Effect of Biasing on Electron Temperature in IR-T1 Tokamak

Similar documents
Direct measurements of the plasma potential in ELMy H mode. plasma with ball pen probes on ASDEX Upgrade tokamak

Electrode and Limiter Biasing Experiments on the Tokamak ISTTOK

Overview the CASTOR Fast Particles experiments

Particle Transport Measurements in the LHD Stochastic Magnetic Boundary Plasma using Mach Probes and Ion Sensitive Probe

High Beta Discharges with Hydrogen Storage Electrode Biasing in the Tohoku University Heliac

Current Drive Experiments in the HIT-II Spherical Tokamak

The Q Machine. 60 cm 198 cm Oven. Plasma. 6 cm 30 cm. 50 cm. Axial. Probe. PUMP End Plate Magnet Coil. Filament Cathode. Radial. Hot Plate.

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

Dynamics of Drift and Flute Modes in Linear Cylindrical ECR Plasma

Experimental Study of Hall Effect on a Formation Process of an FRC by Counter-Helicity Spheromak Merging in TS-4 )

EXD/P3-23. Fluctuations, ELM Filaments and Turbulent Transport in the SOL at the Outer Midplane of ASDEX Upgrade

Study of DC Cylindrical Magnetron by Langmuir Probe

On the physics of shear flows in 3D geometry

Plasma Confinement Using Biased Electrode in the TCABR Tokamak

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

Density Collapse in Improved Confinement Mode on Tohoku University Heliac

A Kinetic Theory of Planar Plasma Sheaths Surrounding Electron Emitting Surfaces

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

Contents: 1) IEC and Helicon 2) What is HIIPER? 3) Analysis of Helicon 4) Coupling of the Helicon and the IEC 5) Conclusions 6) Acknowledgments

Studies of Charge Separation Characteristics for Higher Density Plasma. in a Direct Energy Converter Using Slanted Cusp Magnetic Field

Joint Experiments on Small Tokamaks

SPECTRAL INVESTIGATION OF A COMPLEX SPACE CHARGE STRUCTURE IN PLASMA

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

Capability Assessment of the Equilibrium Field System in KTX

Electrode Biasing Experiment in the Large Helical Device

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

( ) U-probe for the COMPASS Tokamak. Introduction

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

Role of the Electron Temperature in the Current Decay during Disruption in JT-60U )

Plasma Spectroscopy in ISTTOK

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

E. Ortiz, M. Mauel, D. Garnier, A. Hansen - Columbia University - O. Grulke, J. Kesner - MIT PSFC -

Long-Range Correlations and Edge Transport Bifurcation in Fusion Plasmas

Design and construction of a very small repetitive plasma focus device

Capacitive Probe for Plasma Potential Measurements in a Vacuum diode and Polywell Device

Local organizer. National Centralized Tokamak

Triggering Mechanisms for Transport Barriers

Suppression of nonlinear frequency-sweeping of resonant interchange modes in a magnetic dipole with applied radio frequency fields a

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

Electron energy distribution function in the divertor region of the COMPASS tokamak during neutral beam injection heating

A DC probe diagnostics for fast electron temperature measurements in tokamak edge plasmas *)

Langmuir Probes as a Diagnostic to Study Plasma Parameter Dependancies, and Ion Acoustic Wave Propogation

1 EX/P7-35. Spectroscopic Studies on GLAST-III Varying the Inductance and Charging Voltage of Vertical Field Coils

Texas Helimak. Fusion Research Center, University of Texas at Austin, Texas, USA

Intermittent Behavior of Local Electron Temperature in a Linear ECR Plasma )

Confinement of toroidal non-neutral plasma in Proto-RT

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

Confinement of toroidal non-neutral plasma in Proto-RT

Study of Current drive efficiency and its correlation with photon temperature in the HT-7 tokomak

1 IC/P4-5. Spheromak Formation by Steady Inductive Helicity Injection

Bifurcation-Like Behavior of Electrostatic Potential in LHD )

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

Production of Over-dense Plasmas by Launching. 2.45GHz Electron Cyclotron Waves in a Helical Device

0 Magnetically Confined Plasma

Configuration Optimization of a Planar-Axis Stellarator with a Reduced Shafranov Shift )

Driving Mechanism of SOL Plasma Flow and Effects on the Divertor Performance in JT-60U

