A Passion for Plasma Physics and Nuclear Fusion Research. K. A. Connor Plasma Dynamics Laboratory ECSE Department RPI

Similar documents
Magnetic Confinement Fusion and Tokamaks Chijin Xiao Department of Physics and Engineering Physics University of Saskatchewan

Turbulence and Transport The Secrets of Magnetic Confinement

Chapter IX: Nuclear fusion

INTRODUCTION TO MAGNETIC NUCLEAR FUSION

PLASMA: WHAT IT IS, HOW TO MAKE IT AND HOW TO HOLD IT. Felix I. Parra Rudolf Peierls Centre for Theoretical Physics, University of Oxford

Introduction to Fusion Physics

Magnetic Confinement Fusion-Status and Challenges

Toward the Realization of Fusion Energy

ICF ignition and the Lawson criterion

Toroidal confinement devices

Introduction to Nuclear Fusion. Prof. Dr. Yong-Su Na

0 Magnetically Confined Plasma

On the physics of shear flows in 3D geometry

Physics & Engineering Physics University of Saskatchewan. Supported by NSERC, CRC

The Path to Fusion Energy creating a star on earth. S. Prager Princeton Plasma Physics Laboratory

Unpressurized steam reactor. Controlled Fission Reactors. The Moderator. Global energy production 2000

Stellarators. Dr Ben Dudson. 6 th February Department of Physics, University of York Heslington, York YO10 5DD, UK

Controlled Thermonuclear Fusion

The Dynomak Reactor System

purposes is highly encouraged.

Plasma & Fusion on Earth: merging age-old natural phenomena into your present and future

Jacob s Ladder Controlling Lightning

Sensors Plasma Diagnostics

22.615, MHD Theory of Fusion Systems Prof. Freidberg Lecture 15: Alternate Concepts (with Darren Sarmer)

EF2200 Plasma Physics: Fusion plasma physics

ª 10 KeV. In 2XIIB and the tandem mirrors built to date, in which the plug radius R p. ª r Li

MHD. Jeff Freidberg MIT

Physics of fusion power. Lecture 14: Anomalous transport / ITER

References and Figures from: - Basdevant, Fundamentals in Nuclear Physics

Cluster fusion in a high magnetic field

General Physics (PHY 2140)

Notes on fusion reactions and power balance of a thermonuclear plasma!

Sawtooth mixing of alphas, knock on D, T ions and its influence on NPA spectra in ITER plasma

Der Stellarator Ein alternatives Einschlusskonzept für ein Fusionskraftwerk

Ion orbits and ion confinement studies on ECRH plasmas in TJ-II stellarator

Progress of Confinement Physics Study in Compact Helical System

Chapter 1 Nature of Plasma

Simulation of alpha particle current drive and heating in spherical tokamaks

Tokamak Fusion Basics and the MHD Equations

Possibilities for Long Pulse Ignited Tokamak Experiments Using Resistive Magnets

Shear Flow Generation in Stellarators - Configurational Variations

Neutral beam plasma heating

Fusion Principles Jef ONGENA Plasma Physics Laboratory Royal Military Academy Brussels

Introduction to Plasma Physics

Retarding field energy analyzers for the ion temperature measurements in the SOL plasmas of the tokamak ISTTOK and the TJ-II stellarator

Experimental Facility to Study MHD effects at Very High Hartmann and Interaction parameters related to Indian Test Blanket Module for ITER

TWO FUSION TYPES NEUTRONIC ANEUTRONIC

DT Fusion Ignition of LHD-Type Helical Reactor by Joule Heating Associated with Magnetic Axis Shift )

Estimations of Beam-Beam Fusion Reaction Rates in the Deuterium Plasma Experiment on LHD )

Comparison of Ion Internal Transport Barrier Formation between Hydrogen and Helium Dominated Plasmas )

