TY - JOUR
T1 - Overview of ASDEX Upgrade results
JF - Nuclear Fusion
Y1 - 2013
A1 - Stroth, U.
A1 - Adamek, J.
A1 - Aho-Mantila, L.
A1 - Akaslompolo, S.
A1 - Amdor, C.
A1 - Angioni, C.
A1 - Balden, M.
A1 - Bardin, S.
A1 - L. Barrera Orte
A1 - Behler, K.
A1 - Belonohy, E.
A1 - Bergmann, A.
A1 - Bernert, M.
A1 - Bilato, R.
A1 - Birkenmeier, G.
A1 - Bobkov, V.
A1 - Boom, J.
A1 - Bottereau, C.
A1 - Bottino, A.
A1 - Braun, F.
A1 - Brezinsek, S.
A1 - Brochard, T.
A1 - M. Brüdgam
A1 - Buhler, A.
A1 - Burckhart, A.
A1 - Casson, F. J.
A1 - Chankin, A.
A1 - Chapman, I.
A1 - Clairet, F.
A1 - Classen, I.G.J.
A1 - Coenen, J. W.
A1 - Conway, G. D.
A1 - Coster, D. P.
A1 - Curran, D.
A1 - da Silva, F.
A1 - P. de Marné
A1 - D'Inca, R.
A1 - Douai, D.
A1 - Drube, R.
A1 - Dunne, M.
A1 - Dux, R.
A1 - Eich, T.
A1 - Eixenberger, H.
A1 - Endstrasser, N.
A1 - Engelhardt, K.
A1 - Esposito, B.
A1 - Fable, E.
A1 - Fischer, R.
A1 - H. Fünfgelder
A1 - Fuchs, J. C.
A1 - K. Gál
A1 - M. García Muñoz
A1 - Geiger, B.
A1 - Giannone, L.
A1 - T. Görler
A1 - da Graca, S.
A1 - Greuner, H.
A1 - Gruber, O.
A1 - Gude, A.
A1 - Guimarais, L.
A1 - S. Günter
A1 - Haas, G.
A1 - Hakola, A. H.
A1 - Hangan, D.
A1 - Happel, T.
A1 - T. Härtl
A1 - Hauff, T.
A1 - Heinemann, B.
A1 - Herrmann, A.
A1 - Hobirk, J.
A1 - H. Höhnle
A1 - M. Hölzl
A1 - Hopf, C.
A1 - Houben, A.
A1 - Igochine, V.
A1 - Ionita, C.
A1 - Janzer, A.
A1 - Jenko, F.
A1 - Kantor, M.
A1 - C.-P. Käsemann
A1 - Kallenbach, A.
A1 - S. Kálvin
A1 - Kantor, M.
A1 - Kappatou, A.
A1 - Kardaun, O.
A1 - Kasparek, W.
A1 - Kaufmann, M.
A1 - Kirk, A.
A1 - H.-J. Klingshirn
A1 - Kocan, M.
A1 - Kocsis, G.
A1 - Konz, C.
A1 - Koslowski, R.
A1 - Krieger, K.
A1 - Kubic, M.
A1 - Kurki-Suonio, T.
A1 - Kurzan, B.
A1 - Lackner, K.
A1 - Lang, P. T.
A1 - Lauber, P.
A1 - Laux, M.
A1 - Lazaros, A.
A1 - Leipold, F.
A1 - Leuterer, F.
A1 - Lindig, S.
A1 - Lisgo, S.
A1 - Lohs, A.
A1 - Lunt, T.
A1 - Maier, H.
A1 - Makkonen, T.
A1 - Mank, K.
A1 - M.-E. Manso
A1 - Maraschek, M.
A1 - Mayer, M.
A1 - McCarthy, P. J.
A1 - McDermott, R.
A1 - Mehlmann, F.
A1 - Meister, H.
A1 - Menchero, L.
A1 - Meo, F.
A1 - Merkel, P.
A1 - Merkel, R.
A1 - Mertens, V.
A1 - Merz, F.
