LITHIUM DIAGNOSTIC BEAM DEVELOPMENT FOR FUSION PLASMA MEASUREMENTS PhD thesis GÁBOR ANDA. Thesis Supervisor: DR. SÁNDOR ZOLETNIK MTA KFKI RMKI

Similar documents
Study of turbulence and transient events in fusion plasmas with beam emission spectroscopy. PhD thesis

New Detection System for Fast Density Measurements Using the Lithium Beam on the COMPASS Tokamak

Diagnostic Lithium Beam System for COMPASS Tokamak

INVESTIGATING THE INTERACION OF SOLID DEUTERIUM PELLETS WITH HOT PLASMAS PhD thesis

Introduction to Fusion Physics

On the physics of shear flows in 3D geometry

DIAGNOSTICS FOR ADVANCED TOKAMAK RESEARCH

Thesis for the degree of Doctor of Philosophy. Turbulent and neoclassical transport in tokamak plasmas. István Pusztai

Contents. Experimental investigation of pellet-plasma interaction at the ASDEX Upgrade tokamak 7

Partially Coherent Fluctuations in Novel High Confinement Regimes of a Tokamak

Study of B +1, B +4 and B +5 impurity poloidal rotation in Alcator C-Mod plasmas for 0.75 ρ 1.0.

Relating the L-H Power Threshold Scaling to Edge Turbulence Dynamics

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

Triggering Mechanisms for Transport Barriers

SUMMARY OF EXPERIMENTAL CORE TURBULENCE CHARACTERISTICS IN OH AND ECRH T-10 TOKAMAK PLASMAS

The role of stochastization in fast MHD phenomena on ASDEX Upgrade

Turbulence and Transport The Secrets of Magnetic Confinement

TURBULENT TRANSPORT THEORY

The Study of Correlation Properties of Geodesic Acoustic Modes in the T-10 Tokamak

Jacob s Ladder Controlling Lightning

Progress of Confinement Physics Study in Compact Helical System

Formation and Long Term Evolution of an Externally Driven Magnetic Island in Rotating Plasmas )

Upper Hybrid Resonance Backscattering Enhanced Doppler Effect and Plasma Rotation Diagnostics at FT-2 Tokamak

Chapter IX: Nuclear fusion

Finnish-Russian Collaboration: Reflectometry Turbulence Measurements & ELMFIRE Validation on FT-2 Tokamak in St.Petersburg.

Electrode and Limiter Biasing Experiments on the Tokamak ISTTOK

Long-Range Correlations and Edge Transport Bifurcation in Fusion Plasmas

Experimental Achievements on Plasma Confinement and Turbulence

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

arxiv: v1 [physics.plasm-ph] 13 Jan 2019

Observation of Neo-Classical Ion Pinch in the Electric Tokamak*

Measurements of rotational transform due to noninductive toroidal current using motional Stark effect spectroscopy in the Large Helical Device

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

Plasma Heating by an Electron Beam in Corrugated Magnetic Field

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

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

Transport Improvement Near Low Order Rational q Surfaces in DIII D

1 EX/P6-5 Analysis of Pedestal Characteristics in JT-60U H-mode Plasmas Based on Monte-Carlo Neutral Transport Simulation

Electron temperature barriers in the RFX-mod experiment

Bifurcation-Like Behavior of Electrostatic Potential in LHD )

Fast Particle Instabilities in MAST

Issues of Perpendicular Conductivity and Electric Fields in Fusion Devices

Development of a High-Speed VUV Camera System for 2-Dimensional Imaging of Edge Turbulent Structure in the LHD

A sodium (Na) beam edge diagnostic

Shear Flow Generation in Stellarators - Configurational Variations

H-mode in Helical Devices

Spatial, temporal and spectral structure of the turbulence-flow interaction at the L-H transition

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

Direct drive by cyclotron heating can explain spontaneous rotation in tokamaks

MHD. Jeff Freidberg MIT

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

Der Stellarator Ein alternatives Einschlusskonzept für ein Fusionskraftwerk

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

Ion beam analysis methods in the studies of plasma facing materials in controlled fusion devices

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

Bounce-averaged gyrokinetic simulations of trapped electron turbulence in elongated tokamak plasmas

INTRODUCTION TO MAGNETIC NUCLEAR FUSION

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

Minimal Model Study for ELM Control by Supersonic Molecular Beam Injection and Pellet Injection

Plasma Fusion Center Massachusetts Institute of Technology Cambridge, MA Burrell, K.H. General Atomics PO Box San Diego, CA