Inertial Confinement Fusion DR KATE LANCASTER YORK PLASMA INSTITUTE

Introduction Introduction

The Status of the Design and Construction of the Columbia Non-neutral Torus

Confinement of toroidal non-neutral plasma in Proto-RT

Electrode and Limiter Biasing Experiments on the Tokamak ISTTOK

Neoclassical transport

Fusion Energy: Pipe Dream or Panacea

Confinement of toroidal non-neutral plasma in Proto-RT

Joint ITER-IAEA-ICTP Advanced Workshop on Fusion and Plasma Physics October Introduction to Fusion Leading to ITER

Ion Heating Experiments Using Perpendicular Neutral Beam Injection in the Large Helical Device

Fluctuation Suppression during the ECH Induced Potential Formation in the Tandem Mirror GAMMA 10

Conceptual design of an energy recovering divertor

A Technology Review of Electricity Generation from Nuclear Fusion Reaction in Future

MHD instability driven by supra-thermal electrons in TJ-II stellarator

Recent Development of LHD Experiment. O.Motojima for the LHD team National Institute for Fusion Science

Relevant spatial and time scale in tokamaks. F. Bombarda ENEA-Frascati, FSN-FUSPHY-SAD

Formation of High-b ECH Plasma and Inward Particle Diffusion in RT-1

240NU211 - Fusion Technology

The Levitated Dipole Experiment: Towards Fusion Without Tritium

DIAGNOSTICS FOR ADVANCED TOKAMAK RESEARCH

Chapter 12. Magnetic Fusion Toroidal Machines: Principles, results, perspective

Simple examples of MHD equilibria

Fast ion physics in the C-2U advanced, beam-driven FRC

Observation of the H-mode and Electron ITB by Heavy lon Beam Probe on T-10 Tokamak

Introduction to Fusion Physics

Charged particle motion in external fields

Magnetically Confined Fusion: Transport in the core and in the Scrape- off Layer Bogdan Hnat

Mission Elements of the FNSP and FNSF

Polywell Fusion J A E YO UNG PA R K E NN F USION SYMPOSIUM, A P R I L

THE HENRYK NIEWODNICZAŃSKI INSTITUTE OF NUCLEAR PHYSICS POLISH ACADEMY OF SCIENCES PLASMA-FOCUS AND CONTROLLED NUCLEAR FUSION.

Innovative Concepts Workshop Austin, Texas February 13-15, 2006

Fast Ion Confinement in the MST Reversed Field Pinch

Stellar Evolution Stars spend most of their lives on the main sequence. Evidence: 90% of observable stars are main-sequence stars.

Plasma Astrophysics Chapter 1: Basic Concepts of Plasma. Yosuke Mizuno Institute of Astronomy National Tsing-Hua University

Plasma Physics and Fusion Energy Research

Characterization of the Perpendicular Rotation Velocity of the Turbulence by Reflectometry in the Stellarator TJ-II

A Faster Way to Fusion

Exploration of the Feasibility of Polar Drive on the LMJ. Lindsay M. Mitchel. Spencerport High School. Spencerport, New York

JET JET JET EFDA THE JOINT EUROPEAN TORUS A EUROPEAN SUCCESS STORY

Fusion-Enabled Pluto Orbiter and Lander

KE = 1 2 mv2 = ev. (1)

Characterization of Edge Stability and Ohmic H-mode in the PEGASUS Toroidal Experiment

Edge and Internal Transport Barrier Formations in CHS. Identification of Zonal Flows in CHS and JIPPT-IIU

Issues of Perpendicular Conductivity and Electric Fields in Fusion Devices

STELLARATOR REACTOR OPTIMIZATION AND ASSESSMENT

Small Spherical Tokamaks and their potential role in development of fusion power

PHY492: Nuclear & Particle Physics. Lecture 8 Fusion Nuclear Radiation: β decay


Laser in Fusion. Department of Electronics of TEI of Crete. Dr Petridis Kostantinos Lecturer Optoelectronics, Laser and Plasma Technologies Group