DIAGNOSTICS FOR ADVANCED TOKAMAK RESEARCH

Tailoring the charged particle fluxes across the target surface of Magnum-PSI

Non-Solenoidal Plasma Startup in

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

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

Diagnostic Lithium Beam System for COMPASS Tokamak

Magnetic Field Configuration Dependence of Plasma Production and Parallel Transport in a Linear Plasma Device NUMBER )

Measurement of EEDF and Distribution of Primary Electron in a Bucket Ion Source

A THEORETICAL AND EXPERIMENTAL INVESTIGATION INTO ENERGY TRANSPORT IN HIGH TEMPERATURE TOKAMAK PLASMAS

Progress of experimental study on negative ion production and extraction

Lower Hybrid Current Drive Experiments on Alcator C-Mod: Comparison with Theory and Simulation

The FTU facilities. Regarding the the control and data acquisition system, last year we carried out the following activities:

TSC modelling of major disruption and VDE events in NSTX and ASDEX- Upgrade and predictions for ITER

Double Null Merging Start-up Experiments in the University of Tokyo Spherical Tokamak

Recombination and Decay of Plasma Produced by Washer Stacked Plasma Gun inside a Curved Vacuum Chamber

GA A22571 REDUCTION OF TOROIDAL ROTATION BY FAST WAVE POWER IN DIII D

Effect of parallel velocity shear on the excitation of electrostatic ion cyclotron waves

1) Jozef Stefan Institute, Jamova 39, 1000 Ljubljana, Slovenia

Experimental Investigations of Magnetic Reconnection. J Egedal. MIT, PSFC, Cambridge, MA

Expanding Non-Solenoidal Startup with Local Helicity Injection

Derivation of dynamo current drive in a closed current volume and stable current sustainment in the HIT SI experiment

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

The Effects of Noise and Time Delay on RWM Feedback System Performance

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

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

Effect ofe B driven transport on the deposition of carbon in the outer divertor of ASDEX Upgrade

Electron cyclotron resonance plasma enhanced direct current sputtering discharge with magnetic-mirror plasma confinement

GA A26101 HIGH HEAT FLUX LANGMUIR PROBE ARRAY FOR THE DIII-D DIVERTOR PLATES

Plasma Flow in MST: Effects of Edge Biasing and Momentum Transport from Nonlinear Magnetic Torques

11. Discharges in Magnetic Fields

Confinement Studies during LHCD and LHW Ion Heating on HL-1M

Dynamics of ion internal transport barrier in LHD heliotron and JT-60U tokamak plasmas

Physics of Intense Electron Current Sources for Helicity Injection

Behavior of Compact Toroid Injected into the External Magnetic Field

Potential structures and Flow Measurements with Separatrix Biasing in the CASTOR Tokamak

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

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

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

Abstract. The Pegasus Toroidal Experiment is an ultra-low aspect ratio (A < 1.2) spherical tokamak (ST) capable of operating in the high I N

Effect of Spiral Microwave Antenna Configuration on the Production of Nano-crystalline Film by Chemical Sputtering in ECR Plasma

Internal Magnetic Field Measurements and Langmuir Probe Results for the HIT-SI Experiment

An Experimental Study to Show the Effects of Secondary Electron Emission on Plasma Properties in Hall Thrusters

TARGET PLATE CONDITIONS DURING STOCHASTIC BOUNDARY OPERATION ON DIII D

PLASMA CONFINEMENT IN THE GAMMA 10 TANDEM MIRROR

Transcription:

