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Fusion Energy Science Opportunities in Emerging Concepts
Fusion Energy Science Opportunities in Emerging Concepts Los Alamos National Laboratory Report -- LA-UR-99-5052 D. C. Barnes Los Alamos National Laboratory For the Emerging Concepts Working Group Convenors: J. Hammer Lawrence Livermore National Laboratory A. Hassam University of Maryland D. Hill Lawrence Livermore National Laboratory A. Hoffman University of Washington B. Hooper Lawrence Livermore National Laboratory J. Kesner Massachusetts Institute of Technology G. Miley University of Illinois J. Perkins Lawrence Livermore National Laboratory D. Ryutov Lawrence Livermore National Laboratory J. Sarff University of Wisconsin R. E. Siemon Los Alamos National Laboratory J. Slough University of Washington M. Yamada Princeton Plasma Physics Laboratory I. Introduction The development of fusion energy represents one of the few long-term (multi-century time scale) options for providing the energy needs of modern (or postmodern) society. Progress to date, in parameters measuring the quality of confinement, for example, has been nothing short of stellar. While significant uncertainties in both physics and (particularly) technology remain, it is widely believed that a fusion reactor based on the tokamak could be developed within one or two decades. It is also widely held that such a reactor could not compete economically in the projected energy market. A more accurate statement of projected economic viability is that the uncertainty in achieving commercial success is sufficient that the large development costs required for such a program are not justified at this time. While technical progress has been spectacular, schedule estimates for achieving particular milestones along the path of fusion research and development have proven notoriously inaccurate. This inaccuracy reflects two facts. -
A European Success Story the Joint European Torus
EFDA JET JETJETJET LEAD ING DEVICE FOR FUSION STUDIES HOLDER OF THE WORLD RECORD OF FUSION POWER PRODUCTION EXPERIMENTS STRONGLY FOCUSSED ON THE PREPARATION FOR ITER EXPERIMENTAL DEVICE USED UNDER THE EUROPEAN FUSION DEVELOPEMENT AGREEMENT THE JOINT EUROPEAN TORUS A EUROPEAN SUCCESS STORY EFDA Fusion: the Energy of the Sun If the temperature of a gas is raised above 10,000 °C virtually all of the atoms become ionised and electrons separate from their nuclei. The result is a complete mix of electrons and ions with the sum of all charges being very close to zero as only small charge imbalance is allowed. Thus, the ionised gas remains almost neutral throughout. This constitutes a fourth state of matter called plasma, with a wide range of unique features. D Deuterium 3He Helium 3 The sun, and similar stars, are sphe- Fusion D T Tritium res of plasma composed mainly of Li Lithium hydrogen. The high temperature, 4He Helium 4 3He Energy U Uranium around 15 million °C, is necessary released for the pressure of the plasma to in Fusion T balance the inward gravitational for- ces. Under these conditions it is pos- Li Fission sible for hydrogen nuclei to fuse together and release energy. Nuclear binding energy In a terrestrial system the aim is to 4He U produce the ‘easiest’ fusion reaction Energy released using deuterium and tritium. Even in fission then the rate of fusion reactions becomes large enough only at high JG97.362/4c Atomic mass particle energy. Therefore, when the Dn required nuclear reactions result from the thermal motions of the nuclei, so-called thermonuclear fusion, it is necessary to achieve u • extremely high temperatures, of at least 100 million °C. -
Een Kernfusie Concept
