Two Applications of Plasma Physics Modeling for Controlled Fusion Research
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Nuclear Fusion
Copyright © 2016 by Gerald Black. Published by The Mars Society with permission NUCLEAR FUSION: THE SOLUTION TO THE ENERGY PROBLEM AND TO ADVANCED SPACE PROPULSION Gerald Black Aerospace Engineer (retired, 40+ year career); email: [email protected] Currently Chair of the Ohio Chapter of the Mars Society Presented at Mars Society Annual Convention, Washington DC, September 22, 2016 ABSTRACT Nuclear fusion has long been viewed as a potential solution to the world’s energy needs. However, the government sponsored megaprojects have been floundering. The two multi-billion- dollar flagship programs, the International Tokamak Experimental Reactor (ITER) and the National Ignition Facility (NIF), have both experienced years of delays and a several-fold increase in costs. The ITER tokamak design is so large and complex that, even if this approach succeeds, there is doubt that it would be economical. After years of testing at full power, the NIF facility is still far short of achieving its goal of fusion ignition. But hope is not lost. Several private companies have come up with smaller and simpler approaches that show promise. This talk highlights the progress made by one such private company, namely LPPFusion (formerly called Lawrenceville Plasma Physics). LPPFusion is developing focus fusion technology based on the dense plasma focus device and hydrogen-boron 11 fuel. This approach, if it works, would produce a fusion power generator small enough to fit in a truck. This device would produce no radioactivity, there would be no possibility of a meltdown or other safety issues, and it would be more economical than any other source of electricity. -
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. -
Retarding Field Analyzer (RFA) for Use on EAST
Magnetic Confinement Fusion C. Xiao and STOR-M team Plasma Physics Laboratory University of Saskatchewan Saskatoon, Canada \ Outline Magnetic Confinement scheme Progress in the world Tokamak Research at the University of Saskatchewan 2 CNS-2019 Fusion Session, June 24, 2019 Magnetic Confinement Scheme 3 CNS-2019 Fusion Session, June 24, 2019 Charged particle motion in straight magnetic field A charged particle circulates around the magnetic field lines (e.g., produced in a solenoid) Cross-field motion is restricted within Larmor radius 푚푣 푟 = 퐿 푞퐵 Motion along the field lines is still free End loss to the chamber wall Chamber Wall 4 CNS-2019 Fusion Session, June 24, 2019 Toriodal geometry is the solution However, plasma in simple toroidal field drifts to outboard on the wall 5 CNS-2019 Fusion Session, June 24, 2019 Tokamak Bend solenoid to form closed magnetic field lines circular field line without ends no end-loss. Transformer action produces a huge current in the chamber Generate poloidal field Heats the plasma Tokamak: abbreviation of Russian words for toroidal magnetic chamber 6 CNS-2019 Fusion Session, June 24, 2019 Stellarator • The magnetic field are generated by complicated external coils • No plasma current, no disruptions • Engineering is challenge 7 CNS-2019 Fusion Session, June 24, 2019 Wendelstein 7-X, Greifswald, Germany • Completed in October 2015 • Superconducting coils • High density and high temperature have been achieved 8 CNS-2019 Fusion Session, June 24, 2019 Reversed Field Pinch • Toroidal field reverses direction at the edge • The magnetic field are generated by current in plasma • Toroidal filed and poloidal field are of similar strength. -
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. -
NIAC 2011 Phase I Tarditti Aneutronic Fusion Spacecraft Architecture Final Report
