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Optimization of Ion Flow Rates in a Helicon Injected IEC Fusion System
Aeronautics and Aerospace Open Access Journal Research Article Open Access Optimization of ion flow rates in a helicon injected IEC fusion system Abstract Volume 4 Issue 2 - 2020 The Helicon Injected Inertial Electrostatic Confinement (IEC) offers an attractive D-D Qiheng Cai, George H Miley neutron source for neutron commercial and homeland security activation neutron analysis. Department of Nuclear, Plasma & Radiological Engineering, Designs with multiple injectors also provide a potential route to an attractive small fusion University of Illinois at Champaign-Urbana, USA reactor. Use of such a reactor has also been studied for deep space propulsion. In addition, a non-fusion design been studied for use as an electric thruster for near-term space Correspondence: Qiheng Cai, Department of Nuclear, Plasma applications. The Helicon Inertial Plasma Electrostatic Rocket (HIIPER) is an advanced & Radiological Engineering, University of Illinois at Champaign- space plasma thruster coupling the helicon and a modified IEC. A key aspect for all of these Urbana, Urbana, IL, 61801, Tel +15712679353, systems is to develop efficient coupling between the Helicon plasma injector and the IEC. Email This issue is under study and will be described in this presentation. To analyze the coupling efficiency, ion flow rates (which indicate how many ions exit the helicon and enter the IEC Received: May 01, 2020 | Published: May 21, 2020 device per second) are investigated by a global model. In this simulation particle rate and power balance equations are solved to investigate the time evolution of electron density, neutral density and electron temperature in the helicon tube. In addition to the Helicon geometry and RF field design, the use of a potential bias plate at the gas inlet of the Helicon is considered. -
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. -
Plasma Physics I APPH E6101x Columbia University Fall, 2016
Lecture 1: Plasma Physics I APPH E6101x Columbia University Fall, 2016 1 Syllabus and Class Website http://sites.apam.columbia.edu/courses/apph6101x/ 2 Textbook “Plasma Physics offers a broad and modern introduction to the many aspects of plasma science … . A curious student or interested researcher could track down laboratory notes, older monographs, and obscure papers … . with an extensive list of more than 300 references and, in particular, its excellent overview of the various techniques to generate plasma in a laboratory, Plasma Physics is an excellent entree for students into this rapidly growing field. It’s also a useful reference for professional low-temperature plasma researchers.” (Michael Brown, Physics Today, June, 2011) 3 Grading • Weekly homework • Two in-class quizzes (25%) • Final exam (50%) 4 https://www.nasa.gov/mission_pages/sdo/overview/ Launched 11 Feb 2010 5 http://www.nasa.gov/mission_pages/sdo/news/sdo-year2.html#.VerqQLRgyxI 6 http://www.ccfe.ac.uk/MAST.aspx http://www.ccfe.ac.uk/mast_upgrade_project.aspx 7 https://youtu.be/svrMsZQuZrs 8 9 10 ITER: The International Burning Plasma Experiment Important fusion science experiment, but without low-activation fusion materials, tritium breeding, … ~ 500 MW 10 minute pulses 23,000 tonne 51 GJ >30B $US (?) DIII-D ⇒ ITER ÷ 3.7 (50 times smaller volume) (400 times smaller energy) 11 Prof. Robert Gross Columbia University Fusion Energy (1984) “Fusion has proved to be a very difficult challenge. The early question was—Can fusion be done, and, if so how? … Now, the challenge lies in whether fusion can be done in a reliable, an economical, and socially acceptable way…” 12 http://lasco-www.nrl.navy.mil 13 14 Plasmasphere (Image EUV) 15 https://youtu.be/TaPgSWdcYtY 16 17 LETTER doi:10.1038/nature14476 Small particles dominate Saturn’s Phoebe ring to surprisingly large distances Douglas P. -
Trivia Questions
