Author: "Dzysiuk, Natalia" - Searchworks@Jio Institute Digital Library Search Results

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28 results on '"Dzysiuk, Natalia"'

1. Nuclear data for fusion technology – the European approach

Author: Fischer Ulrich, Avrigeanu Marilena, Avrigeanu Vlad, Cabellos Oscar, Dzysiuk Natalia, Koning Arjan, Klix Axel, Konobeev Alexander, Kodeli Ivo, Leeb Helmut, Leichtle Dieter, Nunnenmann Elena, Packer Lee, Rochman Dimitri, Pereslavtsev Pavel, Sauvan Patrick, and Trkov Andrej
Subjects: Physics, QC1-999
Abstract: The European approach for the development of nuclear data for fusion technology applications is presented. Related R&D activities are conducted by the Consortium on Nuclear Data Development and Analysis for Fusion to satisfy the nuclear data needs of the major projects including ITER, the Early Neutron Source (ENS) and DEMO. Recent achievements are presented in the area of nuclear data evaluations, benchmarking and validation, nuclear model improvements, and uncertainty assessments.
Published: 2017
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2. Self-consistent coupling of DSMC method and SOLPS code for modeling tokamak particle exhaust

Author: Bonelli, F., Andersson Sundén, Erik, Binda, Federico, Cecconello, Marco, Conroy, Sean, Dzysiuk, Natalia, Ericsson, Göran, Eriksson, Jacob, Hellesen, Carl, Hjalmarsson, Anders, Possnert, Göran, Sjöstrand, Henrik, Skiba, Mateusz, Weiszflog, Matthias, Zychor, I., Bonelli, F., Andersson Sundén, Erik, Binda, Federico, Cecconello, Marco, Conroy, Sean, Dzysiuk, Natalia, Ericsson, Göran, Eriksson, Jacob, Hellesen, Carl, Hjalmarsson, Anders, Possnert, Göran, Sjöstrand, Henrik, Skiba, Mateusz, Weiszflog, Matthias, and Zychor, I.
Abstract: In this work, an investigation of the neutral gas flow in the JET sub-divertor area is presented, with respect to the interaction between the plasma side and the pumping side. The edge plasma side is simulated with the SOLPS code, while the sub-divertor area is modeled by means of the direct simulation Monte Carlo (DSMC) method, which in the last few years has proved well able to describe rarefied, collisional flows in tokamak sub-divertor structures. Four different plasma scenarios have been selected, and for each of them a user-defined, iterative procedure between SOLPS and DSMC has been established, using the neutral flux as the key communication term between the two codes. The goal is to understand and quantify the mutual influence between the two regions in a self-consistent manner, that is to say, how the particle exhaust pumping system controls the upstream plasma conditions. Parametric studies of the flow conditions in the sub-divertor, including additional flow outlets and variations of the cryopump capture coefficient, have been performed as well, in order to understand their overall impact on the flow field. The DSMC analyses resulted in the calculation of both the macroscopic quantities-i.e. temperature, number density and pressure-and the recirculation fluxes towards the plasma chamber. The consistent values for the recirculation rates were found to be smaller than those according to the initial standard assumption made by SOLPS., For complete list of authors see http://dx.doi.org/10.1088/1741-4326/aa686f
Published: 2017
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3. Overview of the JET results in support to ITER