Chemical Engineering 412

Transcription:

A Passion for Plasma Physics and Nuclear Fusion Research K. A. Connor Plasma Dynamics Laboratory ECSE Department RPI 1

Topics Quick Intro to magnetic confinement fusion energy What is a plasma? Demos Diagnostic needs for fusion relevant experiments The Heavy Ion Beam Probe Doing fusion relevant research Questions 2

Quick introduction to magnetic confinement fusion energy E n = 14MeV deposited in heat exchangers containing lithium for tritium breeding Electrical repulsion Potential energy Total potential E α = 3.5 MeV deposited in plasma, provides self heating Nuclear attraction Energy Yield E F = 17.6 MeV About 10 kev of kinetic energy is required to overcome the Coulomb barrier to obtain nuclear reaction The nuclear interaction has short range whereas the Coulomb interaction is long range The fusion reaction rate of an energetic T in a D target is much less than the energy loss rate due to Coulomb scattering YOU CAN T GET NET ENERGY GAIN BY USING AN ACCELLERATOR, SHOOTING INTO A COLD TARGET 3

Plasma The 4 th State of Matter 4

5

Energy and Temperature Same Thing The energy imparted to a charged particle passing through a voltage or potential difference: 1 2 mv 2 = qv = qφ The average velocity of a thermal distribution of charges (the motion is random in all directions and most velocities are represented) can be related to the energy imparted to a charge by a voltage difference. For a one volt difference, the energy is the same as the average energy of 11,600 degrees K. General formulary reference from NRL http://wwwppd.nrl.navy.mil/nrlformulary/nrl_formulary_07.pdf 6

We can get net energy production from a thermonuclear process We heat the particles so that the average energy is ~ 10keV 100,000,000 PLASMA Then we hold the fuel particles and energy long enough for many reactions to occur Nuclear thermos bottle made of unobtainium alloy Q = P =1 break even fusion > 20 energy feasible P heating ignition P fusion = 1 n 2 4 e σv E F P loss = 3n et τ E = P heating + P α = P heating + E α P fusion E F n e = electron density τ E = energy confinement time Lawson breakeven criterion n e τ E > 10 20 m -3 s Does this expression make sense? 7

Why do the expressions on the last page involve electrons when they are not shown in the fusion process? Plasmas are fully ionized gases. Gases are charge neutral In a fully ionized gas (a plasma), all of the electrons are removed from the atoms Hydrogen has the same number of electrons and protons The number of electrons and protons in a Hydrogen plasma will be the same Assuming the protons and electrons fill the same volume, their volume density will be the same n = n = n e p i Thus, for simplicity, the expressions use only the electron density Note that all the ions and electrons in a plasma are free and, thus, plasmas can be very, very good conductors of electricity. In fact, at the temperatures necessary for fusion, the conductivity is much better than for copper, silver, gold, etc. You have all experienced plasmas as conductors. 8

Examples of Plasmas http://www.plasmas.com/ http://www.plasmas.org/ http://en.wikipedia.org/wiki/plasma_physics 9

Color from plasmas http://www.sciam.com/article.cfm?id=how-do-neon-lights-work 10

Demos Return to the fusion slides 11

We can get net energy production from a thermonuclear process We heat the particles so that the average energy is ~ 10keV 100,000,000 PLASMA Then we hold the fuel particles and energy long enough for many reactions to occur Nuclear thermos bottle made of unobtainium alloy Q = P =1 break even fusion > 20 energy feasible P heating ignition P fusion = 1 n 2 4 e σv E F P loss = 3n et τ E = P heating + P α = P heating + E α P fusion E F n e = electron density τ E = energy confinement time Lawson breakeven criterion n e τ E > 10 20 m -3 s Does this expression make sense? 12

