A Hall Sensor Array for Internal Current Profile Constraint

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

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

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

D.J. Schlossberg, D.J. Battaglia, M.W. Bongard, R.J. Fonck, A.J. Redd. University of Wisconsin - Madison 1500 Engineering Drive Madison, WI 53706

Nonsolenoidal Startup and Plasma Stability at Near-Unity Aspect Ratio in the Pegasus Toroidal Experiment

D.J. Schlossberg, D.J. Battaglia, M.W. Bongard, R.J. Fonck, A.J. Redd. University of Wisconsin - Madison 1500 Engineering Drive Madison, WI 53706

Advancing Local Helicity Injection for Non-Solenoidal Tokamak Startup

Initiatives in Non-Solenoidal Startup and H-mode Physics at Near-Unity A

H-mode and ELM Dynamics Studies at Near-Unity Aspect Ratio in the PEGASUS Toroidal Experiment and their Extension to PEGASUS-Upgrade. M.W.

Advancing Toward Reactor Relevant Startup via Localized Helicity Injection at the Pegasus Toroidal Experiment

Non-Solenoidal Plasma Startup in

Pedestal Stability and Transport on the Alcator C-Mod Tokamak: Experiments in Support of Developing Predictive Capability

H-mode and Non-Solenoidal Startup in the Pegasus Ultralow-A Tokamak

Predictive Power-Balance Modeling of PEGASUS and NSTX-U Local Helicity Injection Discharges

Expanding Non-Solenoidal Startup with Local Helicity Injection

Edge Rotational Shear Requirements for the Edge Harmonic Oscillation in DIII D Quiescent H mode Plasmas

A.J.Redd, D.J.Battaglia, M.W.Bongard, R.J.Fonck, and D.J.Schlossberg

MHD Analysis of the Tokamak Edge Pedestal in the Low Collisionality Regime Thoughts on the Physics of ELM-free QH and RMP Discharges

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

UCLA. Broadband Magnetic and Density Fluctuation Evolution Prior to First ELM in DIII-D Edge Pedestal. Presented by G. Wang a, In collaboration with

ELMs and Constraints on the H-Mode Pedestal:

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

DIAGNOSTICS FOR ADVANCED TOKAMAK RESEARCH

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

Effects of Noise in Time Dependent RWM Feedback Simulations

Abstract. , low-q operating space at near-unity aspect ratio. Plasmas are characterized by high b t ( 20% to date); very low toroidal field (B t

Influence of Beta, Shape and Rotation on the H-mode Pedestal Height

GA A27857 IMPACT OF PLASMA RESPONSE ON RMP ELM SUPPRESSION IN DIII-D

RWM Control in FIRE and ITER

Physics of Intense Electron Current Sources for Helicity Injection

Exponential Growth and Filamentary Structure of Nonlinear Ballooning Instability 1

ELM Suppression in DIII-D Hybrid Plasmas Using n=3 Resonant Magnetic Perturbations

Particle transport results from collisionality scans and perturbative experiments on DIII-D

GA A25592 STABILITY AND DYNAMICS OF THE EDGE PEDESTAL IN THE LOW COLLISIONALITY REGIME: PHYSICS MECHANISMS FOR STEADY-STATE ELM-FREE OPERATION

Modeling of ELM Dynamics for ITER

Non-Solenoidal Startup via Helicity Injection in the PEGASUS ST

- Effect of Stochastic Field and Resonant Magnetic Perturbation on Global MHD Fluctuation -

Localized Electron Cyclotron Current Drive in DIII D: Experiment and Theory

Evolution of the pedestal on MAST and the implications for ELM power loadings

ArbiTER studies of filamentary structures in the SOL of spherical tokamaks

Plasma spectroscopy when there is magnetic reconnection associated with Rayleigh-Taylor instability in the Caltech spheromak jet experiment

GA A22993 EFFECTS OF PLASMA SHAPE AND PROFILES ON EDGE STABILITY IN DIII D

Stationary, High Bootstrap Fraction Plasmas in DIII-D Without Inductive Current Control

Spherical Torus Fusion Contributions and Game-Changing Issues

Hard Xray Diagnostic for Lower Hybrid Current Drive on Alcator C- Mod

KSTAR Equilibrium Operating Space and Projected Stabilization at High Normalized Beta

