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OVERVIEW OF THE DIII–D PROGRAM AND CONSTRUCTION PLANS. Presented by Peter I. Petersen for the DIII–D Team. 23rd Symposium on Fusion Technology 20 - 24 September 2004 - Fondazione Cini, Venice, Italy. 214-04/jy. OUTLINE. Advanced Tokamak Internal Coils (I-coils)
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OVERVIEW OF THE DIII–D PROGRAM AND CONSTRUCTION PLANS Presented by Peter I. Petersen for the DIII–D Team 23rd Symposium on Fusion Technology 20 - 24 September 2004 - Fondazione Cini, Venice, Italy 214-04/jy
OUTLINE • Advanced Tokamak • Internal Coils (I-coils) • Electron Cyclotron System • Plasma Control System • Diagnostics • 2005 – 2006 Upgrades • Conclusion 214-04/jy
DIII–D CAPABILITIES ALLOW A WIDE RANGE OF RESEARCH AND TECHNOLOGY ISSUES TO BE ADDRESSED 60 different diagnostics 214-04/jy
MAIN RESEARCH GOAL FOR DIII–D IS THE ADVANCEDTOKAMAK, WHICH INTEGRATES MANY PHYSICS ELEMENTS 214-04/jy
TOOLS TO MINIMIZE ERROR FIELDS AND RESISTIVE WALL MODES AT HIGH PLASMA PRESSURE • 6 section, external C-coil • 12 section, internal I-coil • 5 C-supplies each @5 kA, 350 V or 7kA at lower voltage tap • 4 Switching Power Amplifiers (SPAs) each @5 kA, 300 V, ~ 4 - 5 s System must provide for both correction of error fields and feedback stabilization of the RWM. 214-04/jy
FLEXIBLE I-COIL POWER SUPPLY CONFIGURATIONSPOSSIBLE WITH PATCH PANEL
I-COILS PROVIDE A FLEXIBLE SYSTEMFOR ELM CONTROL N=3 mode Small islands might be responsible for the ELM suppression Relative small impact on core confinement Enhance magnetic and density fluctuations with no indication of increased stochasticity 214-04/jy
CURRENT ECH SYSTEM ECH System Layout Gyrotron in stand ECH launcher 3 CPI gyrotrons with diamond window, 1 MW 10 s 3 Gycom gyrotrons with boron nitride window, 0.75 MW 2 s 1 MW ECH waveguide 214-04/jy
ECCD STABILIZATION OF NEO-CLASSICALTEARING MODES • Feedback system adjusts q=3/2 surface location to minimize mode amplitude • Active tracking keeps ECCD at the q = 3/2 surface in the absence of the mode • compensates for the Shafranov shift as the plasma pressure bincreases • Mode does not reappear when b is raised above the initial stability limit • Stabilization of the 2/1 mode has also been done. 214-04/jy
THE LITHIUM BEAM DIAGNOSTIC USES ZEEMANPOLARIZATION SPECTROSCOPY TO MEASURETHE EDGE CURRENT DENSITY 214-04/jy
THE UPGRADED BEAM EMISSION SPECTROSCOPY (BES) DIAGNOSTIC BRINGS NEW INSIGHT INTO CORE TURBULENCE AND MHD 214-04/jy
MASSIVE GAS PUFF SUCCESFULLY MITIGATES PLASMA DISRUPTIONS Open jet (Aug. 2003) Directed jet (Mar. 2004) Directed jet w/ reduced back volume (Oct. 2004) • Pjet (r=1) ~ 0.04 atm. • Pjet (r=1) ~ 0.02 atm. • Pjet (r=1) ~ 0.04 atm. • Fast (~ 1ms) rise time • Slower (~3ms) rise time. • Medium (~ 2ms) rise. • Experiments show significant (2-3x) reduction in halo currents and divertor heat • loads (over VDE disruption). • Large (4x) variation in thermal quench time with gas jet pressure indicates that jet • design plays important role. • No observed runaway electron generation (except in low pressure Ar gas puff).