NASA-NIAC 2001 PHASE I RESEARCH GRANT on “Aneutronic Fusion Spacecraft Architecture” Final Research Activity Report (SEPTEMBER 2012) P.I.: Alfonso G. Tarditi1 Collaborators: John H. Scott2, George H. Miley3 1Dept. of Physics, University of Houston – Clear Lake, Houston, TX 2NASA Johnson Space Center, Houston, TX 3University of Illinois-Urbana-Champaign, Urbana, IL Executive Summary - Motivation This study was developed because the recognized need of defining of a new spacecraft architecture suitable for aneutronic fusion and featuring game-changing space travel capabilities. The core of this architecture is the definition of a new kind of fusion-based space propulsion system. This research is not about exploring a new fusion energy concept, it actually assumes the availability of an aneutronic fusion energy reactor. The focus is on providing the best (most efficient) utilization of fusion energy for propulsion purposes. The rationale is that without a proper architecture design even the utilization of a fusion reactor as a prime energy source for spacecraft propulsion is not going to provide the required performances for achieving a substantial change of current space travel capabilities. - Highlights of Research Results This NIAC Phase I study provided led to several findings that provide the foundation for further research leading to a higher TRL: first a quantitative analysis of the intrinsic limitations of a propulsion system that utilizes aneutronic fusion products directly as the exhaust jet for achieving propulsion was carried on. Then, as a natural continuation, a new beam conditioning process for the fusion products was devised to produce an exhaust jet with the required characteristics (both thrust and specific impulse) for the optimal propulsion performances (in essence, an energy-to-thrust direct conversion). -
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. -
Fission and Fusion Can Yield Energy
Nuclear Energy Nuclear energy can also be separated into 2 separate forms: nuclear fission and nuclear fusion. Nuclear fusion is the splitting of large atomic nuclei into smaller elements releasing energy, and nuclear fusion is the joining of two small atomic nuclei into a larger element and in the process releasing energy. The mass of a nucleus is always less than the sum of the individual masses of the protons and neutrons which constitute it. The difference is a measure of the nuclear binding energy which holds the nucleus together (Figure 1). As figures 1 and 2 below show, the energy yield from nuclear fusion is much greater than nuclear fission. Figure 1 2 Nuclear binding energy = ∆mc For the alpha particle ∆m= 0.0304 u which gives a binding energy of 28.3 MeV. (Figure from: http://hyperphysics.phy-astr.gsu.edu/hbase/nucene/nucbin.html ) Fission and fusion can yield energy Figure 2 (Figure from: http://hyperphysics.phy-astr.gsu.edu/hbase/nucene/nucbin.html) Nuclear fission When a neutron is fired at a uranium-235 nucleus, the nucleus captures the neutron. It then splits into two lighter elements and throws off two or three new neutrons (the number of ejected neutrons depends on how the U-235 atom happens to split). The two new atoms then emit gamma radiation as they settle into their new states. (John R. Huizenga, "Nuclear fission", in AccessScience@McGraw-Hill, http://proxy.library.upenn.edu:3725) There are three things about this induced fission process that make it especially interesting: 1) The probability of a U-235 atom capturing a neutron as it passes by is fairly high. -
Fusion Public Meeting Slides-03302021-FINAL
TitleDeveloping Lorem a Regulatory Ipsum Framework for Fusion Energy Systems March 30, 2021 Agenda Time Topic Speaker(s) 12:30-12:40pm Introduction/Opening Remarks NRC Discussion on NAS Report “Key Goals and Innovations Needed for a U.S. Fusion Jennifer Uhle (NEI) 12:40-1:10pm Pilot Plant” Rich Hawryluk (PPPL) Social License and Ethical Review of Fusion: Methods to Achieve Social Seth Hoedl (PRF) 1:10-1:40pm Acceptance Developers Perspectives on Potential Hazards, Consequences, and Regulatory Frameworks for Commercial Deployment: • Fusion Industry Association - Industry Remarks Andrew Holland (FIA) 1:40-2:40pm • TAE – Regulatory Insights Michl Binderbauer (TAE) • Commonwealth Fusion Systems – Fusion Technology and Radiological Bob Mumgaard (CFS) Hazards 2:40-2:50pm Break 2:50-3:10pm Licensing and Regulating Byproduct Materials by the NRC and Agreement States NRC Discussions of Possible Frameworks for Licensing/Regulating Commercial Fusion • NRC Perspectives – Byproduct Approach NRC/OAS 3:10-4:10pm • NRC Perspectives – Hybrid Approach NRC • Industry Perspectives - Hybrid Approach Sachin Desai (Hogan Lovells) 4:10-4:30pm