Electron Bernstein Wave (EBW) Physics In NSTX and PEGASUS

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

The details of point source helicity injection as a noninductive startup technique must be characterized:

Design of next step tokamak: Consistent analysis of plasma flux consumption and poloidal field system

First Observation of ELM Suppression by Magnetic Perturbations in ASDEX Upgrade and Comparison to DIII-D Matched-Shape Plasmas

TRANSPORT PROGRAM C-MOD 5 YEAR REVIEW MAY, 2003 PRESENTED BY MARTIN GREENWALD MIT PLASMA SCIENCE & FUSION CENTER

OV/2-5: Overview of Alcator C-Mod Results

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

Disruption dynamics in NSTX. long-pulse discharges. Presented by J.E. Menard, PPPL. for the NSTX Research Team

Characterization of neo-classical tearing modes in high-performance I- mode plasmas with ICRF mode conversion flow drive on Alcator C-Mod

Model based optimization and estimation of the field map during the breakdown phase in the ITER tokamak

Heat Flux Management via Advanced Magnetic Divertor Configurations and Divertor Detachment.

W.A. HOULBERG Oak Ridge National Lab., Oak Ridge, TN USA. M.C. ZARNSTORFF Princeton Plasma Plasma Physics Lab., Princeton, NJ USA

Progress in characterization of the H-mode pedestal

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

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

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

New bootstrap current formula valid for steep edge pedestal, and its implication to pedestal stability

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

Effect of non-axisymmetric magnetic perturbations on divertor heat and particle flux profiles

GA A26565 LIMITS TO H-MODE PEDESTAL PRESSURE GRADIENT IN DIII-D

Highlights from (3D) Modeling of Tokamak Disruptions

THE DIII D PROGRAM THREE-YEAR PLAN

DEPENDENCE OF THE H-MODE PEDESTAL STRUCTURE ON ASPECT RATIO

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

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

Current Drive Experiments in the HIT-II Spherical Tokamak

CONFINEMENT IN THE RFP: LUNDQUIST NUMBER SCALING, PLASMA FLOW, AND REDUCED TRANSPORT

Large Plasma Device (LAPD)

The Plasma Phase. Chapter 1. An experiment - measure and understand transport processes in a plasma. Chapter 2. An introduction to plasma physics

Ion Temperature Measurements in the

Development and Validation of a Predictive Model for the Pedestal Height (EPED1)

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

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

Scaling of divertor heat flux profile widths in DIII-D

L-Mode and Inter-ELM Divertor Particle and Heat Flux Width Scaling on MAST

Sheared Flow Stabilization in the Z-Pinch

Understanding Edge Harmonic Oscillation Physics Using NIMROD

RESISTIVE WALL MODE STABILIZATION RESEARCH ON DIII D STATUS AND RECENT RESULTS

GA A27444 PROBING RESISTIVE WALL MODE STABILITY USING OFF-AXIS NBI

Possible Experimental Tests of Pedestal Width/ Structure, Motivated by Theory/Modeling

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

Is the Troyon limit a beta limit?

The EPED Pedestal Model: Extensions, Application to ELM-Suppressed Regimes, and ITER Predictions

Density Fluctuation Induced Kinetic Dynamo and Nonlinear Tearing Mode Saturation in the MST Reversed Field Pinch

Study of Enhanced D α H-modes Using the Alcator C-Mod Reflectometer

Characteristics of the H-mode H and Extrapolation to ITER

THE ADVANCED TOKAMAK DIVERTOR

C-Mod Transport Program

GA A26891 A FIRST PRINCIPLES PREDICTIVE MODEL OF THE PEDESTAL HEIGHT AND WIDTH: DEVELOPMENT, TESTING, AND ITER OPTIMIZATION WITH THE EPED MODEL

Physics and Operations Plan for LDX

IF2011 Pedestal/JRT Summary. J.W. Hughes 21 Jan 2011

Spatio-temporal investigations on the triggering of pellet induced ELMs

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

Transcription:

