Measurements and Modelling of Plasma Response Field to RMP On
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Validation of Equilibrium Tools on the COMPASS Tokamak Jakub Urban, L
Validation of equilibrium tools on the COMPASS tokamak Jakub Urban, L. C. Appel, J. F. Artaud, Blaise Faugeras, Josef Havlicek, Michael Komm, Ivan Lupelli, Matěj Peterka To cite this version: Jakub Urban, L. C. Appel, J. F. Artaud, Blaise Faugeras, Josef Havlicek, et al.. Validation of equi- librium tools on the COMPASS tokamak. SOFT 2014, 2014, San Sebastian, Spain. hal-01105044 HAL Id: hal-01105044 https://hal.archives-ouvertes.fr/hal-01105044 Submitted on 9 Oct 2019 HAL is a multi-disciplinary open access L’archive ouverte pluridisciplinaire HAL, est archive for the deposit and dissemination of sci- destinée au dépôt et à la diffusion de documents entific research documents, whether they are pub- scientifiques de niveau recherche, publiés ou non, lished or not. The documents may come from émanant des établissements d’enseignement et de teaching and research institutions in France or recherche français ou étrangers, des laboratoires abroad, or from public or private research centers. publics ou privés. Validation of equilibrium tools on the COMPASS tokamak J. Urbana, L.C. Appelb, J.F. Artaudc, B. Faugerasd, J. Havliceka,e, M. Komma, I. Lupellib, M. Peterkaa,e aInstitute of Plasma Physics ASCR, Za Slovankou 3, 182 00 Praha 8, Czech Republic bCCFE, Culham Science Centre, Abingdon, Oxfordshire, UK cCEA, IRFM, F-13108 Saint Paul Lez Durance, France dLaboratoire J.A. Dieudonn´e,UMR 7351, Universit´ede Nice Sophia-Antipolis, Parc Valrose, 06108 Nice Cedex 02, France eDepartment of Surface and Plasma Science, Faculty of Mathematics and Physics, Charles University in Prague, V Holeˇsoviˇck´ach 2, 180 00 Praha 8, Czech Republic Abstract Various MHD (magnetohydrodynamic) equilibrium tools, some of which being recently developed or considerably updated, are used on the COMPASS tokamak at IPP Prague. -
Visible Light Measurements on the COMPASS Tokamak
Visible light measurements on the COMPASS tokamak by Olivier Van Hoey Faculty of Engineering Department of Applied Physics Head of the department: Prof. Dr. Ir. C. Leys Visible light measurements on the COMPASS tokamak by Olivier Van Hoey Promoter: Prof. Dr. Ir. G. Van Oost Copromoter: D. Naydenkova The research reported in this thesis was performed at the Institute of Plasma Physics AS CR, Za Slovankou 1782/3, 182 00 Prague 8, Czech Republic Thesis submitted in order to obtain the degree of Master of Physics and Astronomy, option: Research Academic year 2009-2010 The most exciting phrase to hear in science, the one that heralds new discoveries, is not 'Eureka!', but 'That's funny...' - Isaac Asimov. Give me a lever long enough and a fulcrum on which to place it, and I shall move the world - Archimedes Nothing in life is to be feared. It is only to be understood - Marie Curie No amount of experimentation can ever prove me right; a single experiment can prove me wrong - Albert Einstein The science of today is the technology of tomorrow - Edward Teller Allowance to loan The author gives permission to make this thesis available for consultation and to copy parts of the thesis for personal use. Any other use is limited by the restrictions of copy- right, in particular with regard to the obligation to mention the source explicitly when citing results from this thesis. Olivier Van Hoey May 20, 2010 i Acknowledgment The achievement of this thesis was not possible without the help and support of a lot of people. -
Alfvén-Character Oscillations in Ohmic Plasmas Observed on the COMPASS Tokamak