Kernfusie Dr. Robert Bussard over kernfusie http://video.google.com/videoplay?docid=1996321846673788606# In de bovenstaande link geeft Robert Bussard een conferentie over alternatieve fusie energie waar hij zijn alternatieve opstelling “de polywell” verdedigt. Hoewel de benadering tot kernfusie in dit document geheel anders is, is het doel en sommige basisprincipes hetzelfde en had ik het zelf niet beter kunnen verwoorden. De opstelling De opstelling bestaat uit een sferische tank die doormiddel van een mechanisch systeem (fig1) wordt rondgedraaid, dit in twee dimensies. Het rondspinnen om twee assen van het lichaam zorgt ervoor dat deeltjes met de hoogste massadichtheid naar buiten worden geslingerd. De deeltjes met de laagste dichtheid worden hierdoor naar het center gedrukt. Als er dus bijvoorbeeld water in de sfeer bevindt, zal deze homogeen over de binnenkant van de sferische wand worden gedrukt. De lichtere, eventueel hetere deeltjes worden in het center gehouden. Warmteconvectie wordt hierdoor onderdrukt. Dit maakt dat het plasma geïsoleerd is zonder dat er een vacuüm kamer noodzakelijk is. Zoals bij een Tokamak, Stellator, Fusor of polywell wel het geval is. Hierdoor kan de druk in het plasma makkelijk opgevoerd worden zonder dat er super magneten voor noodzakelijk zijn, simpel weg door statische druk. Dit zou een drastisch verschil moeten maken in energiedichtheid. De opgewekte energie stijgt kwadratisch met De figuur 1: Het draaimechanisme de druk. Tevens kunnen er energieke geladen plasma deeltjes geïnjecteerd worden, wat bij magnetische opsluiting niet mogelijk is. sferische tank met daar rond het draaimechanisme bevindt zich in een tweede robuustere tank die bestand is tegen hoge druk. De vrijgekomen energie wordt afgevoerd voordat het de reactorwand bereikt evenals de 14Mev neutronen worden gemodereerd. -
Minimization of Magnetic Forces on Stellarator Coils Arxiv:2103.13195
Minimization of magnetic forces on Stellarator coils R´emiRobin∗; 1 and Francesco Volpe †2 1 Laboratoire Jacques-Louis Lions, Sorbonne Universit´e 2Renaissance Fusion, https://stellarator.energy March 25, 2021 Abstract Magnetic confinement devices for nuclear fusion can be large and expensive. Compact stellarators are promising candidates for cost- reduction, but introduce new difficulties: confinement in smaller vol- umes requires higher magnetic field, which calls for higher coil-currents and ultimately causes higher Laplace forces on the coils - if everything else remains the same. This motivates the inclusion of force reduction in stellarator coil optimization. In the present paper we consider a coil winding surface, we prove that there is a natural and rigorous way to define the Laplace force (despite the magnetic field discontinuity across the current-sheet), we provide examples of cost associated (peak force, surface-integral of the force squared) and discuss easy generalizations to parallel and normal force-components, as these will be subject to different engineering constraints. Such costs can then be easily added arXiv:2103.13195v1 [math.OC] 24 Mar 2021 to the figure of merit in any multi-objective stellarator coil optimiza- tion code. We demonstrate this for a generalization of the REGCOIL code [1], which we rewrote in python, and provide numerical examples for the NCSX (now QUASAR) design. We present results for various definitions of the cost function, including peak force reductions by up to 40 %, and outline future work for further reduction. ∗[email protected] †[email protected] 1 1 Introduction Stellarators are non-axisymmetric toroidal devices that magnetically confine fusion plasmas [2]. -
Fusion: the Way Ahead
Fusion: the way ahead Feature: Physics World March 2006 pages 20 - 26 The recent decision to build the world's largest fusion experiment - ITER - in France has thrown down the gauntlet to fusion researchers worldwide. Richard Pitts, Richard Buttery and Simon Pinches describe how the Joint European Torus in the UK is playing a key role in ensuring ITER will demonstrate the reality of fusion power At a Glance: Fusion power • Fusion is the process whereby two light nuclei bind to form a heavier nucleus with the release of energy • Harnessing fusion on Earth via deuterium and tritium reactions would lead to an environmentally friendly and almost limitless energy source • One promising route to fusion power is to magnetically confine a hot, dense plasma inside a doughnut-shaped device called a tokamak • The JET tokamak provides a vital testing ground for understanding the physics and technologies necessary for an eventual fusion reactor • ITER is due to power up in 2016 and will be the next step towards a demonstration fusion power plant, which could be operational by 2035 By 2025 the Earth's population is predicted to reach eight billion. By the turn of the next century it could be as many as 12 billion. Even if the industrialized nations find a way to reduce their energy consumption, this unprecedented increase in population - coupled with rising prosperity in the developing world - will place huge demands on global energy supplies. As our primary sources of energy - fossil fuels - begin to run out, and burning them causes increasing environmental concerns, the human race faces the challenge of finding new energy sources. -