A Hall Sensor Array for Internal Current Profile Constraint M.W. Bongard, R.J. Fonck, B.T. Lewicki, A.J. Redd University of Wisconsin-Madison 18 th Topical Conference on High-Temperature Plasma Diagnostics Poster J34 Wildwood, NJ May 19, 2010 PEGASUS Toroidal Experiment

Abstract Measurements of the internal distribution of B in magnetically confined plasmas are required to obtain current profiles via equilibrium reconstruction with sufficient accuracy to challenge stability theory. A 1D, 16-channel array of InSb Hall effect sensors with 7.5 mm spatial resolution has been constructed to directly measure internal B z (R,t) for determination of J(ψ,t) associated with edge-localized peeling mode instabilities in the Pegasus Toroidal Experiment. The diagnostic is mounted in an electrically isolated vacuum assembly which presents a slim, cylindrical profile (~1 cm OD) to the plasma, using graphite as a low-z PFC. Absolute calibration of the sensors is determined via in situ cross-calibration against existing magnetic pick-up coils. Present channel sensitivities are of order.25 mt. Internal measurements with bandwidth 25 khz have been obtained without measurable plasma perturbation. They resolve n=1 internal MHD and indicate systematic variation in J(ψ) under different stability conditions. Work supported by U.S. DOE Grant DE-FG02-96ER54375

Diagnostic Motivation Edge stability critical to next-step devices Transient ELM heat loads PFC damage in ITER-scale facility PEGASUS: ELM-like edge instabilities at high <j edge /B> Field-aligned filaments similar to ELM bursts in other machines Electromagnetic signature with low- to intermediate-n, high m Edge detachment, outboard radial propagation, and acceleration Consistent with peeling drive Hall Probe diagnostic commissioned to constrain J(Ψ) PEGASUS edge compatible with direct probe measurements

PEGASUS: A Mid-Size, Ultralow-A ST High-stress Ohmic heating solenoid Experimental Parameters Parameter A R(m) I p (MA) I N (MA/m-T) l i κ τ shot (s) β t (%) P HHFW (MW) To Date 1.15 1.3 0.2 0.45.21 6 12 0.2 0.5 1.4 3.7 0.025 25 0.2 RF Heating Antenna

ELM-like Structures Observed in PEGASUS 36116 PEGASUS Maingi, Phys. Plasmas 13, 092510,2006 NSTX Kirk, Plas. Phys. Controlled Fus. 49, 2007 MAST ELMs are filamentary, field-aligned structures Peeling-ballooning theory: trigger mechanism PEGASUS: L-mode edge assumed Peeling instability candidate mechanism

Two Distinct Filament Classes Observed Peeling (a) EM signature: high m, low n Coherent spatial structure Filament rotation Detachment, outboard radial propagation, acceleration Ip (ka) 140 120 100 80 60 40 20 0 15 40585 (a) 20 25 (b) (c) 30 35 100 50 0-50 -100 Midplane dbr/dt (T/s) ms MHD Quiescent L-mode (b) Peeling (a) MHD Quiescent (b) No EM signature Electrostatic turbulence: shortlived filaments observable when τ exp 20 μs Separated by n=1 internal tearing phase (c) 11 μs τ exp, visible λ

Candidate Instability: The Peeling Mode Peeling-ballooning theory is a proposed mechanism for ELMs Localized MHD edge instability Ballooning p drive from H-mode pedestal Peeling Edge current, current gradient drive Snyder, Phys. Plasmas 12, 056115, 2005; see also Hegna, Phys. Plasmas 3, 584, 1996 Qualitative guide: analytic peeling stability criterion* *Review: Connor et. al., Phys. Plasmas 5, 2687,1998

Near-unity A Maximizes Peeling Drive Device J edge (MA/m 2 ) B φ,0 (T) J edge /B PEGASUS ~ 0.1 0.2 0.1 ~ 1 DIII-D* 1 2 2 0.5 1 *: Thomas, Phys. Plasmas 12, 056123 2005 PEGASUS operations at A 1 lead to naturally high J edge /B Comparable to larger machines in H-mode However, source of peeling drive different Large machines: H-mode p J BS PEGASUS: Large di p /dt ( 50 MA/s) transient skin current