TRIVIA QUESTIONS Submitted by: ANS Savannah River - A. Bryson, D. Hanson, B. Lenz, M. Mewborn 1. What was the code name used for the first U.S. test of a dry fuel hydrogen bomb? Castle Bravo 2. What was the name of world’s first artificial nuclear reactor to achieve criticality? Chicago Pile-1 (CP-1), I also seem to recall seeing/hearing them referred to as “number one,” “number two,” etc. 3. How much time elapsed between the first known sustained nuclear chain reaction at the University of Chicago and the _____ Option 1: {first use of this new technology as a weapon} or Option 2: {dropping of the atomic bomb in Hiroshima} A3) First chain reaction = December 2nd 1942, First bomb-drop = August 6th 1945 4. Some sort of question drawing info from the below tables. For example, “what were the names of the other aircraft that accompanied the Enola Gay (one point for each correct aircraft name)?” Another example, “What was the common word in the call sign of the pilots who flew the Japanese bombing missions?” A4) Screenshots of tables from the Wikipedia page “Atomic bombings of Hiroshima and Nagasaki” Savannah River Trivia / Page 1 of 18 5. True or False: Richard Feynman’s name is on the patent for a nuclear powered airplane? (True) 6. What is the Insectary of Bobo-Dioulasso doing to reduce the spread of sleeping sickness and wasting diseases that affect cattle using a nuclear technique? (Sterilizing tsetse flies; IAEA.org) 7. What was the name of the organization that studied that radiological effects on people after the atomic bombings? Atomic Bomb Casualty Commission 8. -
Analysis of Equilibrium and Topology of Tokamak Plasmas
ANALYSIS OF EQUILIBRIUM AND TOPOLOGY OF TOKAMAK PLASMAS Boudewijn Philip van Millig ANALYSIS OF EQUILIBRIUM AND TOPOLOGY OF TOKAMAK PLASMAS BOUDEWHN PHILIP VAN MILUGEN Cover picture: Frequency analysis of the signal of a magnetic pick-up coil. Frequency increases upward and time increases towards the right. Bright colours indicate high spectral power. An MHD mode is seen whose frequency decreases prior to a disruption (see Chapter 5). II ANALYSIS OF EQUILIBRIUM AND TOPOLOGY OF TOKAMAK PLASMAS ANALYSE VAN EVENWICHT EN TOPOLOGIE VAN TOKAMAK PLASMAS (MET EEN SAMENVATTING IN HET NEDERLANDS) PROEFSCHRIFT TER VERKRUGING VAN DE GRAAD VAN DOCTOR IN DE WISKUNDE EN NATUURWETENSCHAPPEN AAN DE RUKSUNIVERSITEIT TE UTRECHT, OP GEZAG VAN DE RECTOR MAGNIFICUS PROF. DR. J.A. VAN GINKEL, VOLGENS BESLUTT VAN HET COLLEGE VAN DECANEN IN HET OPENBAAR TE VERDEDIGEN OP WOENSDAG 20 NOVEMBER 1991 DES NAMIDDAGS TE 2.30 UUR DOOR BOUDEWUN PHILIP VAN MILLIGEN GEBOREN OP 25 AUGUSTUS 1964 TE VUGHT DRUKKERU ELINKWIJK - UTRECHT m PROMOTOR: PROF. DR. F.C. SCHULLER CO-PROMOTOR: DR. N.J. LOPES CARDOZO The work described in this thesis was performed as part of the research programme of the 'Stichting voor Fundamenteel Onderzoek der Materie' (FOM) with financial support from the 'Nederlandse Organisatie voor Wetenschappelijk Onderzoek' (NWO) and EURATOM, and was carried out at the FOM-Instituut voor Plasmafysica te Nieuwegein, the Max-Planck-Institut fur Plasmaphysik, Garching bei Munchen, Deutschland, and the JET Joint Undertaking, Abingdon, United Kingdom. IV iEstos Bretones -
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. -
Plasma Stability and the Bohr - Van Leeuwen Theorem
NASA TECHNICAL NOTE -I m 0 I iii I nE' n z c * v) 4 z PLASMA STABILITY AND THE BOHR - VAN LEEUWEN THEOREM by J. Reece Roth Lewis Research Center Cleueland, Ohio NATIONAL AERONAUTICS AND SPACE ADMINISTRATION WASHINGTON, D. C. APRIL 1967 I ~ .. .. .. TECH LIBRARY KAFB, NM I llllll Illlll lull IIM IIllIll1 Ill1 OL3060b NASA TN D-3880 PLASMA STABILITY AND THE BOHR - VAN LEEWEN THEOREM By J. Reece Roth Lewis Research Center Cleveland, Ohio NATIONAL AERONAUTICS AND SPACE ADMINISTRATION For sale by the Clearinghouse for Federal Scientific and Technical Information Springfield, Virginia 22151 - CFSTI price $3.00 CONTENTS Page SUMMARY.- ........................................ 1 INTRODUCTION-___ ..................................... 2 THE BOHR - VAN LEEUWEN THEOREM ....................... 3 RELATION OF THE BOHR - VAN LEEUWEN THEOREM TO CONVENTIONAL MACROSCOPIC THEORIES OF PLASMA STABILITY ................ 3 The Momentum Equation .............................. 3 The Conventional Magnetostatic and Hydromagnetic Theories .......... 4 The Bohr - van Leeuwen Theorem. ........................ 7 Application of the Bohr - van Leeuwen Theorem to Plasmas ........... 9 The Bohr - van Leeuwen Theorem and the Literature of Plasma Physics .... 10 PLASMA CURRENTS ................................. 11 Assumptions of Analysis .............................. 11 Sources of Plasma Currents ............................ 12 Net Plasma Currents. ............................... 15 CHARACTERISTICS OF PLASMAS SATISFYING THE BOHR - VAN LEEUWEN THEOREM ..................................... -
Plasma Waves
