First Flight of the Levitated Dipole Experiment
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1 First Flight of the Levitated Dipole Experiment Columbia University Darren Garnier, Michael Mauel Columbia University Alex Boxer, Jen Ellsworth, Jay Kesner MIT Plasma Science and Fusion Center APS Division of Plasma Physics Orlando, Florida November 1, 7
2 Abstract In the past year, the first levitated experiments have been conducted in the Levitated Dipole Experiment (LDX). LDX, which consists of a 5 kg superconducting coil floating within a 5m diameter vacuum chamber, is designed to study fusion relevant plasmas confined in a dipole magnetic field. In previous plasma run campaigns, conducted with the dipole coil held by thin supports, stable high beta plasma operations were demonstrated where the plasma kinetic energy is contained in population of energetic particles. It was expected that levitated experiments would improve confinement by removing the primary loss of energy and particles along field lines. This in turn would lead to higher plasma density and broader radial profiles which should increase the stable operational space. In February, the first flight of the floating dipole coil was achieved with minutes of continuous levitation and three demonstration plasma shots. This first flight experiment demonstrated the operation of the digital feedback system that provides for stable levitation of the coil. Further flights were undertaken this fall, leading to the first plasma experiments with the launcher fully removed from the plasma. Initial results confirm many of the expected behaviors.
3 1.1 MA Floating dipole coil Nb3Sn superconductor Levitated Dipole Experiment Inductively charged by 1 MJ charging coil Up to 1 hour levitation using active feedback on upper levitation coil Plasma Two component plasma created by multi-frequency ECRH Diagnostics Magnetics - flux loops, Bp coils, Hall effect sensors Fast electrons - Channel x-ray PHA, x-ray detector, Hard X-ray camera Bulk plasma - edge probes, interferometer, visible cameras, visible diode and array Fluctuations- Edge Isat and Vf probes, Mirnov coils, visible diode array, interferometer
4 Investigating the Dipole Concept Stability: Can a dipole be stable at high β? LDX Phase I Energy Confinement: Sufficient to burn advanced fusion fuels? Particle Confinement: LDX Phase II Levitation Can convection decouple τ p and τ E? Engineering: Superconducting magnet surrounded by fusion plasma?
5 Thin Supports Remain a Major Power Loss Three high-strength, aluminacoated spokes support dipole during Phase I experiments Supports become warm during high-beta plasma operation (Elimination of supports, next step, will further enhance confinement.)
6 LDX Phase I - Hot Electron Results Stable high beta plasmas are created in LDX Large diamagnetic currents carried by fast electrons Imaging shows highly anisotropic plasma that with a localized peak near ECRH resonance (similar to radiation belts in magnetosphere) Magnetic reconstruction gives ~ % peak beta High beta requires sufficient neutral gas pressure 3 regimes found: (1) unstable, () high-β, (3) afterglow Increasing gas pressure causes: (1) dramatic rise in density, () stabilization of the HEI, and (3) transition to high-β regime Hysteresis in gas fueling required to maintain stability
7 Unstable and Stable ECRH regimes Transitory unstable regime with small, localized plasma (anisotropic) and sparks caused by rapid radial loss of hot electrons to coil Bright ionization transition followed by steady large plasma with isotropic profile
8 Typical Shot: Indicates 3 regimes kw a.u. a.u. a.u. mw Heating Power (total). GHz.5 GHz Visible Intensity X-Ray Intensity Edge Ion Saturation Current Diamagetic Flux Time(sec) Unstable Regime: Fast electron radial transport Low density Low diamagnetism (low β) High Beta Regime: Large diamagnetic current Measurable density. β loss events accompanied by xray bursts Low frequency edge electric and magnetic fluctuations Afterglow: (no input power) Low density Slow diamagnetism decay Quiescent with instability bursts
9 Controlling the High-β with Gas Puffing With sufficient neutral gas pressure, plasma enters high-β regime With insufficient neutral gas pressure, the plasma will become unstable (sometimes violently) kw 1 - Torr Total Heating Power Neutral Pressure Visible Intensity A hysteresis is the observed thresholds implies the bifurcation of the low density unstable and stable high-β regimes a.u. a.u X-Ray Intensity Qualitatively consistent with theory of the Hot Electron Interchange Mode stability mw... Diamagetic Flux Time(sec)
10 LDX Phase I - Bulk Plasma Results Quasi-coherent background instability observed Global scale, bulk density and pressure fluctuations Several candidates for mode Entropy mode Interchange driven convective cells Centrifugal driven mode Background fluctuations dependent on density profile Frequency of mode dependent on fueling rate/density profile steepness Fluctuation amplitude reduced with flatter density profile Ongoing investigation
11 Fueling dependent Core Low frequency mode Visible array- Central Chord Visible array- Central Chord Visible Array, Chord 8 8 Frequency (khz) Frequency (khz) Low frequency (few khz) core fluctuation also effected by fueling
12 Next Step: Levitation Fast electron losses to supports eliminated Pitch angle scattering reduce anisotropy, not beta Anisotropy driven modes relax plasma without losses Bulk plasma confinement also improved Stable fast electron fraction with lower neutral gas fueling? Radial transport driven profiles Single peaked, broader (more stable) profiles Expectation of improved stability and confinement Contrast with supported operation will further understanding of unstable/high-β regime bifurcation.