Author: Litaudon, X., Abduallev, S., Abhangi, M., Abreu, P., Afzal, M., Aggarwal, K. M., Ahlgren, T., Ahn, J. H., Aho-Mantila, L., Aiba, N., Airila, M., Albanese, R., Aldred, V., Alegre, D., Alessi, E., Aleynikov, P., Alfier, A., Alkseev, A., Allinson, M., Alper, B., Alves, E., Ambrosino, G., Ambrosino, R., Amicucci, L., Amosov, V., Andersson Sundén, Erik, Angelone, M., Anghel, M., Angioni, C., Appel, L., Appelbee, C., Arena, P., Ariola, M., Arnichand, H., Arshad, S., Ash, A., Ashikawa, N., Aslanyan, V., Asunta, O., Auriemma, F., Austin, Y., Avotina, L., Axton, M. D., Ayres, C., Bacharis, M., Baciero, A., Baiao, D., Bailey, S., Baker, A., Balboa, I., Balden, M., Balshaw, N., Bament, R., Banks, J. W., Baranov, Y. F., Barnard, M. A., Barnes, D., Barnes, M., Barnsley, R., Wiechec, A. Baron, Orte, L. Barrera, Baruzzo, M., Basiuk, V., Bassan, M., Bastow, R., Batista, A., Batistoni, P., Baughan, R., Bauvir, B., Baylor, L., Bazylev, B., Beal, J., Beaumont, P. S., Beckers, M., Beckett, B., Becoulet, A., Bekris, N., Beldishevski, M., Bell, K., Belli, F., Bellinger, M., Belonohy, E., Ben Ayed, N., Benterman, N. A., Bergsaker, H., Bernardo, J., Bernert, M., Berry, M., Bertalot, L., Besliu, C., Beurskens, M., Bieg, B., Bielecki, J., Biewer, T., Bigi, M., Bilkova, P., Binda, Federico, Bisoffi, A., Bizarro, J. P. S., Bjorkas, C., Blackburn, J., Blackman, K., Blackman, T. R., Blanchard, P., Blatchford, P., Bobkov, V., Boboc, A., Bodnar, G., Bogar, O., Bolshakova, I., Bolzonella, T., Bonanomi, N., Bonelli, F., Boom, J., Booth, J., Borba, D., Borodin, D., Borodkina, I., Botrugno, A., Bottereau, C., Boulting, P., Bourdelle, C., Bowden, M., Bower, C., Bowman, C., Boyce, T., Boyd, C., Boyer, H. J., Bradshaw, J. M. A., Braic, V., Bravanec, R., Breizman, B., Bremond, S., Brennan, P. D., Breton, S., Brett, A., Brezinsek, S., Bright, M. D. J., Brix, M., Broeckx, W., Brombin, M., Broslawski, A., Brown, D. P. D., Brown, M., Bruno, E., Bucalossi, J., Buch, J., Buchanan, J., Buckley, M. A., Budny, R., Bufferand, H., Bulman, M., Bulmer, N., Bunting, P., Buratti, P., Burckhart, A., Buscarino, A., Busse, A., Butler, N. K., Bykov, I., Byrne, J., Cahyna, P., Calabro, G., Calvo, I., Camenen, Y., Camp, P., Campling, D. C., Cane, J., Cannas, B., Capel, A. J., Card, P. J., Cardinali, A., Carman, P., Carr, M., Carralero, D., Carraro, L., Carvalho, B. B., Carvalho, I., Carvalho, P., Casson, F. J., Castaldo, C., Catarino, N., Caumont, J., Causa, F., Cavazzana, R., Cave-Ayland, K., Cavinato, M., Cecconello, Marco, Ceccuzzi, S., Cecil, E., Cenedese, A., Cesario, R., Challis, C. D., Chandler, M., Chandra, D., Chang, C. S., Chankin, A., Chapman, I. T., Chapman, S. C., Chernyshova, M., Chitarin, G., Ciraolo, G., Ciric, D., Citrin, J., Clairet, F., Clark, E., Clark, M., Clarkson, R., Clatworthy, D., Clements, C., Cleverly, M., Coad, J. P., Coates, P. A., Cobalt, A., Coccorese, V., Cocilovo, V., Coda, S., Coelho, R., Coenen, J. W., Coffey, I., Colas, L., Collins, S., Conka, D., Conroy, Sean, Conway, N., Coombs, D., Cooper, D., Cooper, S. R., Corradino, C., Corre, Y., Corrigan, G., Cortes, S., Coster, D., Couchman, A. S., Cox, M. P., Craciunescu, T., Cramp, S., Craven, R., Crisanti, F., Croci, G., Croft, D., Crombe, K., Crowe, R., Cruz, N., Cseh, G., Cufar, A., Cullen, A., Curuia, M., Czarnecka, A., Dabirikhah, H., Dalgliesh, P., Dalley, S., Dankowski, J., Darrow, D., Davies, O., Davis, W., Day, C., Day, I. E., De Bock, M., de Castro, A., de la Cal, E., de la Luna, E., De Masi, G., de Pablos, J. L., De Temmerman, G., De Tommasi, G., de Vries, P., Deakin, K., Deane, J., Agostini, F. Degli, Dejarnac, R., Delabie, E., den Harder, N., Dendy, R. O., Denis, J., Denner, P., Devaux, S., Devynck, P., Di Maio, F., Di Siena, A., Di Troia, C., Dinca, P., D'Inca, R., Ding, B., Dittmar, T., Doerk, H., Doerner, R. P., Donne, T., Dorling, S. E., Dormido-Canto, S., Doswon, S., Douai, D., Doyle, P. T., Drenik, A., Drewelow, P., Drews, P., Duckworth, Ph., Dumont, R., Dumortier, P., Dunai, D., Dunne, M., Duran, I., Durodie, F., Dutta, P., Duval, B. P., Dux, R., Dylst, K., Dzysiuk, Natalia, Edappala, P. V., Edmond, J., Edwards, A. M., Edwards, J., Eich, Th., Ekedahl, A., El-Jorf, R., Elsmore, C. G., Enachescu, M., Ericsson, Göran, Eriksson, F., Eriksson, Jacob, Eriksson, L. G., Esposito, B., Esquembri, S., Esser, H. G., Esteve, D., Evans, B., Evans, G. E., Evison, G., Ewart, G. D., Fagan, D., Faitsch, M., Falie, D., Fanni, A., Fasoli, A., Faustin, J. M., Fawlk, N., Fazendeiro, L., Fedorczak, N., Felton, R. C., Fenton, K., Fernades, A., Fernandes, H., Ferreira, J., Fessey, J. A., Fevrier, O., Ficker, O., Field, A., Fietz, S., Figueiredo, A., Figueiredo, J., Fil, A., Finburg, P., Firdaouss, M., Fischer, U., Fittill, L., Fitzgerald, M., Flammini, D., Flanagan, J., Fleming, C., Flinders, K., Fonnesu, N., Fontdecaba, J. M., Formisano, A., Forsythe, L., Fortuna, L., Fortuna-Zalesna, E., Fortune, M., Foster, S., Franke, T., Franklin, T., Frasca, M., Frassinetti, L., Freisinger, M., Fresa, R., Frigione, D., Fuchs, V., Fuller, D., Futatani, S., Fyvie, J., Gal, K., Galassi, D., Galazka, K., Galdon-Quiroga, J., Gallagher, J., Gallart, D., Galvao, R., Gao, X., Gao, Y., Garcia, J., Garcia-Carrasco, A., Garcia-Munoz, M., Gardarein, J. -L, Garzotti, L., Gaudio, P., Gauthier, E., Gear, D. F., Gee, S. J., Geiger, B., Gelfusa, M., Gerasimov, S., Gervasini, G., Gethins, M., Ghani, Z., Ghate, M., Gherendi, M., Giacalone, J. C., Giacomelli, L., Gibson, C. S., Giegerich, T., Gil, C., Gil, L., Gilligan, S., Gin, D., Giovannozzi, E., Girardo, J. B., Giroud, C., Giruzzi, G., Gloeggler, S., Godwin, J., Goff, J., Gohil, P., Goloborod'ko, V., Gomes, R., Goncalves, B., Goniche, M., Goodliffe, M., Goodyear, A., Gorini, G., Gosk, M., Goulding, R., Goussarov, A., Gowland, R., Graham, B., Graham, M. E., Graves, J. P., Grazier, N., Grazier, P., Green, N. R., Greuner, H., Grierson, B., Griph, F. S., Grisolia, C., Grist, D., Groth, M., Grove, R., Grundy, C. N., Grzonka, J., Guard, D., Guerard, C., Guillemaut, C., Guirlet, R., Gurl, C., Utoh, H. H., Hackett, L. J., Hacquin, S., Hagar, A., Hager, R., Hakola, A., Halitovs, M., Hall, S. J., Cook, S. P. Hallworth, Hamlyn-Harris, C., Hammond, K., Harrington, C., Harrison, J., Harting, D., Hasenbeck, F., Hatano, Y., Hatch, D. R., Haupt, T. D. V., Hawes, J., Hawkes, N. C., Hawkins, J., Hawkins, P., Haydon, P. W., Hayter, N., Hazel, S., Heesterman, P. J. L., Heinola, K., Hellesen, Carl, Hellsten, T., Helou, W., Hemming, O. N., Hender, T. C., Henderson, M., Henderson, S. S., Henriques, R., Hepple, D., Hermon, G., Hertout, P., Hidalgo, C., Highcock, E. G., Hill, M., Hillairet, J., Hillesheim, J., Hillis, D., Hizanidis, K., Hjalmarsson, Anders, Hobirk, J., Hodille, E., Hogben, C. H. A., Hogeweij, G. M. D., Hollingsworth, A., Hollis, S., Homfray, D. A., Horacek, J., Hornung, G., Horton, A. R., Horton, L. D., Horvath, L., Hotchin, S. P., Hough, M. R., Howarth, P. J., Hubbard, A., Huber, A., Huber, V., Huddleston, T. M., Hughes, M., Huijsmans, G. T. A., Hunter, C. L., Huynh, P., Hynes, A. M., Iglesias, D., Imazawa, N., Imbeaux, F., Imrisek, M., Incelli, M., Innocente, P., Irishkin, M., Ivanova-Stanik, I., Jachmich, S., Jacobsen, A. S., Jacquet, P., Jansons, J., Jardin, A., Jarvinen, A., Jaulmes, F., Jednorog, S., Jenkins, I., Jeong, C., Jepu, I., Joffrin, E., Johnson, R., Johnson, T., Johnston, Jane, Joita, L., Jones, G., Jones, T. T. C., Hoshino, K. K., Kallenbach, A., Kamiya, K., Kaniewski, J., Kantor, A., Kappatou, A., Karhunen, J., Karkinsky, D., Karnowska, I., Kaufman, M., Kaveney, G., Kazakov, Y., Kazantzidis, V., Keeling, D. L., Keenan, T., Keep, J., Kempenaars, M., Kennedy, C., Kenny, D., Kent, J., Kent, O. N., Khilkevich, E., Kim, H. T., Kim, H. S., Kinch, A., King, C., King, D., King, R. F., Kinna, D. J., Kiptily, V., Kirk, A., Kirov, K., Kirschner, A., Kizane, G., Klepper, C., Klix, A., Knight, P., Knipe, S. J., Knott, S., Kobuchi, T., Koechl, F., Kocsis, G., Kodeli, I., Kogan, L., Kogut, D., Koivuranta, S., Kominis, Y., Koeppen, M., Kos, B., Koskela, T., Koslowski, H. R., Koubiti, M., Kovari, M., 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., Kwiatkowski, R., Kwon, O. J., Laguardia, L., Lahtinen, A., Laing, A., Lam, N., Lambertz, H. T., Lane, C., Lang, P. T., Lanthaler, S., Lapins, J., Lasa, A., Last, J. R., Laszynska, E., Lawless, R., Lawson, A., Lawson, K. D., Lazaros, A., Lazzaro, E., Leddy, J., Lee, S., Lefebvre, X., Leggate, H. J., Lehmann, J., Lehnen, M., Leichtle, D., Leichuer, P., Leipold, F., Lengar, I., Lennholm, M., Lerche, E., Lescinskis, A., Lesnoj, S., Letellier, E., Leyland, M., Leysen, W., Li, L., Liang, Y., Likonen, J., Linke, J., Linsmeier, Ch., Lipschultz, B., Liu, G., Liu, Y., Lo Schiavo, V. P., Loarer, T., Loarte, A., Lobel, R. C., Lomanowski, B., Lomas, P. J., Lonnroth, J., Lopez, J. M., Lopez-Razola, J., Lorenzini, R., Losada, U., Lovell, J. J., Loving, A. B., Lowry, C., Luce, T., Lucock, R. M. A., Lukin, A., Luna, C., Lungaroni, M., Lungu, C. P., Lungu, M., Lunniss, A., Lupelli, I., Lyssoivan, A., Macdonald, N., Macheta, P., Maczewa, K., Magesh, B., Maget, P., Maggi, C., Maier, H., Mailloux, J., Makkonen, T., Makwana, R., Malaquias, A., Malizia, A., Manas, P., Manning, A., Manso, M. E., Mantica, P., Mantsinen, M., Manzanares, A., Maquet, Ph., Marandet, Y., Marcenko, N., Marchetto, C., Marchuk, O., Marinelli, M., Marinucci, M., Markovic, T., Marocco, D., Marot, L., Marren, C. A., Marshal, R., Martin, A., Martin, Y., Martin de Aguilera, A., Martinez, F. J., Martin-Solis, J. R., Martynova, Y., Maruyama, S., Masiello, A., Maslov, M., Matejcik, S., Mattei, M., Matthews, G. F., Maviglia, F., Mayer, M., Mayoral, M. L., May-Smith, T., Mazon, D., Mazzotta, C., McAdams, R., McCarthy, P. J., McClements, K. G., McCormack, O., McCullen, P. A., McDonald, D., McIntosh, S., McKean, R., McKehon, J., Meadows, R. C., Meakins, A., Medina, F., Medland, M., Medley, S., Meigh, S., Meigs, A. G., Meisl, G., Meitner, S., Meneses, L., Menmuir, S., Mergia, K., Merrigan, I. R., Mertens, Ph., Meshchaninov, S., Messiaen, A., Meyer, H., Mianowski, S., Michling, R., Middleton-Gear, D., Miettunen, J., Militello, F., Militello-Asp, E., Miloshevsky, G., Mink, F., Minucci, S., Miyoshi, Y., Mlynar, J., Molina, D., Monakhov, I., Moneti, M., Mooney, R., Moradi, S., Mordijck, S., Moreira, L., Moreno, R., Moro, F., Morris, A. W., Morris, J., Moser, L., Mosher, S., Moulton, D., Murari, A., Muraro, A., Murphy, S., Asakura, N. N., Na, Y. S., Nabais, F., Naish, R., Nakano, T., Nardon, E., Naulin, V., Nave, M. F. F., Nedzelski, I., Nemtsev, G., Nespoli, F., Neto, A., Neu, R., Neverov, V. S., Newman, M., Nicholls, K. J., Nicolas, T., Nielsen, A. H., Nielsen, P., Nilsson, E., Nishijima, D., Noble, C., Nocente, M., Nodwell, D., Nordlund, K., Nordman, H., Nouailletas, R., Nunes, I., Oberkofler, M., Odupitan, T., Ogawa, M. T., O'Gorman, T., Okabayashi, M., Olney, R., Omolayo, O., O'Mullane, M., Ongena, J., Orsitto, F., Orszagh, J., Oswuigwe, B. I., Otin, R., Owen, A., Paccagnella, R., Pace, N., Pacella, D., Packer, L. W., Page, A., Pajuste, E., Palazzo, S., Pamela, S., Panja, S., Papp, P., Paprok, R., Parail, V., Park, M., Diaz, F. Parra, Parsons, M., Pasqualotto, R., Patel, A., Pathak, S., Paton, D., Patten, H., Pau, A., Pawelec, E., Soldan, C. Paz, Peackoc, A., Pearson, I. J., Pehkonen, S. -P, Peluso, E., Penot, C., Pereira, A., Pereira, R., Puglia, P. P. Pereira, von Thun, C. Perez, Peruzzo, S., Peschanyi, S., Peterka, M., Petersson, P., Petravich, G., Petre, A., Petrella, N., Petrzilka, V., Peysson, Y., Pfefferle, D., Philipps, V., Pillon, M., Pintsuk, G., Piovesan, P., Pires dos Reis, A., Piron, L., Pironti, A., Pisano, F., Pitts, R., Pizzo, F., Plyusnin, V., Pomaro, N., Pompilian, O. G., Pool, P. J., Popovichev, S., Porfiri, M. T., Porosnicu, C., Porton, M., Possnert, Göran, Potzel, S., Powell, T., Pozzi, J., Prajapati, V., Prakash, R., Prestopino, G., Price, D., Price, M., Price, R., Prior, P., Proudfoot, R., Pucella, G., Puglia, P., Puiatti, M. E., Pulley, D., Purahoo, K., Puetterich, Th., Rachlew, E., Rack, M., Ragona, R., Rainford, M. S. J., Rakha, A., Ramogida, G., Ranjan, S., Rapson, C. J., Rasmussen, J. J., Rathod, K., Ratta, G., Ratynskaia, S., Ravera, G., Rayner, C., Rebai, M., Reece, D., Reed, A., Refy, D., Regan, B., Regana, J., Reich, M., Reid, N., Reimold, F., Reinhart, M., Reinke, M., Reiser, D., Rendell, D., Reux, C., Reyes Cortes, S. D. A., Reynolds, S., Riccardo, V., Richardson, N., Riddle, K., Rigamonti, D., Rimini, F. G., Risner, J., Riva, M., Roach, C., Robins, R. J., Robinson, S. A., Robinson, T., Robson, D. W., Roccella, R., Rodionov, R., Rodrigues, P., Rodriguez, J., Rohde, V., Romanelli, F., Romanelli, M., Romanelli, S., Romazanov, J., Rowe, S., Rubel, M., Rubinacci, G., Rubino, G., Ruchko, L., Ruiz, M., Ruset, C., Rzadkiewicz, J., Saarelma, S., Sabot, R., Safi, E., Sagar, P., Saibene, G., Saint-Laurent, F., Salewski, M., Salmi, A., Salmon, R., Salzedas, F., Samaddar, D., Samm, U., Sandiford, D., Santa, P., Santala, M. I. K., Santos, B., Santucci, A., Sartori, F., Sartori, R., Sauter, O., Scannell, R., Schlummer, T., Schmid, K., Schmidt, V., Schmuck, S., Schneider, M., Schoepf, K., Schworer, D., Scott, S. D., Sergienko, G., Sertoli, M., Shabbir, A., Sharapov, S. E., Shaw, A., Shaw, R., Sheikh, H., Shepherd, A., Shevelev, A., Shumack, A., Sias, G., Sibbald, M., Sieglin, B., Silburn, S., Silva, A., Silva, C., Simmons, P. A., Simpson, J., Simpson-Hutchinson, J., Sinha, A., Sipila, S. K., Sips, A. C. C., Siren, P., Sirinelli, A., Sjöstrand, Henrik, Skiba, Mateusz, Skilton, R., Slabkowska, K., Slade, B., Smith, N., Smith, P. G., Smith, R., Smith, T. J., Smithies, M., Snoj, L., Soare, S., Solano, E. R., Somers, A., Sommariva, C., Sonato, P., Sopplesa, A., Sousa, J., Sozzi, C., Spagnolo, S., Spelzini, T., Spineanu, F., Stables, G., Stamatelatos, I., Stamp, M. F., Staniec, P., Stankunas, G., Stan-Sion, C., Stead, M. J., Stefanikova, E., Stepanov, I., Stephen, A. V., Stephen, M., Stevens, A., Stevens, B. D., Strachan, J., Strand, P., Strauss, H. R., Strom, P., Stubbs, G., Studholme, W., Subba, F., Summers, H. P., Svensson, J., Swiderski, L., Szabolics, T., Szawlowski, M., Szepesi, G., Suzuki, T. T., Tal, B., Tala, T., Talbot, A. R., Talebzadeh, S., Taliercio, C., Tamain, P., Tame, C., Tang, W., Tardocchi, M., Taroni, L., Taylor, D., Taylor, K. A., Tegnered, D., Telesca, G., Teplova, N., Terranova, D., Testa, D., Tholerus, E., Thomas, J., Thomas, J. D., Thomas, P., Thompson, A., Thompson, C. -A, Thompson, V. K., Thorne, L., Thornton, A., Thrysoe, A. S., Tigwell, P. A., Tipton, N., Tiseanu, I., Tojo, H., Tokitani, M., Tolias, P., Tomes, M., Tonner, P., Towndrow, M., Trimble, P., Tripsky, M., Tsalas, M., Tsavalas, P., Jun, D. Tskhakaya, Turner, I., Turner, M. M., Turnyanskiy, M., Tvalashvili, G., Tyrrell, S. G. J., Uccello, A., Ul-Abidin, Z., Uljanovs, J., Ulyatt, D., Urano, H., Uytdenhouwen, I., Vadgama, A. P., Valcarcel, D., Valentinuzzi, M., Valisa, M., Olivares, P. Vallejos, Valovic, M., Van De Mortel, M., Van Eester, D., Van Renterghem, W., van Rooij, G. J., Varje, J., Varoutis, S., Vartanian, S., Vasava, K., Vasilopoulou, T., Vega, J., Verdoolaege, G., Verhoeven, R., Verona, C., Rinati, G. Verona, Veshchev, E., Vianello, N., Vicente, J., Viezzer, E., Villari, S., Villone, F., Vincenzi, P., Vinyar, I., Viola, B., Vitins, A., Vizvary, Z., Vlad, M., Voitsekhovitch, I., Vondracek, P., Vora, N., Vu, T., Pires de Sa, W. W., Wakeling, B., Waldon, C. W. F., Walkden, N., Walker, M., Walker, R., Walsh, M., Wang, E., Wang, N., Warder, S., Warren, R. J., Waterhouse, J., Watkins, N. W., Watts, C., Wauters, T., Weckmann, A., Weiland, J., Weisen, H., Weiszflog, Matthias, Wellstood, C., West, A. T., Wheatley, M. R., Whetham, S., Whitehead, A. M., Whitehead, B. D., Widdowson, A. M., Wiesen, S., Wilkinson, J., Williams, J., Williams, M., Wilson, A. R., Wilson, D. J., Wilson, H. R., Wilson, J., Wischmeier, M., Withenshaw, G., Withycombe, A., Witts, D. 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D., Strachan, J., Strand, P., Strauss, H. R., Strom, P., Stubbs, G., Studholme, W., Subba, F., Summers, H. P., Svensson, J., Swiderski, L., Szabolics, T., Szawlowski, M., Szepesi, G., Suzuki, T. T., Tal, B., Tala, T., Talbot, A. R., Talebzadeh, S., Taliercio, C., Tamain, P., Tame, C., Tang, W., Tardocchi, M., Taroni, L., Taylor, D., Taylor, K. A., Tegnered, D., Telesca, G., Teplova, N., Terranova, D., Testa, D., Tholerus, E., Thomas, J., Thomas, J. D., Thomas, P., Thompson, A., Thompson, C. -A, Thompson, V. K., Thorne, L., Thornton, A., Thrysoe, A. S., Tigwell, P. A., Tipton, N., Tiseanu, I., Tojo, H., Tokitani, M., Tolias, P., Tomes, M., Tonner, P., Towndrow, M., Trimble, P., Tripsky, M., Tsalas, M., Tsavalas, P., Jun, D. Tskhakaya, Turner, I., Turner, M. M., Turnyanskiy, M., Tvalashvili, G., Tyrrell, S. G. J., Uccello, A., Ul-Abidin, Z., Uljanovs, J., Ulyatt, D., Urano, H., Uytdenhouwen, I., Vadgama, A. P., Valcarcel, D., Valentinuzzi, M., Valisa, M., Olivares, P. Vallejos, Valovic, M., Van De Mortel, M., Van Eester, D., Van Renterghem, W., van Rooij, G. J., Varje, J., Varoutis, S., Vartanian, S., Vasava, K., Vasilopoulou, T., Vega, J., Verdoolaege, G., Verhoeven, R., Verona, C., Rinati, G. Verona, Veshchev, E., Vianello, N., Vicente, J., Viezzer, E., Villari, S., Villone, F., Vincenzi, P., Vinyar, I., Viola, B., Vitins, A., Vizvary, Z., Vlad, M., Voitsekhovitch, I., Vondracek, P., Vora, N., Vu, T., Pires de Sa, W. W., Wakeling, B., Waldon, C. W. F., Walkden, N., Walker, M., Walker, R., Walsh, M., Wang, E., Wang, N., Warder, S., Warren, R. J., Waterhouse, J., Watkins, N. W., Watts, C., Wauters, T., Weckmann, A., Weiland, J., Weisen, H., Weiszflog, Matthias, Wellstood, C., West, A. T., Wheatley, M. R., Whetham, S., Whitehead, A. M., Whitehead, B. D., Widdowson, A. M., Wiesen, S., Wilkinson, J., Williams, J., Williams, M., Wilson, A. R., Wilson, D. J., Wilson, H. R., Wilson, J., Wischmeier, M., Withenshaw, G., Withycombe, A., Witts, D. M., Wood, D., Wood, R., Woodley, C., Wray, S., Wright, J., Wright, J. C., Wu, J., Wukitch, S., Wynn, A., Xu, T., Yadikin, D., Yanling, W., Yao, L., Yavorskij, V., Yoo, M. G., Young, C., Young, D., Young, I. D., Young, R., Zacks, J., Zagorski, R., Zaitsev, F. S., Zanino, R., Zarins, A., Zastrow, K. D., Zerbini, M., Zhang, W., Zhou, Y., Zilli, E., Zoita, V., Zoletnik, S., and Zychor, I.
Abstract: The 2014-2016 JET results are reviewed in the light of their significance for optimising the ITER research plan for the active and non-active operation. More than 60 h of plasma operation with ITER first wall materials successfully took place since its installation in 2011. New multi-machine scaling of the type I-ELM divertor energy flux density to ITER is supported by first principle modelling. ITER relevant disruption experiments and first principle modelling are reported with a set of three disruption mitigation valves mimicking the ITER setup. Insights of the L-H power threshold in Deuterium and Hydrogen are given, stressing the importance of the magnetic configurations and the recent measurements of fine-scale structures in the edge radial electric. Dimensionless scans of the core and pedestal confinement provide new information to elucidate the importance of the first wall material on the fusion performance. H-mode plasmas at ITER triangularity (H = 1 at beta(N) similar to 1.8 and n/n(GW) similar to 0.6) have been sustained at 2 MA during 5 s. The ITER neutronics codes have been validated on high performance experiments. Prospects for the coming D-T campaign and 14 MeV neutron calibration strategy are reviewed.
Published: 2017
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4. The global build-up to intrinsic edge localized mode bursts seen in divertor full flux loops in JET