Plasma Waves S.M.Lea January 2007 1 General considerations To consider the different possible normal modes of a plasma, we will usually begin by assuming that there is an equilibrium in which the plasma parameters such as density and magnetic field are uniform and constant in time. We will then look at small perturbations away from this equilibrium, and investigate the time and space dependence of those perturbations. The usual notation is to label the equilibrium quantities with a subscript 0, e.g. n0, and the pertrubed quantities with a subscript 1, eg n1. Then the assumption of small perturbations is n /n 1. When the perturbations are small, we can generally ignore j 1 0j ¿ squares and higher powers of these quantities, thus obtaining a set of linear equations for the unknowns. These linear equations may be Fourier transformed in both space and time, thus reducing the differential equations to a set of algebraic equations. Equivalently, we may assume that each perturbed quantity has the mathematical form n = n exp i~k ~x iωt (1) 1 ¢ ¡ where the real part is implicitly assumed. Th³is form descri´bes a wave. The amplitude n is in ~ general complex, allowing for a non•zero phase constant φ0. The vector k, called the wave vector, gives both the direction of propagation of the wave and the wavelength: k = 2π/λ; ω is the angular frequency. There is a relation between ω and ~k that is determined by the physical properties of the system. The function ω ~k is called the dispersion relation for the wave. -
Problems for the Course F5170 – Introduction to Plasma Physics
Problems for the Course F5170 { Introduction to Plasma Physics Jiˇr´ı Sperka,ˇ Jan Vor´aˇc,Lenka Zaj´ıˇckov´a Department of Physical Electronics Faculty of Science Masaryk University 2014 Contents 1 Introduction5 1.1 Theory...............................5 1.2 Problems.............................6 1.2.1 Derivation of the plasma frequency...........6 1.2.2 Plasma frequency and Debye length..........7 1.2.3 Debye-H¨uckel potential.................8 2 Motion of particles in electromagnetic fields9 2.1 Theory...............................9 2.2 Problems............................. 10 2.2.1 Magnetic mirror..................... 10 2.2.2 Magnetic mirror of a different construction...... 10 2.2.3 Electron in vacuum { three parts............ 11 2.2.4 E × B drift........................ 11 2.2.5 Relativistic cyclotron frequency............. 12 2.2.6 Relativistic particle in an uniform magnetic field... 12 2.2.7 Law of conservation of electric charge......... 12 2.2.8 Magnetostatic field.................... 12 2.2.9 Cyclotron frequency of electron............. 12 2.2.10 Cyclotron frequency of ionized hydrogen atom.... 13 2.2.11 Magnetic moment.................... 13 2.2.12 Magnetic moment 2................... 13 2.2.13 Lorentz force....................... 13 3 Elements of plasma kinetic theory 14 3.1 Theory............................... 14 3.2 Problems............................. 15 3.2.1 Uniform distribution function.............. 15 3.2.2 Linear distribution function............... 15 3.2.3 Quadratic distribution function............. 15 3.2.4 Sinusoidal distribution function............. 15 3.2.5 Boltzmann kinetic equation............... 15 1 CONTENTS 2 4 Average values and macroscopic variables 16 4.1 Theory............................... 16 4.2 Problems............................. 17 4.2.1 RMS speed........................ 17 4.2.2 Mean speed of sinusoidal distribution........ -
Modeling and Control of Plasma Rotation for NSTX Using
PAPER Related content - Central safety factor and N control on Modeling and control of plasma rotation for NSTX NSTX-U via beam power and plasma boundary shape modification, using TRANSP for closed loop simulations using neoclassical toroidal viscosity and neutral M.D. Boyer, R. Andre, D.A. Gates et al. beam injection - Topical Review M S Chu and M Okabayashi To cite this article: I.R. Goumiri et al 2016 Nucl. Fusion 56 036023 - Rotation and momentum transport in tokamaks and helical systems K. Ida and J.E. Rice View the article online for updates and enhancements. Recent citations - Design and simulation of the snowflake divertor control for NSTX–U P J Vail et al - Real-time capable modeling of neutral beam injection on NSTX-U using neural networks M.D. Boyer et al - Resistive wall mode physics and control challenges in JT-60SA high scenarios L. Pigatto et al This content was downloaded from IP address 128.112.165.144 on 09/09/2019 at 19:26 IOP Nuclear Fusion International Atomic Energy Agency Nuclear Fusion Nucl. Fusion Nucl. Fusion 56 (2016) 036023 (14pp) doi:10.1088/0029-5515/56/3/036023 56 Modeling and control of plasma rotation for 2016 NSTX using neoclassical toroidal viscosity © 2016 IAEA, Vienna and neutral beam injection NUFUAU I.R. Goumiri1, C.W. Rowley1, S.A. Sabbagh2, D.A. Gates3, S.P. Gerhardt3, M.D. Boyer3, R. Andre3, E. Kolemen3 and K. Taira4 036023 1 Department of Mechanical and Aerospace Engineering, Princeton University, Princeton, NJ 08544, USA I.R. Goumiri et al 2 Department of Applied Physics and Applied Mathematics, -
