System Upgrades to the DIII-D Facility

Similar documents
Presented by Rob La Haye. on behalf of Francesco Volpe. at the 4 th IAEA-TM on ECRH for ITER

Status Alcator C-Mod Engineering Systems. DoE Quarterly Review October 27, 2005

Active Control for Stabilization of Neoclassical Tearing Modes

Technical Readiness Level For Plasma Control

RF Physics: Status and Plans

Recent progress of 170 GHz Gyrotron in KSTAR

INITIAL RESULTS FROM THE MULTI-MEGAWATT 110 GHz ECH SYSTEM FOR THE DIII D TOKAMAK

RF Heating and Current Drive in the JT-60U Tokamak

ICRF Physics in KSTAR Steady State

Toroidal Rotation and Ion Temperature Validations in KSTAR Plasmas

Increased Stable Beta in DIII D by Suppression of a Neoclassical Tearing Mode Using Electron Cyclotron Current Drive and Active Feedback

Overview of ICRF Experiments on Alcator C-Mod*

NTM Suppression and Avoidance at DIII-D Using Real-time Mirror Steering of ECCD

Experimental results and Upgrade plan of ECH/CD system in KSTAR

Dust Measurements With The DIII-D Thomson system

Design study for JT-60SA ECRF system and the latest results of JT-60U ECRF system

DIII D Quiescent H-Mode Experiments with Co Plus Counter Neutral Beam Injection

Operational progress of 170GHz 1MW ECH system in KSTAR

National Fusion Research Institute a. Princeton Plasma Physics Laboratory

Development of C-Mod FIR Polarimeter*

Magnetics and Power System Upgrades for the Pegasus-U Experiment

Gyung-Su Lee National Fusion R & D Center Korea Basic Science Institute

Advanced Density Profile Reflectometry; the State-of-the-Art and Measurement Prospects for ITER

Abstract. G.D. Garstka 47 th APS-DPP Denver October 27, Pegasus Toroidal Experiment University of Wisconsin-Madison

GA A25836 PRE-IONIZATION EXPERIMENTS IN THE DIII-D TOKAMAK USING X-MODE SECOND HARMONIC ELECTRON CYCLOTRON HEATING

GA A24030 ECE RADIOMETER UPGRADE ON THE DIII D TOKAMAK

Diagnostic development to measure parallel wavenumber of lower hybrid waves on Alcator C-Mod

Conceptual Design of Magnetic Island Divertor in the J-TEXT tokamak

Physics, Technologies and Status of the Wendelstein 7-X Device

Electromagnetic Field Simulation for ICRF Antenna and Comparison with Experimental Results in LHD

Evaluation of a Field Aligned ICRF Antenna in Alcator C-Mod

Design of the COMPASS Upgrade Tokamak

Abstract. *Supported by U.S. DoE grant No. DE-FG02-96ER Pegasus Toroidal Experiment University of Wisconsin-Madison

Real-time Systems in Tokamak Devices. A case study: the JET Tokamak May 25, 2010

Initial Active MHD Spectroscopy Experiments Exciting Stable Alfvén Eigenmodes in Alcator C-Mod

GA A22963 RECENT DEVELOPMENTS ON THE HIGH POWER ECH INSTALLATION AT THE DIII D TOKAMAK

Development of the 170GHz gyrotron and equatorial launcher for ITER

Improved core transport triggered by off-axis ECRH switch-off on the HL-2A tokamak

GA A24691 STATUS OF THE ELECTRON CYCLOTRON HEATING SYSTEM ON DIII D

Active beam-based diagnostics in KSTAR

ICRF Operation with Improved Antennas in a Full W-wall ASDEX Upgrade, Status and Developments

3.10 Lower Hybrid Current Drive (LHCD) System

Sustainment and Additional Heating of High-Beta Field-Reversed Configuration Plasmas

RECENT UPGRADES AND EXTENSIONS OF THE ASDEX UPGRADE ECRH SYSTEM

TOROIDAL ALFVÉN EIGENMODES

The Compact Toroidal Hybrid A university scale fusion experiment. Greg Hartwell

Advanced Tokamak Program and Lower Hybrid Experiment. Ron Parker MIT Plasma Science and Fusion Center

EX/P9-5. Comprehensive Control of Resistive Wall Modes in DIII-D Advanced Tokamak Plasmas

Status of C-Mod Diagnostics. Presented by Jim Irby For the C-Mod Group

Feedback control of ECRH for MHD mode stabilization on TEXTOR

Field Aligned ICRF Antenna Design for EAST *

First Results From the Alcator C-Mod Lower Hybrid Experiment.

