50 Years of Fusion Research
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Stellarators. Present Status and Future Planning
STELLARATORS Present Status and Future Planning H. Wobig, Garching IMax-Planck-Institut für Plasmaphysikl magnetic axis Fig. 1 — Period of toroidally dosed magnetic surfaces. The stellarator is a closed toroidal device open-ended configurations like mirror ma designed to confine a hot plasma In a ma chines (see EN, 12 8/9) there are always gnetic field. It is one of the oldest concepts plasma particles which escape the confine magnetic surfaces is investigated by field to have been investigated in the search for ment volume along the magnetic field and line integration. The topology of the field controlled thermonuclear fusion. an isotropic distribution function cannot be lines is determined by the rotational trans The basic idea of the stellarator was maintained. If this anisotropy is too strong form or twist number 1/27t (or+), which is developed by Lyman Spitzer, Professor of it gives rise to instabilities and enhanced the number of revolutions of a field line Astronomy at Princeton in 19511). Experi plasma losses. It is mainly to avoid these around the magnetic axis during one toroi mental studies began in 1952 and after the disadvantages that toroidal confinement dal revolution. declassification of fusion research in 1958 has been preferred. The need for a helical field can be under the idea was picked up by other research In toroidal configurations, the currents stood from a look at the particle orbits. groups. In Europe, the first stellarators which generate the confining magnetic Charged particles tend to follow the field were built in the Max-Planck Institute for fields can be classified under three lines and unless these are helical, because Physics and Astrophysics in Munich and categories : of inhomogeneities, the particles will drift later at Culham, Moscow and Karkhov. -
STATUS of FUSION ENERGY Impact & Opportunity for Alberta Volume II
STATUS OF FUSION ENERGY Impact & Opportunity for Alberta Volume II Appendices Prepared by Alberta/Canada Fusion Energy Program March 2014 ALBERTA COUNCIL OF TECHNOLOGIES Gratefully acknowledges the support of: Alberta Energy Stantec Corporation University of Alberta Alberta/Canada Fusion Energy Advisory Committee Gary Albach Nathan Armstrong Brian Baudais Will Bridge Robert Fedosejevs Peter Hackett Chris Holly Jerry Keller Brian Kryska Axel Meisen Rob Pitcairn Klaas Rodenburg John Rose Glenn Stowkowy Martin Truksa Gary Woloshyniuk Perry Kinkaide Allan Offenberger A special thank you is extended to the institutions (identified in this report) that were visited and to the many persons who so graciously hosted our site visits, provided the briefing material presented in this status report and thereby assisted our fusion assessment. Report Authors Allan Offenberger Robert Fedosejevs Klaas Rodenburg Perry Kinkaide Contact: Dr. Perry Kinkaide [email protected] 780-990-5874 Dr. Allan Offenberger [email protected] 780-483-1740 i TABLE OF CONTENTS Page List of Acronyms ………………………………………………………………………….. iii List of Figures……………………………………………………………………………… iv Appendix A: Assessment of Major Global Fusion Technologies 1.0 Context - Global Energy Demand……………………………………………………… 1 1.0.1 Foreward ……………………………………………………………………… 1 1.0.2 Energy Trends………………………………………………………………… 2 1.0.3 Energy From Fusion Reactions……………………………………………… 4 1.1 Major Approaches to Fusion Energy………………………………………………….. 7 1.1.1 Introduction……………………………………………………………………. 7 1.1.2 Fusion Reactions & the Fuel Cycle………………………………………….. 8 1.1.3 IFE Approaches to Fusion…………………………………………………… 11 1.1.3.1 Introduction………………………………………………………….. 11 1.1.3.2 Indirect Drive…………………………………………………………14 1.1.3.3 Direct Drive…………………………………………………………. 16 1.1.3.4 Fast Ignition………………………………………………………… 17 1.1.3.5 Shock Ignition………………………………………………………..19 1.1.3.6 IFE Power Reactor Systems……………………………………….20 1.1.3.7 Modeling Codes……………………………………………………. -
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. -
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. -
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. -
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). -
Significance of MHD Effects in Stellarator Confinement