An Overview of the HIT-SI Research Program and Its Implications for Magnetic Fusion Energy
An overview of the HIT-SI research program and its implications for magnetic fusion energy Derek Sutherland, Tom Jarboe, and The HIT-SI Research Group University of Washington 36th Annual Fusion Power Associates Meeting – Strategies to Fusion Power December 16-17, 2015, Washington, D.C. Motivation • Spheromaks configurations are attractive for fusion power applications. • Previous spheromak experiments relied on coaxial helicity injection, which precluded good confinement during sustainment. • Fully inductive, non-axisymmetric helicity injection may allow us to overcome the limitations of past spheromak experiments. • Promising experimental results and an attractive reactor vision motivate continued exploration of this possible path to fusion power. Outline • Coaxial helicity injection NSTX and SSPX • Overview of the HIT-SI experiment • Motivating experimental results • Leading theoretical explanation • Reactor vision and comparisons • Conclusions and next steps Coaxial helicity injection (CHI) has been used successfully on NSTX to aid in non-inductive startup Figures: Raman, R., et al., Nucl. Fusion 53 (2013) 073017 • Reducing the need for inductive flux swing in an ST is important due to central solenoid flux-swing limitations. • Biasing the lower divertor plates with ambient magnetic field from coil sets in NSTX allows for the injection of magnetic helicity. • A ST plasma configuration is formed via CHI that is then augmented with other current drive methods to reach desired operating point, reducing or eliminating the need for a central solenoid. • Demonstrated on HIT-II at the University of Washington and successfully scaled to NSTX. Though CHI is useful on startup in NSTX, Cowling’s theorem removes the possibility of a steady-state, axisymmetric dynamo of interest for reactor applications • Cowling* argued that it is impossible to have a steady-state axisymmetric MHD dynamo (sustain current on magnetic axis against resistive dissipation). -
The Database for Comparison of Plasma Parameters of the JET Tokamak in Various Regimes of Its Operation
Czech Technical University Faculty of Nuclear Sciences and Physical Engineering Department of Physics The database for comparison of plasma parameters of the JET tokamak in various regimes of its operation (Research project) Martin Kubiˇc Supervisor: Ing. Ivan Duran,ˇ Ph.D Submitted: 24.9.2008 Contents Abstract 2 List of Abbreviations 3 1 Thermonuclear Fusion 4 1.1 Introduction ................................... 4 1.2 Tokamak ..................................... 5 1.3 JET tokamak .................................. 6 1.3.1 Introduction ............................... 6 1.3.2 Description of the JET tokamak .................... 7 2 JET operating regimes 9 2.1 Introduction ................................... 9 2.2 H-mode ..................................... 9 2.3 Internal transport barrier ............................ 11 3 Results 14 3.1 Introduction ................................... 14 3.2 MDB database ................................. 15 3.3 Set-up and evaluation of the database ..................... 16 3.3.1 Impurities ................................ 17 3.3.2 Temperature and density profile .................... 18 3.3.3 Radiation pattern ............................ 18 3.3.4 Energy balance ............................. 21 Summary 22 Bibliography 24 1 Abstract Presently, one of the main responsibilities of JET tokamak is to prepare the operating regimes for future fusion experimental reactor ITER, which is being built in Cadarache, France. The main aim of this report is to compare some aspects of the two ITER candidate operating scenarios, ELMy H-mode and advanced regime with internal transport barrier. For this purpose statistical approach was chosen compiling a large number of JET edge and core plasma quantities across a large discharge database to assess the level of similarity of each type of scenario. The report is focused on influence of gas impurities on plasma performance in both regimes.