GA A26495 PHYSICS OPERATIONS WITH THE DIII-D PLASMA CONTROL SYSTEM

Importance of edge physics in optimizing ICRF performance

SUPPRESSION OF NEOCLASSICAL TEARING MODES IN THE PRESENCE OF SAWTEETH INSTABILITIES BY RADIALLY LOCALIZED OFF-AXIS

Neoclassical Tearing Mode Control with ECCD and Magnetic Island Evolution in JT-60U

Fast Electron Temperature Diagnostic Based on Langmuir Probe Current Harmonic Detection on D-IIID

Observation of Toroidal Flow on LHD

Locked-mode avoidance and recovery without external momentum input using Ion Cyclotron Resonance Heating

Wall Conditioning Strategy for Wendelstein7-X. H.P. Laqua, D. Hartmann, M. Otte, D. Aßmus

Novel Vacuum Vessel & Coil System Design for the Advanced Divertor Experiment (ADX)

EXW/10-2Ra. Avoidance of Disruptions at High β N in ASDEX Upgrade with Off-Axis ECRH

Instrumentation Development for a Novel Local Electric and Magnetic Field Fluctuation Diagnostic

Lower Hybrid. Ron Parker Alcator C-Mod PAC Meeting January January 2006 Alcator C-Mod PAC Meeting 1

Laser-Produced Sn-plasma for Highvolume Manufacturing EUV Lithography

Poloidal Transport Asymmetries, Edge Plasma Flows and Toroidal Rotation in Alcator C-Mod

Investigation of ion toroidal rotation induced by Lower Hybrid waves in Alcator C-Mod * using integrated numerical codes

DEVELOPMENT OF MULTIVARIABLE CONTROL TECHNIQUES FOR USE WITH THE DIII D PLASMA CONTROL SYSTEM

Development Status of KSTAR LHCD System

Initial Results from the C-Mod Prototype Polarimeter/Interferometer

Abstract. heating with a HHFW RF system has begun. This system supplies bulk T(e) heating with

High Performance Computing for Plasma Control

PRESENT STATUS OF THE NEW MULTI-FREQUENCY ECRH SYSTEM FOR ASDEX UPGRADE

Effect of Resonant and Non-resonant Magnetic Braking on Error Field Tolerance in High Beta Plasmas

GA A25780 STABILIZATION OF NEOCLASSICAL TEARING MODES IN TOKAMAKS BY RADIO FREQUENCY CURRENT DRIVE

Profile Scan Studies on the Levitated Dipole Experiment

Abstract. PEGASUS Toroidal Experiment University of Wisconsin-Madison

PERFORMANCE OF THE 110 GHz SYSTEM ON THE DIII D TOKAMAK

Density and temperature maxima at specific? and B

High Field Side Lower Hybrid Current Drive Launcher Design for DIII-D

Edge radiation control in stochastic magnetic field and with RMP application in LHD

High Rep-Rate KrF Laser Development and Intense Pulse Interaction Experiments for IFE*

GA A26816 DESIGNS OF NEW COMPONENTS FOR ITER ECH&CD TRANSMISSION LINES

GA A22776 THE DESIGN AND PERFORMANCE OF WAVEGUIDE TRANSMISSION LINE COMPONENTS FOR PLASMA ELECTRON CYCLOTRON HEATING (ECH) SYSTEMS

Study of Elliptical Polarization Requirement of KSTAR 84-GHz ECH System

2. Composing and characteristics of EAST

Experiments with real-time controlled ECW

IAEA-CN-94/FT/2-2 Test Results on Systems Developed for SST-1 Tokamak

GA A23281 EXTENDING DIII D NEUTRAL BEAM MODULATED OPERATIONS WITH A CAMAC BASED TOTAL ON TIME INTERLOCK

PLASMA BUILD-UP and CONFINEMENT IN URAGAN-2M DEVICE

A REGULATED POWER SUPPLY FOR THE FILAMENTS OF A HIGH POWER GYROTRON

ICRF Mode Conversion Flow Drive Studies with Improved Wave Measurement by Phase Contrast Imaging

ECRF Heating on CS Reactors

Selected highlights of ECH/ECCD physics studies in the TCV tokamak

AN IN-LINE POWER MONITOR FOR HE11 LOW LOSS TRANSMISSION LINES

CT-7Ra Development of Gyrotron and JT-60U EC Heating System for Fusion Reactor

FaDiS, a Fast Switch and Combiner for High-power Millimetre Wave Beams

TOKAMAK T-15MD: experience of scientific and technical project realization in RUSSIA

