Stellarator and Tokamak Plasmas: a Comparison
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FT/P3-20 Physics and Engineering Basis of Multi-Functional Compact Tokamak Reactor Concept R.M.O
FT/P3-20 Physics and Engineering Basis of Multi-functional Compact Tokamak Reactor Concept R.M.O. Galvão1, G.O. Ludwig2, E. Del Bosco2, M.C.R. Andrade2, Jiangang Li3, Yuanxi Wan3 Yican Wu3, B. McNamara4, P. Edmonds, M. Gryaznevich5, R. Khairutdinov6, V. Lukash6, A. Danilov7, A. Dnestrovskij7 1CBPF/IFUSP, Rio de Janeiro, Brazil, 2Associated Plasma Laboratory, National Space Research Institute, São José dos Campos, SP, Brazil, 3Institute of Plasma Physics, CAS, Hefei, 230031, P.R. China, 4Leabrook Computing, Bournemouth, UK, 5EURATOM/UKAEA Fusion Association, Culham Science Centre, Abingdon, UK, 6TRINITI, Troitsk, RF, 7RRC “Kurchatov Institute”, Moscow, RF [email protected] Abstract An important milestone on the Fast Track path to Fusion Power is to demonstrate reliable commercial application of Fusion as soon as possible. Many applications of fusion, other than electricity production, have already been studied in some depth for ITER class facilities. We show that these applications might be usefully realized on a small scale, in a Multi-Functional Compact Tokamak Reactor based on a Spherical Tokamak with similar size, but higher fields and currents than the present experiments NSTX and MAST, where performance has already exceeded expectations. The small power outputs, 20-40MW, permit existing materials and technologies to be used. The analysis of the performance of the compact reactor is based on the solution of the global power balance using empirical scaling laws considering requirements for the minimum necessary fusion power (which is determined by the optimized efficiency of the blanket design), positive power gain and constraints on the wall load. In addition, ASTRA and DINA simulations have been performed for the range of the design parameters. -
Richard G. Hewlett and Jack M. Holl. Atoms
ATOMS PEACE WAR Eisenhower and the Atomic Energy Commission Richard G. Hewlett and lack M. Roll With a Foreword by Richard S. Kirkendall and an Essay on Sources by Roger M. Anders University of California Press Berkeley Los Angeles London Published 1989 by the University of California Press Berkeley and Los Angeles, California University of California Press, Ltd. London, England Prepared by the Atomic Energy Commission; work made for hire. Library of Congress Cataloging-in-Publication Data Hewlett, Richard G. Atoms for peace and war, 1953-1961. (California studies in the history of science) Bibliography: p. Includes index. 1. Nuclear energy—United States—History. 2. U.S. Atomic Energy Commission—History. 3. Eisenhower, Dwight D. (Dwight David), 1890-1969. 4. United States—Politics and government-1953-1961. I. Holl, Jack M. II. Title. III. Series. QC792. 7. H48 1989 333.79'24'0973 88-29578 ISBN 0-520-06018-0 (alk. paper) Printed in the United States of America 1 2 3 4 5 6 7 8 9 CONTENTS List of Illustrations vii List of Figures and Tables ix Foreword by Richard S. Kirkendall xi Preface xix Acknowledgements xxvii 1. A Secret Mission 1 2. The Eisenhower Imprint 17 3. The President and the Bomb 34 4. The Oppenheimer Case 73 5. The Political Arena 113 6. Nuclear Weapons: A New Reality 144 7. Nuclear Power for the Marketplace 183 8. Atoms for Peace: Building American Policy 209 9. Pursuit of the Peaceful Atom 238 10. The Seeds of Anxiety 271 11. Safeguards, EURATOM, and the International Agency 305 12. -
Thermonuclear AB-Reactors for Aerospace
1 Article Micro Thermonuclear Reactor after Ct 9 18 06 AIAA-2006-8104 Micro -Thermonuclear AB-Reactors for Aerospace* Alexander Bolonkin C&R, 1310 Avenue R, #F-6, Brooklyn, NY 11229, USA T/F 718-339-4563, [email protected], [email protected], http://Bolonkin.narod.ru Abstract About fifty years ago, scientists conducted R&D of a thermonuclear reactor that promises a true revolution in the energy industry and, especially, in aerospace. Using such a reactor, aircraft could undertake flights of very long distance and for extended periods and that, of course, decreases a significant cost of aerial transportation, allowing the saving of ever-more expensive imported oil-based fuels. (As of