44th EPS Conference on Plasma Physics P5.140 Alfvén-character oscillations in ohmic plasmas observed on the COMPASS tokamak T. Markovicˇ1;2, A. Melnikov3;4, J. Seidl1, L. Eliseev3, J. Havlicek1, A. Havránek1;5, M. Hron1, M. Imríšek1;2, K. Kovaríkˇ 1;2, K. Mitošinková1;2, J. Mlynar1, R. Pánek1, J. Stockel1, J. Varju1, V. Weinzettl1, the COMPASS Team1 1 Institute of Plasma Physics of the CAS, Prague, Czech Republic 2 Faculty of Mathematics and Physics, Charles Uni. in Prague, Prague, Czech Republic 3 National Research Centre ’Kurchatov Institute’, Moscow, Russian Federation 4 National Research Nuclear University MEPhi, Moscow, Russian Federation 5 Faculty of Electrical Engineering, Czech Tech. Uni. in Prague, Prague, Czech Republic Energetic Particle (EP) driven plasma modes resulting from interaction of shear Alfvén waves with fast (i.e. comparable to plasma Alfvén velocity VA) ions generated by fu- sion reactions, NBI or ICRH heating [1] are capable of causing fast particle losses, hence negatively affecting the plasma per- formance or having detrimental effects on plasma-facing components or vacuum vessel [2]. A number of comprehensive reviews has already been published, describing properties of EP modes, their appearance, excitation and damping mechanisms, etc. (e.g. [1, 2, 3]). The modes are not trivially expected to appear in ohmic plasmas, however, plasma oscillations bearing their typical signatures have been re- ported in plasmas without an apparent source of EP on a number of devices (such as TFTR [5], ASDEX-U [6], MAST [7], TUMAN-3M Figure 1: High-frequency magnetic fluctuations. [8]). While impact of these specific phenom- fAE curve from eq. -
Provisional Programme
Provisional Programme MONDAY TUESDAY WEDNESDAY THURSDAY Chair Persons Chair Persons Chair Persons Chair Persons 09:00 OPENING B. Gonçalves, D. Batani TUTORIAL T2 F. Wang, J. Santos TUTORIAL T3 M. Simek, R. Luis TUTORIAL T4 C. Silva, G. Zeraouli 09:15 09:30 TUTORIAL T1 A. Tuccillo, A. Romano 09:45 INVITED I2.1 INVITED I3.1 INVITED I4.1 10:00 10:15 ORAL O1.1 ORAL O2.1 ORAL O3.1 ORAL O4.1 10:30 COFFEE POSTER 1 COFFEE POSTER 2 COFFEE POSTER 3 COFFEE 10:45 11:00 ORAL O4.2 C. Silva, G. Zeraouli 11:15 ORAL O4.3 11:30 ORAL O4.4 11:45 ORAL O4.5 12:00 INVITED I1.1 A. Tuccillo, A. Romano INVITED I2.2 F. Wang, J. Santos INVITED I3.2 M. Simek, R. Luis INVITED I4.2 12:15 12:30 ORAL O1.2 INVITED I2.3 ORAL O3.2 INVITED I4.3 12:45 ORAL O1.3 ORAL O3.3 13:00 LUNCH LUNCH LUNCH LUNCH 13:15 13:30 13:45 14:00 14:15 14:30 14:45 INVITED I1.2 M. Fajardo, D. Mancelli FAENOV SESSION D. Batani, S. Malko INVITED I3.3 M. Feroci, P. Varela INVITED I4.4 L.L. Alves, L. Guimarãis 15:00 INTRO+ 2 TALKS 15:15 ORAL O1.4 F1-F2 ORAL O3.4 ORAL O4.6 15:30 COFFEE POSTER 1 COFFEE POSTER 2 COFFEE POSTER 3 COFFEE 15:45 16:00 ORAL O4.7 L.L. Alves, L. Guimarãis 16:15 INVITED I4.5 16:30 16:45 ORAL O1.5 M. -
2Nd IAEA Technical Meeting on Fusion Data Processing, Validation and Analysis
nd 2 IAEA Technical Meeting on Fusion Data Processing, Validation and Analysis Programme Book of Abstracts Boston, USA 30 May – 2 June, 2017 DISCLAIMER: This is not an official IAEA publication. The views expressed do not necessarily reflect those of the International Atomic Energy Agency or its Member States. The material has not undergone an official review by the IAEA. This document should not be quoted or listed as a reference. The use of particular designations of countries or territories does not imply any judgement by the IAEA, as to the legal status of such countries or territories, of their authorities and institutions or of the delimitation of their boundaries. The mention of names of specific companies or products (whether or not indicated as registered) does not imply any intention to infringe proprietary rights, nor should it be construed as an endorsement or recommendation on the part of the IAEA. Second Joint ITER-IAEA Technical Meeting Analysis of ITER Materials and Technologies 11-13 December 2012 The Gateway Hotel Ummed Ahmedabad Ahmedabad, India 2nd IAEA Technical Meeting on Fusion Data Processing, Validation and Analysis 30 May – 2 June, 2017 Boston, USA IAEA Scientific Secretary International Atomic Energy Agency Vienna International Centre Wagramer Straße 5, PO Box 100 Ms. Sehila Maria Gonzalez de Vicente A-1400 Vienna, Austria NAPC Physics Section Tel: +43-1-2600-21753 Fax: +43-1-26007 E-mail: [email protected] International Programme Advisory Committee Chair: N. Howard (USA) A. Dinklage (Germany), R. Fischer (Germany), S. Kajita (Japan), S. Kaye (USA), D. Mazon (France), D. McDonald (Eurofusion/EU), A. -