Improved J edge Measurements Desirable p(ψ) typically constrained via multichannel Thomson Scattering PEGASUS system under design; initial implementation FY 2011 Edge J(ψ) equally important to validate theory; rarely measured Extremely challenging measurement on high-temperature ATs Best results to date: DIII-D Li beam polarimetry Typical alternative: compute J Calculates J BS given experimental p(ψ) Questionable assumptions in edge Thomas, Phys. Plasmas 12, 056123, 2005

J Determined by B(R,t) Internal B constrains J through Ampere s law: Requires spatially localized measurements Edge stability theory validation demands time resolution ~ τ ELM 100 μs J(ψ) obtained through equilibrium reconstruction Successful approaches to measuring J(R,t) employ B p (R,t) Beam-based methods: Localized, but poor- to moderate time resolution Motional Stark Effect spectroscopy: core J Li beam polarimetry: edge J Faraday rotation polarimetry: good time response, but chordal 1 B J µ = Direct probes: Localized, good time response, but incompatible with high T plasmas 0 M.W. Bongard, 18 th HTPD, Wildwood, NJ, May 2010

Stability Analysis Requires Local Measurements Comparison of experimental equilibria with a stability analysis depends crucially on accuracy of reconstructions E.g. Peeling-ballooning: edge P(ψ), J(ψ) profiles PEGASUS: Edge conditions allow for direct measurement of internal B z New diagnostic capability provides experimental constraint on J(ψ)

Solid-state Hall Sensors Sample B Directly B High spatial resolution Good temporal response ~10-30 khz typical Simple operation Requires modest control current I c Generates V H = G H I c B sinφ G H combines all Hall physics effects; must be determined by calibration DC contribution: V DC =1/2 I c R in G H, R in can weakly vary with device, operational parameters Hall semiconductor, T sensor, B

Hall Arrays Provide Local B(t) in Tokamaks TEXTOR * External B R, B z fluctuations HBT-EP ** db z /dt, internal B z TEXTOR Hall Probe * CASTOR *** External B z plasma position PEGASUS Internal B z J(ψ) HBT-EP Hall Probe Array ** *: Ďuran, et al., Rev. Sci. Instrum. 73, 3482, 2002 **: Liu, et al., Rev. Sci. Instrum. 76, 093501, 2005 ***: Ďuran, et al., Rev. Sci. Instrum. 79, 10F123, 2008 CASTOR Hall Array ***

PEGASUS Hall Probe Deployed Solid-state InSb Hall sensors Sypris model SH-410 16 channels, 7.5 mm radial resolution C armor as low-z PFC Slim profile minimizes plasma perturbation

Integrated Electrical Shielding Required Hall Enclosure Signal Processing Enclosure Screen Room Digitizer ~30 m ~1 m Three electrostatically shielded segments Necessary for EMI immunity Interconnects via SCSI-68, triaxial cabling Four logical subsystems Hall Probe Assembly Signal Processing Module I c Source Data Acquisition

Sypris SH-410 Chosen as Hall Sensor Hall plate material: InSb High intrinsic sensitivity 2.7 17.6 V/T, at 5 ma I c PEGASUS average: ~ 6 V H /T Low Power Requirements I c ~ few ma Actual Size: Mass-produced technology Surface-mount: small footprint Low cost Sypris SH-410 Datasheet

Narrow, long form factor 0.5 cm x 30.0 cm 16 Hall Sensor Locations 7.5 mm center-center spacing Series electrical topology Ensures I c is constant in all devices Six signal routing layers Hall PCB Layout Overlapping trace design Minimizes parasitic inductive pickup, compensates I c

Modular Mechanical Design Implemented Shielded Hall Enclosure Electrically isolated Modularity: PCB easily replaced Forced air probe cooling for temperature regulation M.W. Bongard, 18 th HTPD, Wildwood, NJ, May 2010 Vacuum Mount and Linear Drive Narrow snout: 9/32 OD,.005 thick Graphite armor as low-z PFC Allows inner enclosure rotation for field alignment Stepper motor drive

Constant Current Source Provides I c Hall sensors resistance R in weakly varies with temperature, B Constant-I c source counteracts these effects Initial implementation: brute force HVPS + ballast resistor Approximates stiff source as R ballast >> R probe M.W. Bongard, 18 th HTPD, Wildwood, NJ, May 2010