mid-2006, the USA’s DoD has a program to make aircraft fuel from domestic natural gas sources.) The temperature and pressure required for any particular fuel to fuse is known as the Lawson criterion L. Lawson criterion relates to plasma production temperature, plasma density and time. The thermonuclear reaction is realised when L > 1014. There are two main methods of nuclear fusion: inertial confinement fusion (ICF) and magnetic confinement fusion (MCF). Existing thermonuclear reactors are very complex, expensive, large, and heavy. They cannot achieve the Lawson criterion. The author offers several innovations that he first suggested publicly early in 1983 for the AB multi- reflex engine, space propulsion, getting energy from plasma, etc. (see: A. Bolonkin, Non-Rocket Space Launch and Flight, Elsevier, London, 2006, Chapters 12, 3A). It is the micro-thermonuclear AB- Reactors. That is new micro-thermonuclear reactor with very small fuel pellet that uses plasma confinement generated by multi-reflection of laser beam or its own magnetic field. -
Digital Physics: Science, Technology and Applications
Prof. Kim Molvig April 20, 2006: 22.012 Fusion Seminar (MIT) DDD-T--TT FusionFusion D +T → α + n +17.6 MeV 3.5MeV 14.1MeV • What is GOOD about this reaction? – Highest specific energy of ALL nuclear reactions – Lowest temperature for sizeable reaction rate • What is BAD about this reaction? – NEUTRONS => activation of confining vessel and resultant radioactivity – Neutron energy must be thermally converted (inefficiently) to electricity – Deuterium must be separated from seawater – Tritium must be bred April 20, 2006: 22.012 Fusion Seminar (MIT) ConsiderConsider AnotherAnother NuclearNuclear ReactionReaction p+11B → 3α + 8.7 MeV • What is GOOD about this reaction? – Aneutronic (No neutrons => no radioactivity!) – Direct electrical conversion of output energy (reactants all charged particles) – Fuels ubiquitous in nature • What is BAD about this reaction? – High Temperatures required (why?) – Difficulty of confinement (technology immature relative to Tokamaks) April 20, 2006: 22.012 Fusion Seminar (MIT) DTDT FusionFusion –– VisualVisualVisual PicturePicture Figure by MIT OCW. April 20, 2006: 22.012 Fusion Seminar (MIT) EnergeticsEnergetics ofofof FusionFusion e2 V ≅ ≅ 400 KeV Coul R + R V D T QM “tunneling” required . Ekin r Empirical fit to data 2 −VNuc ≅ −50 MeV −2 A1 = 45.95, A2 = 50200, A3 =1.368×10 , A4 =1.076, A5 = 409 Coefficients for DT (E in KeV, σ in barns) April 20, 2006: 22.012 Fusion Seminar (MIT) TunnelingTunneling FusionFusion CrossCross SectionSection andand ReactivityReactivity Gamow factor . Compare to DT . April 20, 2006: 22.012 Fusion Seminar (MIT) ReactivityReactivity forfor DTDT FuelFuel 8 ] 6 c e s / 3 m c 6 1 - 0 4 1 x [ ) ν σ ( 2 0 0 50 100 150 200 T1 (KeV) April 20, 2006: 22.012 Fusion Seminar (MIT) Figure by MIT OCW. -
Tokamak Foundation in USSR/Russia 1950--1990
IOP PUBLISHING and INTERNATIONAL ATOMIC ENERGY AGENCY NUCLEAR FUSION Nucl. Fusion 50 (2010) 014003 (8pp) doi:10.1088/0029-5515/50/1/014003 Tokamak foundation in USSR/Russia 1950–1990 V.P. Smirnov Nuclear Fusion Institute, RRC ’Kurchatov Institute’, Moscow, Russia Received 8 June 2009, accepted for publication 26 November 2009 Published 30 December 2009 Online at stacks.iop.org/NF/50/014003 In the USSR, nuclear fusion research began in 1950 with the work of I.E. Tamm, A.D. Sakharov and colleagues. They formulated the principles of magnetic confinement of high temperature plasmas, that would allow the development of a thermonuclear reactor. Following this, experimental research on plasma initiation and heating in toroidal systems began in 1951 at the Kurchatov Institute. From the very first devices with vessels made of glass, porcelain or metal with insulating inserts, work progressed to the operation of the first tokamak, T-1, in 1958. More machines followed and the first international collaboration in nuclear fusion, on the T-3 tokamak, established the tokamak as a promising option for magnetic confinement. Experiments continued and specialized machines were developed to test separately improvements to the tokamak concept needed for the production of energy. At the same time, research into plasma physics and tokamak theory was being undertaken which provides the basis for modern theoretical work. Since then, the tokamak concept has been refined by a world-wide effort and today we look forward to the successful operation of ITER. (Some figures in this article are in colour only in the electronic version) At the opening ceremony of the United Nations First In the USSR, NF research began in 1950. -
