Prospects of Nuclear Fusion Energy Research in Lebanon and the Middle-East

Similar documents
Nuclear Fusion Energy Research at AUB Ghassan Antar. Physics Department American University of Beirut

INTRODUCTION TO MAGNETIC NUCLEAR FUSION

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

A Faster Way to Fusion

240NU211 - Fusion Technology

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

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

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

for the French fusion programme

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

Issues for Neutron Calculations for ITER Fusion Reactor

ArbiTER studies of filamentary structures in the SOL of spherical tokamaks

Plasma Wall Interactions in Tokamak

TWO FUSION TYPES NEUTRONIC ANEUTRONIC

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

Nuclear Energy in the Future. The ITER Project. Brad Nelson. Chief Engineer, US ITER. Presentation for NE-50 Symposium on the Future of Nuclear Energy

Alcator C-Mod. Particle Transport in the Alcator C-Mod Scrape-off Layer

ITER operation. Ben Dudson. 14 th March Department of Physics, University of York, Heslington, York YO10 5DD, UK

JET and Fusion Energy for the Next Millennia

Disruption mitigation in ITER

Implementation of a long leg X-point target divertor in the ARC fusion pilot plant

Tokamak Divertor System Concept and the Design for ITER. Chris Stoafer April 14, 2011

Materials for Future Fusion Reactors under Severe Stationary and Transient Thermal Loads

ITER A/M/PMI Data Requirements and Management Strategy

240 ETSEIB Escola Tècnica Superior d Enginyeria Industrial de. European Master in Innovation in Nuclear Energy (EMINE)

Disruption Mitigation on Tore Supra

purposes is highly encouraged.

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

Chapter IX: Nuclear fusion

Comparison of tungsten fuzz growth in Alcator C-Mod and linear plasma devices!

Macroscopic Stability

Neutronic Activation Analysis for ITER Fusion Reactor

The Spherical Tokamak as a Compact Fusion Reactor Concept

Toward the Realization of Fusion Energy

Possibilities for Long Pulse Ignited Tokamak Experiments Using Resistive Magnets

Magnetic Confinement Fusion-Status and Challenges

The Dynomak Reactor System

Tokamak Fusion Basics and the MHD Equations

Analyses of Visible Images of the Plasma Periphery Observed with Tangentially Viewing CCD Cameras in the Large Helical Device

Mission Elements of the FNSP and FNSF

Blob motion and control. simple magnetized plasmas

Drift-Driven and Transport-Driven Plasma Flow Components in the Alcator C-Mod Boundary Layer

Thomas Schwarz-Selinger. Max-Planck-Institut for Plasmaphysics, Garching Material Science Division Reactive Plasma Processes

0 Magnetically Confined Plasma

Overview the CASTOR Fast Particles experiments

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

Flow measurements in the Scrape-Off Layer of Alcator C-Mod using Impurity Plumes

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

Preliminary experiment of plasma current startup by ECR wave on SUNIST spherical tokamak

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

Nuclear Fusion and ITER

Nuclear Fusion 1 of 24 Boardworks Ltd 2011

Modelling of plasma edge turbulence with neutrals

C-Mod Core Transport Program. Presented by Martin Greenwald C-Mod PAC Feb. 6-8, 2008 MIT Plasma Science & Fusion Center

Highlights from (3D) Modeling of Tokamak Disruptions

Partially Coherent Fluctuations in Novel High Confinement Regimes of a Tokamak

Electrode and Limiter Biasing Experiments on the Tokamak ISTTOK

GA A23168 TOKAMAK REACTOR DESIGNS AS A FUNCTION OF ASPECT RATIO

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

Controlled Thermonuclear Fusion

Role and Challenges of Fusion Nuclear Science and Technology (FNST) toward DEMO

The Power of the Universe on Earth: Plasma Physics and Fusion Energy

Reduction of Turbulence and Transport in the Alcator C-Mod Tokamak by Dilution of Deuterium Ions with Nitrogen and Neon Injection

Self-consistent modeling of ITER with BALDUR integrated predictive modeling code

and expectations for the future

Generating of fusion plasma neutron source with AFSI for Serpent MC neutronics computing Serpent UGM 2015 Knoxville, TN,

The measurement of plasma equilibrium and fluctuations near the plasma edge using a Rogowski probe in the TST-2 spherical tokamak

Diagnostics for Burning Plasma Physics Studies: A Status Report.

