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Supported by Columbia U Research tool development for high Comp-X General Atomics INEL Johns Hopkins U performance steady-state plasma LANL LLNL Lodestar MIT operations on NSTX Nova Photonics NYU ORNL PPPL PSI SNL UC Davis UC


  1. Supported by Columbia U Research tool development for high Comp-X General Atomics INEL Johns Hopkins U performance steady-state plasma LANL LLNL Lodestar MIT operations on NSTX Nova Photonics NYU ORNL PPPL PSI SNL UC Davis UC Irvine UCLA Masayuki Ono UCSD U Maryland For the NSTX Team U New Mexico U Rochester U Washington U Wisconsin Culham Sci Ctr Hiroshima U HIST Kyushu Tokai U Joint Spherical Torus Workshop and Niigata U Tsukuba U US-Japan Exchange Meetings (STW2004) U Tokyo JAERI Ioffe Inst TRINITI 29 th September – 1 st October, 2004 KBSI KAIST Kyoto University, Japan ENEA, Frascati CEA, Cadarache IPP, Jülich IPP, Garching U Quebec

  2. NSTX Talk Outline • Research Tool Development - RWM and PF1A for high beta operations - Core/Edge Fluctuations Diagnostics - HHFW/ EBW for heating and current drive - High frequency MHD for alpha-particle physics - Power and Particle Handling - Solenoid-free start-up • Summary Related presentations: M. Peng, ST Overview D. Gates - MHD, Confinement, Scenarios N. Nishino - Divertor fast camera R. Raman - Coaxial Helicity Injection

  3. Plasma Shaping and Resistive Wall Mode Control for near ideal MHD limit operation RWM System PF1A Upgrade D. Gates in this meeting

  4. The full Six-element RWM coil system powered with the SPA supply scheduled to be available for the FY 05 run • Error field reduction • Rotation control • Locked-mode control • RWM feed-back stabilization Columbia University

  5. New PF 1A Coils to improve plasma shaping Goal of Achieved 114465 • Shorter PF 1A is needed to 2005 2004 improve the plasma shaping control ( κ = 2.5 and δ = 0.8) for advanced ST operations. • Due to the success of high κ operation this year, the new PF 1A coil will be installed this year ahead of schedule. • Should be available for FY 05 run starting in Feb. 05. PF1A

  6. Measuring Fluctuations to gain understanding of plasma transport MSE Core reflectometer Fast X-ray camera High-k scattering Low-k imaging D. Gates in this meeting

  7. MSE/CIF begun taking plasma current profile data F. Levinton

  8. T. Peebles, UCLA

  9. Fast X-ray Camera Reveals Core Electron Dynamics CCD MSE Multistage Lyot Filter camera Image intensifier Pinholes and inside magnetic shield Be foils • Images of core n=1 tearing mode with time resolution down to ~ 2 µs t=0 t=270 µ s t=90 µ s t=180 µ s B. Stratton and PSI

  10. High k scattering measurements will be developed in FY’ 05 • Initial system will allow range High k of k measurements in select scattering locations (2 - 20 cm -1 ) • Major installation this opening. Luhmann (UC Davis), Munsat (U. Colorado) Mazzucato, Park, Smith (Princeton U.)

  11. The plan aims to make NSTX a test bed for turbulence theory validation on at least three leading fronts GS2 flux tube simulations of NSTX turbulence (Dorland, U. Maryland) Low-k imaging being developed (Mazzucato, Park; Luhmann (UC Davis)) • Critical physics (2): • Critical physics (3) • Critical physics (1): interactions between ion electron thermal electromagnetic and electron scale transport effects in turbulence as turbulence local β --> 1 Need & opportunity: strong theory community coupling

  12. Non-Inductive Sustainment HHFW Heating and CD EBW CD for profile control* *M. Peng in this meeting

  13. Multiple Roles of HHFW & • Bulk plasma heating to enhance bootstrap currents in advanced ST Operations • Plasma start-up and current ramp-up • Super-Alfvenic energetic particle physics (ITER) 12 antennas powered by • Edge physics for ICRF (ITER) 6 MW sources ORNL, PPPL, MIT, GA, CompX

  14. Increase understand of HHFW Heating Lower than NBI heating efficiency Modulation Exp performed 80 L H 70 W MHD 180° W e 60 W <ITER-97L> 50 -90° kJ 40 30 20 10 Deuterium, 0.6MA, 0.45T 0 0 1 2 3 4 Heating efficiency decreases P HHFW [MW] with k || • Electron heating vs ion heating? 180° ~ 80% • Role of plasma rotation? +90° (counter CD) ~ 50% • Edge power loss? Very little heating for 30° J. R. Wilson

  15. Edge Ion Heating Observed Pump at 30 MHz IBW Side-bands separated by ~ fci • An innovative edge ion temperature and rotation diagnostic revealed strong edge ion heating and rotation • Parametric instability consistent with decay into IBW and Ion Quasi- mode observed - lower power threshold and robust • Edge ion can drain a significant fraction of wave power ~ 30% T. Biewer