NIMROD FROM THE CUSTOMER S PERSPECTIVE MING CHU. General Atomics. Nimrod Project Review Meeting July 21 22, 1997

High-m Multiple Tearing Modes in Tokamaks: MHD Turbulence Generation, Interaction with the Internal Kink and Sheared Flows

Toward the Realization of Fusion Energy

Spatio-temporal investigations on the triggering of pellet induced ELMs

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

GA A25853 FAST ION REDISTRIBUTION AND IMPLICATIONS FOR THE HYBRID REGIME

Bolometry. H. Kroegler Assciazione Euratom-ENEA sulla Fusione, Frascati (Italy)

Excitation of Alfvén eigenmodes with sub-alfvénic neutral beam ions in JET and DIII-D plasmas

Current Drive Experiments in the HIT-II Spherical Tokamak

Heating and Confinement Study of Globus-M Low Aspect Ratio Plasma

Beam Driven Alfvén Eigenmodes and Fast Ion Transport in the DIII-D and ASDEX Upgrade (AUG) Tokamaks

LCDC IN TOKAMAKS. THE LOCAL COLD AND DENSE COMPRESS What to Measure and How to Measure. Waseda University 2

Correlation reflectometry in fusion plasmas an application at TEXTOR

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

Studies of H Mode Plasmas Produced Directly by Pellet Injection in DIII D

GA A26741 SCINTILLATOR-BASED DIAGNOSTIC FOR FAST ION LOSS MEASUREMENTS ON DIII-D

Improved Plasma Confinement by Ion Bernstein Waves (IBWs) Interacting with Ions in JET (Joint European Torus)

Effect of Biasing on Electron Temperature in IR-T1 Tokamak

Observation of geodesic acoustic modes (GAMs) and their radial propagation at the edge of TEXTOR tokamak

Progress in characterization of the H-mode pedestal

Observation of Reduced Core Electron Temperature Fluctuations and Intermediate Wavenumber Density Fluctuations in H- and QH-mode Plasmas

Size Scaling and Nondiffusive Features of Electron Heat Transport in Multi-Scale Turbulence

Runaway electron losses enhanced by resonant magnetic perturbations

Nonlinear Gyrokinetic Simulations of Ion Turbulence in Impurity Seeded and High Density Toroidal Plasmas

Non-inductive plasma startup and current profile modification in Pegasus spherical torus discharges

Denis Bytschkow. Investigation of MHD mode rotation in the tokamak ASDEX Upgrade

Impact of Toroidal Flow on ITB H-Mode Plasma Performance in Fusion Tokamak

Confinement of toroidal non-neutral plasma in Proto-RT

Princeton Plasma Physics Laboratory, Princeton University, Princeton, New Jersey, U.S.A

Confinement of toroidal non-neutral plasma in Proto-RT

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

Effect of the Radial Electric Field on Lower Hybrid Plasma Heating in the FT-2 Tokamak

Influence of the Dynamic Ergodic Divertor on TEXTOR Discharges

Beams and magnetized plasmas

Short Wavelength Density and Low Frequency MHD Fluctuation Measurements in the STOR-M Tokamak

Overview of results from MAST Presented by: Glenn Counsell, for the MAST team

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

Effects of Noise in Time Dependent RWM Feedback Simulations

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

Development of a New Gas Puff Imaging Diagnostic on the HL-2A Tokamak

Transcription:

LITHIUM DIAGNOSTIC BEAM DEVELOPMENT FOR FUSION PLASMA MEASUREMENTS PhD thesis GÁBOR ANDA Thesis Supervisor: DR. SÁNDOR ZOLETNIK MTA KFKI RMKI Departmental supervisor: DR. GÁBOR PÓR BME NTI BUDAPEST UNIVERSITY OF TECHNOLOGY AND ECONOMICS INSTITUTE OF NUCLEAR TECHNIQUES MTA KFKI RESEARCH INSTITUTE FOR PARTICLE AND NUCLEAR PHYSICS 2009