THE 110 GHz MICROWAVE HEATING SYSTEM ON THE DIII D TOKAMAK

Study of Plasma Equilibrium during the AC Current Reversal Phase on the STOR-M Tokamak

Transcription:

System Upgrades to the DIII-D Facility A.G. Kellman for the DIII-D Team 24th Symposium on Fusion Technology Warsaw, Poland September 11-15, 2006

Upgrades Performed During the Long Torus Opening (LTOA) Significantly Enhance The DIII-D Facility Capability Lower Divertor Modification Rotation of neutral beam line from co- to counter injection Upgraded Resistive Wall Mode Stabilization system Upgraded Electron Cyclotron System Reduced error field of Toroidal Field feedpoint Improved cooling of TF return bus for longer pulse operation Expanded Diagnostic Set New cooling towers, transformers for 10 sec full power operation

New Lower Divertor with Extended Shelf Has Been Installed for Pumping High Triangularity Double Null Discharges Contoured Tile Faces No Bolt Holes in High Heat Flux Areas Pumping Aperture Extended Divertor Shelf DESIGN FEATURES: 316 SS, water cooled, low gas leakage to main chamber, no bolt holes in high heat flux areas, contoured tiles

Tile Design of New Lower Divertor Improves Toroidal Symmetry and Reduces Material Erosion New design features Reduced gaps between tiles Improved alignment of tiles Elimination of bolt holes in high heat flux area Clear reduction in toroidal asymmetries in tile heating

New Lower Divertor Has Improved Density Control in Double Null, Advanced Tokamak Plasmas Measured pumping speed of lower pump is S~35,000 l/s Effective pumping speed is reduced ~50% by the restrictive conductance under the shelf S~18,000 l/s In high triangularity balanced double nulls, the lower pump provides 50% additional pumping over the upper two pumps. Balanced Double Null

Rotation of Neutral Beam Enables Both Co and Counter Injection and Provides Significant New Research Capability ENABLES Physics at low rotation, more ITER relevant Physics of Rotation, NBCD RWM stability at low rotation NTM stabilization with modulated ECCD Transport barrier control Fast ion distribution control DIAGNOSTICS Co plus counter viewing MSE, J(ρ) and Er with high resolution Co plus counter CER, improved poloidal and toroidal rotation

Many Experiments Have Utilized 4 MW of Counter NBI for Physics Studies Example: Applying 4 MW counter NBI in otherwise constant conditions results in: Sustained toroidal rotation near zero across entire profile Modest reduction in plasma confinement P (MW) Co-NBI km/s

Simultaneous Feedback Control of Stored Energy and Rotation Velocity Have Been Achieved Feedback system adjusts mix of co and counter beams to provide required power and torque input. PID algorithm adjusts duty cycle of modulated neutral beams to enable smooth variation of energy and rotation

Co/Counter Injection Has Enabled ITER Relevant (low rotation) RWM Stabilization Research NB rotation control has shown that threshold for RWM stabilization is at lower rotation than previous observations. β n sustained above no-wall stability limit at very low rotation. RWM Feedback System Upgrades have further enhanced research High bandwidth amplifier system enlarged from 6 to 12 (10 kw each). 24 amplifiers in Fall 06. Feedback delay time reduced to 50 µs. CPU cycle time reduced from 50 to 11 µs.

Upgraded EC System Will Provide Additional Power and Pulse Length for Enhanced Off-Axis Current Control Narrow beam sweeping in collector led to excessive heat loads and vacuum leaks in 2 earlier gyrotrons Upgrade adds 3 new long pulse gyrotrons (6 MW total) First replacement gyrotron fully operational (1 MW, l0 s) Developmental Depressed collector 1.2 MW gyrotron installed and ready for testing Broader sweeping at a higher frequency (5 Hz) reduced loads by 40% and increased expected lifetime to 50,000, 5 s pulses

New Toroidal Field Feedpoint Significantly Reduced Magnetic Error Fields TF Feedpoint was rebuilt to avoid rotated beamline port. New connections reduce error fields associated with old TF feedpoint by a factor of 10. Feed conductors changed from dipole to quadrupole Missing dipole field added back in this new design. Reduced field error has had a significant favorable impact on DIII-D experiments Expanded DIII-D operating space to lower density w/o locked modes Reduced external torque aids in formation of low rotation plasmas

