Overview and Experimental Program of the Levitated Dipole Experiment
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1 Overview and Experimental Program of the Levitated Dipole Experiment Columbia University D.T.Garnier, A.K. Hansen, M.E.Mauel, E.E.Ortiz Columbia University A. Boxer, J. Ellsworth, O. Grulke, I. Karim, J. Kesner, I.Karim, J.Minervini, P. Michael, A.Zhukovsky MIT Plasma Science and Fusion Center Presented at the American Physical Society 45th Annual Meeting of the Division of Plasma Physics Albuquerque, New Mexico October 27, 2003
2 Abstract The Levitated Dipole Experiment (LDX) is the first experiment to investigate the behavior of high-temperature plasma confined by a levitated magnetic dipole. LDX consists of a large, high-field, superconducting coil magnetically levitated within a large vacuum vessel. Since field lines pass through the inner bore of the floating coil, the plasma is not lost to the poles. High-temperature plasma having pressure comparable to the confining magnetic pressure ~ 1 can be produced and studied. LDX will test recent theories showing unique equilibrium and stability properties of confined plasma with stationary profiles. The LDX physics plan includes the study of high- plasma, investigation of dipole confinement characteristics, the formation of convective cells within the closed field line geometry, and the possibility of non-local transport. With its three super-conducting magnets, LDX highlights the role of innovative magnetic technology that makes possible explorations of entirely new confinement concepts. We describe the project goals, overall program plan, and current status of the experiment.
3 Why is dipole confinement interesting? The Io Plasma Torus around Jupiter J. Spencer Simplest confinement field High- confinement occurs naturally in magnetospheres ( ~ 2 in Jupiter) Possibility of fusion power source with nearclassical energy confinement Opportunity to study new physics relevant to fusion and space science
4 Dipole Plasma Confinement If p 1 V 1 = p 2 V 2, then interchange does not change pressure profile. For = d ln T d ln n = 2, density and 3 temperature profiles are also stationary. Toroidal confinement without toroidal field Stabilized by plasma compressibility Not average well No magnetic shear No neoclassical effects No TF or interlocking coils Poloidal field provided by internal coil Steady-state w/o current drive J = 0 -> no kink instability drive
5 Dipole Confinement continued... Marginally stable profiles satisfy adiabaticity condition. M.N. Rosenbluth and Longmire, Ann. Phys. 1 (1957) 120. (pv ) = 0, where V = Equilibria exist at high- that are interchange and ideal MHD ballooning stable For marginal profiles with = 2/3, dipoles also drift wave stable Near-classical confinement? Drift waves exist at other values of, but with with reduced growth rates No Magnetic Shear -> Convective cells are possible For marginal profiles, convective cells convect particles but not energy. Possible to have low p with high E. dl B, = 5 3 Convective cells are non-linear solution to plasmas linearly unstable to interchange
6 LDX Experiment Cross-Section
7 LDX Test Cell MIT provided support stand installed May 2003 Doubles available space surrounding LDX Provides safe and easy access to LDX diagnostic ports Provision made for possible future lead shielding wall
8 LDX Vacuum Vessel Specifications 5 meter (198 ) diameter, 3 m high, elevated off chamber floor 11.5 Ton weight 7.5 x 10-8 Torr base pressure Manufactured by DynaVac Completed Sept. 1999
9 Unique high-performance Nb3Sn superconducting coil 1.5 MA, 800 kj 1300 lbs weight 8 hr levitation Inductively charged Cryostat made from three concentric tori Design < 1 Watt heat leak to Coil Helium Pressure Vessel Lead Radiation Shield Outer Vacuum Shell Current Status Final leak checking at MIT Two leaks identified LDX Floating Coil
10 Floating Coil Cross-Section 1. Magnet Winding Pack 2. Heat Exchanger tubing 3. Winding pack centering clamp 4. He Pressure Vessel (Inconel625) 5. Thermal Shield (Lead/glass composite) 6. Shield supports (Pyrex) 7. He Vessel Vertical Supports/Bumpers 8. He Vessel Horizontal Bumpers 9. Vacuum Vessel (SST) 10. Multi-Layer Insulation 11. Laser measurement surfaces 13. Outer structural ring
11 Floating Coil Winding Pack Advanced Nb 3 Sn react & wind conductor 8 mm epoxied and finally tested to full current (1.56 MA) and field (6 T) in 4.2K LHe bath. wound very carefully
12 F-Coil Helium Pressure Vessel Inconel 625 Pressure Vessel 125 ATM at 300 K 2-3 ATM cold 1.5 kg He storage Fully machined weight 150 kg Completed construction at Ability Engineering Technology, South Holland, IL. Pressure tested & code stamped Leak test to 125 atm. for both vessel and heat exchanger Covered in Al tape to give low emissivity at 4 K.
