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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. -
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. -
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© -
Interface of EPICS with Marte for Real-Time Application
1 Interface of EPICS with MARTe for Real-time Application October 23, 2012 Sangwon Yun Interface of EPICS with MARTe for Real-time Applications, October 23, 2012 2 Outlines Introduction ITER Task Overview of main technical subjects Multi-threaded Application Real-Time executor (MARTe) Portable Channel Access Server (pCAS) Interface of EPICS with MARTe The result of performance evaluation of MARTe Conclusions Acknowledgements and references Interface of EPICS with MARTe for Real-time Applications, October 23, 2012 3 Introduction ITER Task CODAC HPC (High Performance Computer) Dedicated computers running plasma control algorithms The Plasma Control System(PCS) requires the hard real-time operation The hard real-time control system requires the predictability in response time and deterministic upper bound in latency. In this regard, RTOS and real-time software framework are required to achieve those ITER Task : Evaluation and Demonstration of ITER CODAC Technologies at KSTAR Subtask : Implement density feedback control and verify its performance in a running device • To collect elements for decision making on PCS software framework • Deploy different PCS software framework based on KSTAR PCS on modified Linux and MARTe on RTOS for comparison KSTAR PCS Modified Linux RTOS (Based on RHEL) (MRG Realtime) See: Fast Controller Workshop, Feb 28, 2011. ITER IO Interface of EPICS with MARTe for Real-time Applications, October 23, 2012 4 Introduction MARTe framework for Hard Real-time Control System MARTe is a solution to be considered for a Real-time control system • The three considered system histogram The optimized reference program EPICS IOC MARTe application • Test conditions Run the system by providing an external sampling clock of 1 kHz 30,000 cycles Priority of the thread for ADC has been set to Latency distribution the highest CPU affinity (excepts EPICS IOC) • Result Reference EPICS IOC MARTe MARTe provides a shorter and, above all, Prog. -
Imaging and Probe Techniques for Wave Dispersion Estimates in Magnetized Plasmas
Imaging and Probe Techniques for Wave Dispersion Estimates in Magnetized Plasmas by A. D. Light B.A./B.S., Case Western Reserve University, 2005 A thesis submitted to the Faculty of the Graduate School of the University of Colorado in partial fulfillment of the requirements for the degree of Doctor of Philosophy Department of Physics 2013 This thesis entitled: Imaging and Probe Techniques for Wave Dispersion Estimates in Magnetized Plasmas written by A. D. Light has been approved for the Department of Physics Prof. Tobin Munsat Prof. Martin Goldman Date The final copy of this thesis has been examined by the signatories, and we find that both the content and the form meet acceptable presentation standards of scholarly work in the above mentioned discipline. Light, A. D. (Ph.D., Physics) Imaging and Probe Techniques for Wave Dispersion Estimates in Magnetized Plasmas Thesis directed by Prof. Tobin Munsat Fluctuations in magnetized laboratory plasmas are ubiquitous and complex. In addition to deleterious effects, like increasing heat and particle transport in magnetic fusion energy devices, fluctuations also provide a diagnostic opportunity. Identification of a fluctuation with a particular wave or instability gives detailed information about the properties of the underlying plasma. In this work, diagnostics and spectral analysis techniques for fluctuations are developed and applied to two different laboratory plasma experiments. The first part of this dissertation discusses imaging measurements of coherent waves in the Controlled Shear Decorrelation Experiment (CSDX) at the University of California, San Diego. Visible light from ArII line emission is collected at high frame rates using an intensified digital camera. -
Book of Abstracts Contribution: T1 / Beam Plasmas and Inertial Fusion
Book of Abstracts Contribution: T1 / Beam Plasmas and Inertial Fusion Exploring HED physics, ICF dynamics and lab astrophysics with advanced nuclear diagnostics Chikang Li Massachusetts Institute of Technology, Cambridge, MA 02139, USA Significant progress has recently been made in developing advanced nuclear diagnostics for the OMEGA laser facility and the National Ignition Facility (NIF). Both self-emitted fusion products and backlighting nuclear particles have been measured and used to study a large range of basic physics of high-energy-density (HED) plasmas. The highlights of these achievements are manifested by numerous recent publications. For ignition science in inertial-confinement fusion (ICF) experiments, for example, these works have helped to advance our understanding of kinetic effects in exploding-pusher ICF implosions and our understanding of NIF capsule