Author: Chapman, S. C., Andersson Sundén, Erik, Militello Asp, Emilia, Binda, Federico, Cecconello, Marco, Conroy, Sean, Dzysiuk, Natalia, Ericsson, Göran, Eriksson, Jacob, Hellesen, Carl, Hjalmarsson, Anders, Possnert, Göran, Sjöstrand, Henrik, Skiba, Mateusz, Weiszflog, Matthias, and Zychor, I.
Subjects: Fusion, plasma och rymdfysik, Fusion, Plasma and Space Physics
Abstract: A global signature of the build-up to an intrinsic edge localized mode (ELM) is found in the temporal analytic phase of signals measured in full flux azimuthal loops in the divertor region of JET. Toroidally integrating, full flux loop signals provide a global measurement proportional to the voltage induced by changes in poloidal magnetic flux; they are electromagnetically induced by the dynamics of spatially integrated current density. We perform direct time-domain analysis of the high time-resolution full flux loop signals VLD2 and VLD3. We analyze plasmas where a steady H-mode is sustained over several seconds during which all the observed ELMs are intrinsic; there is no deliberate intent to pace the ELMing process by external means. ELM occurrence times are determined from the Be II emission at the divertor. We previously [ Chapman et al., Phys. Plasmas 21, 062302 (2014); Chapman et al., in 41st EPS Conference on Plasma Physics, Europhysics Conference Abstracts (European Physical Society, 2014), Vol. 38F, ISBN 2-914771-90-8] found that the occurrence times of intrinsic ELMs correlate with specific temporal analytic phases of the VLD2 and VLD3 signals. Here, we investigate how the VLD2 and VLD3 temporal analytic phases vary with time in advance of the ELM occurrence time. We identify a build-up to the ELM in which the VLD2 and VLD3 signals progressively align to the temporal analytic phase at which ELMs preferentially occur, on a similar to 2 - 5ms timescale. At the same time, the VLD2 and VLD3 signals become temporally phase synchronized with each other, consistent with the emergence of coherent global dynamics in the integrated current density. In a plasma that remains close to a global magnetic equilibrium, this can reflect bulk displacement or motion of the plasma. This build-up signature to an intrinsic ELM can be extracted from a time interval of data that does not extend beyond the ELM occurrence time, so that these full flux loop signals could assist in ELM prediction or mitigation. (C) 2015 Author(s). All article content, except where otherwise noted, is licensed under a Creative Commons Attribution 3.0 Unported License. For complete list of authors see http://dx.doi.org/10.1063/1.4926592
Published: 2015

