Characterizing Magnetized Plasmas with Dynamic Mode Decomposition
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Magnetohydrodynamics - Overview
Center for Turbulence Research 361 Proceedings of the Summer Program 2006 Magnetohydrodynamics - overview Magnetohydrodynamics (MHD) is the study of the interaction of electrically conduct- ing fluids and electromagnetic forces. MHD problems arise in a wide variety of situations ranging from the explanation of the origin of Earth's magnetic field and the prediction of space weather to the damping of turbulent fluctuations in semiconductor melts dur- ing crystal growth and even the measurement of the flow rates of beverages in the food industry. The description of MHD flows involves both the equations of fluid dynamics - the Navier-Stokes equations - and the equations of electrodynamics - Maxwell's equa- tions - which are mutually coupled through the Lorentz force and Ohm's law for moving electrical conductors. Given the vast range of Reynolds numbers and magnetic Reynolds numbers characterising astrophysical, geophysical, and industrial MHD problems it is not feasible to devise an all-encompassing numerical code for the simulation of all MHD flows. The challenge in MHD is rather to combine a judicious application of analytical tools for the derivation of simplified equations with accurate numerical algorithms for the solution of the resulting mathematical models. The 2006 summer program provided a unique opportunity for scientists and engineers working in different sub-disciplines of MHD to interact with each other and benefit from the numerical capabilities available at the Center for Turbulence Research. In materials processing such as the growth of semiconductor crystals or the continuous casting of steel turbulent flows are often undesirable. The application of steady magnetic fields provides a convenient means for the contactless damping of turbulent fluctuations and for the laminarisation of flows. -
A Mathematical Introduction to Magnetohydrodynamics
Typeset in LATEX 2" July 26, 2017 A Mathematical Introduction to Magnetohydrodynamics Omar Maj Max Planck Institute for Plasma Physics, D-85748 Garching, Germany. e-mail: [email protected] 1 Contents Preamble 3 1 Basic elements of fluid dynamics 4 1.1 Kinematics of fluids. .4 1.2 Lagrangian trajectories and flow of a vector field. .5 1.3 Deformation tensor and vorticity. 14 1.4 Advective derivative and Reynolds transport theorem. 17 1.5 Dynamics of fluids. 20 1.6 Relation to kinetic theory and closure. 24 1.7 Incompressible flows . 32 1.8 Equations of state, isentropic flows and vorticity. 34 1.9 Effects of Euler-type nonlinearities. 35 2 Basic elements of classical electrodynamics 39 2.1 Maxwell's equations. 39 2.2 Lorentz force and motion of an electrically charged particle. 52 2.3 Basic mathematical results for electrodynamics. 57 3 From multi-fluid models to magnetohydrodynamics 69 3.1 A model for multiple electrically charged fluids. 69 3.2 Quasi-neutral limit. 74 3.3 From multi-fluid to a single-fluid model. 82 3.4 The Ohm's law for an electron-ion plasma. 86 3.5 The equations of magnetohydrodynamics. 90 4 Conservation laws in magnetohydrodynamics 95 4.1 Global conservation laws in resistive MHD. 95 4.2 Global conservation laws in ideal MHD. 98 4.3 Frozen-in law. 100 4.4 Flux conservation. 105 4.5 Topology of the magnetic field. 109 4.6 Analogy with the vorticity of isentropic flows. 117 5 Basic processes in magnetohydrodynamics 119 5.1 Linear MHD waves. -
LA-8700-C N O Proceedings of the Third Symposium on the Physics