Effect of Biasing on Electron Temperature in IR-T1 Tokamak Sakineh Meshkani 1, Mahmood Ghoranneviss 1 and Mansoureh Lafouti 2 1 Plasma Physics Research Center, Science and Research Branch, Islamic Azad University, Tehran, Iran 2 Damavand Branch, Islamic Azad University, Damavand, Iran Abstract In this paper, the effect of limiter biasing on the plasma parameters as floating potential, ion and electron saturation currents, plasma potential and electron temperature has been investigated. The measurements have been done by the Langmuir-ball pen probe in IR-T1 plasma edge. For this purpose, this probe has been constructed and installed on IR-T1. In this work, the biased limiter voltages are V=+200V, V=0 and V=-200V. The results show that ion and electron saturation currents have decreased when the collector retracts inside the tube. The negative biased voltage has reduced the ion and electron saturation currents while the positive voltage has increased them. The ratio R I is very close to one at a certain collector position. The results show that this position changes with the applying limiter biasing. The results show that the ratio R is very close to one at h=-1.1mm, h=-0.7mm and h=-0.6mm for V biasing =+200V, V biasing =0 and V biasing =-200V, respectively. In this collector position, the plasma potential that is close to floating potential is about 54V, 45V and 39V for V biasing =+200V, V biasing =0 and V biasing =- 200V respectively, in plasma edge. The biased limiter with V biasing =+200V causes to the increase of plasma potential (>20%) and electron temperature (>30%) in plasma edge. But the plasma potential and electron temperature decrease (<15%) and (>40%) due to applying the negative biased voltage (V biasing =- 200V). Keywords Tokamak, Langmuir-Ball Pen Probe, Limiter Biasing, Electron Temperature I 1. Introduction The relation between the floating potential V fl of a Langmuir probe and the plasma potential V p in the case of a conventional Maxwellian plasma is well known from simple probe theory: [1-5] 1 The quantities k B, e and T e represent the Boltzmann constant, the elementary charge and electron temperature, respectively. The quantity R expresses the ratio of electron and ion saturation current, respectively. If R=1, the floating potential is equal to plasma potential. This is the basic idea of the direct plasma potential measurement (emissive probe, Ball-pen probe, baffled probe). The Ball-Pen Probe (BPP) has been recently developed by Adamek et al. in the Institute of Plasma Physics in ASCR [2, 5] and used on different fusion devices (ASDEX Upgrade, COMPASS, ISTTOK) [6-10]. It is based on the Katsumata probe concept [11]. The Ball-Pen probe consists of a movable metallic collector placed inside an insulating ISBN: 978-960-474-400-8 370

tube. The ratio R, using the Ball-Pen probe, can be adjusted to one. The probe is designed so that the ratio R can be modified by changing the collecting areas for electrons and ions, taking advantage of the fact that the Larmor radii of electrons and ions are strongly different [2-5]. When R=1, floating potential is equaled with plasma potential. Langmuir-Ball Pen Probe is a combined probe. It contains a Ball-Pen probe (for the direct measurement of plasma potential) and a Langmuir probe-ring. The Langmuir probe-ring has been attached around the tube [12]. So it contacts with the plasma. Therefore, it can measure the floating potential. Regarding to Eq. (1), electron temperature can be calculated. This paper is organized as follows. A description of the IR-T1 and the experimental set-up is presented in Sec. 2. The results and discussion are presented in Sec. 3 and conclusions are given in Sec. 4. 2. Experimental Set-up IR-T1 is a small research Tokamak located at the Plasma Physics Research Center (PPRC). This Tokamak is an air core Tokamak without a copper shell. It has a major radius of R = 45 cm and a minor radius a = 12.5 cm, the plasma current I p = 20 30 ka, the toroidal magnetic field B t = 0.7 0.8 T, the average electron density n = (0.3 1.5) 10 19 m -3. This device consists of a vacuum vessel with circular cross-section that was made from a stainless steel welding structure with two toroidal breaks and a minor radius b = 15 cm. The probe consists of a conically shaped collector, which is shielded by an insulating tube made of Alumina (Al 2 O 3 ). The Langmuir probe-ring that has been attached around the Al 2 O 3 tube has been made of tungsten. The similar design has been used on tokamak CASTOR in 2005 [12]. Regarding to the IR-T1 plasma properties, we have constructed and installed Langmuir-Ball Pen Probe on IR-T1. For investigation of ring-probe surface effect in future works, we installed two Langmuir ring-probes with different radius. The radii of Langmuir ring-probes are about 5mm (No. 1) and 8mm (No. 2) (See Fig.1). In this work, the ball-pen collector and the Langmuir ring-probe that has been attached around the tube (with radius of 5mm (No.1)), have been floated. The measurements have been done in IR-T1 plasma edge. Tokamak limiter biasing has been very successful in improving the global plasma energy and particle confinement parameters and edge plasma rotation by setting up a radial electric field at the plasma edge. The biased limiter drives a radial current between itself and the vacuum vessel and the resulting force originates sheared flows, which have a suppressing effect on turbulence and related transport. Limiter biasing experiments have been performed on IR-T1 in order to control the edge radial electric field and investigate its impact on gross global particle confinement [13-15]. A schematic illustration of limiter biasing is presented in Fig. 2. The limiter was set on a fixed position during the following experiments. In this work, effect positive and negative biased voltages (V=+200v and V=-200v) has been investigated. ISBN: 978-960-474-400-8 371