A1 - Mlynek, A.
A1 - Monaco, F.
A1 - Müller, S.
A1 - H.W. Müller
A1 - M. Münich
A1 - Neu, G.
A1 - Neu, R.
A1 - Neuwirth, D.
A1 - Nocente, M.
A1 - Nold, B.
A1 - Noterdaeme, J. M.
A1 - Pautasso, G.
A1 - Pereverzev, G.
A1 - B. Plöckl
A1 - Podoba, Y.
A1 - Pompon, F.
A1 - Poli, E.
A1 - Polozhiy, K.
A1 - Potzel, S.
A1 - M. J. Pueschel
A1 - Putterich, T.
A1 - Rathgeber, S. K.
A1 - Raupp, G.
A1 - Reich, M.
A1 - Reimold, F.
A1 - Ribeiro, T.
A1 - Riedl, R.
A1 - Rohde, V.
A1 - G. J. van Rooij
A1 - Roth, J.
A1 - Rott, M.
A1 - Ryter, F.
A1 - Salewski, M.
A1 - Santos, J.
A1 - Sauter, P.
A1 - Scarabosio, A.
A1 - Schall, G.
A1 - Schmid, K.
A1 - Schneider, P. A.
A1 - Schneider, W.
A1 - Schrittwieser, R.
A1 - Schubert, M.
A1 - Schweinzer, J.
A1 - Scott, B.
A1 - Sempf, M.
A1 - Sertoli, M.
A1 - Siccinio, M.
A1 - Sieglin, B.
A1 - Sigalov, A.
A1 - Silva, A.
A1 - Sommer, F.
A1 - A. Stäbler
A1 - Stober, J.
A1 - Streibl, B.
A1 - Strumberger, E.
A1 - Sugiyama, K.
A1 - Suttrop, W.
A1 - Tala, T.
A1 - Tardini, G.
A1 - Teschke, M.
A1 - Tichmann, C.
A1 - Told, D.
A1 - Treutterer, W.
A1 - Tsalas, M.
A1 - VanZeeland, M. A.
A1 - Varela, P.
A1 - Veres, G.
A1 - Vicente, J.
A1 - Vianello, N.
A1 - Vierle, T.
A1 - Viezzer, E.
A1 - Viola, B.
A1 - Vorpahl, C.
A1 - Wachowski, M.
A1 - Wagner, D.
A1 - Wauters, T.
A1 - Weller, A.
A1 - Wenninger, R.
A1 - Wieland, B.
A1 - Willensdorfer, M.
A1 - Wischmeier, M.
A1 - Wolfrum, E.
A1 - E. Würsching
A1 - Yu, Q.
A1 - Zammuto, I.
A1 - Zasche, D.
A1 - Zehetbauer, T.
A1 - Zhang, Y.
A1 - Zilker, M.
A1 - Zohm, H.
AB - The medium size divertor tokamak ASDEX Upgrade (major and minor radii 1.65 m and 0.5 m, respectively, magnetic-field strength 2.5 T) possesses flexible shaping and versatile heating and current drive systems. Recently the technical capabilities were extended by increasing the electron cyclotron resonance heating (ECRH) power, by installing 2 × 8 internal magnetic perturbation coils, and by improving the ion cyclotron range of frequency compatibility with the tungsten wall. With the perturbation coils, reliable suppression of large type-I edge localized modes (ELMs) could be demonstrated in a wide operational window, which opens up above a critical plasma pedestal density. The pellet fuelling efficiency was observed to increase which gives access to H-mode discharges with peaked density profiles at line densities clearly exceeding the empirical Greenwald limit. Owing to the increased ECRH power of 4 MW, H-mode discharges could be studied in regimes with dominant electron heating and low plasma rotation velocities, i.e. under conditions particularly relevant for ITER. The ion-pressure gradient and the neoclassical radial electric field emerge as key parameters for the transition. Using the total simultaneously available heating power of 23 MW, high performance discharges have been carried out where feed-back controlled radiative cooling in the core and the divertor allowed the divertor peak power loads to be maintained below 5 MW m −2 . Under attached divertor conditions, a multi-device scaling expression for the power-decay length was obtained which is independent of major radius and decreases with magnetic field resulting in a decay length of 1 mm for ITER. At higher densities and under partially detached conditions, however, a broadening of the decay length is observed. In discharges with density ramps up to the density limit, the divertor plasma shows a complex behaviour with a localized high-density region in the inner divertor before the outer divertor detaches. Turbulent transport is studied in the core and the scrape-off layer (SOL). Discharges over a wide parameter range exhibit a close link between core momentum and density transport. Consistent with gyro-kinetic calculations, the density gradient at half plasma radius determines the momentum transport through residual stress and thus the central toroidal rotation. In the SOL a close comparison of probe data with a gyro-fluid code showed excellent agreement and points to the dominance of drift waves. Intermittent structures from ELMs and from turbulence are shown to have high ion temperatures even at large distances outside the separatrix.