Inis: Terminology Charts
IAEA-INIS-13A(Rev.0) XA0400071 INIS: TERMINOLOGY CHARTS agree INTERNATIONAL ATOMIC ENERGY AGENCY, VIENNA, AUGUST 1970 INISs TERMINOLOGY CHARTS TABLE OF CONTENTS FOREWORD ... ......... *.* 1 PREFACE 2 INTRODUCTION ... .... *a ... oo 3 LIST OF SUBJECT FIELDS REPRESENTED BY THE CHARTS ........ 5 GENERAL DESCRIPTOR INDEX ................ 9*999.9o.ooo .... 7 FOREWORD This document is one in a series of publications known as the INIS Reference Series. It is to be used in conjunction with the indexing manual 1) and the thesaurus 2) for the preparation of INIS input by national and regional centrea. The thesaurus and terminology charts in their first edition (Rev.0) were produced as the result of an agreement between the International Atomic Energy Agency (IAEA) and the European Atomic Energy Community (Euratom). Except for minor changesq the terminology and the interrela- tionships btween rms are those of the December 1969 edition of the Euratom Thesaurus 3) In all matters of subject indexing and ontrol, the IAEA followed the recommendations of Euratom for these charts. Credit and responsibility for the present version of these charts must go to Euratom. Suggestions for improvement from all interested parties. particularly those that are contributing to or utilizing the INIS magnetic-tape services are welcomed. These should be addressed to: The Thesaurus Speoialist/INIS Section Division of Scientific and Tohnioal Information International Atomic Energy Agency P.O. Box 590 A-1011 Vienna, Austria International Atomic Energy Agency Division of Sientific and Technical Information INIS Section June 1970 1) IAEA-INIS-12 (INIS: Manual for Indexing) 2) IAEA-INIS-13 (INIS: Thesaurus) 3) EURATOM Thesaurusq, Euratom Nuclear Documentation System. -
The Stellarator Program J. L, Johnson, Plasma Physics Laboratory, Princeton University, Princeton, New Jersey
The Stellarator Program J. L, Johnson, Plasma Physics Laboratory, Princeton University, Princeton, New Jersey, U.S.A. (On loan from Westlnghouse Research and Development Center) G. Grieger, Max Planck Institut fur Plasmaphyslk, Garching bel Mun<:hen, West Germany D. J. Lees, U.K.A.E.A. Culham Laboratory, Abingdon, Oxfordshire, England M. S. Rablnovich, P. N. Lebedev Physics Institute, U.S.3.R. Academy of Sciences, Moscow, U.S.S.R. J. L. Shohet, Torsatron-Stellarator Laboratory, University of Wisconsin, Madison, Wisconsin, U.S.A. and X. Uo, Plasma Physics Laboratory Kyoto University, Gokasho, Uj', Japan Abstract The woHlwide development of stellnrator research is reviewed briefly and informally. I OISCLAIWCH _— . vi'Tli^liW r.'r -?- A stellarator is a closed steady-state toroidal device for cer.flning a hot plasma In a magnetic field where the rotational transform Is produced externally, from torsion or colls outside the plasma. This concept was one of the first approaches proposed for obtaining a controlled thsrtnonuclear device. It was suggested and developed at Princeton in the 1950*s. Worldwide efforts were undertaken in the 1960's. The United States stellarator commitment became very small In the 19/0's, but recent progress, especially at Carchlng ;ind Kyoto, loeethar with «ome new insights for attacking hotii theoretics] Issues and engineering concerns have led to a renewed optimism and interest a:; we enter the lQRO's. The stellarator concept was borr In 1951. Legend has it that Lyman Spiczer, Professor of Astronomy at Princeton, read reports of a successful demonstration of controlled thermonuclear fusion by R. -
Formation of Hot, Stable, Long-Lived Field-Reversed Configuration Plasmas on the C-2W Device