LA-8700-C n Conference Proceedings of the Third Symposium on the Physics and Technology of Compact Toroids in the Magnetic Fusion Energy Program Held at the Los Alamos National Laboratory Los Alamos, New Mexico December 2—4, 1980 c "(0 O a> 9 n& anna t LOS ALAMOS SCIENTIFIC LABORATORY Post Office Box 1663 Los Alamos. New Mexico 87545 An Affirmative Aution/f-qual Opportunity Fmployei This report was not edited by the Technical Information staff. This work was supported by the US Depart- ment of Energy, Office of Fusion Energy. DISCLAIM) R This report WJJ prepared as jn JLUOUIH of work sponsored by jn agency of ihc Untied Slates (.ovcrn- rneni Neither the United Suit's (iovci.iment nor anv a^cmy thereof, nor any HI theu employees, makes Jn> warranty, express or in,Hied, o( assumes any legal liability 01 responsibility for the jn-ur- aty. completeness, or usefulness of any information, apparatus, product, 01 process disiiosed, or rep- resents thai its use would not infringe privately owned rights. Reference herein to any specifu- com- mercial product process, or service by tradr name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommcniidlK>n, or favoring by the United Stales Government or any agency thereof. The views and opinions of authors expressed herein do not nec- essarily state 01 reflect those nf llic United Stales Government or any agency thereof. UfJITED STATES DEPARTMENT OF ENERGY CONTRACT W-7405-ENG. 36 LA-8700-C Conference UC-20 issued: March 1981 Proceedings of the Third Symposium on the Physics and Technology of Compact Toroids in the Magnetic Fusion Energy Program Heki at the Los Alamos National Laboratory Los Alamos, New Mexico Decamber 2—4, 1980 Compiled by Richard E. -
Stability Study of the Cylindrical Tokamak--Thomas Scaffidi(2011)
Ecole´ normale sup erieure´ Princeton Plasma Physics Laboratory Stage long de recherche, FIP M1 Second semestre 2010-2011 Stability study of the cylindrical tokamak Etude´ de stabilit´edu tokamak cylindrique Author: Supervisor: Thomas Scaffidi Prof. Stephen C. Jardin Abstract Une des instabilit´es les plus probl´ematiques dans les plasmas de tokamak est appel´ee tearing mode . Elle est g´en´er´ee par les gradients de courant et de pression et implique une reconfiguration du champ magn´etique et du champ de vitesse localis´ee dans une fine r´egion autour d’une surface magn´etique r´esonante. Alors que les lignes de champ magn´etique sont `al’´equilibre situ´ees sur des surfaces toriques concentriques, l’instabilit´econduit `ala formation d’ˆıles magn´etiques dans lesquelles les lignes de champ passent d’un tube de flux `al’autre, rendant possible un trans- port thermique radial important et donc cr´eant une perte de confinement. Pour qu’il puisse y avoir une reconfiguration du champ magn´etique, il faut inclure la r´esistivit´edu plasma dans le mod`ele, et nous r´esolvons donc les ´equations de la magn´etohydrodynamique (MHD) r´esistive. On s’int´eresse `ala stabilit´ede configurations d’´equilibre vis-`a-vis de ces instabilit´es dans un syst`eme `ala g´eom´etrie simplifi´ee appel´ele tokamak cylindrique. L’´etude est `ala fois analytique et num´erique. La solution analytique est r´ealis´ee par une m´ethode de type “couche limite” qui tire profit de l’´etroitesse de la zone o`ula reconfiguration a lieu. -
Magnetohydrodynamics 1 19.1Overview
Contents 19 Magnetohydrodynamics 1 19.1Overview...................................... 1 19.2 BasicEquationsofMHD . 2 19.2.1 Maxwell’s Equations in the MHD Approximation . ..... 4 19.2.2 Momentum and Energy Conservation . .. 8 19.2.3 BoundaryConditions. 10 19.2.4 Magneticfieldandvorticity . .. 12 19.3 MagnetostaticEquilibria . ..... 13 19.3.1 Controlled thermonuclear fusion . ..... 13 19.3.2 Z-Pinch .................................. 15 19.3.3 Θ-Pinch .................................. 17 19.3.4 Tokamak.................................. 17 19.4 HydromagneticFlows. .. 18 19.5 Stability of Hydromagnetic Equilibria . ......... 22 19.5.1 LinearPerturbationTheory . .. 22 19.5.2 Z-Pinch: Sausage and Kink Instabilities . ...... 25 19.5.3 EnergyPrinciple ............................. 28 19.6 Dynamos and Reconnection of Magnetic Field Lines . ......... 29 19.6.1 Cowling’stheorem ............................ 30 19.6.2 Kinematicdynamos............................ 30 19.6.3 MagneticReconnection. 