DISTRIBUTION of THIS DOCUMENT IS UNLIMITED Temperatures in the Range 5-10 Kev Are Still Needed, but the Lawson Number Can Be Reduced to the Low 10 Cm Sec Range
TFTR and Other Large Tokamaks Plasma Physics Laboratory, Princeton University Princeton, New Jersey 08544 H.P. Furth CONF-8604223—1 DE86 012761 Introduction The near-term goal of fusion research is to produce deuterium-tritium plasmas with temperatures above 10 keV and Lawson numbers nTE above 10 cm sec. As indicated in Fig. 1, experiments entering this parameter range will be able to satisfy Lawson's break-even criterion, where the fusion power output equals the required plasma-heating-power input (Q = 1 ). The ultimate reactor goal is to reach equilibrium-burn conditions, where the energetic alpha particles generated by the D-T reaction are sufficient to maintain the plasma temperature against all heat losses (Q = °°). At the outset of the international controlled-fusion research effort in the 19 50's, Lawson's goal seemed intimidatingly remote from experimental capabilities. During the following ten years, substantial scientific progress was made, but the rate of advance in the Lawson diagram was not such as to inspire confidence that the fusion program would reach fruition within the lifetime of its pioneers. The notable success of the Kurchatov Institute's T-3 tokamak during 1968-69 brightened the outlook considerably. The tokamak configuration was recognized as a cost-effective experimental tool and has permitted steady progress during subsequent decades. World-wide recognition of the favorable experimental opportunity for entry into the reactor plasma regime led to the initiation, in the mid-1970's, of four large new tokamak projects (Table I). Plans for the Joint European Torus (JET) were defined in 1971-73: th_ very large plasma size and high current of the JET plasma offered a potential for exceeding the Lawson break- even criterion and possibly evan reaching ignition in D-T plasmas. -
Corrosion Issues in Fusion Reactors
Corrosion Issues in Fusion Reactors Digby D. Macdonald1 and George R. Engelhardt2 1Department of Nuclear Engineering University of California at Berkeley Berkeley, CA 94720 2OLI Systems, Inc. 240 Cedar Knolls Rd Cedar Knolls, NJ 07927 WCO Forum Corrosion 2020 Houston, TX, USA Background • Nuclear fusion is the process of fusing the light elements (primarily 1 2 3 the isotopes of hydrogen, H1, D1, T1. • Fusion results in a loss of mass, which is converted into energy, E = Δm.c2. • Process that occurs in the sun and stars in nuclear synthesis. Minimum temperature for D + T is 10 keV = 300,000,000 oC equivalent. • First demonstrated on earth in 1950s through thermonuclear weapons. • Almost a limitless source of clean energy if it can be made to work. • First controlled fusion demonstrated at JET in Oxford, UK, Q =0.75. • First technology demonstration, ITER (‘the way”), being constructed at Cadarache, France. Q > 10. Thermonuclear Reactions Reaction Reaction Equation Initial Mass (u) Mass Change (u) % Mass Change 2 2 3 1 -3 D-D D1 + D1 → He2 + n0 4.027106424 -2.44152x10 0.06062 2 2 3 1 -3 D-D D1 + D1 → H1 + p1 4.027106424 -3.780754x10 0.09388 2 3 4 1 D-T D1 + T1 → He2 + n0 5.029602412 -0.019427508 0.3863 e--p+ e- + p+ → 2hν 1.8219x10-31 -1.8219x10-31 100 Must overcome Coulombic repulsion of nuclei in the plasma Preferred Reaction • The easiest reaction to achieve 2 3 4 1 is: D1 + T1 → He2 + n0 because it has the lowest ignition temperature (10 keV). -
June 2018 Fusion in Europe