implosion dynamics and symmetry. For basic physics in HED plasmas and laboratory astrophysics, our research contributed to the understanding of nuclear plasma science, the generation and reconnection of self-generated spontaneous electromagnetic fields and associated plasma instabilities, high-Mach-number plasma jets, Weibel-mediated electromagnetic collisionless shocks, and charged-particle stopping power in various laser-produced HED plasmas. In this Tutorials and Topical Lecture, we will present details of these researches. The work described herein was performed in part at the LLE National Laser User’s Facility (NLUF), and was supported in part by US DOE, LLNL and LLE. 3rd European Conference on Plasma Diagnostics (ECPD), 6-9 May 2019, Lisbon, Portugal https://www.ipfn.tecnico.ulisboa.pt/ECPD2019/ Contribution: T2 / Basic and Astrophysical Plasmas Detection of the missing baryons by studying the lines from the Warm Hot Intergalactic Medium (WHIM) F. -
EX/P5-8 Effects of Viscosity on Magnetohydrodynamic Behaviour
1 EX/P5-8 Effects of Viscosity on Magnetohydrodynamic Behaviour During Limiter Biasing on the CT-6B Tokamak P. Khorshid 1), L. Wang 2), M. Ghoranneviss 3), X.Z. Yang 2), C.H. Feng 2) 1) Department of Physics, Islamic Azad University, Mashhad, Iran, 2) Institute of Physics, Chinese Academy of Sciences, Beijing, China 3) Plasma Physics Research Center, Islamic Azad University, Tehran, Iran E-mail: [email protected] Abstract. Effects of viscosity on magnetohydrodynamics behaviour during limiter biasing in the CT-6B Tokamak has been investigated. The results shown that subsequent to the application of a positive bias, a decrease followed by an increase in the frequency of magnetic field fluctuations was observed. With contribution of viscous force effects in the radial force balance equation for Limiter Biasing, in terms of the nonstationarity model, it allows us to identify the understanding physics responsible for change in the Mirnov oscillations that could be related to poloidal rotation velocity and radial electric field. It could be seen that the time scale of responses to biasing is important. The response of ∇pi, decrease of poloidal rotation velocity, the edge electrostatics and magnetic fluctuations to external field have been investigated. The results shown that momentum balance equation with considering viscous force term can be use for modeling of limiter biasing in the tokamak. 1. Introduction Many experiments have shown the importance of the radial electric field in improved confinement states and several theories can explain the transition mechanism. There are several methods for controlling the radial electric field externally [1,2]. Edge biasing experiments have been found to be important in modifying edge turbulence and transport, but the mechanism of biasing penetration in edge fluctuations and its levels are different with respect to devices operation. -
THE BIG STEP from ITER to DEMO J. Ongena , R.Koch, Ye.O
THE BIG STEP FROM ITER TO DEMO J. Ongena , R.Koch, Ye.O.Kazakov Laboratorium voor Plasmafysica - Laboratoire de Physique des Plasmas Koninklijke Militaire School - Ecole Royale Militaire Association"EURATOM - Belgian State", B-1000 Brussels, Belgium Partner in the Trilateral Euregio Cluster (TEC) N. Bekris European Fusion Development Agreement JET Close Support Unit, Culham Science Centre Culham, OX14 3DB, United Kingdom D.Mazon Institut de Recherche sur la Fusion par Confinement Magnetique CEA Cadarache, 13108 St Paul-lez-Durance, France ABSTRACT ITER. Reactor studies are also being developed for Helical Devices (see e.g. [1-4]). However, a decision on a next step Extrapolation of the knowledge base towards a future stellarator/helical device can only take place when the main fusion power reactor is discussed. Although fusion research results of the current large helical devices in operation or has achieved important milestones since the start and construction have been obtained. The largest helical device continues achieving successes, we show that there are still currently in operation is LHD (Large Helical Device, in the important challenges that have to be addressed before the National Institute for Fusion Science (NIFS), close to construction and operation of an economical fusion power Nagoya, Japan). The construction of the largest stellarator reactor. Both physics and technological questions have to in the world Wendelstein 7-X (Max-Planck Institute, be solved. ITER is a significant step that will lead to major Greifswald, Germany) is nearly finished with first progress; for a DEMO reactor however, there will still be operations foreseen for beginning 2015. In this paper, we outstanding physics and engineering questions that require will therefore restrict ourselves to the discussion of a further R&D. -
Lerner-Nobigbang.Pdf