13 Levitation Control System F-Coil LDX Plasma DAQ System L-Coil QNX Real Time Computer (RTC) High Speed I/O Feedback Loop LDX Data System Magnetic Loops Laser Position Detectors Operator Interface LDX Control Room 15 kw Power Supply PLC Low Speed I/O Coil and Bus Temperature and Joint Voltage Montoring Interlocks STOP Launcher Catcher 5 A / 5 V Power supply Resistive coil allows for rapid shutdown Realtime digital control computer Allows different control methods to be implemented Matlab/Simulink Opal-RT development environment khz feedback loop Failsafe backup for upper fault Programmable Logic Controller Slow fault conditions Interlocks Coil and Bus temperature and resistance monitoring Optical link to control room User interface LDX data system
14 New levitation coil has been installed Levitation coil is used to support floating coil and to feedback on f-coil position 8 turn water cooled Cu coil 5 A power supply and bus work complete
15 Upper Catcher / Space frame Upper catcher Limit upward motion Align radial motion for fall to catcher Space frame structure Allows internal magnetic flux loops near plasma
16 Phase II Launcher / Catcher Lightweight cone to minimize impulse on F-coil contact Partial F-coil deceleration while launcher mass accelerates Limit all accelerations to less than 5 g
17 Laser Alignment Ring Ring placed on floating coil to occult laser beams Horizontal lasers pass through small ports ( of 8 shown here) Alternating bands of specular reflective silver and rough stainless steel to allow rotation monitoring
18 Occultation detection COTS - Keyence Extensive testing Plasma light not important Vibration somewhat important ECRF electrical isolation pickup noise measured. GHz reduces laser power interferes with power regulator circuit in LED laser? Wire grid screens installed Laser Position Detector
19 Steady state levitation cm separation between catcher mechanism and dipole coil Z position control to.1 mm Statistics 7 successful launches > hours total levitation Control algorithm P - I - D - A control of voltage PS voltage feedback fast Small operating space of reliable gains Full state control under development (Extended) Kalman filter Optimal control Full Levitation
20 Dipole Dynamics - 5 minute flight L-coil Current (Amps) Launcher Force/g (kg) Z position (mm) X position (mm) Y position (mm) Slow toroidal rotation oscillation undamped minute period Time (sec)
21 Dipole Dynamics - Launch L-coil Current (Amps) Launcher Force/g (kg) Z position (mm) mm excursion caused by launcher residual magnetism -1 1 X position (mm) Stable modes damp in 1 s 1 Y position (mm) X rotation (mrad) Y rotation (mrad) Time (sec)
22 Levitated Plasma Operations Have Begun Launcher fully extracted past plasma LCFS 5 kw ECRH Input power Marked changes compared to simlilar supported operation Higher density for less neutral pressure Flatter density profiles HEI stability Eliminated observed quasicoherent mode Fast electron buildup changed
23 HEI relaxation - Supported 5. Total Heating Power kw Torr. 3 1 Neutral Pressure a.u. mwb Visible Intensity Energy lost to (non-disruptive) HEI relaxation events Diamagetic Flux Time (sec)
24 No HEI observed when Levitated 5. Total Heating Power kw Torr. 3 1 Neutral Pressure Much lower operating neutral pressure allowable a.u. mwb Visible Intensity Diamagetic Flux Much different beta buildup (Heating accessiblity?). 8 1 Time (sec)
25 . GHz Heating (Supported) mwb kw Torr l/s a.u. < 1 1 m -3 > Total Heating Power Reaches steady state in s Diamagetic Flux Gas fueling rate Chord average density Strong density gradient at core Density Fluctuation Level Fueling greatly effects stored energy and density gradient khz 8 1 Time (sec)
26 . GHz Heating (Levitated) mwb kw Torr l/s a.u. < 1 1 m -3 > Total Heating Power Reaches steady state in ~ 1s Diamagetic Flux Gas fueling rate Chord average density Density Fluctuation Level Flat core density (ECRH cutoff?) Fueling has minimal effect on density and beta khz Broadband density fluctuations unaffected by levitation Time (sec)
27 Gas Puff (Supported) mwb Torr l/s kw 1 - Torr <G/s> khz Total Heating Power Diamagetic Flux Gas fueling rate Neutral Pressure Mirnov Fluctuation Level Mirnov TFD Neutrals ruin fast electron confinement (pitch angle scattering) Quasi-coherent mode reduced by gas puffing 8 Time (sec)
28 Gas Puff (Levitated) mwb Torr l/s kw 1 - Torr <G/s> Total Heating Power Diamagetic Flux Gas fueling rate Neutral Pressure Mirnov Fluctuation Level Mirnov TFD Reduced effect of pitch angle scattering No evidence of quasi-coherent mode khz 8 1 Time (sec)
29 Synopsis Full levitation achieved Several hours of levitation with new Cu upper levitation coil Levitation control system well developed One run (11/8/7) with launcher removed past plasma LCFS Embarking on experimental phase of project Levitation allows access to higher density, high beta plasmas Focus on stability, control and confinement of bulk plasma Initial plasma run gives evidence of several expectations Elimination of parallel loss channel for background and fast electrons Flatter radial profiles Better stability to hot electron interchange mode
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