Fusion Programme Evaluation, Airagi Panel
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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. -
Engineering Optimization of Stellarator Coils Lead to Improvements in Device Maintenance
2015 IEEE 26th Symposium on Fusion Engineering (SOFE 2015) Austin, Texas, USA 31 May – 4 June 2015 IEEE Catalog Number: CFP15SOF-POD ISBN: 978-1-4799-8265-3 Copyright © 2015 by the Institute of Electrical and Electronics Engineers, Inc All Rights Reserved Copyright and Reprint Permissions: Abstracting is permitted with credit to the source. Libraries are permitted to photocopy beyond the limit of U.S. copyright law for private use of patrons those articles in this volume that carry a code at the bottom of the first page, provided the per-copy fee indicated in the code is paid through Copyright Clearance Center, 222 Rosewood Drive, Danvers, MA 01923. For other copying, reprint or republication permission, write to IEEE Copyrights Manager, IEEE Service Center, 445 Hoes Lane, Piscataway, NJ 08854. All rights reserved. ***This publication is a representation of what appears in the IEEE Digital Libraries. Some format issues inherent in the e-media version may also appear in this print version. IEEE Catalog Number: CFP15SOF-POD ISBN (Print-On-Demand): 978-1-4799-8265-3 ISBN (Online): 978-1-4799-8264-6 ISSN: 1078-8891 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) 758-2633 E-mail: [email protected] Web: www.proceedings.com TABLE OF CONTENTS ENGINEERING OPTIMIZATION OF STELLARATOR COILS LEAD TO IMPROVEMENTS IN DEVICE MAINTENANCE ..................................................................................................................................................1 T. Brown, J. Breslau, D. Gates, N. Pomphrey, A. Zolfaghari NSTX TOROIDAL FIELD COIL TURN TO TURN SHORT DETECTION .................................................................7 S. Ramakrishnan, W. -
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. -
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. -
Time Evaluation of Diamagnetic Loop and Mirnov Oscillations in a Major Plasma Disruption and Comparison with a Normal Shot
International Nano Letters https://doi.org/10.1007/s40089-018-0259-x ORIGINAL ARTICLE Time evaluation of diamagnetic loop and Mirnov oscillations in a major plasma disruption and comparison with a normal shot R. Sadeghi1 · Mahmood Ghoranneviss1 · M. K. Salem1 Received: 21 November 2018 / Accepted: 7 December 2018 © The Author(s) 2018 Abstract In this paper, plasma disruption was investigated in IR-T1 tokamak. Moreover, the time evaluation of plasma parameters such as plasma current, Ip; loop voltage, Vloop; power heating; and safety factor was illustrated. The results of diamagnetic loop and Mirnov oscillations in a major disruption were compared with their results in a normal shot. In addition, plasma disruption in diferent tokamaks was investigated and the results were compared with the IR-T1 tokamak. Keywords Disruption · Runaway electrons · Mirnov coils · Diamagnetic loop · Tokamak · MHD instability Introduction tokamak disruptions cause plasma confinement to be destroyed by restriction of current and density which ends Among various tools of magnetic confnement, tokamak to large mechanical stresses. Plasma disruption is caused containing hot plasma is one of the best and developed by strong stochastic magnetic feld formed due to nonlin- devices [1]. Tokamaks are divided into two groups: frst, the earity excited low-mode number magneto–hydro–dynamics large tokamaks for studying large plasmas such as DIII-D (MHD) modes. The safety factor (q) is very important in [2] and Tore–Supra [3] with high-cost testing conditions and determining stability and transport theory [9–13]. The paper second, small tokamaks such as STOR-M [4] and ISTTOK is organized as follows: in Sect. -
Edge Turbulence in ISTTOK: a Multi-Code Fluid Validation B Dudson, W Gracias, R Jorge, a Nielsen, J Olsen, P Ricci, C Silva, P