Local Preamplifier Obtains V H Custom NIM Implementation Six-layer PCB, 32-channel module Precision instrumentation amplifier AD8250: Digitally-programmable gain Sallen-Key Butterworth Antialiasing Differential Line Driver National LMH6550: Active EMI rejection M.W. Bongard, 18 th HTPD, Wildwood, NJ, May 2010

Electrostatic Noise Effectively Suppressed PEGASUS 100 MVA switching power systems generate transient noise bursts dv CM /dt ~ 2 kv/μs @ 5 khz Capacitively coupled Successful suppression techniques developed High-quality electrostatic shields Triaxial shielding for cabling Fully differential analog signal processing Differential line drivers Local DC-DC conversion for electronic power supplies M.W. Bongard, 18 th HTPD, Wildwood, NJ, May 2010 Noise pulses in unshielded digitizer. Hall signal processing electronics actively suppress pickup in 30m cable run.

In-situ Calibration Compensates Weak Nonlinearites Hall G H varies with physical, operational parameters Linear in temperature, weakly nonlinear in B Nevertheless, effects are repeatable and well-characterized V H in EF Only Calibration Pulse Two-shot calibration technique accounts for these effects TF only: Obtains V H due to probe misalignment TF + long-pulse EF: V H due to B z G H from comparison to absolutelycalibrated Mirnovcoils Nonlinear gain reduction in G H due to presence of B φ exceeds misalignment voltage; similar effects seen on HBT-EP.

Initial Tests Yield Precision B z Measurements Internal probing yields no measurable plasma perturbation, according to: I p evolution / sustaining V loop Achieved shape (l i evolution) SPRED impurity spectroscopy Compares favorably with external Mirnov coils n=1 MHD well-resolved Full array yields spatially resolved B z (R,t) Allows inference of J(R,t), J(Ψ) M.W. Bongard, 18 th HTPD, Wildwood, NJ, May 2010

Initial Reconstructions Constrain J(ψ) 5-knot cubic spline parameterization using KFIT* Grad- Shafranov solver *Sontag, A., Nucl. Fusion 48, 095006, 2008 ψ N HP Constraint locations ( ) I p R 0 a A 1.2 κ 2.2 l i.25 β p.10 β t.02 q 0 6.1 q 95 17 157 ka.30 m.24 m

Observed Edge Instability Consistent with Qualitative Peeling Stability Criterion Connor s peeling stability criterion computed KFIT spline fits coupled to DCON Peeling calculated unstable at all times (not observed) However, peeling phase is least stable of all phases, in agreement with theoretical expectation RHS, MHD Quiescent RHS Peeling Motivates additional, detailed comparisons with peelingballooning theory Stability analysis via DCON, ELITE RHS m/1 LHS Unstable if RHS > LHS

Current and Future Work Equilibrium and stability studies with accurate j(ψ) Enhancements to KFIT to accommodate diagnostic capabilities Significant code development activity underway Direct analysis techniques * Infer J(R,t) directly from B z (R,t) Improvements to Hall Probe System Near-term: Improve signal conditioning, data acquisition to increase S/N Longer-term: 2 nd generation PCB: improved spatial resolution, stronger J(ψ) constraint *: Petty, et al., Nucl. Fusion 42, 1124, 2002

Summary Localized filamentary edge instabilities in PEGASUS consistent with peeling drive Triggered during conditions of naturally high <J edge /B> Initial equilibrium analysis: strongest peeling drive present when observed Improvements to equilibrium parameterization and coupling to DCON, ELITE to provide more rigorous comparison with peeling-ballooning theory New Hall probe diagnostic deployed to directly constrain J(ψ) Precision, internal B z (R,t) obtained without plasma perturbation Electrostatic shielding scheme, signal processing suppress switching noise Modular design allows simplified upgrades

Acknowledgements The authors wish to thank D. Shiraki and the HBT-EP group for advice regarding their practical experiences with Hall probes. Reprints of this and other PEGASUS presentations are available at http://pegasus.ep.wisc.edu/technical_reports