5. Determination of tungsten and molybdenum concentrations from an x-ray range spectrum in JET with the ITER-like wall configuration

Author: Nakano, T., Andersson Sundén, Erik, Militello Asp, Emilia, Binda, Federico, Cecconello, Marco, Conroy, Sean, Dzysiuk, Natalia, Ericsson, Göran, Eriksson, Jacob, Hellesen, Carl, Hjalmarsson, Anders, Possnert, Göran, Sjöstrand, Henrik, Skiba, Mateusz, Weiszflog, Matthias, Zychor, I., Nakano, T., Andersson Sundén, Erik, Militello Asp, Emilia, Binda, Federico, Cecconello, Marco, Conroy, Sean, Dzysiuk, Natalia, Ericsson, Göran, Eriksson, Jacob, Hellesen, Carl, Hjalmarsson, Anders, Possnert, Göran, Sjöstrand, Henrik, Skiba, Mateusz, Weiszflog, Matthias, and Zychor, I.
Abstract: The W45+ and W46+ 3p-4d inner shell excitation lines in addition to Mo32+ 2p-3s lines have been identified from the spectrum taken by an upgraded high-resolution x-ray spectrometer. It is found from analysis of the absolute intensities of the W46+ and Mo32+ lines that W and Mo concentrations are in the range of similar to 10(-5) and similar to 10(-6), respectively, with a ratio of similar to 5% in JET with the ITER-like wall configuration for ELMy H-mode plasmas with a plasma current of 2.0-2.5 MA, a toroidal magnetic field of 2.7 T and a neutral beam injection power of 14-18 MW. For the purpose of checking self-consistency, it is confirmed that the W concentration determined from the W45+ line is in agreement with that from the W46+ line within 20% and that the plasma effective charge determined from the continuum of the first order reflection spectrum is also in agreement with that from the second order within 50%. Further, the determined plasma effective charge is in agreement with that determined from a visible spectroscopy, confirming that the sensitivity of the x-ray spectrometer is valid and that the W and the Mo concentrations are also likely to be valid., For complete list of authors see http://dx.doi.org/10.1088/0953-4075/48/14/144023
Published: 2015
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6. Ion target impact energy during Type I edge localized modes in JET ITER-like Wall

Author: Guillemaut, C., Andersson Sundén, Erik, Militello Asp, Emilia, Binda, Federico, Cecconello, Marco, Conroy, Sean, Dzysiuk, Natalia, Ericsson, Göran, Eriksson, Jacob, Hellesen, Carl, Hjalmarsson, Anders, Possnert, Göran, Sjöstrand, Henrik, Skiba, Mateusz, Weiszflog, Matthias, Zychor, I., Guillemaut, C., Andersson Sundén, Erik, Militello Asp, Emilia, Binda, Federico, Cecconello, Marco, Conroy, Sean, Dzysiuk, Natalia, Ericsson, Göran, Eriksson, Jacob, Hellesen, Carl, Hjalmarsson, Anders, Possnert, Göran, Sjöstrand, Henrik, Skiba, Mateusz, Weiszflog, Matthias, and Zychor, I.
Abstract: The ITER baseline scenario, with 500 MW of DT fusion power and Q = 10, will rely on a Type I ELMy H-mode, with Delta W = 0.7 MJ mitigated edge localized modes (ELMs). Tungsten (W) is the material now decided for the divertor plasma-facing components from the start of plasma operations. W atoms sputtered from divertor targets during ELMs are expected to be the dominant source under the partially detached divertor conditions required for safe ITER operation. W impurity concentration in the plasma core can dramatically degrade its performance and lead to potentially damaging disruptions. Understanding the physics of plasma-wall interaction during ELMs is important and a primary input for this is the energy of incoming ions during an ELM event. In this paper, coupled Infrared thermography and Langmuir Probe (LP) measurements in JET-ITER-Like-Wall unseeded H-mode experiments with ITER relevant ELM energy drop have been used to estimate the impact energy of deuterium ions (D+) on the divertor target. This analysis gives an ion energy of several keV during ELMs, which makes D+ responsible for most of the W sputtering in unseeded H-mode discharges. These LP measurements were possible because of the low electron temperature (T-e) during ELMs which allowed saturation of the ion current. Although at first sight surprising, the observation of low T-e at the divertor target during ELMs is consistent with the 'Free-Streaming' kinetic model which predicts a near-complete transfer of parallel energy from electrons to ions in order to maintain quasi-neutrality of the ELM filaments while they are transported to the divertor targets., For complete list of authors see http://dx.doi.org/10.1088/0741-3335/57/8/085006
Published: 2015
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7. Experimental evaluation of stable long term operation of semiconductor magnetic sensors at ITER relevant environment

Author: Bolshakova, I., Andersson Sundén, Erik, Militello Asp, Emilia, Binda, Federico, Cecconello, Marco, Conroy, Sean, Dzysiuk, Natalia, Ericsson, Göran, Eriksson, Jacob, Hellesen, Carl, Hjalmarsson, Anders, Possnert, Göran, Sjöstrand, Henrik, Skiba, Mateusz, Weiszflog, Matthias, Zychor, I., Bolshakova, I., Andersson Sundén, Erik, Militello Asp, Emilia, Binda, Federico, Cecconello, Marco, Conroy, Sean, Dzysiuk, Natalia, Ericsson, Göran, Eriksson, Jacob, Hellesen, Carl, Hjalmarsson, Anders, Possnert, Göran, Sjöstrand, Henrik, Skiba, Mateusz, Weiszflog, Matthias, and Zychor, I.
Abstract: The paper deals with radiation resistant sensors and their associated measuring instrumentation developed in the course of R and D activities carried out in the framework of an international collaboration. The first trial tests of three-dimensional (3D) probes with Hall sensors have been performed in European tokamaks TORE SUPRA (2004) and JET (2005). Later in 2009 six sets of 3D probes were installed in JET and now continue to operate. The statistical analysis performed in 2014 on the basis of the JET database have demonstrated stable long term operation of all 18 sensors of 3D probes. The results of measurements conducted at the neutron fluxes of nuclear reactors have demonstrated the operability of the sensors up to high neutron fluences of F > 10(18)n , cm(-2) that exceeds the maximum one for the locations of steady state sensors in ITER over its total lifetime., For complete list of authors see http://dx.doi.org/10.1088/0029-5515/55/8/083006
Published: 2015
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8. On the interpretation of high-resolution x-ray spectra from JET with an ITER-like wall

Author: Slabkowska, K., Andersson Sundén, Erik, Militello Asp, Emilia, Binda, Federico, Cecconello, Marco, Conroy, Sean, Dzysiuk, Natalia, Ericsson, Göran, Eriksson, Jacob, Hellesen, Carl, Hjalmarsson, Anders, Possnert, Göran, Sjöstrand, Henrik, Skiba, Mateusz, Weiszflog, Matthias, Zychor, I., Slabkowska, K., Andersson Sundén, Erik, Militello Asp, Emilia, Binda, Federico, Cecconello, Marco, Conroy, Sean, Dzysiuk, Natalia, Ericsson, Göran, Eriksson, Jacob, Hellesen, Carl, Hjalmarsson, Anders, Possnert, Göran, Sjöstrand, Henrik, Skiba, Mateusz, Weiszflog, Matthias, and Zychor, I.
Abstract: The upgraded x-ray crystal spectrometer KX1 on the Joint European Torus (JET) can now measure the M x-ray lines from tungsten with sufficiently high resolution to evaluate how much tungsten may sputter from the plasma-facing tungsten wall planned for the International Thermonuclear Experimental Reactor (ITER). However, a test run on JET found that the L x-ray lines of a molybdenum impurity, which happen to occur in the targeted wavelength region of 5.00-5.35 angstrom, must be taken into account together with the radiation from the M x-ray lines of tungsten to match the high-resolution spectra. Such detailed radiation modeling is expected to be needed for ASDEX Upgrade tokamak, and for other tokamaks such as ITER and tungsten (W) Environment in Steady-state Tokamak (WEST), which will implement tungsten plasma-facing components and a high-resolution spectrometer to keep track of with a similar x-ray diagnostics., For complete list of authors see http://dx.doi.org/10.1088/0953-4075/48/14/144028
Published: 2015
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9. Discriminating the trapped electron modes contribution in density fluctuation spectra