Addition of cooling plates to TF bus will double the long pulse capability of TF system Water Cooled copper plates were added to TF bundle-tobundle connections (55% complete) Uncooled conductor temperature ratchets up during day Temp o C Time Cooled conductors return to base temperature after each shot

Significant New Measurement Capability Will Be Available Following the LTOA New Capability *MSE ( j(ρ)) counter viewing CER (T i,ω) counter viewing BES (δn) double high-sensitivity channels *SXR poloidal array MDS, under shelf spectral views MIMES (midplane) ITER Relevant Diagnostics B-Stark - B and B θ /B T Quartz microbalance Fast ion diagnostics Mirror testing Improved Capability FIR Scattering ECE Radiometer Langmuir Probes-floor Recycling camera Filterscope views Fast framing camera Divertor Thomson scattering Reflectometer Interferometer *will be completed in Oct. 06

Significant New Diagnostic Capabilities Have Been Added New Capability *MSE ( j(ρ)) counter viewing CER (T i,ω) counter viewing BES, (δn) double high-sensitivity channels *SXR poloidal array MDS, under shelf spectral views MIMES (midplane) ITER Relevant Diagnostics B-Stark - B and B θ /B T Quartz Microbalance Fast ion diagnostics Mirror testing Redesigned Poloidal arrays with flexible filter wheel will bring new capabilities for stability studies, including disruption characterization

Additional Facility Upgrades will Expand Capabilities of DIII-D 138kV to 12.47kV Transformer for Auxiliary Heating 12.47kV to 4160V Transformer for MG#2 Motor Two new cooling towers can handle expected heat loads for long pulse with auxiliary heating FWCD antenna fitted with double-layer Faraday shield to investigate antenna rf voltage standoff during ELMs

Major Upgrades Installed During the LTOA Significantly Enhance DIII-D Capabilities Many significant upgrades were completed during the recent LTOA: New lower divertor, counter injection neutral beam, new diagnostic systems, upgraded RWM feedback system, new long pulse gyrotron, cooling towers. New systems enhance the ability of DIII-D to address issues critical to ITER, to pursue Advanced Tokamak studies, and to advance basic fusion research. These systems are now operational and have been used successfully in the recent 12 week campaign.

ELM Suppression Using n=3 RMPs in the ITER Shape and Collisionality Enabled by New Lower Divertor However, ELM control lost when rotation reduced by counter injection

Significant New Measurement Capability Will Be Available Following the LTOA New Capability *MSE, counter viewing CER, counter viewing BES, double high-sensitivity channels *SXR poloidal array MDS, under shelf spectral views MIMES (midplane) ITER Relevant Diagnostics B-STARX - B and B θ /B T Quartz microbalance Fast ion diagnostics mirror testing Complete installation in October Stark Splitting of Dα provides B and Bθ/BT Potentially easier to implement on ITER

Pumped Double Null Allows Significantly Higher Sustained Performance than Pumped Single Null Sustained higher β operation is demostrated Higher confinement quality is obtained at higher β Both shapes yield fusion fusion gain parameters at or above the ITER steady-state target Density control from new divertor enables better ECCD efficiency

NTM Control System Upgraded to Enable Gyrotron Modulation Detection algorithm extracts mode frequency and phase from Fourier analysis of midplane prove array After initial calculation period, algorithm identifies ~constant frequency, time-varying phase Command to dedicated cpu produces modulation signal for gyrotrons phase locked to island at ECCD location Initial calculation period Time-varying phase command ECCD power synchronized with island

Significant New Measurement Capability Will Be Available Following the LTOA New Capability *MSE, counter viewing CER, counter viewing BES, double high-sensitivity channels *SXR poloidal array MDS, under shelf spectral views MIMES (midplane) ITER Relevant Diagnostics B-Stark - B and B θ /B T Quartz microbalance Fast ion diagnostics Mirror testing 20 New shelf and Floor Langmuir probes Modular design for easy installation

Significant New Measurement Capability Will Be Available Following the LTOA New Capability *MSE, counter viewing CER, counter viewing BES, double high-sensitivity channels *SXR poloidal array MDS, under shelf spectral views MIMES (midplane) QMB ITER Relevant Diagnostics B-Stark - B and B θ /B T Quartz Microbalance Fast ion diagnostics Mirror testing Quartz Microbalance measures material deposition (e.g. Carbon) in real time 2 locations installed near lower inner corner tile