MHD Stabilization Analysis in Tokamak with Helical Field

FAST 1 : a Physics and Technology Experiment on the Fusion Road Map

Recent Experiments on the STOR-M Tokamak

Spherical Torus Fusion Contributions and Game-Changing Issues

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

EXD/P3-13. Dependences of the divertor and midplane heat flux widths in NSTX

Comparison of tungsten fuzz growth in Alcator C-Mod and linear plasma devices

Dust Studies in Fusion Devices

S1/2 EX/S, EX/D, EX/W

Noninductive Formation of Spherical Tokamak at 7 Times the Plasma Cutoff Density by Electron Bernstein Wave Heating and Current Drive on LATE

On tokamak plasma rotation without the neutral beam torque

Plasma-neutrals transport modeling of the ORNL plasma-materials test stand target cell

FAR SCRAPE-OFF LAYER AND NEAR WALL PLASMA STUDIES IN DIII D

Effect of ideal kink instabilities on particle redistribution

Direct drive by cyclotron heating can explain spontaneous rotation in tokamaks

Steady State, Transient and Off-Normal Heat Loads in ARIES Power Plants

The extrapolation of the experimentally measured energy confinement time in existing tokamaks towards ITER is considered to be robust because the

Conceptual design of an energy recovering divertor

Plasma Science and Fusion Center

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

Initial Investigations of H-mode Edge Dynamics in the PEGASUS Toroidal Experiment

Jacob s Ladder Controlling Lightning

Current Drive Experiments in the HIT-II Spherical Tokamak

Atomic physics in fusion development

Plasma Spectroscopy in ISTTOK

Perspective on Fusion Energy

Additional Heating Experiments of FRC Plasma

OVERVIEW OF THE ALCATOR C-MOD PROGRAM. IAEA-FEC November, 2004 Alcator Team Presented by Martin Greenwald MIT Plasma Science & Fusion Center

Turbulence and flow in the Large Plasma Device

II: The role of hydrogen chemistry in present experiments and in ITER edge plasmas. D. Reiter

Overview Impact of 3D fields (RMP) on edge turbulence and turbulent transport

Axial symmetric open magnetic traps with depressed transversal losses of plasmas

Transcription:

Prospects of Nuclear Fusion Energy Research in Lebanon and the Middle-East Ghassan Antar Physics Department American University of Beirut http://www.aub.edu.lb/physics/lpfd

Outline 1. Introduction and Motivation to Magnetic Fusion Research 2. Challenge I: Experimental Research on Turbulence 3. Challenge II: Theoretical Research on Turbulence 4. Challenge III: Research on Disruption mitigation 5. Challenge IV: Research on Plasma Facing Components 6. Conclusion G. Antar 2

Fusion Occurs when Two Nuclei Unite to Form One The Energy Results from the Difference in Mass between the Initial and the Final Nuclei Abundant Energy from Sea Water, few numbers to keep in mind! G. Antar 3

Advantages of Fusion on other ways to Produce Energy Abundant Fuel Supply on Earth and Beyond No Risk of a Nuclear Accident No Air Pollution No High-level Nuclear Waste No Generation of Weapons Material G. Antar 4

The Strategic Importance of Fusion: The ITER Project Countries in ITER: Cost of ITER > 5 billion dollars Site of ITER: Cadarache (France) Human scale G. Antar 5