Author: Arnichand, H., Andersson Sundén, Erik, Militello Asp, Emilia, Binda, Federico, Cecconello, Marco, Conroy, Sean, Dzysiuk, Natalia, Ericsson, Göran, Eriksson, Jacob, Hellesen, Carl, Hjalmarsson, Anders, Possnert, Göran, Sjöstrand, Henrik, Skiba, Mateusz, Weiszflog, Matthias, Zychor, I., Arnichand, H., Andersson Sundén, Erik, Militello Asp, Emilia, Binda, Federico, Cecconello, Marco, Conroy, Sean, Dzysiuk, Natalia, Ericsson, Göran, Eriksson, Jacob, Hellesen, Carl, Hjalmarsson, Anders, Possnert, Göran, Sjöstrand, Henrik, Skiba, Mateusz, Weiszflog, Matthias, and Zychor, I.
Abstract: Quasi-coherent (QC) modes have been reported for more than 10 years in reflectometry fluctuations spectra in the core region of fusion plasmas. They have characteristics in-between coherent and broadband fluctuations as they oscillate at a marked frequency but have a wide spectrum. This work presents further evidences of the link recently established between QC modes and the trapped electron modes (TEM) instabilities (Arnichand et al 2014 Nucl. Fusion 54 123017). In electron cyclotron resonance heated discharges of Tore Supra, an enhancement of QC modes amplitude is observed in a region where TEM cause impurity transport and turbulence. In JET Ohmic plasmas, QC modes disappear during density ramp-up and current ramp-down. This is reminiscent of Tore Supra and TEXTOR observations during transitions from the linear Ohmic confinement (LOC) to the saturated Ohmic confinement (SOC) regimes. Evidencing TEM activity then becomes experimentally possible via analysis of fluctuation spectra., For complete list of authors see http://dx.doi.org/10.1088/0029-5515/55/9/093021
Published: 2015
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10. Influence of the E X B drift in high recycling divertors on target asymmetries

Author: Chankin, A. V., Andersson Sundén, Erik, Militello Asp, Emilia, Binda, Federico, Cecconello, Marco, Conroy, Sean, Dzysiuk, Natalia, Ericsson, Göran, Eriksson, Jacob, Hellesen, Carl, Hjalmarsson, Anders, Possnert, Göran, Sjöstrand, Henrik, Skiba, Mateusz, Weiszflog, Matthias, Zychor, I., Chankin, A. V., Andersson Sundén, Erik, Militello Asp, Emilia, Binda, Federico, Cecconello, Marco, Conroy, Sean, Dzysiuk, Natalia, Ericsson, Göran, Eriksson, Jacob, Hellesen, Carl, Hjalmarsson, Anders, Possnert, Göran, Sjöstrand, Henrik, Skiba, Mateusz, Weiszflog, Matthias, and Zychor, I.
Abstract: Detailed analysis of convective fluxes caused by E x B drifts is carried out in a realistic JET configuration, based on a series of EDGE2D-EIRENE runs. The EDGE2D-EIRENE code includes all guiding centre drifts, E x B as well as. B and centrifugal drifts. Particle sources created by divergences of radial and poloidal components of the E x B drift are separately calculated for each flux tube in the divertor. It is demonstrated that in high recycling divertor conditions radial E x B drift creates particle sources in the common flux region (CFR) consistent with experimentally measured divertor and target asymmetries, with the poloidal E x B drift creating sources of an opposite sign but smaller in absolute value. That is, the experimentally observed asymmetries in the CFR are the opposite to what poloidal E x B drift by itself would cause. In the private flux region (PFR), the situation is reversed, with poloidal E x B drift being dominant. In this region poloidal E x B drift by itself contributes to experimentally observed asymmetries. Thus, in each region, the dominant component of the E x B drift acts so as to create the density (and hence, also temperature) asymmetries that are observed both in experiment and in 2D edge fluid codes. Since the total number of charged particles is much greater in the CFR than in PFR, divertor asymmetries caused by the E x B drift should be attributed primarily to particle sources in the CFR caused by radial E x B drift., For complete list of authors see http://dx.doi.org/10.1088/0741-3335/57/9/095002
Published: 2015
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11. Key impact of finite-beta and fast ions in core and edge tokamak regions for the transition to advanced scenarios

Author: Garcia, J., Andersson Sundén, Erik, Militello Asp, Emilia, Binda, Federico, Cecconello, Marco, Conroy, Sean, Dzysiuk, Natalia, Ericsson, Göran, Eriksson, Jacob, Hellesen, Carl, Hjalmarsson, Anders, Possnert, Göran, Sjöstrand, Henrik, Skiba, Mateusz, Weiszflog, Matthias, Zychor, I., Garcia, J., Andersson Sundén, Erik, Militello Asp, Emilia, Binda, Federico, Cecconello, Marco, Conroy, Sean, Dzysiuk, Natalia, Ericsson, Göran, Eriksson, Jacob, Hellesen, Carl, Hjalmarsson, Anders, Possnert, Göran, Sjöstrand, Henrik, Skiba, Mateusz, Weiszflog, Matthias, and Zychor, I.
Abstract: Extensive linear and non-linear gyrokinetic simulations and linear magnetohydrodynamic (MHD) analyses performed for JET hybrid discharges with improved confinement have shown that the large population of fast ions found in the plasma core under particular heating conditions has a strong impact on core microturbulence and edge MHD by reducing core ion heat fluxes and increasing pedestal pressure in a feedback mechanism. In the case of the ITER like wall, it is shown how this mechanism plays a decisive role for the transition to plasma regimes with improved confinement and it can explain the weak power degradation obtained in dedicated power scans. The mechanism is found to be highly dependent on plasma triangularity as it changes the balance between the improvement in the plasma core and the edge. The feedback mechanism can play a similar role in the ITER hybrid scenario as in the JET discharges analysed due to its high triangularity plasmas and the large amount of fast ions generated in the core by the heating systems and the alpha power., For complete list of authors see http://dx.doi.org/10.1088/0029-5515/55/5/053007
Published: 2015
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12. Comparative analysis of core heat transport of JET high density H-mode plasmas in carbon wall and ITER-like wall

Author: Kim, Hyun-Tae, Andersson Sundén, Erik, Militello Asp, Emilia, Binda, Federico, Cecconello, Marco, Conroy, Sean, Dzysiuk, Natalia, Ericsson, Göran, Eriksson, Jacob, Hellesen, Carl, Hjalmarsson, Anders, Possnert, Göran, Sjöstrand, Henrik, Skiba, Mateusz, Weiszflog, Matthias, Zychor, I., Kim, Hyun-Tae, Andersson Sundén, Erik, Militello Asp, Emilia, Binda, Federico, Cecconello, Marco, Conroy, Sean, Dzysiuk, Natalia, Ericsson, Göran, Eriksson, Jacob, Hellesen, Carl, Hjalmarsson, Anders, Possnert, Göran, Sjöstrand, Henrik, Skiba, Mateusz, Weiszflog, Matthias, and Zychor, I.
Abstract: A consistent deterioration of global confinement in H-mode experiments has been observed in JET [1] following the replacement of all carbon plasma facing components (PFCs) with an all metal ('ITER-like') wall (ILW). This has been correlated to the observed degradation of the pedestal confinement, as lower electron temperature (T-e) values are routinely measured at the top of the edge barrier region. A comparative investigation of core heat transport in JET-ILW and JET-CW (carbon wall) discharges has been performed, to assess whether core confinement has also been affected by the wall change. The results presented here have been obtained by analysing a set of discharges consisting of high density JET-ILW H-mode plasmas and comparing them against their counterpart discharges in JET-CW having similar global operational parameters. The set contains 10 baseline (beta(N) = 1. 5 similar to 2) discharge-pairs with 2.7 T toroidal magnetic field, 2.5 MA plasma current, and 14 to 17 MW of neutral beam injection (NBI) heating. Based on a T-e profile analysis using high resolution Thomson scattering (HRTS) data, the T-e profile peaking (i.e. core T-e (rho = 0.3)/edge T-e (rho = 0.7)) is found to be similar, and weakly dependent on edge T-e, for both JET-ILW and JET-CW discharges. When ILW discharges are seeded with N-2, core and edge T-e both increase to maintain a similar peaking factor. The change in core confinement is addressed with interpretative TRANSP simulations. It is found that JET-ILW H-mode plasmas have higher NBI power deposition to electrons and lower NBI power deposition to ions as compared to the JET-CW counterparts. This is an effect of the lower electron temperature at the top of the pedestal. As a result, the core electron energy confinement time is reduced in JET-ILW discharges, but the core ion energy confinement time is not decreased. Overall, the core energy confinement is found to be the same in the JET-ILW discharges compared to the JET-CW counterparts., For complete list of authors see http://dx.doi.org/10.1088/0741-3335/57/6/065002
Published: 2015
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13. Conceptual Design Of The Mechanical Tritium Pumping System For Jet Dte2

Author: Giegerich, Thomas, Andersson Sundén, Erik, Militello Asp, Emilia, Binda, Federico, Cecconello, Marco, Conroy, Sean, Dzysiuk, Natalia, Ericsson, Göran, Eriksson, Jacob, Hellesen, Carl, Hjalmarsson, Anders, Possnert, Göran, Sjöstrand, Henrik, Skiba, Mateusz, Weiszflog, Matthias, Zychor, I., Giegerich, Thomas, Andersson Sundén, Erik, Militello Asp, Emilia, Binda, Federico, Cecconello, Marco, Conroy, Sean, Dzysiuk, Natalia, Ericsson, Göran, Eriksson, Jacob, Hellesen, Carl, Hjalmarsson, Anders, Possnert, Göran, Sjöstrand, Henrik, Skiba, Mateusz, Weiszflog, Matthias, and Zychor, I.
Abstract: This paper describes the conceptual design of the Mechanical Tritium Pumping System (MTPS) that shall be installed and tested at JET during the next Deuterium-Tritium-Experiment (DTE2). This pump train uses a two-stage liquid ring pump in combination with a booster pump to cover a pressure regime from 10(-1) Pa to 10(5) Pa. As working fluid for all pumps, mercury will be used for tritium compatibility reasons. Starting from the requirements to MTPS, the pumps and their arrangement will be described in this paper as well as the mercury containment strategy and safety- and control issues., For complete list of authors see http://dx.doi.org/10.13182/FST14-950
Published: 2015
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14. WALLDYN simulations of global impurity migration in JET and extrapolations to ITER