INTEGRATED PLASMA CONTROL ISKEY TO THE DIII–D AT PROGRAM Real Time Feedback Controlled (Actuator, Sensor) • Long experience: Global parameters and equilibrium • Recent progress:Two-point Te control • Under development:Real-time, multi-point profile control • Te(r,t):ECH, ECE, Thomson scattering • j(r,t):ECCD, MSE • … Te: ECH,ECE NTM:ECCD, magnetics Disruption:Gas jet, magnetics, bolometers NBI Plasma b:Paux, RTEFIT RWM:C-Coil, I-Coil, RTEFIT Equilibrium:PF-Coils, RTEFIT Density:Pellet/Cryopumps/Gas valves, CO2 Interferometers
FLEXIBLE DIII–D PLASMA CONTROL SYSTEM SUPPORTS INTEGRATED PLASMA CONTROL 214-04/jy
PLANNED ECH UPGRADE DURING 2005 - 2006 • 3 CPI gyrotrons have been purchased • — Delivery scheduled Jul 05 – Jan 06 • — Ready for operation in May 06 • 1 CPI development gyrotron will be available for DIII–D FY05 • 1 Russian short pulse gyrotron will be available • 8 operating gyrotrons might be available in May 06 • but only power supplies and transmission lines for 6 214-04/jy
LOWER DIVERTOR WILL BE MODIFIED FOR DENSITY CONTROL OF HIGH TRIANGULARITY DOUBLE NULL DIVERTORS New configuration double null shape New configuration ITER shape Current configuration 214-04/jy
A BEAMLINE REVERSAL IS NECESSARY FOR NEW PHYSICSSTUDIES AND IMPROVED PLASMA MEASUREMENTS • QDB regime with central co-rotation • Understanding physics of rotation • Transport barrier control (separate ExB and Shafranov shift effects) • RWM stability with low rotation • NTM stabilization with modulated rf • Separate Er and J(r) in MSE measurement 214-04/jy
OTHER DIII–D UPGRADES Two Cooling Tower (replace old ones) Beltbus (upgrade to 10 s) 12 audio amplifiers to stabilize RWMs 2 shown on this picture Upgrade 2 Toroidal Field Circuit Diodes (1 shown) (upgrade to 10 s) 214-04/jy
OTHER DIII–D/GA PAPERS P3C-A-72 OVERVIEW OF THE DIII–D PROGRAM AND CONSTRUCTION PLANS* PETERSEN, P.I. Selected also for oral presentation O3B-A-72 P3T-B-78 THE UPGRADE OF THE DIII-D EC SYSTEM USING 120 GHZ ITER GYROTRONS CALLIS, R.W. P3T-B-246 ECH MW-LEVEL CW TRANSMISSION LINE COMPONENTS SUITABLE FOR ITER OLSTAD, R.A P3C-C-77 HIGH PERFORMANCE INTEGRATED PLASMA CONTROL IN DIII–D* HUMPHREYS, D.A. P3C-C-79 PROGRESS TOWARDS ACHIEVING PROFILE CONTROL IN THERECENTLY UPGRADED DIII-D PLASMA CONTROL SYSTEM* PENAFLOR, B.G P3C-C-149 DIII-D INTEGRATED PLASMA CONTROL TOOLS APPLIED TO NEXT GENERATION TOKAMAKS* LEUER, J.A P2C-D-80 REAL-TIME MULTIPLE NETWORKED VIEWER CAPABILITY OFTHE DIII-D EC DATA ACQUISITION SYSTEM* PONCE, D. P2T-E-81 OVERVIEW OF THE DIII–D INTERNAL RESISTIVE WALL MODE STABILIZATION POWER SUPPLY SYSTEM* SZYMANSKI, D.D P4T-G-71 STRUCTURAL UPGRADE OF IN-VESSEL CONTROL COIL ON DIII D* ANDERSON, P.M. P2C-D-251 ADVANCES IN REMOTE PARTICIPATION FOR FUSION EXPERIMENTS* SCHISSEL, D.P Selected also for oral presentation O2B-D-251 P1C-H-467 EVALUATION OF SUPER CRITICAL HELIUM AS A COOLANT FOR DIII-D TYPE CRYOCONDENSATION BAXI, C.B., 214-04/jy