  16. High Frequency MHDs For Alpha-physics reseach A unique super-Alfvenic physics test bed: - ITER and BPs alphas are likely to be super-Alfvenic - Achieved V NBI ion /V Alfv up to ~ 5 (100 keV NBI) and high energetic ion pressure fraction up to 50%

  17. NPA data proves that HHFW accelerates beam ions 50 Most effective is the RF Ion Acceleration above Eb, Δ E HHFW (keV) perp. acceleration 40 30 20 HHFW preferentially accelerates beam ions in the perpendicular direction 10 v || /v ~ 0.5 v || /v ~ 1.0 0 0 20 40 60 80 100 120 NPA Rtan (cm) • Comparable RF acceleration of neutral beam ions observed at E b ~ 65 keV and E b ~ 90 keV for all NB sources. • The energetic ion tails form in < 15 ms for P HHFW ~ 2 MW. • Tail decay time ~ 12 ms. S. Medley 6

  18. HHFW increases the neutron rate. Chirping causes rapid 5-25% drops • Successfully developed our target helium L-mode HHFW plasma • Early chirping (during current ramp-up) seen only for the most tangential full energy beam injection (source A, 2MW / 90 keV). • Late chirping seen in all shots. Ruskov, UCI 5

  19. HHFW suppresses MHD modes: early chirping TAEs Shows delicate dependence on velocity distribution function Note: These two shots use beams B and C with 1MW / 60KeV, and have nearly identical plasma parameters . 7

  20. Power and Particle Handling Gas Puff Imaging Divertor Camera* Fast Probe Divertor Spectroscopy Lithium Pellet Supersonic Gas Injector * N. Nishino

  21. GPI Image Orientation viewing area ≈ 25x25 cm spatial resolution ≈ 1-2 cm separatrix RF limiter Typical image Using Princeton Scientific Instruments PSI-5 camera 250,000 frames/sec @ 64 x 64 pixels/frame 300 frames/shot, 14 bit digitizer, intensified S. Zweben

  22. Simulation of NSTX Edge Shows “Blob-like” Structures Preliminary results M.V. Umansky, LLNL

  23. Fast probe provided edge density and temperarure profile n e rises faster than T e J. Boedo, UCSD

  24. Outer divertor not detached yet V. Soukhanoskii, LLNL

  25. Lithium Pellets Injection to Control Particle Recycling • Capability for injecting solid AXLE LOAD PORT FEEDTHRU pellets (<1 – 5 mg) & powder (micro-pellets) • 10 – 200 m/s radial injection • 1 – 8 pellets per discharge • 400 pellet capacity PROPELLENT PORT • Develop optimized scenarios OUTBOARD VIEW 400 BARREL TURRET Lithium vapor spreading along the center-stack Lithium Pellet moving through plasma after entering at 296ms In-board gas injector Lithium “vapor ball” surrounding pellet H. Kugel as it approaches the center-stack

  26. Supersonic gas jet penetrates well through a thick scrape-off layer CHERS camera DEGAS 2 Neutral transport modeling reproduces observed 114449 features (D. P Stotler) Preliminary fueling efficiency estimate shows ~ 3 - 4 times V. Soukhanoskii, LLNL improvement over gas puff

  27. NSTX is developing ITER/BP relevant time resolved surface deposition monitors Deposition over 4 shots 112014-017. depositi on • Quartz microbalance shows time resolved deposition on NSTX in geometry typical of a diagnostic mirror - results show significant deposition after plasma discharge. temperature • Novel electrostatic surface particle detector works well in air and vacuum environments. • First time-resolved measurements of surface dust in tokamaks. C. Skinner

  28. Solenoid-Free Start-Up - Coaxial Helicity Injection(R. Raman) - Outer poloidal field start-up

  29. Possible Improvements to the Transient CHI System • Operated reliably up to 1 kV Absorber • Produced reliable breakdown with lower gas pressure • Generated I p ~ 140 kA with I inj ~ 4 kA in a few milliseconds • Measured peaked profiles T e0 ~ 16 eV Injector Roger Raman in this meeting

  30. Solenoid-Free Start-Up Research on NSTX Begun Plasma initiation has been identified an important issue Null Size Evolution During PF-Only Start-Up (Null size: E T B T /B P >0.1kV/m) 3 OH 2.5 XP433-I 2 Null Size (m^2) XP433-II 1.5 1 XP448-I XP431 XP448-II 0.5 0 0 2 4 6 8 10 Time (msec) Successful initiations: Not successful initiations: J. Menard OH:112152, 4.5 kG XP431: H:11293, 4.5 kG Y. Takase XP433-I: 113612, 3.5 kG XP448-I: 113609, 3.5 kG M. Ono XP433-II:114405, 3 kG XP448-II:114484, 3 kG W. Choe

  31. J. Menard

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