Fusion output power Fusion power out P = 1 n 2 σv E 4 fusion e F Cross section σv Sigma is the effective size of the interaction. In unit time, the particles travel a distance v so the unit time interaction volume is given by this product. Thus, the number of fusion events per unit time in the interaction volume is given by the product of this with the density. The energy density produced in the volume is the particle density times the energy per event. 13

What can we really use for our nuclear thermos bottle? Gravitational confinement it works for the sun Inertial confinement it works for H bombs, and maybe for laser fusion We use magnetic fields + + ρ D ~ 0.3 cm } ρ e ~ 0.05 mm Example: B = 5 Tesla E = 10 kev B - - A uniform, straight magnetic field confines particles in the direction perpendicular to B, but allows free flow along the field (V D ~ 700 km/s at 10 kev) To get confinement along the field we bend the field lines into a torus 14

Motion of charges in magnetic fields Charges moving in uniform magnetic fields are forced to travel in circles. Radius = mv qb Also called the gyroradius or the Larmor Radius (check Wikipedia) Why only the perpendicular velocity? 15

Particle confinement in toroidal magnetic geometry So we add a magnetic field component winding the short way around poloidal field A simple toroidal magnetic field doesn t provide confinement B drift due to 1/R electrons, ions Vertical charge separation vertical E field E B radial expansion rapid plasma loss Magnetic field lines lie on closed, nested surfaces flux surfaces, Ψ = const. Vertical B drift averages to zero as particle follows field around poloidally 16

Early Stellarator (B-3) 17

Required poloidal magnetic field is produced either by large internal plasma current (tokamak) or external coils (stellarator) Magnetic flux surfaces, ρ = const. Tokamak, axisymmetric Compact Stellarator non-axisymmetric!! Magnetic axis separatrix Tokamaks: Axisymmetric very good plasma confinement Large internal current a problem Instability source, Inductive drive pulsed, non-inductive drive expensive Stellarators: Non-axisymmetric not so good plasma confinement Small internal current Inherently steady state, less susceptible to current driven instability 18

The next big step for the world fusion program is to explore the physics of a burning plasma ITER ITER an international effort: Japan, Europe, US, Russia, China, Korea R 0 = 6 m Fusion power ~ 400MW I plasma = 15 MA, B 0 = 5 Tesla T ~ 10 kev, τ E ~ 4 sec Large 30m tall, 20kTons 12.8 billion ($18.7 Expensive ~ $5B+ billion) total cost High level negotiations under way on site and cost-sharing First burning plasmas ~2018 Note the person! Latest news http://www.iter.org 19

Present fusion experiments are at the scientific breakeven level of performance http://www.toodlepip.com/tokamak/table-of-tokamaks.shtml 20

Fusion power plant KAC 10/23/2008 21

Other former, operating and proposed experiments TEXT (Texas) Tuman-3 (Ioffe) HSX (Wisconsin) MST (Wisconsin) 22

Other operating, former and proposed experiments LHD (NIFS) CHS (NIFS) Wendelstein 7X (Greifswald) Person 23

Stellarators and Bumpy Tori Not axisymmetric, but may have many other symmetries Because of bumpiness, there are generally small holes in confinement space The magnetic mirror is the classic case of extreme bumpiness In such a device, the electrons sample the bumpiness differently than the ions, because their Larmor radii are so different Confinement is therefore different for ions and electrons If electrons are lost more rapidly than ions, the plasma will be positively charged which results in a positive electric field that speeds up ion loss and slows down electron loss The measurement of the electric field or plasma potential is critical for understanding plasma confinement 24

The Heavy Ion Beam Probe A diagnostic for measuring the plasma potential (and other parameters) For very low temperature plasmas, the conventional method for measuring voltage is the Langmuir probe. An electrode is placed in the plasma, which produces a diode-like response. The diode characteristic is measured. From the model of the electrode-plasma interaction, the plasma potential, density, temperature, etc. can be determined. This measurement is indirect, quite perturbing when the plasma is even warm, much less hot, and active. We need an approach to determine the local voltage in the plasma which is, if possible, direct, non-perturbing and active. What do these terms mean? What approach should we take? 25

