, Pau, A, Pautasso, G, Pavlichenko, R, Pavone, A, Pawelec, E, Soldan, Cp, Peackoc, A, Pehkonen, Sp, Peluso, E, Penot, C, Penzo, J, Pepperell, K, Pereira, R, Cippo, Ep, von Thun, Cp, Pericoli, V, Peruzzo, S, Peterka, M, Petersson, P, Petravich, G, Petre, A, Petrzilka, V, Philipps, V, Pigatto, L, Pillon, M, Pinches, S, Pintsuk, G, Piovesan, P, de Sa, Wp, dos Reis, Ap, Piron, L, Piron, C, Pironti, A, Pisano, F, Pitts, R, Plyusnin, V, Poli, Fm, Pomaro, N, Pompilian, Og, Pool, P, Popovichev, S, Poradzinski, M, Porfiri, Mt, Porosnicu, C, Porton, M, Possnert, G, Potzel, S, Poulipoulis, G, Powell, T, Prajapati, V, Prakash, R, Predebon, I, Prestopino, G, Price, D, Price, M, Price, R, Primetzhofer, D, Prior, P, Pucella, G, Puglia, P, Puiatti, Me, Purahoo, K, Pusztai, I, Putterich, T, Rachlew, E, Rack, M, Ragona, R, Rainford, M, Raj, P, Rakha, A, Ramogida, G, Ranjan, S, Rapson, Cj, Rasmussen, D, Rasmussen, Jj, Rathod, K, Ratta, G, Ratynskaia, S, Ravera, G, Rebai, M, Reed, A, Refy, D, Regana, J, Reich, M, Reid, N, Reimold, F, Reinhart, M, Reinke, M, Reiser, D, Rendell, D, Reux, C, Cortes, Sdar, Reynolds, S, Ricci, D, Richiusa, M, Rigamonti, D, Rimini, Fg, Risner, J, Riva, M, Rivero-Rodriguez, J, Roach, C, Robins, R, Robinson, S, Robson, D, Rodionov, R, Rodrigues, P, Rodriguez, J, Rohde, V, Romanelli, M, Romanelli, F, Romanelli, S, Romazanov, J, Rowe, S, Rubel, M, Rubinacci, G, Rubino, G, Ruchko, L, Ruset, C, Rzadkiewicz, J, Sabot, R, Saez, X, Safi, E, Sahlberg, A, Saibene, G, Saleem, M, Salewski, M, Salmi, A, Salmon, R, Salzedas, F, Samm, U, Sandiford, D, Santa, P, Santala, Mik, Santos, B, Santucci, A, Sartori, F, Sartori, R, Sauter, O, Scannell, R, Schluck, F, Schlummer, T, Schmid, K, Schmuck, S, Schopf, K, Schweinzer, J, Schworer, D, Scott, Sd, Sergienko, G, Sertoli, M, Shabbir, A, Sharapov, Se, Shaw, A, Sheikh, H, Shepherd, A, Shevelev, A, Shiraki, D, Shumack, A, Sias, G, Sibbald, M, Sieglin, B, Silburn, S, Silva, J, Silva, A, Silva, C, Silvagni, D, Simmons, P, Simpson, J, Sinha, A, Sipila, Sk, Sips, Acc, Siren, P, Sirinelli, A, Sjostrand, H, Skiba, M, Skilton, R, Skvara, V, Slade, B, Smith, R, Smith, P, Smith, Sf, Snoj, L, Soare, S, Solano, Er, Somers, A, Sommariva, C, Sonato, P, Sos, M, Sousa, J, Sozzi, C, Spagnolo, S, Sparapani, P, Spelzini, T, Spineanu, F, Sprada, D, Sridhar, S, Stables, G, Stallard, J, Stamatelatos, I, Stamp, Mf, Stan-Sion, C, Stancar, Z, Staniec, P, Stankunas, G, Stano, M, Stavrou, C, Stefanikova, E, Stepanov, I, Stephen, Av, Stephen, M, Stephens, J, Stevens, B, Stober, J, Stokes, C, Strachan, J, Strand, P, Strauss, Hr, Strom, P, Studholme, W, Subba, F, Suchkov, E, 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Vincenzi, P, Vinyar, I, Viola, B, Vitins, A, Vizvary, Z, Vlad, M, Voitsekhovitch, I, Voltolina, D, von Toussaint, U, Vondracek, P, Vuksic, M, Wakeling, B, Waldon, C, Walkden, N, Walker, R, Walker, M, Walsh, M, Wang, N, Wang, E, Warder, S, Warren, R, Waterhouse, J, Watts, C, Wauters, T, Webb, M, Weckmann, A, Weiland, J, Weiland, M, Weisen, H, Weiszflog, M, Welch, P, West, A, Wheatley, M, Wheeler, S, Whitehead, Am, Whittaker, D, Widdowson, Am, Wiesen, S, Wilkie, G, Williams, J, Willoughby, D, Wilson, J, Wilson, I, Wilson, Hr, Wischmeier, M, Withycombe, A, Witts, D, Wolfrum, E, Wood, R, Woodley, R, Woodley, C, Wray, S, Wright, Jc, Wright, P, Wukitch, S, Wynn, A, Xiang, L, Xu, T, Xue, Y, Yadikin, D, Yakovenko, Y, Yanling, W, Yavorskij, V, Young, I, Young, R, Young, D, Zacks, J, Zagorski, R, Zaitsev, F, Zakharov, L, Zanino, R, Zarins, A, Zarins, R, Fernandez, Dz, Zastrow, Kd, Zerbini, M, Zhang, W, Zhou, Y, Zilli, E, Zocco, A, Zoita, V, Zoletnik, S, Zwingmann, W, Zychor, I, and JET Contributors