Next Steps/Questions All Public Meeting Format The Commission recently revised its policy statement on how the agency conducts public meetings (ADAMS No.: ML21050A046). NRC Public Website - Fusion https://www.nrc.gov/reactors/new-reactors/advanced/fusion-energy.html NAS Report “Key Goals and Innovations Needed for a U.S. Fusion Pilot Plant” Bringing Fusion to the U.S. Grid R. J. Hawryluk J. Uhle D. Roop D. Whyte March 30, 2021 Committee Composition Richard J. Brenda L. Garcia-Diaz Gerald L. Kathryn A. Per F. Peterson (NAE) Jeffrey P. Hawryluk (Chair) Savannah River National Kulcinski (NAE) McCarthy (NAE) University of California, Quintenz Princeton Plasma Laboratory University of Oak Ridge National Berkeley/ Kairos Power TechSource, Inc. -
Stellarator and Tokamak Plasmas: a Comparison
Home Search Collections Journals About Contact us My IOPscience Stellarator and tokamak plasmas: a comparison This article has been downloaded from IOPscience. Please scroll down to see the full text article. 2012 Plasma Phys. Control. Fusion 54 124009 (http://iopscience.iop.org/0741-3335/54/12/124009) View the table of contents for this issue, or go to the journal homepage for more Download details: IP Address: 130.183.100.97 The article was downloaded on 22/11/2012 at 08:08 Please note that terms and conditions apply. IOP PUBLISHING PLASMA PHYSICS AND CONTROLLED FUSION Plasma Phys. Control. Fusion 54 (2012) 124009 (12pp) doi:10.1088/0741-3335/54/12/124009 Stellarator and tokamak plasmas: a comparison P Helander, C D Beidler, T M Bird, M Drevlak, Y Feng, R Hatzky, F Jenko, R Kleiber,JHEProll, Yu Turkin and P Xanthopoulos Max-Planck-Institut fur¨ Plasmaphysik, Greifswald and Garching, Germany Received 22 June 2012, in final form 30 August 2012 Published 21 November 2012 Online at stacks.iop.org/PPCF/54/124009 Abstract An overview is given of physics differences between stellarators and tokamaks, including magnetohydrodynamic equilibrium, stability, fast-ion physics, plasma rotation, neoclassical and turbulent transport and edge physics. Regarding microinstabilities, it is shown that the ordinary, collisionless trapped-electron mode is stable in large parts of parameter space in stellarators that have been designed so that the parallel adiabatic invariant decreases with radius. Also, the first global, electromagnetic, gyrokinetic stability calculations performed for Wendelstein 7-X suggest that kinetic ballooning modes are more stable than in a typical tokamak. -
Arxiv:2002.12686V1 [Physics.Pop-Ph] 28 Feb 2020 SOI Sphere of Influence VEV Variable Ejection Velocity
Achieving the required mobility in the solar system through Direct Fusion Drive Giancarlo Genta1 and Roman Ya. Kezerashvili2;3;4, 1Department of Mechanical and Aerospace Engineering, Politecnico di Torino, Turin, Italy 2Physics Department, New York City College of Technology, The City University of New York, Brooklyn, NY, USA 3The Graduate School and University Center, The City University of New York, New York, NY, USA 4Samara National Research University, Samara, Russian Federation (Dated: March 2, 2020) To develop a spacefaring civilization, humankind must develop technologies which enable safe, affordable and repeatable mobility through the solar system. One such technology is nuclear fusion propulsion which is at present under study mostly as a breakthrough toward the first interstellar probes. The aim of the present paper is to show that fusion drive is even more important in human planetary exploration and constitutes the natural solution to the problem of exploring and colonizing the solar system. Nomenclature Is specific impulse m mass mi initial mass ml mass of payload mp mass of propellant ms structural mass mt mass of the thruster mtank mass of tanks t time td departure time ve ejection velocity F thrust J cost function P power of the jet α specific mass of the generator γ optimization parameter ∆V velocity increment DFD Direct Fusion Drive IMLEO Initial Mass in Low Earth Orbit LEO Low Earth Orbit LMO Low Mars Orbit NEP Nuclear Electric Propulsion NTP Nuclear Thermal Propulsion SEP Solar Electric Propulsion arXiv:2002.12686v1 [physics.pop-ph] 28 Feb 2020 SOI Sphere of Influence VEV Variable Ejection Velocity I.