Plasma Diagnostics Ian Hutchinson s Diagnostics Book 26

Next, one of the fun stages of Physics Back of the envelope calculations Cocktail napkin physics 27

HIBP 28

HIBP 29

HIBP 30

HIBP 31

HIBP 32

HIBP 33

HIBP 34

HIBP 35

HIBP Non-perturbing Density of charges in probing beam is too small to affect the properties of the plasma Additional charge deposition also too small to change the electric field Active Requires probing beam, does not just collect particles from the plasma Direct (at least for potential) Energy difference directly gives the potential (voltage) Space and Time Resolved Secondary ions come from a small piece of the probing beam Transit time across the plasma is microseconds, so frequency response of 1MHz is possible, even in a large system Simple Physics Mostly classical mechanics, E&M Difficult Engineering Noise suppression (huge problem), power supplies, vacuum systems, amplifiers, ion sources, ion beam focusing and control, system control, data acquisition, 36

HIBP Systems 37

HIBP Systems 38

TJ-II HIBP HIBP 39

TJ-II HIBP Data Acquisition and Control System a Institute of Plasma Physics of National Scientific Centre Kharkov Institute of Physics and Technology, Kharkov, Ukraine b Centro de Inestigaciones Energeticas, Medioambientales y Tecnologias, Madrid, Spain c Institute of Nuclear Fusion of Russian Research Centre Kurchatov Institute, Moscow, Russia d Centro de Fusao Nuclear, Lisbon, Portugal L.I. Krupnik a, I.S. Bondarenko a, A.A. Chmyga a, M.B. Dreval a, S.M. Khrebtov a, A.D. Komarov a, A.S. Kozachok a, C. Hidalgo b, I. Garcia- Cortes b, L. Rodriguez-Rodrigo b, A.V. Melnikov c, P. Coelho d, M. Cunha d, B. Goncalves d, A. Malaquias d, I.S. Nedzelskiy d, C.A.F. Varandas d 40

RPI Plasma Lab 41

Trajectory Calculations Using Matlab %Charged Particle Trajectory in B Field % K. A. Connor mp=1.67e-27;e=1.6e-19; B=1;mi=100*mp; Vacc=1e5;a=1; om=e*b/mi; %Steps ts=30;st=600; % Initial Conditions vbo=sqrt(2*e*vacc/mi);vx(1)=vbo;vy(1 )=0;t(1)=0; rl=mi*vbo/(e*b);%larmor Radius; x(1)=0;y(1)=rl; tp=a/vbo;dt=tp/ts; % Step in Velocity and Position for ii=2:st; vx(ii)=vx(ii-1)+vy(ii-1)*om*dt; vy(ii)=vy(ii-1)-vx(ii-1)*om*dt; x(ii)=x(ii-1)+vx(ii)*dt; y(ii)=y(ii-1)+vy(ii)*dt; if sqrt(x(ii)^2+y(ii)^2) > a; om=0; else; om=om; end; t(ii)=t(ii-1)+dt; end; plot(x,y,'.');grid;axis equal;axis(2.*[-a a - a a]); 42

Trajectories The B field is directed out of the page. The orbit is a circle. 2 2 1.5 1.5 1 1 0.5 0.5 0 0-0.5-0.5-1 -1-1.5-1.5-2 -2-1.5-1 -0.5 0 0.5 1 1.5 2-2 -2-1.5-1 -0.5 0 0.5 1 1.5 2 %Steps ts=30;st=600; %Steps ts=500;st=2000; 43

Where Has This Work Taken Me? Where are these buildings? 44

Where Has This Work Taken Me? 45

Where Has This Work Taken Me? 46

Where Has This Work Taken Me? 47

Questions? 48