13 Thermal Radiation Shield Cored fiberglass composite construction 2 fiberglass skins, 0.5mm thick and separated by core Lead core panels provide thermal inertia at 20 K and intercept heat from vacuum vessel to 4 K helium vessel Copper heat exchange tubing & conduction strips for cooldown Status Fabrications and installation complete
14 Support Washer Stacks Specification Hold heat leak to 5 K < 10 mw Withstand 10g crash (5 Tons!) Solution Stack of 400 4mil thick washers Status: Complete! Prototype testing complete 24 Stacks (~7000 coins) Assembled, Sized and Installed
15 F-coil Multilayer Insulation (MLI) F-coil Multilayer Insulation (MLI) Alternating layers of Remay spun polyester fabric and double aluminized Mylar film MLI system developed at Fermilab for use on the Superconducting Supercollider. Low heat leak and simplified application make it ideal for toroidally shaped cryostat Up to 96 layers applied by hand Initial 36 layers made from individually fitted bow ties to minimize joint defects
16 Outer Floating Coil Cryostat Low heat leak anti-rotation devices complete, tested and installed Unique low heat-leak LHe feedthoughs tested Electrical feedthrough complete Support space frame complete and installed Currently repairing internal helium leaks Final welds procedure tested Inverted Cryogenic Feedthrough Cryostat vacuum vessel and support space frame Charging station Electrical vacuum vessel feedthrough
17 Floating Coil Charging Station Rotary bearing table Fixes radial motion but allows azimuthal alignment of feedthroughs Vacuum jacketed cryogenic feedthroughs Electrical connection for magnet temperature measurement Status: Acceptance tests complete. rotary bearing table Charging station Station cylinder vacuum vessel
18 Superconducting Charging Coil Large superconducting coil NbTi conductor 4.5 K LHe pool-boiling cryostat with LN2 radiation shield 1.2 m diameter warm bore 5.6 T peak field 12 MJ stored energy Cycled 2X per day Ramping time for F-Coil < 30 min. Built and tested at SINTEZ Efremov Institute in St. Petersburg, Russia Received at MIT 9/03.
19 Charging Coil Winding Pack Winding pack after impregnation Winding 37 km of superconducting cable Electrical tests after 100 T of axial preload
20 Charging Coil Cryostat Construction Coil held from upper supports He can currently being welded closed Vapor cooled leads installed LN2 cooled copper shield ready for installation next
21 C-coil Cryostat Assembly Inner LN2 can installed Installation of monocrystalline Al coated SS sheets LHe can installed on LN2 cooled struts Outer vacuum vessel lowered over assembly (with outer LN2 can installed)
22 C-coil Acceptance Tests Vacuum, cryogenic and magnetic tests completed Tests completed 3/8/03 Vacuum and cryogenic tests indicate small He leak Causes acceptable increase in cryogen consumption 3 Magnetic tests showed magnet quench at 440 A (4.3T peak field) No training observed Safe operating point at 425A (roughly 80% of nominal design point) Tests indicate Charging coil will meet all LDX physics objectives Received at MIT Installation procedures underway
23 High T c Superconducting Levitation Coil SBIR collaboration with American Superconductor First HTS coil in the fusion community Uses available BSSCO-2223 conductor Operational temp K Feedback gain selected for 5Hz mode frequency < 20 W AC loss 20 kj stored energy Emergency dump in < 1 second. Coil Completed & Tested 77 K superconducting tests successful 20 K tests complete Preliminary assessment: GOOD!