Background of the research Nucelar fusion as clean (free from long half-life radioactive waste) and inexhaustible energy source is an intensively studied research field from the 1950 s. The most promising fusion process is the Deuterium-Tritium reaction, which can be used for practical energy generation if the thermal energy of the particles is in the 10-15 kev range, meaning very high, about 100 million K temperature. At this temperature materials are ineviatbly in the plasma state. Among fusion devices the most promising one is the tokamak, which confines a torus shaped plasma in a helically twisted toroidal magnetic field. In contrast to the theoretical calculations experiments showed that the particle and heat transport through the magnetic confining magnetic field is well above the so-called neoclassical particle and heat transport, calculated from the Coulomb collisions of plasma particles in toroidal geometry. This process is called anomalous transport which is, according to the mostly accepted theories, driven by plasma microturbulence arising from mm and smaller scale instabilities. The past decade a wealth of experimental evidence has been collected on plasma turbulence mostly through the measurable density, temperature and potential fluctuations caused by it. Turbulence arises from instabilities driven by inhomogeneities in plasma parameters. So-called drift waves are considered to be the most ubiquitous instabilities in the core plasma, while other processes are responsible for turbulence at the plasma edge. These primary unstable waves can induce different mesoscopic (i.e. between the microturbulence and the device scale) flow structures: poloidal zonal flows and radial streamers. The sheared flow stuctures act on the drift waves as they tear eddies apart built by the drift waves. The unstable drift waves and flow structures establish a self regulating system which is responsible for the control of the above mentioned anomalous heat and particle transport. In special cases the flows in the boundary layer can amplify and stabilise to the extent to suppress the turbulence in a macroscopic layer, i.e. a transpoert barrier develops at the plasma edge and the plasme global confinement inproves. This is called High Confinement Mode (H-mode). At present, besides the qualitative understanding of turbulence and H-mode, there is no theory capable of reliably and quantitatively predicting anomalous heat and particle transport.. The most critical problem is that the H-mode and the parameters of the related transport barrier (width, temperature maximum at the top of the pedestal) are not given by any model. Because of this the experimental study of the turbulence and flows is of special importance from the aspect of the progress of fusion research. The plasma diagnostic methods developed in the past decades can measure most of the plasma parameters (temperature, density, potential, current distribution, flow velocity, etc.) but most of these diagnostics are not able to measure with such a high spatial and/or temporal resolution which is necessary for the study of turbulence. The difficulty is that the correlation length of the turbulence is about mm-cm, the relative fluctuation amplitude is 0.1-10% and the frequency is about 10-100 khz. Moreover the statistical character of the turbulence makes it necessary to study long time series. There are only a limited number of such special plasma turbulence diagnostics.

Objectives The self regulating system of drift waves and mesoscopic flows can be well studied by the different types of beam emission spectroscopy (BES) diagnostic. The basis of this method is that some kind of atomic beam is injected into the plasma and the atoms excited by the plasma emit characteristic photons in the visible electromagnetic range. The intensity of this photon flux is measured. Earlier measurements made by accelerated Lithium BES diagnostics showed that the appropriate spatial and temporal resolution needed for turbulence and flow velocity measurement can be achieved, but the statistical error of the diagnostics makes the measurement possible only in the outer regime of the plasma, where the relative amplitude of the turbulence is high. The measurement is limited by the low photon flux, which is determined by (additionally to the parameters of the detection system) the typically 2 ma beam current. The measurement accuracy could be increased, the range could be extended and even new measurement possibilites would open up if a stronger beam and better detectors were available. The objectives of this thesis is the detailed experimental characterisaction and numerical simulation of the recently used accelerated Lithium beam diagnostic in order to determine the limiting phenomena of the beam current and diameter. After this study proposals for upgrading the diagnostics can be elaborated. New types of ion sources and ion accelerating systems can designed, which provide higher beam current and possibly smaller beam diameter. This knowledge was used at the optimization, upgrade and construction of the JET, TEXTOR and COMPASS tokamak Lithium beam diagnostics. Methods Study of the accelerated Lithium beams were done in the laboratory of the KFKI Research Institute for Particle and Nuclear Physics, in the Li-beam laboratory of the Institut für Plasmaphysik, Garching and at Forschungszentrum Jülich. I developed a novel method to measure the beam diameter and current distribution. Intersecting the beam path with a metal plate, the beam ions get neutralized on the surface and some of them become excited to the 2p state. Measurement of the distribution of this light emission reveals information on the beam current distribution. The proportionality between the beam current and the total detected light was poven by experiments. The ion and atom beam current distribution was investigated in detail by this method in the whole operational parameter range of the Li-beam. I studied the beam formation and the process of acceleration by two different numerical simulations. These are the CPO and the AXCEL numerical codes. The numerical results were systematically compared to the results of the laboratory experiments. The validated numerical techniques were used to investigate the beam current and diameter for different accelerating systems. Proposals were made for the modification of the ion optic and for the direction of ion source development. I participated in the modification and reinstallation of the TEXTOR Lithium beam diagnostic, in the development of the new beam control and observation system. Using this diagnostic I measured the plasma electron density distribution at the edge plasma edge at the H-mode transition. Based on the results of the laboratory experiments, the numerical simulations and the measurements at TEXTOR I designed and built up the COMPASS Lithium beam diagnostic.