Magnetic Fusion: Particle are Confined Inside a Tokamak so as to increase the Probability of Nuclear Reaction The JET (Joint European Torus) tokamak from Inside without plasma and with plasma Movie from the MAST tokamak G. Antar 6

Challenge I: Develop Local Experimental Tools to Study Turbulent transport Turbulence decreases the confinement time of magnetic confinement devices Confined zone Unconfined zone G. Antar 7

Challenge I: Build the Lebanese Linear Plasma Device [LLPD) We are in the process of building a plasma simulator at AUB. It consists of: vacuum chamber RF power source (2 kw) axial magnetic field about 1000 G. Diagnostics G. Antar 8

Challenge I: Maintain a high-level of International Collaboration with France, Germany, UK and the USA Tore Supra tokamak Alcator C-MOD tokamak MAST Spherical tokamak PISCES a = 76 cm, R = 2.32 m B T = 3.5 T, Ip =1 MA limiter machine a = 21 cm, R = 70 cm B T = 5.3 T I p ~ 0.8 MA divertor machine a = 52 cm, R = 73 cm B T = 0.6 T, I p =700 ka First wall far from the LCFS n e ~ 10 17 m -3, T e ~ 10 ev, B = 0.12-0.24 T Plasma radius = 2.5 cm Vessel radius = 10 cm G. Antar 9

Research done on linear devices is relevant to toroidal fusion tokamak physics Similarity of the PDF of I sat fluctuations Gaussian for negative fluctuations Strongly Skewed for positive fluctuations Similarity of the power spectra of I sat One scaling region approximately the same scaling exponent -1.6 G. Antar 10

Challenge I: Developing table-top experiments to Investigate Quasi-2D turbulence This setup uses a solution of KOH Liquid gallium Electrodes Magnetic coils G. Antar 11

Challenge II: Develop Activity to Complement the Experiment based on Numerical Simulation of Turbulence The goal is to develop knowledge and expertise in simulating plasma turbulence. Our starting point is to use simple models (e.g. Hasegawa-Mima and Hasegawa-Wakatani) for turbulence and then gradually increase the complexity of the problem. Apply the newest numerical schemes that do not generate artificial vorticity and energy as they both have to be conserved. Develop strong collaborations with the fluid community taking advantage of their expertise. G. Antar 12

Challenge III: Simulating disruption mitigation in tokamaks using experiment and simulation It is proposed to mitigate disruptions by using a massive gas jet which as it penetrates the plasma, density is increased by ionization which also leads to the decrease of temperature. The questions we want to answer by numerical simulations: How deep will the jet penetrates How fast will the jet penetrates The type of gas to use The design of the setup will it help? G. Antar 13

Challenge IV: Plasma Facing Components for Fusion Application Surface properties as a function of the Laser Energy 250 mj 320 mj 420 mj 512 mj 612 mj Fusion first wall is a major issue as it not only determines its life-time but also dictates the quality of the plasma by the type and the amount of impurities that it releases back into the plasma. Our goal is to understand and quantify the growth of tungsten films on graphite using, and for the first time, the pulsed laser deposition (PLD) technique and the surface diagnostics at AUB. G. Antar 14

Conclusion Various experimental and theoretical research projects on nuclear fusion are being developed at AUB with the goal to have a Program in this field. These projects are in parallel to continuous collaborations with international institutions world-wide. The main application is to study fundamental issues encountered in magnetic fusion plasmas. What we need is: Education, education and education in science and engineering to build up our own expertise in this strategic field. Further funding and hiring in this field are also of prime importance to build the necessary equipments and to have at least a critical mass to start competing with other institutions. G. Antar 15

Simulating disruption mitigation in tokamaks I Disruptions are an abrupt and violent halt of the plasma. Most of the plasma energy is dumped on the walls Most of the magnetic energy is also dumped into the vessel structure It is one the main parameters limiting the life-time of tokamaks and causing a high risk of a large damage G. Antar 16

Three Ways to Achieve Fusion This presentation SOHO G. Antar 17