Subjects
Physics, Nuclear and High Energy Physics, Fusion, Jet (fluid), Maximum power principle, Nuclear engineering, Context (language use), Plasma, Fusion power, Condensed Matter Physics, 01 natural sciences, 7. Clean energy, ICRH, Charged particle, 010305 fluids & plasmas, JET, transport, TRANSPORT, Physics::Plasma Physics, Beta (plasma physics), 0103 physical sciences, 010306 general physics
Abstract

Predictability of burning plasmas is a key issue for designing and building credible future fusion devices. In this context, an important effort of physics understanding and guidance is being carried out in parallel to the on-going JET experimental campaigns in H, D and T by performing analyses and modelling towards an improvement of the understanding of DT physics for the optimization of the JET-DT neutron yield and fusion born alpha particle physics. Extrapolations to JET-DT from recent experiments using the maximum power available have been performed including some of the most sophisticated codes and a broad selection of models. There is a general agreement that 11-15MW of fusion power can be expected in DT for the hybrid and baseline scenarios. On the other hand, in high beta, torque and fast ion fraction conditions, isotope effects could be favourable leading to higher fusion yield. It is shown that alpha particles related physics, such as TAE destabilization or fusion power electron heating, could be studied in ITER relevant JET-DT plasmas.

Published
2019

49. Mechanism for orientation dependence of blisters on W surface exposed to D plasma at low temperature

Author

Y.Z. Jia, G.-N. Luo, Thomas Morgan, Ben Xu, G. De Temmerman, Wei Liu, and S.L. Qu

Subjects
Nuclear and High Energy Physics, Morphology (linguistics), Materials science, Scanning electron microscope, chemistry.chemical_element, Blisters, Plasma, Chemical vapor deposition, Tungsten, 01 natural sciences, 010305 fluids & plasmas, Nuclear Energy and Engineering, chemistry, 0103 physical sciences, Perpendicular, medicine, General Materials Science, Composite material, medicine.symptom, 010306 general physics, Electron backscatter diffraction
Abstract

The orientation dependence of blister formation induced by D plasma exposure at low temperature (about 523 K) on rolled tungsten and chemical vapor deposition (CVD) W samples was studied by scanning electron microscopy and electron backscatter diffraction. Severe blistering was observed on grains with surface normal directions close to [111], while the [001] surfaces are the most resistant to blister formation. Cavities induced by D2 gas were observed beneath [111], [110] and [001] surfaces, independently on whether blisters were observed on the surface or not. The [111] surface is more prone to blister formation, because it is easily plastically deformed by the D2 gas pressure. Some blister edges and steps were perpendicular to [110] directions, which may be induced by the slipping of dislocations on {110} planes. The blister morphology induced by D plasma can be well explained by the blister model based on plastic deformation mechanism.

Published
2016

50. Re: Re: Mandibular Wing Osteotomy: technical modification

Author

Constantinus Politis, R. Coopman, G. De Temmerman, and T. Aerden

Subjects
Orthodontics, Wing, business.industry, medicine.medical_treatment, Mandibular Osteotomy, Mandible, 030206 dentistry, Osteotomy, Mandibular osteotomy, 03 medical and health sciences, 0302 clinical medicine, Otorhinolaryngology, 030220 oncology & carcinogenesis, medicine, Humans, Surgery, Oral Surgery, business
Published
2017

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