Edge turbulence in ISTTOK: a multi-code fluid validation B Dudson, W Gracias, R Jorge, A Nielsen, J Olsen, P Ricci, C Silva, P. Tamain, G. Ciraolo, N Fedorczak, et al. To cite this version: B Dudson, W Gracias, R Jorge, A Nielsen, J Olsen, et al.. Edge turbulence in ISTTOK: a multi-code fluid validation. Plasma Physics and Controlled Fusion, IOP Publishing, 2021. hal-03179634 HAL Id: hal-03179634 https://hal.archives-ouvertes.fr/hal-03179634 Submitted on 24 Mar 2021 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. Edge turbulence in ISTTOK: a multi-code fluid validation B. D. Dudson1, W. A. Gracias2, R. Jorge3;4, A. H. Nielsen5, J. M. B. Olsen5, P. Ricci3, C. Silva4, P. Tamain6, G. Ciraolo6, N. Fedorczak6, D. Galassi3;7, J. Madsen5, F. Militello8, N. Nace6, J. J. Rasmussen5, F. Riva3;8, E. Serre7 1York Plasma Institute, Department of Physics, University of York YO10 5DQ, UK 2Universidad Carlos III de Madrid, Leganés, 28911, Madrid, Spain 3École Polytechnique Fédérale de Lausanne (EPFL), Swiss Plasma Center (SPC), CH-1015 Lausanne, Switzerland 4Instituto de Plasmas e Fusão Nuclear, Instituto Superior Técnico, Universidade de Lisboa, 1049-001 Lisboa, Portugal 5Department of Physics, Technical University of Denmark, Fysikvej, DK-2800 Kgs.-Lyngby, Denmark 6IFRM, CEA Cadarache, F-13108 St. -
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. -
Subject Categories and Scope Descriptions Co Q
International Nuclear Information System (INIS) • LU Q CD XA0202260 D) c CO IAEA-ETDE/TNIS-2 o X LU CO -I—• SUBJECT CATEGORIES AND SCOPE DESCRIPTIONS CO Q ETDE/INIS Joint Reference Series No. 2 CT O c > LU O O E "- =3 CO I? O cB CD C , LU • CD 3 CO -Q T3 CD >- c •a « C c CD o o CD «2 i- CO .3-3/33 CO ,_ CD a) O % 3 O •z. a. Renewable energy technologies • Radiation protection • Energy storage, conversion, and consumption Radioactive waste management • Energy policy • Radiation effects on living organisms • Fossil fuels INTERNATIONAL ATOMIC ENERGY AGENCY, VIENNA, JULY 2002 ETDE/INIS Joint Reference Series No. 2 SUBJECT CATEGORIES AND SCOPE DESCRIPTIONS INTERNATIONAL ATOMIC ENERGY AGENCY VIENNA, JULY 2002 SUBJECT CATEGORIES AND SCOPE DESCRIPTIONS IAEA, VIENNA, 2002 IAEA-ETDE/INIS-2 ISBN 92-0-112902-5 ISSN 1684-095X © IAEA, 2002 Printed by the IAEA in Austria July 2002 PREFACE This document is one in a series of publications known as the ETDE/INIS Joint Reference Series. It defines the subject categories and provides the scope descriptions to be used for categorization of the nuclear literature for the preparation of INIS input by national and regional centers. Together with volumes of the INIS Reference Series and ETDE/INIS Joint Reference Series it defines the rules, standards and practices and provides the authorities to be used in the International Nuclear Information System. A list of the volumes published in the IMS Reference Series and ETDE/ENIS Joint Reference Series can be found at the end of this publication. -
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). -
LA-7973-MS the Reversed-Field Pinch Reactor (RFPR) Concept O
LA-7973-MS Informal Report The Reversed-Field Pinch Reactor (RFPR) Concept 01 O LOS ALAMOS SCIENTIFIC LABORATORY Post Office Box 1663 Los Alamos. New Mexico 87545 LA-7973-MS Informal Report UC-20d MOT Issued: August 1979 The Reversed-Field Pinch Reactor (RFPR) Concept R. L. Hagenson R. A. Krakowski G. E. Cort MAJOR CONTRIBUTORS Engineering: W. E. Fox, R. W. Teasdale Neutronics: P. D. Soran Tritium: C. G. Bathke, H. Cullingford Materials: F. W. Clinard, Jr. Plasma Engineering: R. L. Miller Physics: D. A. Baker, J. N. DiMarco Electrotechnology: R. W. Moses l-neip. :«. makes s any legal inW,i» „. ,«p..nS*.lil> >"' <'« 11|lll.CSi Ulit l'ISCl • '' ! 1. Equilibrium and Stability 15b 2. Transport 155 3-. Startup . 