Ms-313705 Final Paper Significance of MHD Effects in Stellarator Confinement A. Weller1, S. Sakakibara2, K.Y. Watanabe2, K. Toi2, J. Geiger1, M.C. Zarnstorff3, S.R. Hudson3, A. Reiman3, A. Werner1, C. Nührenberg1, S. Ohdachi2, Y. Suzuki2, H. Yamada2, W7-AS Team1, LHD Team2 1Max-Planck-Institut für Plasmaphysik, EURATOM-IPP Association, D-17491 Greifswald, Germany 2National Institute for Fusion Science, Toki 509-5292, Japan 3Princeton Plasma Physics Laboratory, Princeton, NJ 08543, USA Corresponding Author: Dr. Arthur Weller ( [email protected] ) Max-Planck-Institut für Plasmaphysik, EURATOM-IPP Association, Wendelsteinstr. 1, D-17491 Greifswald, Germany Fax: +49 (0)3834 88 2509 Content of Paper: Main Text: 27 pages (including references and figure captions) 12 Figures, no Table - 1 - Ms-313705 Final Paper Abstract Substantial progress has been achieved to raise the plasma beta in stellarators and helical systems by high power neutral beam heating, approaching reactor relevant values [1-3]. The achievement of high-β operation is closely linked with configuration effects on the confinement and with magnetohydrodynamic (MHD) stability. The magnetic configurations of the Wendelstein W7-AS stellarator and of the Large Helical Device (LHD) and their optimization for high-β operation within the flexibility of the devices are characterized. A comparative description of the accessible operational regimes in W7-AS and LHD is given. The finite-β effects on the flux surfaces depend on the degree of configuration optimization. In particular, a large Shafranov shift is accompanied by formation of islands and stochastic field regions as found by numerical equilibrium studies [2,4]. However, the observed pressure gradients indicate some mitigation of the effects on the plasma confinement, presumably because of the high collisionality of high-β plasmas and island healing effects (LHD [5-7]). -
Physicists Propose New Way to Stabilize Next-Generation Fusion
PRINCETON PLASMA PHYSICS LABORATORY A Collaborative National Center for Fusion & Plasma Research WEEKLY October 16, 2017 THIS WEEK WEDNESDAY, OCT. 18 Council Café Lunch Physicists propose new way 12 p.m. u Cafeteria Andrea Moten, Interim Head of HR to stabilize next-generation PPPL Colloquium 4:15 p.m. u MBG Auditorium fusion plasmas Properties and Degradation By Raphael Rosen of Polyimide in Extreme Hygrothermal Environments Alan Zehnder, Cornell University key issue for next-generation fusion reactors is the possible impact of many unsta- A ble Alfvén eigenmodes, wave-like disturbances produced by the fusion reac- THURSDAY, OCT. 19 tions that ripple through the plasma in doughnut-shaped fusion facilities called toka- maks. Deuterium and tritium fuel react when heated to temperatures near 100 million Open Forum with Dave McComas degrees Celsius, producing high-energy helium ions called alpha particles that heat 2 p.m. the plasma and sustain the fusion reactions. See page 6 for details. These alpha particles are even hotter than the fuel and have so much energy that FRIDAY, OCT. 20 they can drive Alfvén eigenmodes that allow the particles to escape from the reac- Public Tour tion chamber before they can heat the plasma. Understanding these waves and how 10 a.m. they help alpha particles escape is a key research topic in fusion science. Email [email protected] for info. continued on page 4 UPCOMING OCT. 23–27 Project Matterhorn physicist Rolf Sinclair 59th Annual Meeting of the APS Division of Plasma Physics returns to PPPL 45 years after he left Milwaukee, Wisconsin By Jeanne Jackson DeVoe THURSDAY, OCT. -
Years of Fusion Research
“50” Years of Fusion Research Dale Meade Fusion Innovation Research and Energy® Princeton, NJ Independent Activities Period (IAP) January 19, 2011 MIT PSFC Cambridge, MA 02139 1 FiFusion Fi FiPre Powers th thSe Sun “We nee d to see if we can mak e f usi on work .” John Holdren @MIT, April, 2009 3 Toroidal Magg(netic Confinement (1940s-earlyy) 50s) • 1940s - first ideas on using a magnetic field to confine a hot plasma for fusion. • 1947 Sir G.P. Thomson and P. C. Thonemann began classified investigations of toroidal “pinch” RF discharge, eventually lead to ZETA, a large pinch at Harwell, England 1956. • 1949 Richter in Argentina issues Press Release proclaiming fusion, turns out to be bogus, but news piques Spitzer’s interest. • 1950 Spitzer conceives stellarator while on a ski lift, and makes ppproposal to AEC ($50k )-initiates Project Matterhorn at Princeton. • 1950s Classified US Program on Controlled Thermonuclear Fusion (Project Sherwood) carried out until 1958 when magnetic fusion research was declassified. US and others unveil results at 2nd UN Atoms for Peace Conference in Geneva 1958. Fusion Leading to 1958 Geneva Meeting • A period of rapid progress in science and technology – N-weapons, N-submarine, Fission energy, Sputnik, transistor, .... • Controlled Thermonuclear Fusion had great potential – Much optimism in the early 1950s with expectation for a quick solution – Political support and pressure for quick results (but bud gets were low, $56M for 1951-1958) – Many very “innovative” approaches were put forward. – Early fusion reactor concepts - Tamm/Sakharov, Spitzer (Model D) very large. • Reality began to set in by the mid 1950s – Coll ectiv e eff ects - MHD instability ( 195 4), Bo hm d iffus io n was ubi qui tous – Meager plasma physics understanding led to trial and error approaches – A multitude of experiments were tried and ended up far from fusion conditions – Magnetic Fusion research in the U.S. -
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.