IOP Nuclear Fusion International Atomic Energy Agency Nuclear Fusion Nucl. Fusion Nucl. Fusion 59 (2019) 112009 (16pp) https://doi.org/10.1088/1741-4326/ab0be9 59 Formation of hot, stable, long-lived 2019 field-reversed configuration plasmas © 2019 IAEA, Vienna on the C-2W device NUFUAU H. Gota1 , M.W. Binderbauer1 , T. Tajima1, S. Putvinski1, M. Tuszewski1, 1 1 1 1 112009 B.H. Deng , S.A. Dettrick , D.K. Gupta , S. Korepanov , R.M. Magee1 , T. Roche1 , J.A. Romero1 , A. Smirnov1, V. Sokolov1, Y. Song1, L.C. Steinhauer1 , M.C. Thompson1 , E. Trask1 , A.D. Van H. Gota et al Drie1, X. Yang1, P. Yushmanov1, K. Zhai1 , I. Allfrey1, R. Andow1, E. Barraza1, M. Beall1 , N.G. Bolte1 , E. Bomgardner1, F. Ceccherini1, A. Chirumamilla1, R. Clary1, T. DeHaas1, J.D. Douglass1, A.M. DuBois1 , A. Dunaevsky1, D. Fallah1, P. Feng1, C. Finucane1, D.P. Fulton1, L. Galeotti1, K. Galvin1, E.M. Granstedt1 , M.E. Griswold1, U. Guerrero1, S. Gupta1, Printed in the UK K. Hubbard1, I. Isakov1, J.S. Kinley1, A. Korepanov1, S. Krause1, C.K. Lau1 , H. Leinweber1, J. Leuenberger1, D. Lieurance1, M. Madrid1, NF D. Madura1, T. Matsumoto1, V. Matvienko1, M. Meekins1, R. Mendoza1, R. Michel1, Y. Mok1, M. Morehouse1, M. Nations1 , A. Necas1, 1 1 1 1 1 10.1088/1741-4326/ab0be9 M. Onofri , D. Osin , A. Ottaviano , E. Parke , T.M. Schindler , J.H. Schroeder1, L. Sevier1, D. Sheftman1 , A. Sibley1, M. Signorelli1, R.J. Smith1 , M. Slepchenkov1, G. Snitchler1, J.B. Titus1, J. Ufnal1, Paper T. Valentine1, W. Waggoner1, J.K. Walters1, C. -
1. Introduction 2. the ROSE Code
M. Drevlak et al. New results in stellarator optimisation M. Drevlak , C. D. Beidler, J. Geiger, P. Helander, S. Henneberg, C. N¨uhrenberg, Y. Turkin Max-Planck-Institut f¨ur Plasmaphysik, 17491 Greifswald, Germany Email: [email protected] Abstract The ROSE code was written for the optimisation of stellarator equilibria. It uses VMEC for the equilibrium calculation and several different optimising algorithms for adjusting the boundary coefficients of the plasma. Some of the most important capabilities include optimisation for simple coils, the ability to simultaneously optimise vacuum and finite beta field, direct analysis of particle drift orbits and direct shaping of the magnetic field structure. ROSE was used to optimise quasi- isodynamic, quasi-axially symmetric and quasi-helically symmetric stellarator configurations. 1. Introduction The performance of stellarators, characterised by properties related to MHD stability, confinement of fast particles, neoclassical and anomalous transport and engineering complexity, is known to depend strongly on the underlying equilibrium configuration. While the first fully optimised stellarators, HSX and Wendelstein 7-X, have entered operation, new stellarator designs are being considered. In particular, a possible stellarator reactor needs to be optimised beyond the optimisation level achieved for these devices. A strong need for progress has been identified in the confinement of fast particles significantly away from the magnetic axis. At the same time, coil complexity must not exceed the limits of feasibility. 2. The ROSE Code The ROSE [1] code was written for the optimi- VMEC Equilibrium field sation of stellarator equilibria. Like other tools Brents algorithm created for the optimisation of stellarator equilib- Parallel Line−Search VM2MAG B spectrum ria [2] [3], it uses VMEC [4] for the equilibrium Genetic Optimisation mn calculation and several different optimising algo- Harmony Search SURFGEN, Coil complexity rithms for adjusting the coefficients of the bound- Particle Swarm NESCOIL ary shape of the plasma. -
1 Looking Back at Half a Century of Fusion Research Association Euratom-CEA, Centre De
Looking Back at Half a Century of Fusion Research P. STOTT Association Euratom-CEA, Centre de Cadarache, 13108 Saint Paul lez Durance, France. This article gives a short overview of the origins of nuclear fusion and of its development as a potential source of terrestrial energy. 