31 19.7 Magnetosonic Waves and the Scattering of Cosmic Rays . ......... 33 19.7.1 CosmicRays ............................... 33 19.7.2 Magnetosonic Dispersion Relation . ..... 34 19.7.3 ScatteringofCosmicRays . 36 0 Chapter 19 Magnetohydrodynamics Version 1219.1.K.pdf, 7 September 2012 Please send comments, suggestions, and errata via email to [email protected] or on paper to Kip Thorne, 350-17 Caltech, Pasadena CA 91125 Box 19.1 Reader’s Guide This chapter relies heavily on Chap. 13 and somewhat on the treatment of vorticity • transport in Sec. 14.2 Part VI, Plasma Physics (Chaps. 20-23) relies heavily on this chapter. • 19.1 Overview In preceding chapters, we have described the consequences of incorporating viscosity and thermal conductivity into the description of a fluid. We now turn to our final embellishment of fluid mechanics, in which the fluid is electrically conducting and moves in a magnetic field. -
Application of High Performance Computing for Fusion Research Shimpei Futatani
Application of high performance computing for fusion research Shimpei Futatani Department of Physics, Universitat Politècnica de Catalunya (UPC), Barcelona, Spain The study of the alternative energy source is one of the absolutely imperative research topics in the world as our present energy sources such as fossil fuels are limited. This work is dedicated to the nuclear fusion physics research in close collaboration with existing experimental fusion devices and the ITER organization (www.iter.org) which is an huge international nuclear fusion R&D project. The goal of the ITER project is to demonstrate a clean and safe energy production by nuclear fusion which is the reaction that powers the sun. One of the ideas of the nuclear fusion on the earth is that the very high temperature ionized particles, forming a plasma can be controlled by a magnetic field, called magnetically confined plasma. This is essential, because no material can be sustained against such high temperature reached in a fusion reactor. Tokamak is a device which uses a powerful magnetic field to confine a hot plasma in the shape of a torus. It is a demanding task to achieve a sufficiently good confinement in a tokamak for a ‘burning plasma’ due to various kinds of plasma instabilities. One of the critical unsolved problems is MHD (MagnetoHydroDynamics) instabilities in the fusion plasmas. The MHD instabilities at the plasma boundary damages the plasma facing component of the fusion reactor. One of techniques to control the MHD instabilities is injection of pellets (small deuterium ice bodies). The physics of the interaction between pellet ablation and MHD dynamics is very complex, and uncertainties still remain regarding the theoretical physics as well as the numerical modelling point of view. -
Identification of the Sequence of Steps Intrinsic to Spheromak Formation
Identification of the Sequence of Steps Intrinsic to Spheromak Formation P.M. Bellan, S. You, and G. S. Yun California Institute of Technology Pasadena, CA 91125, USA Abstract. A planar coaxial electrostatic helicity source is used for studying the relaxation process intrinsic to spheromak formation. Experimental observations reveal that spheromak formation involves: (1) breakdown and creation of a number of distinct, arched, filamentary, plasma-filled flux loops that span from cathode to anode gas nozzles, (2) merging of these loops to form a central column, (3) jet-like expansion of the central column, (4) kink instability of the central column, (5) conversion of toroidal flux to poloidal flux by the kink instability. Steps 1 and 3 indicate that spheromak formation involves an MHD pumping of plasma from the gas nozzles into the magnetic flux tube linking the nozzles. In order to measure this pumping, the gas puffing system has been modified to permit simultaneous injection of different gas species into the two ends of the flux tube linking the wall. Gated CCD cameras with narrow-band optical filters are