Losses of Runaway Electrons in MHD-Active Plasmas of the COMPASS Tokamak
Losses of runaway electrons in MHD-active plasmas of the COMPASS tokamak O Ficker1;2, J Mlynar1, M Vlainic1;2;3, J Cerovsky1;2, J Urban1, P Vondracek1;4, V Weinzettl1, E Macusova1, J Decker5,M Gospodarczyk5, P Martin7, E Nardon8, G Papp9,VV Plyusnin10, C Reux8, F Saint-Laurent8, C Sommariva8,J Cavalier1;11, J Havlicek1, A Havranek1;12, O Hronova1,M Imrisek1, T Markovic1;4, J Varju1, R Paprok1;4, R Panek1,M Hron1 and the COMPASS team 1 Institute of Plasma Physics of the CAS, CZ-18200 Praha 8, Czech Republic 2 FNSPE, Czech Technical University in Prague, CZ-11519 Praha 1, Czech Republic 3 Department of Applied Physics, Ghent University, 9000 Ghent, Belgium 4 FMP, Charles University, Ke Karlovu 3, CZ-12116 Praha 2, Czech Republic 5 Swiss Plasma Centre, EPFL, CH-1015 Lausanne, Switzerland 6 Universita’ di Roma Tor Vergata, 00133 Roma, Italy 7 Consorzio RFX, Corso Stati Uniti 4, 35127 Padova, Italy 8 CEA, IRFM, F-13108 Saint-Paul-lez-Durance, France 9 Max Planck Institute for Plasma Physics, Garching D-85748, Germany 10 Centro de Fusao Nuclear, IST, Lisbon, Portugal 11 Institut Jean Lamour IJL, Universite de Lorraine, 54000 Nancy, France 12 FEE, Czech Technical University in Prague, CZ-12000 Praha 2, Czech Republic E-mail: [email protected] Abstract. Significant role of magnetic perturbations in mitigation and losses of Runaway Electrons (REs) was documented in dedicated experimental studies of RE at the COMPASS tokamak. RE in COMPASS are produced both in low density quiescent discharges and in disruptions triggered by massive gas injection (MGI). -
Lyra' Divertor
ENERGY AND PARTICLE CONTROL CHARACTERISTICS OF THE ASDEX UPGRADE `LYRA' DIVERTOR M. Kaufmann, H-S. Bosch, A. Herrmann, A. Kallenbach, K. Borrass, A. Carlson, D. Coster, J.C. Fuchs, J. Gafert, K. Lackner, J. Neuhauser, R. Schneider, J. Schweinzer, W. Suttrop, W. Ullrich, U. Wenzel, and ASDEX Upgrade team Max-Planck-Institut fÈurPlasmaphysik, EURATOM-IPP Association, Garching und Berlin, Germany Abstract In 1997 the new `LYRA' divertor went into operation at ASDEX Upgrade and the neutral beam heating power was increased to 20 MW by installation of a second injector. This leads to the relatively high value of P/R of 12 MW/m. It has been shown that the ASDEX Upgrade LYRA divertor is capable of handling such high heating powers. Mea- surements presented in this paper reveal a reduction of the maximum heat ¯ux in the LYRA divertor by more than a factor of two compared to the open Divertor I. This reduction is caused by radiative losses inside the divertor region. Carbon radiation cools the divertor plasma down to a few eV where hydrogen radiation losses become signi®cant. They are increased due to an effective re¯ection of neutrals into the hot separatrix region. B2-Eirene modelling of the performed experiments supports the experimental ®ndings and re®nes the understanding of loss processes in the divertor region. 1. INTRODUCTION The width of the scrape-off layer (SOL) does not necessarily increase in proportion to the size of the device. This poses severe problems for the power exhaust in a fusion reactor. If we take ITER as described in the ®nal design report (FDR) [1], a power ¯ow across the separatrix in the order of 100 to 150 MW might be needed to stay in the H-mode [2]. -
Advanced Tokamak Experiments in Full-W ASDEX Upgrade