New scientific results (thesis) The new scientific results achieved during my PhD work are summarised in the following theses: 1. I developed a novel method to measure the ion and atom beam current distribution. The accelerated Lithium beam diagnostics of the JET and TEXTOR tokamaks were investigated in detail in the full operational parameter range of the the ion source and accelaration system using this method. [1] 2. I pointed out that the effect of the space charge will act on the beam current distribution above 1 ma beam current. This effect appears only inside the ion optic, because outside that secondary electrons originating from the vessel wall neutralize the space charge. Measurements showed that in the case of both diagnostic beams current is limited by the ion source [1, 2] 3. I designed and built up a special ion optic where, without beam forming, the beam current and the temperature of the emission surface can be measured at the same time [1]. 4. To interpret the results of the experiments I used two different simulation codes. I got good correspondence between the codes and the experiment if I took into account the space charge effect inside the ion optic. Using the validated methods I gave proposals for the modification of the ion optic and the ion source which can enhance the current of the diagnostic beams and can decrease the divergence of them [3]. 5. By the help of Lithium beam diagnostic I measured the electron density distribution in the edge plasma of the TEXTOR tokamak [5, 6, 7, 8, 9, 10]. 6. I designed and built up the accelerated alkali beam diagnostics of the COMPASS tokamak [10]. 7. I designed and built up a novel neutralizator for alkali atom beam diagnostics. Related publications [1] G. Anda, S. Bató, G. Petravich, S. Zoletnik, Li-beam developments for highenergy plasma diagnostics, Fusion Engineering and Design, Volume 74, Issues 1-4, November 2005, Pages 715-719 [2] G. Anda, S. Bató, G. Petravich, S. Zoletnik, R. Uhlemann, Li-beam developments, 32nd EPS Conference on Plasma Phys. Tarragona, 27 June - 1 July 2005 ECA Vol.29C, P-2.077 (2005) [3] M. Berta, A. Bencze, G. Anda, M. Aradi, D. Dunai, G. Veres, S. Zoletnik, Concept of an Atomic Beam Probe diagnostic on COMPASS tokamak, 36th EPS Conference on Plasma Phys. Sofia, June 29 - July 3, 2009 ECA Vol.33E, P-5.139 (2009) [4] G. Anda, D. Dunai, G. Petravich, J. Sárközi, S. Zoletnik, B. Schweer, First Measurements with the re-installed accelerated Lithium beam diagnostics on TEXTOR, 35th EPS Conference on Plasma Phys. Hersonissos, 9 13 June 2008 ECA Vol.32D, P-5.076 (2008) [5] D. Dunai, S. Zoletnik, G. Anda, G. Petravich, S. Kálvin, J. Sárközi,A. Krämer- Flecken, B. Schweer, S. Soldatov, Turbulence properties of the edge plasma at

TEXTOR measured by Beam Emission Spectroscopy, 36th EPS Conference on Plasma Phys. Sofia, 29 June - 3 July [6] S. Zoletnik, L. Bardoczi, G. Anda, D. Dunai, G. Petravich, A. Krämer-Flecken, S. Soldatov, Poloidal flow velocity measurement at the edge of the TEXTOR tokamak using quasi twodimensonal Lithium Beam Emission Spectroscopy, 36th EPS Conference on Plasma Phys. Sofia, 29 June - 3 July [7] G. Petravich, G. Anda, D. Dunai, S. Kálvin, S. Zoletnik, Light profile measurement on the 35keV Lithium beam on TEXTOR, 36th EPS Conference on Plasma Phys. Sofia, 29 June - 3 July [8] S. Kálvin, G. Anda, D. Dunai, G. Petravich, S. Zoletnik, G. Pokol, B. Játékos, I. Pusztai3, D. Réfi, 36th EPS Conference on Plasma Phys. ECA Vol.33E, P-5.211 (2009) [9] I. Pusztai, G. Pokol, D. Dunai, D. Réfy, G. Pór, G. Anda, S. Zoletnik, and J. Schweinzer Deconvolution-based correction of alkali beam emission spectroscopy density profile measurements, Rev. Sci. Instrum. 80 083502 (2009) [10] D. Guszejnov, Pokol Gergő, Réfy Dániel, Anda Gábor, Petravich Gábor, Dunai Dániel, Pusztai István, A COMPASS tokamakra építendő atomnyaláb diagnosztika tervezésének támogatása szimulációk segítségével, Nukleon, május (2010)