FUSION IN EUROPE NEWS & VIEWS ON THE PROGRESS OF FUSION RESEARCH “Let us face it: TO DTT OR NOT TO DTT there is no VACUUM – HOW NOTHING REALLY planet B!” MATTERS NOW IS THE TIME TO BE AT JET 2 2018 Fusion Writers … wanted! … and Artists This could be you Fusion in Europe is call- ing for aspiring writers and gifted artists! Introduce yourself to an international audience! Catch one of our topics and turn it into your own! • The future powered by fusion energy • Fusion science and industrial reality • Fusion - a melting pot of different sciences • Fusion drives innovation Find the entire list here: tinyurl.com/ybd4omz7 Your application should include a short CV and a motivational letter. Please apply here: tinyurl.com/ybd4omz7 EUROfusion | Communications Team | Anne Purschwitz (”Fusion in Europe“ Editor) Boltzmannstr. 2 | 85748Application Garching | +49 89 deadline: 3299 4128 | [email protected] 25 June 2018 | Editorial | EUROfusion | “It is the best time to be at JET right now” says a passionate Eva Belo nohy. The member of JET’s Exploitation Unit has recently organised a very suc- cessful workshop. It was aimed to ‘refresh’ the knowledge of European fu- sion researchers regarding the Joint European Torus (JET) but that was a classic understatement. The meeting was a fully-fledged overview on JET’s capabilities which have tremendously changed in the past. The tokamak has gone through major upgrades since it saw its first deuterium tritium campaign in 1997. Those include not only an ITER-like wall but also an Fusion Writers… wanted! … increase of the heating power by 50 percent. -
Introduction to Nuclear Fusion
Introduction to Nuclear Fusion Prof. Dr. Yong-Su Na To build a sun on earth - Open magnetic confinement - Closed magnetic confinement 2 What is closed magnetic confinement? 3 Open Magnetic System B sin 2 min Bmax v|| loss cone loss cone - Suffering from end losses J.P. Freidberg, “Ideal Magneto-Hydro-Dynamics”, lecture note A. A. Harms et al, “Principles of Fusion Energy”, World Scientific (2000) 4 Open Magnetic System Magnetic field Is this motion realistic? ion Dunkin donuts (2010) 5 Closed Magnetic System Magnetic field Donut-shaped vacuum vessel ion 6 Closed Magnetic System 7 Closed Magnetic System Magnetic field R 0 a Plasma needs to be confined ion R0 = 1.8 m, a = 0.5 m in KSTAR 8 Closed Magnetic System Magnetic field R 0 a Plasma needs to be confined ion R0 = 6.2 m, a = 2.0 m in ITER 9 Closed Magnetic System Toroidal Field (TF) coil Magnetic field Toroidal direction Applying toroidal magnetic field ion 3.5 T in KSTAR, 5.3 T in ITER 10 Closed Magnetic System Toroidal Field (TF) coil Toroidal direction Applying toroidal magnetic field 3.5 T in KSTAR, 5.3 T in ITER 11 Closed Magnetic System Toroidal Field (TF) coil Magnetic field Toroidal direction Magnetic field of earth? 0.5 Gauss = 0.00005 T ion 12 http://www.crystalinks.com/earthsmagneticfield.html Closed Magnetic System Magnetic field Magnetic field of earth? 0.5 Gauss = 0.00005 T ion http://www.transformacionconciencia.com/archives/2384 13 Closed Magnetic System Magnetic field ion 14 Lesch, Astrophysics, IPP Summer School (2008) Closed Magnetic System Magnetic field ion electron -
Written Statement of Dr. Stephen O. Dean President, Fusion Power Associates to Meeting of DOE Fusion Energy Sciences Advisory Committee February 29, 2012
Written Statement Of Dr. Stephen O. Dean President, Fusion Power Associates To Meeting of DOE Fusion Energy Sciences Advisory Committee February 29, 2012 Public Comment Session First, let me say that I endorse the recommendation just made by Dr. Earl Marmar of MIT that no irrevocable decisions be made relative to reductions in the fusion program, as proposed in the President’s FY 2013 budget submission to Congress, until a vetting of such reductions occurs within the U.S. fusion community. This should be done by FESAC, or otherwise, to seek community consensus relative to priorities identified previously by FESAC. Much of the discussion has been focused on the proposed termination of the Alcator C- Mod program at MIT. The proposed termination is of serious concern, since that program has made, and is making, important contributions to our understanding of tokamak physics and, furthermore, is important to the training of the next generation of fusion scientists. Termination of Alcator C-Mod would mean a “double whammy” for the MIT fusion program, since DOE terminated the other significant experimental facility there last year, the Levitated Dipole Experiment (LDX). Without these two facilities, MIT will lack the facilities to continue providing experience to students doing experimental fusion research. But the problem with the proposed reductions is much broader and more serious that just the role and future of the MIT program. Reductions in other areas, such as High Energy Density Laboratory Plasmas (HEDLP), theory, and systems studies will result not only in a loss of valuable talent and expertise throughout the U.S. -