158 4. Rundown (Quench) 159 B. T'jchnolofey Assessment 160 1. First wall 160 2. Blanket 160 3» Energy Transfer, Storage and Switching 161 4. Magnets 162 5« Vacuum and Tritium Recovery 162 C. Summary Assessment 163 APPENDIX A. RFPR BURN MODEL AND REACTOR'CODE 166 1. Plasma and Magnetic Field Models 166 2. Plasma Energy balance 169 3. Anomalous Radial Transport 17A APPENDIX B. COSTING MODEL 176 APPENDIX C. STANDARD FUSIOt: REACTOR DESIGN TABLE 185 APPENDIX D. BLANKET TRITIUM TRANSPORT MODEL 197 1. Development of Model 197 2. Evaluation of Model 200 3. Tritium Inventory Question - 202 APPENDIX E. SUMMARY REVIEW OF DESIGN POINT EVOLUTION 206 vn TABLE OF CONTENTS THL REVERSED-FIELI) PINCH REACTOR (KFPR) CONCEPT 1 ABSTRACT 1 I. INTRODUCTION 2 II. EXECUTIVE SUMMARY 4 A. Fundamental Physics Issues 4 B. Reactor Description ••* 9 1. Reactor Operation 10 2. -
The Titan Reversed-Field-Pinch Fusion Reactor Study
4X* I ^© tf> UCLA-PPG-1200 THE TITAN REVERSED-RELD-PINCH FUSION REACTOR STUDY gFVysw^Bijyp. Final Report 1990 Volume III: TITAN-I Fusion Power Core University of California, Los Angeles Los Alamos National Laboratory Department of Mechanical, Aerospace, Los Alamos, NM and Nuclear Engineering and Institute of Plasma and Fusion Research. Los Angeles, CA Rensselaer Polytechnic Institute General Atomics Department of Nuclear Engineering San Diego, CA Troy, NY ClSTRIBUTION OF THIS DOCUMENT IS UNLIMITED DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agen cy thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or useful ness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately r-wned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommen dation, or favoring by the United States Government or any agency thereof, the views and opinions of authors expressed herein do not necessarily state or reflect those of the united State Government or any agency thereof. UCLA/PPG—1200-Vol .3 DE92 000139 THE TITAN REVERSED-FIELD-PINCH FUSION REACTOR STUDY FINAL REPORT 1090 Volume III: TITAN-I Fusion Power Core University of California, Los Angeles Los Alamos National Laboratory Department of MeehanicaJ, Aerospace, Los Alamos, NM and Nuclear Engineering and Institute of Plasma and Fusion Research Los Angeles, CA Rensselaer Polytechnic Institute General Atomics Department of Nuclear Engineering San Diego, Ca Troy, NY MASTER ^ DISTRIBUTION OF THIS DOCUMENT IS UNLIMITED CONTRIBUTING AUTHORS UNIVERSITY OF CALIFORNIA, LOS ANGELES Farrokh Najmabadi, Robert W. -
Tokamak Energy April 2019
Faster Fusion through Innovations M Gryaznevich and Tokamak Energy Ltd. Team FusionCAT Webinar 14 September 2020 © 2020 Tokamak Energy Tokamak 20202020 © Energy Tokamak Fusion Research – Public Tokamaks JET GLOBUS-M Oxford, UK StPetersburg, RF COMPASS KTM Prague, CZ (1) Kurchatov, KZ (3) T15-M Alcator C-Mod Moscow STOR-M Cambridge, MA MAST Saskatoon, SK Oxford, UK ASDEX KSTAR ITER(1)(2) / WEST Garching, DE Daejeon, KR LTX / NSTX Cadarache, FR FTU HL-2 (1) Pegasus Princeton, NJ Frascati, IT JT-60SA DIII-D Madison, WI TCV Chengdu, CN QUEST Naka, JP San Diego, CA ISTTOK Lausanne, CH Kasuga, JP Lisbon, PT SST-1 / ADITY EAST Gandhinagar, IN Hefei, CN Conventional Tokamak • Fusion research is advancing Spherical Tokamak • However, progress towards Fusion Power is constrained Note: Tokamaks are operating unless indicated otherwise. (1) Under construction. (2) The International Thermonuclear Experimental Reactor (“ITER”) megaproject is supported by China, the European Union, India, Japan, Korea, Russia and the United States. © 2020© Energy Tokamak (3) No longer in use. 2 Fusion Development – Private Funding Cambridge, MA Langfang, PRC Vancouver, BC Los Angeles, CA Orange County, CA • Common goal of privately and publicly Oxford, UK Oxford, UK funded Fusion research is to develop technologies and Fusion Industry • At TE, we have identified the key technology Conventional Tokamak Spherical Tokamak gaps needed to create a commercial fusion Non-Tokamak Technology reactor and then used Technology Roadmapping as an approach chart our path. © 2020©