1 Introduction A hundred years ago, at the dawn of the twentieth century, physicists did not understand the source of the Sun‘s energy. Although classical physics had made major advances during the nineteenth century and many people thought that there was little of the physical sciences left to be discovered, they could not explain how the Sun could continue to radiate energy, apparently indefinitely. The law of energy conservation required that there must be an internal energy source equal to that radiated from the Sun‘s surface but the only substantial sources of energy known at that time were wood or coal. The mass of the Sun and the rate at which it radiated energy were known and it was easy to show that if the Sun had started off as a solid lump of coal it would have burnt out in a few thousand years. It was clear that this was much too shortœœthe Sun had to be older than the Earth and, although there was much controversy about the age of the Earth, it was clear that it had to be older than a few thousand years. The realization that the source of energy in the Sun and stars is due to nuclear fusion followed three main steps in the development of science. -
Highlights in Early Stellarator Research at Princeton
J. Plasma Fusion Res. SERIES, Vol.1 (1998) 3-8 Highlights in Early Stellarator Research at Princeton STIX Thomas H. Department of Astrophysical Sciences, Princeton University, Princeton, NJ 08540, USA (Received: 30 September 1997/Accepted: 22 October 1997) Abstract This paper presents an overview of the work on Stellarators in Princeton during the first fifteen years. Particular emphasis is given to the pioneering contributions of the late Lyman Spitzer, Jr. The concepts discussed will include equilibrium, stability, ohmic and radiofrequency plasma heating, plasma purity, and the problems associated with creating a full-scale fusion power plant. Brief descriptions are given of the early Princeton Stellarators: Model A, Model B, Model B-2, Model B-3, Models 8-64 and 8-65, and Model C, and also of the postulated fusion power plant, Model D. Keywords: Spitzer, Kruskal, stellarator, rotational transform, Bohm diffusion, ohmic heating, magnetic pumping, ion cyclotron resonance heating (ICRH), magnetic island, tokamak On March 31 of this year, at the age of 82, Lyman stellarator was brought to the headquarters of the U.S. Spitzer, Jr., a true pioneer in the fields of astrophysics Atomic Energy Commission in Washington where it re- and plasma physics, died. I wish to dedicate this presen- ceived a favorable reception. Spitzer chose the name tation to his memory. "Project Matterhorn" for the project which was to be Forty-six years ago, in early 1951, Spitzer, then sited in the Princeton area, on the newly acquired For- chair of the Department of Astronomy at Princeton restal tract, and funding began on July 1 of that year University, together with Princeton physicist John 121- Wheeler, had been thinking about the physics of ther- Spitzer's earliest stellarator papers comprise a truly monoclear processes. -
Tomographic Inversion of Wendelstein 7-X Stellarator Plasmas
45th EPS Conference on Plasma Physics P4.1056 Tomographic inversion of Wendelstein 7-X stellarator plasmas C. Brandt1, H. Thomsen1, T. Andreeva, N. Lauf1, U. Neuner1, K. Rahbarnia1, J. Schilling1, T. Broszat1, R. Laube1 and the Wendelstein 7-X Team 1 Max-Planck-Institute for Plasma Physics, Greifswald, Germany In the operational phase OP1.2a (Aug-Dec 2017) of the Wendelstein 7-X (W7-X) stellarator experiment the soft X-ray tomography diagnostic (XMCTS: soft X-ray multi camera tomogra- phy system) has been commissioned. Soft X-ray tomography systems are powerful diagnostics for high temperature plasmas measuring spatiotemporal X-ray emissivity profiles. The XMCTS consists of 20 poloidally arranged pinhole cameras at one toroidal location observing a triangu- lar shaped up-down symmetric plasma cross section. X-ray radiation is mainly emitted in the hot plasma core (electron temperatures > 1keV). In the pinhole cameras the plasma radiation is filtered by a beryllium foil of 12:5 mm thickness being transmissible for X-ray radiation above 1keV. Taking into account the detector silicon thickness of 100 mm the detectable energy range is limited to approximately 1 − 10keV. With 18 available cameras in OP1.2a the soft X-ray emissivity has been recorded along 324 lines-of-sight with a time resolution of 0:5 ms. The presentation concentrates on the preparation and first results of the tomographic inver- sion. For correct calculation of the tomograms, both, the knowledge of the exact geometry of the lines-of-sight and the sensitivity of each photodiode are of crucial importance. The as-built coordinates of the cameras have been measured after the in-vessel installation.