Transcript OVERVIEW OF THE DIII-D PROGRAM AND CONSTRUCTION …

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
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OUTLINE
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Advanced Tokamak
Internal Coils (I-coils)
Electron Cyclotron System
Plasma Control System
Diagnostics
2005 – 2006 Upgrades
Conclusion
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DIII–D CAPABILITIES ALLOW A WIDE RANGE OF RESEARCH
AND TECHNOLOGY ISSUES TO BE ADDRESSED
60 different diagnostics
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MAIN RESEARCH GOAL FOR DIII–D IS THE ADVANCED
TOKAMAK, WHICH INTEGRATES MANY PHYSICS ELEMENTS
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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.
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FLEXIBLE I-COIL POWER SUPPLY CONFIGURATIONS
POSSIBLE WITH PATCH PANEL
I-COILS PROVIDE A FLEXIBLE SYSTEM
FOR 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
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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
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ECCD STABILIZATION OF NEO-CLASSICAL
TEARING MODES
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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 b increases
Mode does not reappear when b is raised above the initial stability limit
Stabilization of the 2/1 mode has also been done.
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THE LITHIUM BEAM DIAGNOSTIC USES ZEEMAN
POLARIZATION SPECTROSCOPY TO MEASURE
THE EDGE CURRENT DENSITY
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THE UPGRADED BEAM EMISSION SPECTROSCOPY (BES) DIAGNOSTIC
BRINGS NEW INSIGHT INTO CORE TURBULENCE AND MHD
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MASSIVE GAS PUFF SUCCESFULLY MITIGATES PLASMA
DISRUPTIONS
Open jet (Aug. 2003)
• Pjet (r=1) ~ 0.04 atm.
• Fast (~ 1ms) rise time
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Directed jet (Mar. 2004)
• Pjet (r=1) ~ 0.02 atm.
• Slower (~3ms) rise time.
Directed jet w/ reduced
back volume (Oct. 2004)
• Pjet (r=1) ~ 0.04 atm.
• 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 IS
KEY TO THE DIII–D AT PROGRAM
Real Time Feedback Controlled (Actuator, Sensor)
Te:
ECH,ECE
 Long experience:
NTM:
Global parameters and
ECCD, magnetics
equilibrium
Disruption:
 Recent progress:
Gas jet, magnetics,
Two-point Te control
bolometers
 Under development:
NBI
Real-time, multi-point
profile control
Plasma b:
Paux, RTEFIT
– Te(r,t): ECH, ECE,
Thomson
RWM:
C-Coil, I-Coil, RTEFIT
scattering
– j(r,t): ECCD, MSE
Equilibrium:
PF-Coils, RTEFIT
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Density:
Pellet/Cryopumps/Gas valves, CO2 Interferometers
FLEXIBLE DIII–D PLASMA CONTROL SYSTEM SUPPORTS
INTEGRATED PLASMA CONTROL
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PLANNED ECH UPGRADE DURING 2005 - 2006
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3 CPI gyrotrons have been purchased
— Delivery scheduled Jul 05 – Jan 06
— Ready for operation in May 06
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1 CPI development gyrotron will be available for DIII–D FY05
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1 Russian short pulse gyrotron will be available
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8 operating gyrotrons might be available in May 06
but only power supplies and transmission lines for 6
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LOWER DIVERTOR WILL BE MODIFIED FOR DENSITY CONTROL
OF HIGH TRIANGULARITY DOUBLE NULL DIVERTORS
Current configuration
New configuration
double null shape
New configuration
ITER shape
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A BEAMLINE REVERSAL IS NECESSARY FOR NEW PHYSICS
STUDIES AND IMPROVED PLASMA MEASUREMENTS
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QDB regime with central co-rotation
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Understanding physics of rotation
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Transport barrier control (separate ExB
and Shafranov shift effects)
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RWM stability with low rotation
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NTM stabilization with modulated rf
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Separate Er and J(r) in MSE measurement
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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)
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DIII–D LONG TORUS OPENING ACTIVITIES SCHEDULE
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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.,
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