Neutron Emission Spectrometry for Fusion Reactor Diagnosis
Digital Comprehensive Summaries of Uppsala Dissertations from the Faculty of Science and Technology 1244 Neutron Emission Spectrometry for Fusion Reactor Diagnosis Method Development and Data Analysis JACOB ERIKSSON ACTA UNIVERSITATIS UPSALIENSIS ISSN 1651-6214 ISBN 978-91-554-9217-5 UPPSALA urn:nbn:se:uu:diva-247994 2015 Dissertation presented at Uppsala University to be publicly examined in Polhemsalen, Ångströmlaboratoriet, Lägerhyddsvägen 1, Uppsala, Friday, 22 May 2015 at 09:15 for the degree of Doctor of Philosophy. The examination will be conducted in English. Faculty examiner: Dr Andreas Dinklage (Max-Planck-Institut für Plasmaphysik, Greifswald, Germany). Abstract Eriksson, J. 2015. Neutron Emission Spectrometry for Fusion Reactor Diagnosis. Method Development and Data Analysis. Digital Comprehensive Summaries of Uppsala Dissertations from the Faculty of Science and Technology 1244. 92 pp. Uppsala: Acta Universitatis Upsaliensis. ISBN 978-91-554-9217-5. It is possible to obtain information about various properties of the fuel ions deuterium (D) and tritium (T) in a fusion plasma by measuring the neutron emission from the plasma. Neutrons are produced in fusion reactions between the fuel ions, which means that the intensity and energy spectrum of the emitted neutrons are related to the densities and velocity distributions of these ions. This thesis describes different methods for analyzing data from fusion neutron measurements. The main focus is on neutron spectrometry measurements, using data used collected at the tokamak fusion reactor JET in England. Several neutron spectrometers are installed at JET, including the time-of-flight spectrometer TOFOR and the magnetic proton recoil (MPRu) spectrometer. Part of the work is concerned with the calculation of neutron spectra from given fuel ion distributions. -
Plasma Physics Laboratory
fco^m OCTOBER 1980 UC-20b,d NON-SUPERCONDUCTING- MAGNET STRUCTURES FOR NEAR^TEfti LARGE FUSION EXPERIMENTAL DEVICES -:BY J. FILE, D. S, KHUT^xiU, R, E, MARINO, AND G. ti, RAPPE PLASMA PHYSICS LABORATORY r,7 PRINCETON UNIVERSITY PRINCETON, NEW JERSEY m tr T;;;S 30CUV£MT !S iHnwrru NON-SUPERCONDUCTING MAGNET STRUCTURES FOR NBRR-'IERM, LARGE FUSION EXPERIMENTAL DEVICES J. File, D.S. Knutson, R.E. Marino and G.H. Rappe Plasma Physics Laboratory, Princeton University, Princeton, New Jersey 08544, USA ABSTRACT Water cooled copper magnets provide a means of producing high magnetic fields for tokamaks using a well developed existing technology. The basic function of these magnets is to provide reliable, both time varying and steady state, magnetic fields. Copper electrical properties, insulation, and water cooling systems play major roles in design selection. Aside from being electro-magnetic devices, coils designed for tokamaks must be self-supporting structures, capable of resisting large I x B magnetic forces. These magnets require the integration of both electrical and structural design considerations. Magnet integrity is enhanced by the presence of structures which lend additional external support. These external structural systems are highly stressed and, often, deflection limited. This paper describes the magnet and structural design in the following American tokamak devices: the Princeton Large Torus (PLT), the Princeton Divertor Experiment (PDX), and the Tokamak Fusion Test Reactor (TFTR). The Joint European Torus (JET), also presented herein, has a magnet structure evolved from several European programs and, like TFTR, represents state of the art magnet and structure design. | DISCLAIMER TliTtbOGknA!}!K>£!K!ajn*^oun1i''M?l looniofeo cyan Jgency of fifl Unrie-J Slaftt Gowmrien*.