Author: Schmid, K., Andersson Sundén, Erik, Militello Asp, Emilia, Binda, Federico, Cecconello, Marco, Conroy, Sean, Dzysiuk, Natalia, Ericsson, Göran, Eriksson, Jacob, Hellesen, Carl, Hjalmarsson, Anders, Possnert, Göran, Sjöstrand, Henrik, Skiba, Mateusz, Weiszflog, Matthias, Zychor, I., Schmid, K., Andersson Sundén, Erik, Militello Asp, Emilia, Binda, Federico, Cecconello, Marco, Conroy, Sean, Dzysiuk, Natalia, Ericsson, Göran, Eriksson, Jacob, Hellesen, Carl, Hjalmarsson, Anders, Possnert, Göran, Sjöstrand, Henrik, Skiba, Mateusz, Weiszflog, Matthias, and Zychor, I.
Abstract: The migration of first wall material due to erosion, plasma transport and re-deposition is one of the key challenges in current and future fusion devices. To predict erosion/re-deposition patterns and to understand the underlying principal processes, the global simulation code WallDYN was developed. It couples the evolution of the first wall surface composition to plasma impurity transport. To benchmark the WallDYN model, it was applied to the JET ITER-like wall experiment (JET-ILW), which mimics the ITER first wall material configuration and is thus an ideal environment to validate the predictive significance of WallDYN calculations for ITER application. The WallDYN calculations show good agreement with the Be deposition patterns determined from JET-ILWpost-campaign wall tile analysis. The WallDYN results on W erosion and deposition also qualitatively match the post mortem patterns but quantitatively fall short by a factor of 20 which can be consolidated by including the influence of ELMs on the W erosion source. Applying the same model and process physics as for the JET calculations, the impurity migration and resulting fuel species co-deposition in ITER for different wall configurations and background plasmas were calculated. The simulations show that C containing wall configurations lead to unacceptable T retention whereas for the current ITER material choice (Be wall and W divertor) co-deposition will not limit the ITER operation. However the erosion of W by self-sputtering even without the contribution of ELMs could hamper ITER operation under certain plasma scenarios., For complete list of authors see http://dx.doi.org/10.1088/0029-5515/55/5/053015
Published: 2015
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15. Integrated core-SOL-divertor modelling for ITER including impurity : effect of tungsten on fusion performance in H-mode and hybrid scenario

Author: Zagorski, R., Andersson Sundén, Erik, Militello Asp, Emilia, Binda, Federico, Cecconello, Marco, Conroy, Sean, Dzysiuk, Natalia, Ericsson, Göran, Eriksson, Jacob, Hellesen, Carl, Hjalmarsson, Anders, Possnert, Göran, Sjöstrand, Henrik, Skiba, Mateusz, Weiszflog, Matthias, Zychor, I., Zagorski, R., Andersson Sundén, Erik, Militello Asp, Emilia, Binda, Federico, Cecconello, Marco, Conroy, Sean, Dzysiuk, Natalia, Ericsson, Göran, Eriksson, Jacob, Hellesen, Carl, Hjalmarsson, Anders, Possnert, Göran, Sjöstrand, Henrik, Skiba, Mateusz, Weiszflog, Matthias, and Zychor, I.
Abstract: The compatibility of two operational constraints-operation above the L-H power threshold and at low power to divertor-is examined for ITER long pulse H-mode and hybrid scenarios in integrated core-scrape off layer (SOL)-divertor modelling including impurities (intrinsic Be, He, Wand seeded Ne). The core thermal, particle and momentum transport is simulated with the GLF23 transport model tested in the self-consistent simulations of temperatures, density and toroidal rotation velocity in JET hybrid discharges and extrapolated to ITER. The beneficial effect of toroidal rotation velocity on fusion gain is shown. The sensitivity studies with respect to operational (separatrix and pedestal density, Ne gas puff) and unknown physics (W convective velocity and perpendicular diffusion in SOL as well as W prompt re-deposition) parameters are performed to determine their influence on the operational window and fusion gain., For complete list of authors see http://dx.doi.org/10.1088/0029-5515/55/5/053032
Published: 2015
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16. The impact of poloidal asymmetries on tungsten transport in the core of JET H-mode plasmas

Author: Angioni, C., Andersson Sundén, Erik, Militello Asp, Emilia, Binda, Federico, Cecconello, Marco, Conroy, Sean, Dzysiuk, Natalia, Ericsson, Göran, Eriksson, Jacob, Hellesen, Carl, Hjalmarsson, Anders, Possnert, Göran, Sjöstrand, Henrik, Skiba, Mateusz, Weiszflog, Matthias, Zychor, I., Angioni, C., Andersson Sundén, Erik, Militello Asp, Emilia, Binda, Federico, Cecconello, Marco, Conroy, Sean, Dzysiuk, Natalia, Ericsson, Göran, Eriksson, Jacob, Hellesen, Carl, Hjalmarsson, Anders, Possnert, Göran, Sjöstrand, Henrik, Skiba, Mateusz, Weiszflog, Matthias, and Zychor, I.
Abstract: Recent progress in the understanding and prediction of the tungsten behaviour in the core of JET H-mode plasmas with ITER-like wall is presented. Particular emphasis is given to the impact of poloidal asymmetries of the impurity density. In particular, it is shown that the predicted reduction of temperature screening induced by the presence of low field side localization of the tungsten density produced by the centrifugal force is consistent with the observed tungsten behaviour in a JET discharge in H-mode baseline scenario. This provides first evidence of the role of poloidal asymmetries in reducing the strength of temperature screening. The main differences between plasma parameters in JET baseline and hybrid scenario discharges which affect the impact of poloidally asymmetric density on the tungsten radial transport are identified. This allows the conditions by which tungsten accumulation can be avoided to be more precisely defined., For complete list of authors see http://dx.doi.org/10.1063/1.4919036
Published: 2015
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17. Three-dimensional non-linear magnetohydrodynamic modeling of massive gas injection triggered disruptions in JET

Author: Fil, A., Andersson Sundén, Erik, Militello Asp, Emilia, Binda, Federico, Cecconello, Marco, Conroy, Sean, Dzysiuk, Natalia, Ericsson, Göran, Eriksson, Jacob, Hellesen, Carl, Hjalmarsson, Anders, Possnert, Göran, Sjöstrand, Henrik, Skiba, Mateusz, Weiszflog, Matthias, Zychor, I., Fil, A., Andersson Sundén, Erik, Militello Asp, Emilia, Binda, Federico, Cecconello, Marco, Conroy, Sean, Dzysiuk, Natalia, Ericsson, Göran, Eriksson, Jacob, Hellesen, Carl, Hjalmarsson, Anders, Possnert, Göran, Sjöstrand, Henrik, Skiba, Mateusz, Weiszflog, Matthias, and Zychor, I.
Abstract: JOREK 3D non-linear MHD simulations of a D-2 Massive Gas Injection (MGI) triggered disruption in JET are presented and compared in detail to experimental data. The MGI creates an overdensity that rapidly expands in the direction parallel to the magnetic field. It also causes the growth of magnetic islands (m/n = 2/1 and 3/2 mainly) and seeds the 1/1 internal kink mode. O-points of all island chains (including 1/1) are located in front of the MGI, consistently with experimental observations. A burst of MHD activity and a peak in plasma current take place at the same time as in the experiment. However, the magnitude of these two effects is much smaller than in the experiment. The simulated radiation is also much below the experimental level. As a consequence, the thermal quench is not fully reproduced. Directions for progress are identified. Radiation from impurities is a good candidate. (C) 2015 AIP Publishing LLC., For complete list of authors see http://dx.doi.org/10.1063/1.4922846
Published: 2015
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18. Beryllium migration in JET ITER-like wall plasmas

Author: Brezinsek, S., Andersson Sundén, Erik, Militello Asp, Emilia, Binda, Federico, Cecconello, Marco, Conroy, Sean, Dzysiuk, Natalia, Ericsson, Göran, Eriksson, Jacob, Hellesen, Carl, Hjalmarsson, Anders, Possnert, Göran, Sjöstrand, Henrik, Skiba, Mateusz, Weiszflog, Matthias, Zychor, I., Brezinsek, S., Andersson Sundén, Erik, Militello Asp, Emilia, Binda, Federico, Cecconello, Marco, Conroy, Sean, Dzysiuk, Natalia, Ericsson, Göran, Eriksson, Jacob, Hellesen, Carl, Hjalmarsson, Anders, Possnert, Göran, Sjöstrand, Henrik, Skiba, Mateusz, Weiszflog, Matthias, and Zychor, I.
Abstract: JET is used as a test bed for ITER, to investigate beryllium migration which connects the lifetime of first-wall components under erosion with tokamak safety, in relation to long-term fuel retention. The (i) limiter and the (ii) divertor configurations have been studied in JET-ILW (JET with a Be first wall and W divertor), and compared with those for the former JET-C (JET with carbon-based plasma-facing components (PFCs)). (i) For the limiter configuration, the Be gross erosion at the contact point was determined in situ by spectroscopy as between 4% (E-in = 35 eV) and more than 100%, caused by Be self-sputtering (E-in = 200 eV). Chemically assisted physical sputtering via BeD release has been identified to contribute to the effective Be sputtering yield, i.e. at E-in = 75 eV, erosion was enhanced by about 1/3 with respect to the bare physical sputtering case. An effective gross yield of 10% is on average representative for limiter plasma conditions, whereas a factor of 2 difference between the gross erosion and net erosion, determined by post-mortem analysis, was found. The primary impurity source in the limiter configuration in JET-ILW is only 25% higher (in weight) than that for the JET-C case. The main fraction of eroded Be stays within the main chamber. (ii) For the divertor configuration, neutral Be and BeD from physically and chemically assisted physical sputtering by charge exchange neutrals and residual ion flux at the recessed wall enter the plasma, ionize and are transported by scrape-off layer flows towards the inner divertor where significant net deposition takes place. The amount of Be eroded at the first wall (21 g) and the Be amount deposited in the inner divertor (28 g) are in fair agreement, though the balancing is as yet incomplete due to the limited analysis of PFCs. The primary impurity source in the JET-ILW is a factor of 5.3 less in comparison with that for JET-C, resulting in lower divertor material deposition, by more than one order of magni, For complete list of authors see http://dx.doi.org/10.1088/0029-5515/55/6/063021
Published: 2015
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19. Free boundary equilibrium in 3D tokamaks with toroidal rotation