CONTENTS Preface to the Vintage Edition xv Introduction 3 Part One THE COSMOLOGICAL DEBATE 9 1. The Big Bang Never Happened 11 2. A History of Creation 58 3. The Rise of Science 85 4. The Strange Career of Modern Cosmology 113 5. The Spears of Odin 169 6. The Plasma Universe 214 Part Two IMPLICATIONS 281 7. The Endless Flow of Time 283 8. Matter 328 9. Infinite in Time and Space 382 10. Cosmos and Society 405 Appendix 425 Bibliography 431 Index 441 XIII PREFACE TO THE VINTAGE EDITION Four hundred years ago Galileo broke the bonds that had entangled science with reli- gion. Defying his fellow scientists' near unanimous commitment to Ptolemy's finite, earth- centered universe, Galileo defended Corperni- cus's unlimited, sun-centered cosmos. He argued that observation, not scientific or religious author- ity, must be the test of cosmological theory. Sci- ence and religion must be separate, he declared: "Religion teaches how to go to heaven, not how the heavens go." But now, four centuries after the Scientific Rev- olution, we seem to have come full circle. "His- toric Big Bang Discovery May Prove God's Existence" reads the headline of an Associated Press story dated April 25, 1992. Leading cosmol- ogists are quoted as saying that recent astronomi- cal discoveries "are like looking at God," that they prove the reality of the Big Bang—a scientific ver- sion of the Biblical story of Creation. Cosmology again seems to be entangled with religion, at least in the headlines and in the minds of some cosmol- ogists. -
The Plasma Universe Is a Matter of Mind
www.amatterofmind.org Page 1 of 21 From the desk of Pierre Beaudry THE PLASMA UNIVERSE IS A MATTER OF MIND By Pierre Beaudry. March 20, 2012. “And the emphasis, for us, is placed largely on the question of the fact that living processes, first of all, living processes’ increase in the power drives the universe of our experience; and secondly, that the creative powers of mankind, which are unique to mankind in our experience, drive the universe, in turn, as a higher form of authority in the universe itself.” Lyndon LaRouche. “If nature can execute such organization in the plasma focus, she can certainly do so with the primordial plasma.” Winston Bostick. “We are going to need a lot of axiomatic pinch effect instabilities to make the world grow peacefully.” Dehors Debonneheure. Figure 1. An Oligarchical Pinch Effect. www.amatterofmind.org Page 2 of 21 FOREWORD Is there proportionality between the human mind and the universe? If so, what determines it? The irony present in all galactic plasma studies is that plasma physicists have the opportunity to replicate the immense magnitudes of the galactic creative activity of the universe as a whole inside of the apparently small area of their own minds, and demonstrate how that idea works in their laboratories. Christian Birkeland, Irving Langmuir, Hannes Alfvén, Winston Bostick, and Anthony Peratt have all experimented this during their amazing discoveries of principle of the Plasma Universe. The central paradox of that principle, common to all of those scientists, is that the fusion process of the human mind is the paradigm for the behavior of the universe as a whole. -
2007 Particle Accelerator Conference Meet In
NPS0307.qxd 2/8/07 8:49 AM Page 1 A Publication of the Institute of Electrical and Electronics Engineers Number 1 • March 2007 SOCIETY NEWS CONFERENCES PULSED POWER AND PLASMA SCIENCE 2007; SYMPOSIUM on FUSION ENGINEERING; 2007 PARTICLE ACCELERATOR CONFERENCE MEET IN ALBUQUERQUE June 17 – 29, 2007 PULSED POWER AND PLASMA SCIENCE 2007 June 17-22, 2007 Albuquerque Convention Center Albuquerque, New Mexico, USA lbuquerque, New Mexico will achieve critical Convention Center. Registrants of either conference mass when attendees of the 34th IEEE will be able to attend sessions in both conferences. AInternational Conference on Plasma Science Albuquerque is the largest city in New Mexico (ICOPS) and the 16th IEEE International Pulsed with a metropolitan population of nearly 800,000 Power Conference (PPC) meet at the Albuquerque people and home to the University of New Mexico, Convention Center June 17-22, 2007 for “PPPS- Kirtland Air Force Base, Sandia National 2007.” This is the second time that these two con- Laboratories, and many high tech companies, both ferences are combining their activities, following the large and small. Los Alamos National Laboratory is initial joint event in Las Vegas in 2001. Extending only 90 minutes to the Northwest. The cotton- the concept, the IEEE Nuclear and Plasma Sciences wood-shaded Rio Grande River Valley and Society’s Symposium on Fusion Engineering (SOFE Petroglyph National Monument lie to the west and Conference) will also be collocating with PPPS- the majestic Sandia Peak lies to the east. The Sangre 2007, using the west wing of the Albuquerque continued on page 3 Edl Schamiloglu Frank Peterkin John Gaudet Charles Reuben General Chair Technical Program Finance Chair Conference Chair Coordinator NUCLEAR & PLASMA SCIENCES SOCIETY March 2007 1 NPS0307.qxd 2/8/07 8:49 AM Page 2 TABLE OF CONTENTS IEEE NUCLEAR AND PLASMA SCIENCES SOCIETY NEWS Pulsed Power and Plasma Science 2007 .