discharge (Wang et al. 1995). In all experiments, the biasing has been applied from 15 ms and is continued to the end of shot. The effect of biased limiter on the time evolution of the plasma current has been illustrated in Fig. 3. The results show that the plasma current has increased (about 10%) with applying positive biased voltage V biasing =+200v while it has decreased (about 15%) after applying negative biased voltage V biasing =-200v. Fig.1. The photos of the constructed Langmuir-Ball Pen Probe on IR-T1 Tokamak. Fig.2. Typical schematic of the limiter biasing set-up on IR-T1. 3. Result and Discussion In IR-T1, the biased voltage is applied after the tokamak plasma has reached the equilibrium, because it was reported that if the biased voltage is applied before or at the same time as the startup phase (most often, the plasma disrupts after a few tens of milliseconds and before equilibrium is established). The radial Electric Field produced by biasing is therefore believed to disturb the start-up condition of the Fig. 3. Time evolution of the plasma current without biasing and (a) positive biased voltage (V bias = +200 V) and (b) negative biased voltage (V bias = 200 V). The biasing has been applied at t = 15 ms until the end of the shot. ISBN: 978-960-474-400-8 372

Fig. 4. Dependence of (a) Ion and (b) electron saturation current on the collector position in the IR- T1 plasma edge for V biasing = +200V, V biasing = 0V and V biasing = -200 V. Dependence of ion and electron saturation current on the collector position for different voltages (V biasing =+200V, V biasing =0V and V biasing =-200 V) has been displayed in Fig. 4. Measurements have been done in plasma edge (r/a=0.9). Decrease of electron saturation current is steeper than in case of ion saturation current because the electrons have smaller Larmor radius compare to the ions. The positive biased voltage V biasing =+200V increases ion and electron saturation currents while negative biased voltage V biasing =-200V decreases them. Results show that the ion saturation current is very close to electron saturation current but not equal as seen in Fig. 5 for position h=-0.7mm. So the ratio R is very close to one (ln(r) attains a minimum (ln(r) = 0.17) when h=-0.7mm) and therefore floating potential V fl is very close to plasma potential V p. For the investigation of influence of biased limiter on plasma potential, the dependence of ln(r) on the collector position has been investigated for different voltages (V biasing =+200V and V biasing =-200V) in Fig. 6. The results show that ln(r) attains a minimum in different collector positions after the applying biased limiter. As can be seen from Fig. 6, the ratio R is very close to one at collector positions h=-1.1mm, h=- 0.7mm and h=-0.6mm for V biasing =+200V, V biasing =0V and V biasing =-200V, respectively. The effect of limiter biasing on floating potential of IR-T1 edge plasma for different collector positions has been illustrated in Fig. 7. Fig. 5. The comparison of the ion and electron saturation currents in different collector positions. The measurements has been done in IR-T1 plasma edge for V biasing = 0V. ISBN: 978-960-474-400-8 373

The floating potential has increased with applying positive biased voltage (V biasing = +200V) while it has decreased after applying negative biased voltage (V biasing = -200V). For each voltage, floating potential increases when the collector retracts into tube. Floating potential is very close to plasma potential for collector positions h=-1.1mm, h=-0.7mm and h=-0.6mm for V biasing =+200V, V biasing =0V and V biasing =- 200V, respectively. We can see from Fig. 7 that IR-T1 edge plasma potential is about 54V, 45V and 39V for V biasing =+200V, V biasing =0V and V biasing =-200V. The time evolution of IR-T1 edge plasma potential for different voltages has been shown in Fig.8. Temporal evolution of measured floating potential by Ball-Pen Probe (h=-0.7mm) and Langmuir probe-ring (No.1) has been represented in Fig. 9. The measurements have been done in plasma edge without applying bias (V biasing = 0V). Indeed the temporal evolution of measured floating potential by Ball-Pen Probe in h=-0.7mm (black line) is nearly the same as temporal evolution of plasma potential. Regarding to the Eq. (1), electron temperature is calculated from difference of plasma potential and floating potential. The time evolution of electron temperature of plasma edge has been illustrated in Fig. 10. Moreover, the effect of limiter biasing on electron temperature can be seen in this figure. The results show that the electron temperature of edge plasma increases from 14eV to 19eV after applying biased voltage V biasing =+200V. While the applying negative biased voltage (V biasing =-200V) reduces it. This reduction is about 8eV. Fig. 6. Dependence of on collector position for V biasing = +200V, V biasing = 0V and V biasing = -200 V in IR-T1 plasma edge. Fig. 7. Dependence of floating potential on collector position for V biasing = +200V, V biasing = 0V and V biasing = +200 V in IR-T1 plasma edge. Fig. 8. Time evolution of the IR-T1 edge plasma potential for V biasing = +200V, V biasing = 0V and V biasing = -200 V. The biasing has been applied at t = 15ms until the end of the shot. ISBN: 978-960-474-400-8 374