Author: Cooper, W. A., Andersson Sundén, Erik, Militello Asp, Emilia, Binda, Federico, Cecconello, Marco, Conroy, Sean, Dzysiuk, Natalia, Ericsson, Göran, Eriksson, Jacob, Hellesen, Carl, Hjalmarsson, Anders, Possnert, Göran, Sjöstrand, Henrik, Skiba, Mateusz, Weiszflog, Matthias, Zychor, I., Cooper, W. A., Andersson Sundén, Erik, Militello Asp, Emilia, Binda, Federico, Cecconello, Marco, Conroy, Sean, Dzysiuk, Natalia, Ericsson, Göran, Eriksson, Jacob, Hellesen, Carl, Hjalmarsson, Anders, Possnert, Göran, Sjöstrand, Henrik, Skiba, Mateusz, Weiszflog, Matthias, and Zychor, I.
Abstract: The three-dimensional VMEC equilibrium solver has been adapted to numerically investigate the approximate toroidal rotation model we have derived. We concentrate our applications on the simulation of JET snakes and MAST long-lived modes under free boundary conditions. Helical core solutions are triggered when exceeds a threshold value, typically 2.7% in JET-like plasmas. A large plasma current and edge bootstrap current can drive helical core formations at arbitrarily small in which the ideal saturated internal kink coexists with an ideal saturated external kink structure of opposite phase. The centrifugal force linked with the rotation has the effect of displacing the plasma column away from the major axis, but does not alter significantly the magnitude of the edge corrugation of the plasma. Error field correction coil currents in JET-like configurations increase the outer midplane distortions by 2 cm. The edge bootstrap current enhances the edge modulation of the plasma driven by the core snake deformations in MAST., For complete list of authors see http://dx.doi.org/10.1088/0029-5515/55/6/063032
Published: 2015
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20. WEST Physics Basis

Author: Bourdelle, C., Andersson Sundén, Erik, Militello Asp, Emilia, Binda, Federico, Cecconello, Marco, Conroy, Sean, Dzysiuk, Natalia, Ericsson, Göran, Eriksson, Jacob, Hellesen, Carl, Hjalmarsson, Anders, Possnert, Göran, Sjöstrand, Henrik, Skiba, Mateusz, Weiszflog, Matthias, Zychor, I., Bourdelle, C., Andersson Sundén, Erik, Militello Asp, Emilia, Binda, Federico, Cecconello, Marco, Conroy, Sean, Dzysiuk, Natalia, Ericsson, Göran, Eriksson, Jacob, Hellesen, Carl, Hjalmarsson, Anders, Possnert, Göran, Sjöstrand, Henrik, Skiba, Mateusz, Weiszflog, Matthias, and Zychor, I.
Abstract: With WEST (Tungsten Environment in Steady State Tokamak) (Bucalossi et al 2014 Fusion Eng. Des. 89 907-12), the Tore Supra facility and team expertise (Dumont et al 2014 Plasma Phys. Control. Fusion 56 075020) is used to pave the way towards ITER divertor procurement and operation. It consists in implementing a divertor configuration and installing ITER-like actively cooled tungsten monoblocks in the Tore Supra tokamak, taking full benefit of its unique long-pulse capability. WEST is a user facility platform, open to all ITER partners. This paper describes the physics basis of WEST: the estimated heat flux on the divertor target, the planned heating schemes, the expected behaviour of the L-H threshold and of the pedestal and the potential W sources. A series of operating scenarios has been modelled, showing that ITER-relevant heat fluxes on the divertor can be achieved in WEST long pulse H-mode plasmas., For complete list of authors see http://dx.doi.org/10.1088/0029-5515/55/6/063017
Published: 2015
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21. L to H mode transition : parametric dependencies of the temperature threshold

Author: Bourdelle, C., Andersson Sundén, Erik, Militello Asp, Emilia, Binda, Federico, Cecconello, Marco, Conroy, Sean, Dzysiuk, Natalia, Ericsson, Göran, Eriksson, Jacob, Hellesen, Carl, Hjalmarsson, Anders, Possnert, Göran, Sjöstrand, Henrik, Skiba, Mateusz, Weiszflog, Matthias, Zychor, I., Bourdelle, C., Andersson Sundén, Erik, Militello Asp, Emilia, Binda, Federico, Cecconello, Marco, Conroy, Sean, Dzysiuk, Natalia, Ericsson, Göran, Eriksson, Jacob, Hellesen, Carl, Hjalmarsson, Anders, Possnert, Göran, Sjöstrand, Henrik, Skiba, Mateusz, Weiszflog, Matthias, and Zychor, I.
Abstract: The L to H mode transition occurs at a critical power which depends on various parameters, such as the magnetic field, the density, etc. Experimental evidence on various tokamaks (JET, ASDEX-Upgrade, DIII-D, Alcator C-Mod) points towards the existence of a critical temperature characterizing the transition. This criterion for the L-H transition is local and is therefore easier to be compared to theoretical approaches. In order to shed light on the mechanisms of the transition, simple theoretical ideas are used to derive a temperature threshold (T-th). They are based on the stabilization of the underlying turbulence by a mean radial electric field shear. The nature of the turbulence varies as the collisionality decreases, from resistive ballooning modes to ion temperature gradient and trapped electron modes. The obtained parametric dependencies of the derived T-th are tested versus magnetic field, density, effective charge. Various robust experimental observations are reproduced, in particular T-th increases with magnetic field B and increases with density below the density roll-over observed on the power threshold., For complete list of authors see http://dx.doi.org/10.1088/0029-5515/55/7/073015
Published: 2015
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22. Turbulent transport analysis of JET H-mode and hybrid plasmas using QuaLiKiz and Trapped Gyro Landau Fluid

Author: Baiocchi, B., Andersson Sundén, Erik, Militello Asp, Elina, Binda, Federico, Cecconello, Marco, Conroy, Sean, Dzysiuk, Natalia, Ericsson, Göran, Eriksson, Jacob, Hellesen, Carl, Hjalmarsson, Anders, Possnert, Göran, Sjöstrand, Henrik, Skiba, Mateusz, Weiszflog, Matthias, Zychor, I., Baiocchi, B., Andersson Sundén, Erik, Militello Asp, Elina, Binda, Federico, Cecconello, Marco, Conroy, Sean, Dzysiuk, Natalia, Ericsson, Göran, Eriksson, Jacob, Hellesen, Carl, Hjalmarsson, Anders, Possnert, Göran, Sjöstrand, Henrik, Skiba, Mateusz, Weiszflog, Matthias, and Zychor, I.
Abstract: The physical transport processes at the basis of JET typical inductive H-mode scenarios and advanced hybrid regimes, with improved thermal confinement, are analyzed by means of some of the newest and more sophisticated quasi-linear transport models: trapped gyro Landau fluid (TGLF) and QuaLiKiz. The temporal evolution of JET pulses is modelled by CRONOS where the turbulent transport is modelled by either QuaLiKiz or TGLF. Both are first principle models with a more comprehensive physics than the models previously developed and therefore allow the analysis of the physics at the basis of the investigated scenarios. For H-modes, ion temperature gradient (ITG) modes are found to be dominant and the transport models are able to properly reproduce temperature profiles in self-consistent simulations. However, for hybrid regimes, in addition to ITG trapped electron modes (TEM) are also found to be important and different physical mechanisms for turbulence reduction play a decisive role. Whereas E x B flow shear and plasma geometry have a limited impact on turbulence, the presence of a large population of fast ions, quite important in low density regimes, can stabilize core turbulence mainly when the electromagnetic effects are taken into account. The TGLF transport model properly captures these mechanisms and correctly reproduces temperatures., For complete list of authors see http://dx.doi.org/10.1088/0741-3335/57/3/035003
Published: 2015
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23. Plasma isotopic changeover experiments in JET under carbon and ITER-like wall conditions

Author: Loarer, T., Andersson Sundén, Erik, Militello Asp, Elina, Binda, Federico, Cecconello, Marco, Conroy, Sean, Dzysiuk, Natalia, Ericsson, Göran, Eriksson, Jacob, Hellesen, Carl, Hjalmarsson, Anders, Possnert, Göran, Sjöstrand, Henrik, Skiba, Mateusz, Weiszflog, Matthias, Zychor, I., Loarer, T., Andersson Sundén, Erik, Militello Asp, Elina, Binda, Federico, Cecconello, Marco, Conroy, Sean, Dzysiuk, Natalia, Ericsson, Göran, Eriksson, Jacob, Hellesen, Carl, Hjalmarsson, Anders, Possnert, Göran, Sjöstrand, Henrik, Skiba, Mateusz, Weiszflog, Matthias, and Zychor, I.
Abstract: In JET-ILWisotopic plasma wall changeover experiments have been carried out to determine the amount of particles accessible by changing the plasma from H to D and from D to H. The gas balance analysis integrated over the experimental sessions show that the total amount of H or D removed from the wall is in the range of (1-3) x 10(22)D. For both changeover experiments, the respective plasma isotopic ratio behaviour is exactly the same as a function of the pulse number. After only 80 s of plasma (4 pulses), the plasma isotopic ratio is lower than 10%, below 4.5% after 13 pulses and then saturates around similar to 2-3%. In these conditions, the removal efficiency through plasma operation becomes very poor. The saturation of the plasma isotopic ratio in the range of 10% is also observed for the JET-C configuration although the amount of tritium retained in the vessel after the DT pulses was more than one order of magnitude compared to the retention observed with the JET-ILW. This demonstrates that the amount of particle recovery through plasma changeover is independent from the long term retention. Since this long term reservoir results from codeposition, these experiments suggest that there is a limited access to these codeposited particles by plasma isotopic changeover. Finally, in ITER, change over from D/T to H at the end of the discharge for possibly reducing the long term retention does not appear as a good strategy., For complete list of authors see http://dx.doi.org/10.1088/0029-5515/55/4/043021
Published: 2015
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24. Improved confinement in JET high beta plasmas with an ITER-like wall