used to track the pumped flows. Keywords: spheromak, magnetohydrodynamics, kink, jet PACS: 52.55.Ip, 52.35.Py, 52.55.Wq, 52.59.Dk INTRODUCTION which is rich in toroidal field energy (typical poloidal currents are 100 kA) but poor in poloidal field energy. Spheromaks are toroidal MHD equilibria incorporating Spheromak formation involves conversion of toroidal nested poloidal magnetic flux surfaces suitable for magnetic flux into poloidal magnetic flux while confining a fusion plasma. Unlike tokamaks, conserving magnetic helicity (but not conserving spheromaks are a self-organizing, minimum-energy magnetic energy). -
Paper Session III-A - Space Transportation Options for the 21St Century
The Space Congress® Proceedings 1999 (36th) Countdown to the Millennium Apr 29th, 1:00 PM Paper Session III-A - Space Transportation Options for the 21st Century George Schmidt NASA Marshall Space Flight Center Mike Houts NASA Marshall Space Flight Center Harold Gerrish NASA Marshall Space Flight Center Jim Martin NASA Marshall Space Flight Center Follow this and additional works at: https://commons.erau.edu/space-congress-proceedings Scholarly Commons Citation Schmidt, George; Houts, Mike; Gerrish, Harold; and Martin, Jim, "Paper Session III-A - Space Transportation Options for the 21st Century" (1999). The Space Congress® Proceedings. 8. https://commons.erau.edu/space-congress-proceedings/proceedings-1999-36th/april-29-1999/8 This Event is brought to you for free and open access by the Conferences at Scholarly Commons. It has been accepted for inclusion in The Space Congress® Proceedings by an authorized administrator of Scholarly Commons. For more information, please contact [email protected]. Space Transportation Options for the 21'1 Century George Schmidt, Mike Houts, Harold Gerrish, Jim Martin #ASA ;//ors/Jo// Spoce ll!g/JI CMler Abstract As NASA's designated Center of Excellence in Space Propulsion, Marshall Space Flight Center (MSFC) recently established the Propulsion Research and Technology Division (PRTD), an organization responsible for the theoretical and experimental study of advanced propulsion concepts and technologies. Although the scope of the division is broad, the mission is quite focused - to demonstrate the critical propulsion functions and technologies underpinning the transportation systems and spacecraft needed to achieve NASA's Grand Vision for exploration, commercial development and ultimately human settlement of space. -
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. -
Peaceful Uses of Atomic Energy, Held in Point of Discussions Back in 1958
INTERNATIONAL ATOMIC ENERGY AGENCY Wagramer Strasse 5, P.O. Box 100 A-1400 Vienna, Austria www.iaea.org CONTENT Guenter Mank, Head, Physics Section Alan Aqrawi, Physics Section Division of Physical and Chemical Sciences Division of Physical and Chemical Sciences Department of Nuclear Sciences and Applications Department of Nuclear Sciences and Applications CREDITS Photography: UNOG Archives Geneva (page 4,5,6,16,17,20,24,25,26), Nuclear Fusion Institute RRC "Kurchatov Institute" Russia (page 9,18,19), KFA Kernforschungsanlage Juelich Germany (page 10,11,15), ORNL Oak Ridge National Laboratory USA (page 6), IAEA Archives Vienna (page 8). DESIGN Alan Aqrawi © IAEA, 2008 INDEX FOREWORD Foreword “Celebrating fifty years of fusion… Foreword 2 …entering into the burning plasma era.” Energy in all its forms has always driven been achieved every 1.8 years. New human development. New technologies in developments in science and engineering energy production, starting from the use of fire have led to an optimized magnetic prototype The 2nd Geneva Conference - Introduction 4 itself, have driven economic and social reactor, with corresponding cost savings. development. In the mid-1950s, nuclear Inertial confinement experiments have energy created new hope for an abundant achieved similar progress. The culmination of source of that energy for the world. international collaborative efforts in fusion is the start of construction of the International Declassification 6 To promote this groundbreaking technology, Thermonuclear Experimental Reactor (ITER), and to host a neutral ground for substantive the biggest scientific endeavour the world has scientific debate, the United Nations in 1955 ever seen involving States with more than half organized the first of a series of conferences of the world’s population. -