1 PDP-4 Advanced tokamak experiments in full-W ASDEX Upgrade J. Stober, A. Bock, E. Fable, R. Fischer, C. Angioni, V. Bobkov, A. Burckhart, H. Doerk, A. Herrmann, J. Hobirk, Ch. Hopf, A. Kallenbach, A. Mlynek, R. Neu, Th. Putterich,¨ M. Reich, D. Rittich, M. Schubert, D. Wagner, H. Zohm and the ASDEX Upgrade Team Max-Planck-Institut fur¨ Plasmaphysik, Boltzmannstr. 2, 85748 Garching, Germany email: [email protected] Abstract. Full W-coating of the plasma facing components of ASDEX Upgrade (AUG) in 2007 ini- tially prevented H-mode operation with little or no gas puff, due to collapses driven by W accumulation, also due to a lack of adequate central wave heating. Additionally, the limits for power loads to the di- vertor were reduced. Under these conditions low density, high beta plasmas with significant external current drive were virtually impossible to operate, i.e. the operational window for advanced tokamak (AT) research was effectively closed. To recover this operational window several major achievements were necessary: the understanding of the changes in pumping and recycling, the change to a full W divertor capable to handle higher power loads, a substantial increase of the ECRH/CD power and pulse length to avoid W accumulation and to adjust the current profile and, finally, new or upgraded diagnostics for the current profile, since the original MSE system turned out to be heavily disturbed by polarizing re- flections on W-coated surfaces. With these efforts it was possible to recover improved H-mode operation as well as to develop a new scenario for fully non-inductive operation at q95 = 5:3, bN of 2.7 and 50% of bootstrap current. -
Snowflake Divertor Studies in DIII-D and NSTX Aimed at the Power
40th EPS Conference on Plasma Physics (EPS 2013) Europhysics Conference Abstracts Vol. 37D Espoo, Finland 1 - 5 July 2013 Part 1 of 2 ISBN: 978-1-63266-310-8 Printed from e-media with permission by: Curran Associates, Inc. 57 Morehouse Lane Red Hook, NY 12571 Some format issues inherent in the e-media version may also appear in this print version. Copyright© (2013) by the European Physical Society (EPS) All rights reserved. Printed by Curran Associates, Inc. (2014) For permission requests, please contact the European Physical Society (EPS) at the address below. European Physical Society (EPS) 6 Rue des Freres Lumoere F-68060 Mulhouse Cedex France Phone: 33 389 32 94 40 Fax: 33 389 32 94 49 [email protected] Additional copies of this publication are available from: Curran Associates, Inc. 57 Morehouse Lane Red Hook, NY 12571 USA Phone: 845-758-0400 Fax: 845-758-2634 Email: [email protected] Web: www.proceedings.com 40th EPS Conference on Plasma Physics 1 - 5 July 2013 Espoo, Finland Snowflake Divertor Studies in O2.101 Soukhanovskii, V.A. DIII-D and NSTX Aimed at the Power Exhaust Solution for the Tokamak Lang, P.T., Bernert, M., Burckhart, A., Casali, L., Fischer, R., Pellet as tool for high density O2.102 Kardaun, O., Kocsis, G., Maraschek, M., Mlynek, A., Ploeckl, B., operation and ELM control in Reich, M., Francois, R., Schweinzer, J., Sieglin, B., Suttrop, W., ASDEX Upgrade Szepesi, T., Tardini, G., Wolfrum, E., Zohm, H., Team, A. Modelling of the O2.103 Panayotis, S. erosion/deposition pattern on the Tore Supra Toroidal Pumped Limiter Non-inductive Plasma Current Start-up in NSTX Raman, R., Jarboe, T.R., Jardin, S.C., Kessel, C.E., Mueller, D., using Transient CHI and O2.104 Nelson, B.A., Poli, F., Gerhardt, S., Kaye, S.M., Menard, J.E., Ono, subsequent Non-inductive M., Soukhanovskii, V. -
June 2018 Fusion in Europe
FUSION IN EUROPE NEWS & VIEWS ON THE PROGRESS OF FUSION RESEARCH “Let us face it: TO DTT OR NOT TO DTT there is no VACUUM – HOW NOTHING REALLY planet B!” MATTERS NOW IS THE TIME TO BE AT JET 2 2018 Fusion Writers … wanted! … and Artists This could be you Fusion in Europe is call- ing for aspiring writers and gifted artists! Introduce yourself to an international audience! Catch one of our topics and turn it into your own! • The future powered by fusion energy • Fusion science and industrial reality • Fusion - a melting pot of different sciences • Fusion drives innovation Find the entire list here: tinyurl.com/ybd4omz7 Your application should include a short CV and a motivational letter. Please apply here: tinyurl.com/ybd4omz7 EUROfusion | Communications Team | Anne Purschwitz (”Fusion in Europe“ Editor) Boltzmannstr. 