Author: Challis, C. D., Andersson Sundén, Erik, Militello Asp, Elina, Binda, Federico, Cecconello, Marco, Conroy, Sean, Dzysiuk, Natalia, Ericsson, Göran, Eriksson, Jacob, Hellesen, Carl, Hjalmarsson, Anders, Possnert, Göran, Sjöstrand, Henrik, Skiba, Mateusz, Weiszflog, Matthias, Zychor, I., Challis, C. D., Andersson Sundén, Erik, Militello Asp, Elina, Binda, Federico, Cecconello, Marco, Conroy, Sean, Dzysiuk, Natalia, Ericsson, Göran, Eriksson, Jacob, Hellesen, Carl, Hjalmarsson, Anders, Possnert, Göran, Sjöstrand, Henrik, Skiba, Mateusz, Weiszflog, Matthias, and Zychor, I.
Abstract: The replacement of the JET carbon wall (C-wall) by a Be/W ITER-like wall (ILW) has affected the plasma energy confinement. To investigate this, experiments have been performed with both the C-wall and ILW to vary the heating power over a wide range for plasmas with different shapes. It was found that the power degradation of thermal energy confinement was weak with the ILW; much weaker than the IPB98(y,2) scaling and resulting in an increase in normalized confinement from H-98 similar to 0.9 at beta(N) similar to 1.5 to H-98 similar to 1.2 - 1.3 at beta(N) similar to 2.5 - 3.0 as the power was increased (where H-98 = tau(E)/tau(IPB98(y, 2)) and beta(N) = beta B-T(T)/aI(P) in %T/mMA). This reproduces the general trend in JET of higher normalized confinement in the so-called 'hybrid' domain, where normalized beta is typically above 2.5, compared with 'baseline' ELMy H-mode plasmas with beta(N) similar to 1.5-2.0. This weak power degradation of confinement, which was also seen with the C-wall experiments at low triangularity, is due to both increased edge pedestal pressure and core pressure peaking at high power. By contrast, the high triangularity C-wall plasmas exhibited elevated H-98 over a wide power range with strong, IPB98(y,2)-like, power degradation. This strong power degradation of confinement appears to be linked to an increase in the source of neutral particles from the wall as the power increased, an effect that was not reproduced with the ILW. The reason for the loss of improved confinement domain at low power with the ILW is yet to be clarified, but contributing factors may include changes in the rate of gas injection, wall recycling, plasma composition and radiation. The results presented in this paper show that the choice of wall materials can strongly affect plasma performance, even changing confinement scalings that are relied upon for extrapolation to future devices., For complete list of authors see http://dx.doi.org/10.1088/0029-5515/55/5/053031
Published: 2015
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25. Runaway electron beam generation and mitigation during disruptions at JET-ILW

Author: Reux, C., Andersson Sundén, Erik, Militello Asp, Emilia, Binda, Federico, Cecconello, Marco, Conroy, Sean, Dzysiuk, Natalia, Ericsson, Göran, Eriksson, Jacob, Hellesen, Carl, Hjalmarsson, Anders, Possnert, Göran, Sjöstrand, Henrik, Skiba, Mateusz, Weiszflog, Matthias, Zychor, I., Reux, C., Andersson Sundén, Erik, Militello Asp, Emilia, Binda, Federico, Cecconello, Marco, Conroy, Sean, Dzysiuk, Natalia, Ericsson, Göran, Eriksson, Jacob, Hellesen, Carl, Hjalmarsson, Anders, Possnert, Göran, Sjöstrand, Henrik, Skiba, Mateusz, Weiszflog, Matthias, and Zychor, I.
Abstract: Disruptions are a major operational concern for next generation tokamaks, including ITER. They may generate excessive heat loads on plasma facing components, large electromagnetic forces in the machine structures and several MA of multi-MeV runaway electrons. A more complete understanding of the runaway generation processes and methods to suppress them is necessary to ensure safe and reliable operation of future tokamaks. Runaway electrons were studied at JET-ILW showing that their generation dependencies (accelerating electric field, avalanche critical field, toroidal field, MHD fluctuations) are in agreement with current theories. In addition, vertical stability plays a key role in long runaway beam formation. Energies up to 20 MeV are observed. Mitigation of an incoming runaway electron beam triggered by massive argon injection was found to be feasible provided that the injection takes place early enough in the disruption process. However, suppressing an already accelerated runaway electron beam in the MA range was found to be difficult even with injections of more than 2 kPa.m(3) high-Z gases such as krypton or xenon. This may be due to the presence of a cold background plasma weakly coupled to the runaway electron beam which prevents neutrals from penetrating in the electron beam core. Following unsuccessful mitigation attempts, runaway electron impacts on beryllium plasma-facing components were observed, showing localized melting with toroidal asymmetries., For complete list of authors see http://dx.doi.org/10.1088/0029-5515/55/9/093013
Published: 2015
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26. The effects of impurities and core pressure on pedestal stability in Joint European Torus (JET)

Author: Saarelma, S., Andersson Sundén, Erik, Militello Asp, Elina, Binda, Federico, Cecconello, Marco, Conroy, Sean, Dzysiuk, Natalia, Ericsson, Göran, Eriksson, Jacob, Hellesen, Carl, Hjalmarsson, Anders, Possnert, Göran, Sjöstrand, Henrik, Skiba, Mateusz, Weiszflog, Matthias, Zychor, I., Saarelma, S., Andersson Sundén, Erik, Militello Asp, Elina, Binda, Federico, Cecconello, Marco, Conroy, Sean, Dzysiuk, Natalia, Ericsson, Göran, Eriksson, Jacob, Hellesen, Carl, Hjalmarsson, Anders, Possnert, Göran, Sjöstrand, Henrik, Skiba, Mateusz, Weiszflog, Matthias, and Zychor, I.
Abstract: The H-mode pedestal plays an important role in determining global confinement in tokamaks. In high triangularity H-mode experiments in Joint European Torus with the ITER-like wall (JET-ILW), significantly higher pedestal temperature and global confinement have been achieved with nitrogen seeding. The experimentally observed increase in pedestal height is inconsistent with the stability calculations using the experimental profiles. Numerically, we find that the consistency with stability improvement can be restored if we assume a shift of the pedestal inwards and increased ion dilution due to the impurity seeding. Significantly better confinement and pedestal height have been observed in JET-ILW plasmas when the core pressure is increased. The enhanced pedestal height can be linked to an improvement in edge stability arising from an increase in the Shafranov-shift, higher edge current, and pedestal widening in flux space., For complete list of authors see http://dx.doi.org/10.1063/1.4921413
Published: 2015
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27. Neutron production targets for a new Single Event Effects facility at the 70 MeV Cyclotron of LNL-INFN

Author: Bisello, Dario, primary, Candelori, Andrea, additional, Dzysiuk, Natalia, additional, Esposito, Juan, additional, Mastinu, Pierfrancesco, additional, Mattiazzo, Serena, additional, Prete, Gianfranco, additional, Silvestrin, Luca, additional, and Wyss, Jeffery, additional
Published: 2012
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28. A new irradiation facility for neutron-induced Single Event Effect studies at LNL

Author: Bisello, Dario, primary, Candelori, Andrea, additional, Dzysiuk, Natalia, additional, Esposito, Juan, additional, Mastinu, Pierfrancesco, additional, Mattiazzo, Serena, additional, Prete, Gianfranco, additional, Silvestrin, Luca, additional, and Wyss, Jeffery, additional
Published: 2011
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28 results on '"Dzysiuk, Natalia"'

1. Nuclear data for fusion technology – the European approach

2. Self-consistent coupling of DSMC method and SOLPS code for modeling tokamak particle exhaust

3. Overview of the JET results in support to ITER

4. The global build-up to intrinsic edge localized mode bursts seen in divertor full flux loops in JET

5. Determination of tungsten and molybdenum concentrations from an x-ray range spectrum in JET with the ITER-like wall configuration

6. Ion target impact energy during Type I edge localized modes in JET ITER-like Wall

7. Experimental evaluation of stable long term operation of semiconductor magnetic sensors at ITER relevant environment

8. On the interpretation of high-resolution x-ray spectra from JET with an ITER-like wall

9. Discriminating the trapped electron modes contribution in density fluctuation spectra

10. Influence of the E X B drift in high recycling divertors on target asymmetries

11. Key impact of finite-beta and fast ions in core and edge tokamak regions for the transition to advanced scenarios

12. Comparative analysis of core heat transport of JET high density H-mode plasmas in carbon wall and ITER-like wall

13. Conceptual Design Of The Mechanical Tritium Pumping System For Jet Dte2

14. WALLDYN simulations of global impurity migration in JET and extrapolations to ITER

15. Integrated core-SOL-divertor modelling for ITER including impurity : effect of tungsten on fusion performance in H-mode and hybrid scenario

16. The impact of poloidal asymmetries on tungsten transport in the core of JET H-mode plasmas

17. Three-dimensional non-linear magnetohydrodynamic modeling of massive gas injection triggered disruptions in JET

18. Beryllium migration in JET ITER-like wall plasmas

19. Free boundary equilibrium in 3D tokamaks with toroidal rotation

20. WEST Physics Basis

21. L to H mode transition : parametric dependencies of the temperature threshold

22. Turbulent transport analysis of JET H-mode and hybrid plasmas using QuaLiKiz and Trapped Gyro Landau Fluid

23. Plasma isotopic changeover experiments in JET under carbon and ITER-like wall conditions

24. Improved confinement in JET high beta plasmas with an ITER-like wall

25. Runaway electron beam generation and mitigation during disruptions at JET-ILW

26. The effects of impurities and core pressure on pedestal stability in Joint European Torus (JET)

27. Neutron production targets for a new Single Event Effects facility at the 70 MeV Cyclotron of LNL-INFN

28. A new irradiation facility for neutron-induced Single Event Effect studies at LNL

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28 results on '"Dzysiuk, Natalia"'

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