Energetic Beam Ion Transport in LHD the Distribution of Energetic Beam Ions Is Measured by Fast Neutral Particle Analysis Using a Natural Dia- Mond Detector in LHD
Published by Fusion Energy Division, Oak Ridge National Laboratory Building 9201-2 P.O. Box 2009 Oak Ridge, TN 37831-8071, USA Editor: James A. Rome Issue 69 May 2000 E-Mail: [email protected] Phone (865) 574-1306 Fax: (865) 576-5793 On the Web at http://www.ornl.gov/fed/stelnews Greifswald Branch of IPP moves into new building In early April, about 120 employees of the Max-Planck- Institut für Plasmaphysik (IPP), Greifswald Branch, moved into their new building on the outskirts of the old university town. Up to this time the staff of the Stellarator Theory, Wendelstein 7-X Construction, and Experimental Plasma Physics divisions as well as Administration, Tech- nical Services, and the Computer Center had worked in rented offices at two different locations. Now everybody works under one roof — a roof in the shape of a wave (see Fig. 1), symbolizing the waves on the Baltic Sea. Fig. 2. After unpacking their boxes, the staff of IPP Greif- About 300 persons will work in this new branch institute swald gathered on the galleries above the institute’s “main by the start of the Wendelstein 7-X (W7-X) experiment, road” for an informal opening ceremony on 3 April 2000. scheduled for 2006. This experiment is the successor to the W7-AS stellarator in Garching, with a goal of demon- strating that the advanced stellarator concept, developed at In this issue . IPP, is suitable as a fusion reactor. Even before W7-X has Greifswald Branch of IPP moves into new its first plasma, a smaller, classical stellarator will run in building Greifswald. -
Plasma Physics and Controlled Fusion Research During Half a Century Bo Lehnert
SE0100262 TRITA-A Report ISSN 1102-2051 VETENSKAP OCH ISRN KTH/ALF/--01/4--SE IONST KTH Plasma Physics and Controlled Fusion Research During Half a Century Bo Lehnert Research and Training programme on CONTROLLED THERMONUCLEAR FUSION AND PLASMA PHYSICS (Association EURATOM/NFR) FUSION PLASMA PHYSICS ALFV N LABORATORY ROYAL INSTITUTE OF TECHNOLOGY SE-100 44 STOCKHOLM SWEDEN PLEASE BE AWARE THAT ALL OF THE MISSING PAGES IN THIS DOCUMENT WERE ORIGINALLY BLANK TRITA-ALF-2001-04 ISRN KTH/ALF/--01/4--SE Plasma Physics and Controlled Fusion Research During Half a Century Bo Lehnert VETENSKAP OCH KONST Stockholm, June 2001 The Alfven Laboratory Division of Fusion Plasma Physics Royal Institute of Technology SE-100 44 Stockholm, Sweden (Association EURATOM/NFR) Printed by Alfven Laboratory Fusion Plasma Physics Division Royal Institute of Technology SE-100 44 Stockholm PLASMA PHYSICS AND CONTROLLED FUSION RESEARCH DURING HALF A CENTURY Bo Lehnert Alfven Laboratory, Royal Institute of Technology S-100 44 Stockholm, Sweden ABSTRACT A review is given on the historical development of research on plasma physics and controlled fusion. The potentialities are outlined for fusion of light atomic nuclei, with respect to the available energy resources and the environmental properties. Various approaches in the research on controlled fusion are further described, as well as the present state of investigation and future perspectives, being based on the use of a hot plasma in a fusion reactor. Special reference is given to the part of this work which has been conducted in Sweden, merely to identify its place within the general historical development. Considerable progress has been made in fusion research during the last decades.