4. Conclusion In general, Langmuir probe has two weak points: Measurement of the ion temperature and plasma potential. Spectroscopy can measure the ion temperature but the measuring is global. The best presented method of the plasma potential measuring is Ball-Pen probe. The Ball-Pen probe was already used in many fusion devices (CASTOR, AUG, ISTTOK, COMPASS), but regarding to the IR-T1 plasma properties, this probe has been designed and constructed for first time in this Tokamak. In this paper, the effect of limiter biasing on the plasma parameters as floating potential, ion and electron saturation currents, plasma potential and electron temperature has been investigated. The measurements have been done by the Langmuir-ball pen probe in IR- T1 plasma edge. For this purpose, this probe has been constructed and installed on IR-T1. In this work, the biased limiter voltages are V=+200V, V=0 and V=-200V. The results show that ion and electron saturation currents have decreased when the collector retracts inside the tube. The negative biased voltage has reduced the ion and electron saturation currents while the positive voltage has increased them. The ratio very close to one at a certain collector position. The results show that this position changes with the applying limiter biasing. The results show that the ratio R is very close to one at h=-1.1mm, h=-0.7mm and h=-0.6mm for V biasing =+200V, V biasing =0 and V biasing =-200V, respectively. In this collector position, the plasma potential that is close to floating potential is about 54V, 45V and is 39V for V biasing =+200V, V biasing =0 and V biasing =-200V respectively, in plasma edge. The biased limiter with V biasing =+200V causes to the increase of plasma potential (>20%) and electron temperature (>30%) in plasma edge. But the plasma potential and electron temperature decrease (<15%) and (>40%) due to applying the negative biased voltage (V biasing =-200V). Fig. 9. Time evolution of the measured floating potential by the Ball-pen probe (h=-0.7mm) and Langmuir probe-ring. The measurements has been done in IR-T1 plasma edge for V biasing = 0V. Fig. 10. Time evolution of the IR-T1 electron temperature in plasma edge for V biasing = +200V, ISBN: 978-960-474-400-8 375

V biasing = 0V and V biasing = -200V. The biasing has been applied at t = 15 ms until the end of the shot. The investigation of effect of Resonant Helical magnetic Field (RHF) on the measured parameters by Langmuir-Ball Pen probe will done in the later works. References [1] I. H. Huchinson, Cambridge Univ. Press, 2nd edition, 2002. [2] J. Adámek et al., Czech J Phys, 54, pp: 95 99, 2004. [3] G. Van Oost, J. Transactions of fusion science and technology, 53, pp: 387-397, 2008. [4] R. Schrittwieser et al., Plasma Phys.and Contr. Fusion, 44, 567, 2002. [5] J. Adamek et al., Czech. J. Phys. 55, 235 (2005). [6] J. Adamek et al., Contrib. Plasma Phys. 50, 9 (2010). [7] J. Horacek et al., Nucl. Fusion 50, 105001 (2010). [8] H. W. Muller et al., Nucl. Fusion 51, 073023 (2011). [9] C. Silva et al., 40th EPS conference on plasma physics, Espoo, Finland P5.103, (2013). [10] J. Adamek et al., Contrib. Plasma Phys. 54, No. 3, 279-284 (2014) [11] I. Katsumata et al., Japan J. Appl. Phys., 6, pp: 123 124, 1967. [12] J. Adámek et al., 32nd EPS Conference on Plasma Physics and Controlled Fusion. Tarragona, P5_081 (2005). [13] S. Meshkani et al., J. Plasma Physics, 79, 5, pp: 647 655 (2013). [14] S. Meshkani et al., Phys. Scr., 88, 035502 (2013). [15] M.Lafouti et al., Review of Scientific Instruments, 84, 5, p0535042013 (2013). ISBN: 978-960-474-400-8 376