2 | 85748Application Garching | +49 89 deadline: 3299 4128 | [email protected] 25 June 2018 | Editorial | EUROfusion | “It is the best time to be at JET right now” says a passionate Eva Belo nohy. The member of JET’s Exploitation Unit has recently organised a very suc- cessful workshop. It was aimed to ‘refresh’ the knowledge of European fu- sion researchers regarding the Joint European Torus (JET) but that was a classic understatement. The meeting was a fully-fledged overview on JET’s capabilities which have tremendously changed in the past. The tokamak has gone through major upgrades since it saw its first deuterium tritium campaign in 1997. Those include not only an ITER-like wall but also an Fusion Writers… wanted! … increase of the heating power by 50 percent. -
Model for Screening of Resonant Magnetic Perturbations by Plasma
Model for screening of resonant magnetic perturbations by plasma in a realistic tokamak geometry and its impact on divertor strike points P. Cahynaa,1,∗, E. Nardonb, JET EFDA Contributors2 aInstitute of Plasma Physics, AS CR, v.v.i., Association EURATOM/IPP.CR, Za Slovankou 3, 182 00 Prague, Czech Republic bAssociation EURATOM-CEA, CEA/DSM/IRFM, CEA Cadarache, 13108 St-Paul-lez-Durance, France Abstract This work addresses the question of the relation between strike-point splitting and magnetic stochasticity at the edge of a poloidally diverted tokamak in the presence of externally imposed magnetic perturbations. More specifically, ad-hoc helical current sheets are introduced in order to mimic a hypothetical screening of the external resonant magnetic perturbations by the plasma. These current sheets, which suppress magnetic islands, are found to reduce the amount of splitting expected at the target, which suggests that screening effects should be observable experimentally. Multiple screening current sheets reinforce each other, i.e. less current relative to the case of only one current sheet is required to screen the perturbation. Keywords: Theory and Modelling, Plasma properties, Plasma-Materials Interaction arXiv:1012.4015v2 [physics.plasm-ph] 27 Jan 2011 ∗Corresponding author Email address: [email protected] (P. Cahyna) 1Presenting author 2See the Appendix of F. Romanelli et al., Proceedings of the 22nd IAEA Fusion Energy Conference 2008, Geneva, Switzerland Preprint submitted to Journal of Nuclear Materials November 10, 2018 1. Introduction An axisymmetric, single null, poloidally diverted tokamak has two strike-lines where the plasma hits the divertor targets: one on the high field side (HFS) and one on the low field side (LFS). -
Disruption Mitigation Studies at ASDEX Upgrade in Support of ITER
Disruption mitigation studies at ASDEX Upgrade in support of ITER G. Pautasso1, M. Bernert1, M. Dibon1, B. Duval2, R. Dux1, E. Fable1, C. Fuchs1, G.D. Conway1, L. Giannone1, A. Gude1, A. Herrmann1, M. Hoelzl1, P.J. McCarthy3, A. Mlynek1, M. Maraschek1, E. Nardon4, G. Papp1, S. Potzel1, C. Rapson1, B. Sieglin1, W. Suttrop1, W. Treutterer1, the ASDEX Upgrade1 and the EUROfusion MST15 teams 1 Max-Plank-Institute fuer Plasma Physik, D-85748, Garching, Germany 2 Swiss Plasma Centre, EPFL, CH-1016 Lausanne, Switzerland 3 Department of Physics, University College Cork, Ireland 4 CEA, IRFM, F-13108 Saint Paul lez Durance, France 5 http://www.euro-fusionscipub.org/mst1 IEA Workshop on Disruptions, July 20-22 2016, PPPL, USA 1 Content Experimental scenarios and rational behind interpretation of pre-thermal quench force mitigation in MGI(*) induced plasma termination; focus on small gas quantities thermal load mitigation runaway electron generation and losses; focus on MGI suppression (*) MGI = massive gas injection IEA Workshop on Disruptions, July 20-22 2016, PPPL, USA 2 Background 22 3 2008-2013: MGI exp.s in AUG aimed at reaching ne ~ nc ~ O (10 ) / m during or just after TQ for RE suppression poor impurity assimilation at large Ninj → attempts to reach nc abandoned ITER DMS consists now of several injectors for TQ & force mitigation + RE suppression TQ: Minimum impurity amount for force & thermal load mitigation? CQ: Is control and/or suppression of REs possible? IEA Workshop on Disruptions, July 20-22 2016, PPPL, USA 3 AUG: Mitigation valves,