24 Levitation Coil Construction Completion of cryogen free cooling structure 105 layers wound of very small and fragile HTS Coil in first stage of cryostat assembly
25 L-coil Cryostat Construction Installation of HTS leads and cold finger conduction cooling from cold head. Assembly of coil, cold head, nitrogen can and copper thermal shield Multilayer Insulaiton (MLI) installed Received L-coil undergoing tests
26 Launcher/Catcher Bellows feedthrough High vacuum required Long (> 2m) motion Used in both supported and levitated operation Central rod limits fault motion of floating coil without interrupting plasma. Integral shock absorbers to keep drop deceleration < 10g Status Built and tested for Phase 1 (supported) operations
27 Launcher Fixture - Phase 1 The floating coil rests on a conformal ring. Field lines close to the coil intercept the lifting fixture at the spokes. Shown: Support loaded with dummy shell of same dimensions as those of the floating coil system. Dummy shell lifted into operating position within the vacuum chamber. Not shown: 1 wide boron nitride shields over spokes.
28 Levitation Control System Levitation from above Requires stabilization of vertical motion by feedback Other motions are stable Levitation control system Optical detection system measures position and attitude of floating coil with 10 µm resolution Digital control system
29 Digital Feedback System Win 2000 Development System / Operator Interface Computer (control room) 100BT Ethernet Digital Control Computer (in experimental hall) QNX 6 RTOS Launcher / Catcher Panic Button Design Requirements All digital process control Mathworks Matlab/Simulink design tool and visualization software Process control on hard real-time operating system based computer Modular Opal-RT / QNX Neutrino Real-time system implemented Hardware/Software testing with desktop model - LCX II High Speed I/O F-coil Optical Position Detection System L-coil Crowbar Circuit Misc Interlocks Magnet Power Supplies
30 LDX Experimental Goals Investigate high-beta plasmas stabilized by compressibility Also the stability and dynamics of high-beta, energetic particles in dipolar magnetic fields Examine the coupling between the scrape-off-layer and the confinement and stability of a high-temperature core plasma. Study plasma confinement in magnetic dipoles Explore relationship between drift-stationary profiles having absolute interchange stability and the elimination of drift-wave turbulence. Explore convective cell formation and control and the role convective cells play in transport in a dipole plasma. The long-time (near steady-state) evolution of high-temperature magnetically-confined plasma. Demonstrate reliable levitation of a persistent superconducting ring using distant control coils.
31 LDX Experimental Plan Supported Dipole Hot Electron Plasmas High- Hot Electron plasmas with mirror losses ECRH Plasma formation Instabilities and Profile control Levitated Dipole Hot Electron Plasmas No plasma losses to supports enhancement Confinement studies Thermal Plasmas Thermalization of hot electron energy with gas puffs / pellets Convective cell studies Concept Optimization / Evaluation
32 Initial Supported Hot Electron Plasmas Low density, quasi steady-state plasmas formed by multi-frequency ECRH with mirror-like losses from supported dipole Areas of investigation Plasma formation & density control Pressure profile control with ECRH Supercritical profiles & instability Compressibility Scaling ECRH and diagnostics development Unique to supported operation B field scaling Floating ring potential control
33 Multi-frequency ECRH on LDX Multi-frequency electron cyclotron resonant heating Effective way to create high- hot electron population Tailor multi-frequency heating power to produce ideal (stable) pressure profile with maximum peak. Individual Heating Profiles 6 Tailored Pressure Profile st Harmonic resonances 2nd Harmonic resonances 28 Freq. (GHz)
34 Initial Plasma Diagnostic Set Top Ports N Bottom Ports N NW NE NW NE LEGEND W SW SE E W SW SE Magnetics Interferometer X-Ray PHA X-Ray Camera Probes ECRH Visible Camera Vacuum Pumping GDC Levitation Control S S Horizontal Ports N NE E SE S SW W NW Magnetics (flux loops, hall probes) Plasma equilibrium shape Mirnov coils for magnetic fluctuations Interferometer Density profile and macroscopic density fluctuations X-rays diagnostics PHA hot electron energy distribution / profile Hard X-Ray Camera D camera Edge probes Edge plasma density and temperature Fluctuations
35 Conclusions LDX is the first experiment to investigate plasmas stabilized by compressibility with near-classical confinement Capable of directly testing effects of compressibility, pressure profile control and axisymmetry on plasma stability and confinement Relevant to both space and laboratory fusion plasma physics Initial diagnostic set and experimental plan to focus on stability of high- hot electron plasmas in supported and levitated operation LDX is a world class superconducting fusion experiment with sophisticated magnet technology Three unique superconducting magnet systems are received at MIT and nearly completed Check for updates on progress
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