VL - 53
UR - http://hdl.handle.net/11858/00-001M-0000-0026-E166-7
IS - 10
U1 - FP
U2 - PDG
U5 - 0b5b08fdc590c85cc01e6d1db1958848
ER -
TY - JOUR
T1 - Recent results on Ion Cyclotron Wall Conditioning in mid and large size tokamaks
JF - Journal of Nuclear Materials
Y1 - 2011
A1 - Douai, D.
A1 - Lyssoivan, A.
A1 - Philipps, V.
A1 - Rohde, V.
A1 - Wauters, T.
A1 - Blackman, T.
A1 - Bobkov, V.
A1 - Bremond, S.
A1 - Brezinsek, S.
A1 - Clairet, F.
A1 - De La Cal, E.
A1 - Coyne, T.
A1 - Gauthier, E.
A1 - Gerbaud, T.
A1 - Graham, M.
A1 - Jachmich, S.
A1 - Joffrin, E.
A1 - Koch, R.
A1 - Kreter, A.
A1 - Laengner, R.
A1 - Lamalle, P. U.
A1 - Lerche, E.
A1 - Lombard, G.
A1 - Maslov, M.
A1 - Mayoral, M. L.
A1 - Miller, A.
A1 - Monakhov, I.
A1 - Noterdaeme, J. M.
A1 - Ongena, J.
A1 - Paul, M. K.
A1 - Pegourie, B.
A1 - Pitts, R.A.
A1 - Plyusnin, V.
A1 - Schüller, F. C.
A1 - Sergienko, G.
A1 - Shimada, M.
A1 - Sirinelli, A.
A1 - Suttrop, W.
A1 - Sozzi, C.
A1 - Tsalas, M.
A1 - Tsitrone, E.
A1 - Unterberg, B.
A1 - Van Eester, D.
KW - beryllium
KW - CLEANINGS
KW - DISCHARGES
KW - PERMANENT MAGNETIC-FIELD
KW - TORE-SUPRA
AB - Wall conditioning techniques applicable in the presence of permanent toroidal magnetic field will be required for the operation of ITER, in particular for recovery from disruptions, vent and air leak, isotopic ratio control, recycling control and mitigation of the tritium inventory build-up. Ion Cyclotron Wall Conditioning (ICWC) is one of the most promising options and has been the subject of considerable recent study on current tokamaks. This paper reports on the findings of such studies performed on European tokamaks, covering a range of plasma-facing materials: TORE SUPRA, TEXTOR, ASDEX Upgrade and JET. (C) 2010 Elsevier B.V. All rights reserved.

VL - 415
SN - 0022-3115
IS - 1, Suppl.
N1 - ISI Document Delivery No.: 862XTTimes Cited: 5Cited Reference Count: 1819th International Conference on Plasma-Surface Interactions in Controlled Fusion Devices (PSI)MAY 24-28, 2010San Diego, CALawrence Livermore Natl LabS
U1 - FP

U2 - PDG

U5 - 8cf46194dfe54d360b4630dacdd87add
ER -