DIII D OVERVIEW DIII D. by R.D. Stambaugh. Presented to DIII D Program Advisory Committee Meeting. January 20 21, 2000.

Transcription

1 OVERVIEW by R.D. Stambaugh Presented to Program Advisory Committee Meeting January 20 21, 2000

2 INTRODUCTION National Program 1999 DAC recommendations 1999 Research highlights Research and facility planning and FESAC goals the charge

3 THE NATIONAL FUSION TEAM LANL Columbia University University of Wisconsin University of Texas ANL Hampton University UCSD Lehigh University ORNL PPPL RPI UCB EUROPEAN COMMUNITY Joint European Torus IPP (Germany) Cadarache (France) Culham (England) Lausanne (Switzerland) KFA (Germany) FOM (Holland) Frascati (Italy) Georgia Tech RUSSIA Kurchatov Troitsk Ioffe Keldysh Moscow State GA JAPAN JAERI JT 60U JFT-2M NIFS LHD Tsukuba U. University of Alaska LLNL OTHER INTERNATIONAL KAIST (Korea) ASIPP (China) CCFM (Canada) SWIP (China) U. Alberta (Canada) U. Toronto (Canada) Chalmers U. (Sweden) Helsinki U. (Finland) U. Wales (Wales) KBSI (Korea) SINICA (China) Southwest Inst. (China) SNL Palomar College UCLA UCI MIT INEL INDUSTRY CPI Gycom CompX Orincon Creare Thermacore IR&T Surmet HiTech Metallurgical TSI Research FAR Tech PNL University of Maryland Cal Tech Johns Hopkins University University of Washington QTYUIOP RT/wj

4 LLNL CONTRIBUTES TO IN BOTH AT: (J, Er PROFILE MEASUREMENTS, CORSICA) AND DIVERTOR: (EXPERIMENTS, UEDGE) kv/m Magnetic Axis Er 315 MSE Edge MSE Toroidal Field Coils R (m) B T v b Ω α 360/ Edge Chans (δr=3.5 mm) 15 MSE 1 12 Radial Channels 45 MSE 30 Left Neutral Beam Detachment Physics in Upper Divertor New 2-D carbon TV UEDGE modeling of closed divertor Improved IRTV for Heat Flux Improved Bolometer J(r) and E r Measurements with MSE, Improved E r Corsica simulation at 2.1 T and 3 MW ECH initial final T i T e q n e n i n ith n ifast J T Experiments: Divertor shape and volume-thrust 5 Details of detachment Detailed UEDGE Benchmarking ρ J NB J BS J EC ρ q J OH Time-Dependent CORSICA Simulation Measurements in Lower Divertor 2-D Carbon Inversions Improved IRTV, DTS

5 Stability physics Co-leader (with Columbia and GA) in RWM feedback stabilization experiments Investigated stabilization of locked modes Confirmed kink-like structure of RWM's Measured halo currents during non-disruptive MHD events Confinement physics Co-leader (with GA) in ITB experiments Clarified roles of pressure/rotation profiles in ITB dynamics by /TFTR comparison Investigated plasma transport properties with pellet injection (with ORNL) Wave-plasma interaction physics Investigated internal kink instability during off-axis ECH and Alfvén instabilities during ICRF Developed theoretical model for core plasma rotation by ICRF 1999 PPPL ACCOMPLISHMENTS Implemented new diagnostics Tangential Central Thomson Scattering (with LLNL and GA) Expanded divertor neutral gas pressure gauges (with ORNL and GA) Expanded resistive wall mode saddle loop system Completed projects Procured and commissioned three power supplies for RWM feedback stabilization Designed, developed, and built remotely steerable ECH/ECCD launcher operations Procured full-time on-site chief operations engineer and RF technician Provided engineering/technician support during shutdown periods /RDS/jy

6 HIGHLIGHTS OF ORNL/ COLLABORATION IN CY99: HANDSHAKE ACROSS THE SEPARATRIX Inside launch pellet injection Strongly improved fueling efficiency Created internal transport barrier (PEP mode) with a very sharp density gradient with T i T e Induced H mode transitions at power levels 25% to 30% below the normal H mode threshold Neutral effects on transport barrier Spatially resolved neutral density measurements and modeling L-H transition power thresholds are correlated with neutrals in the shear layer Divertor spectroscopy Deuterium dynamics and flows in the SOL and divertor Impurity transport Measurements in VH mode consistent with temperature screening effects Improved confinement with radiating mantle Factor of ~2 improvement of τ E, and dramatic reduction in density fluctuations Synergism between reduction of turbulence growth-rate and E B shearing Advanced tokamak scenario modeling Off-axis ECCD scenario modeling based on experimental transport coefficients Edge stability and modeling Analysis and transport simulation of the current profile evolution during the ELMing high performmance discharge MHD stability Sawteeth in an oval and bean shape plasma to clearify the role of the Mercier stability criterion Conversion of two ICRF transmitters and 120 MHz operation

7 Research staff UCLA ROLE IN THE RESEARCH PROGRAM Onsite 3 Edward Doyle: Onsite leader, Deputy Thrust Leader for Internal Transport Barriers 3 Terry Rhodes: Correlation reflectometry, comparison with gyrokinetic codes, selforganized criticality 3 Curt Rettig: FIR scattering, ITG mode studies, high k turbulence 3 Lei Zeng: Reflectometry density profile measurement Off-site 3 Tony Peebles: Member of Executive Committee 3 Zuan Nguyen: Technical support Accomplishments At a technical level UCLA supports critical elements of the program through development and operation of a wide range of both profile and microturbulence measurement systems Scientifically, UCLA has a major role in the turbulence and transport topical area, as well as in a number of thrusts 3 Comparison of a variety of turbulence measurements with gyrocode predictions (Leboeuf, Syndora) 3 Search for evidence of ITG mode and short wavelength (high k) turbulence 3 Study of self-organized criticality, internal transport barriers, L-H transition physics, etc. UCLA EE UCLA Electrical Engineering

8 CY99 HIGHLIGHTS OF UCSD/ COLLABORATION ON BOUNDARY PLASMA TURBULENCE, FLOWS, AND DISRUPTIONS Completed probe measurements of electric field structure in attached divertor plasmas and resulting E B flows. Paper accepted in Phys. Plasmas Lett., January 2000 Completed survey of parallel flows in the divertor for attached and detached plasmas. Results published in Phys. Plasmas Completed analysis of turbulence and transport behavior in very slow L to H transitions and published results in Plasma Phys. and Contr. Fusion Analyzed plasma turbulence and transport data for avalanche and self-organized criticality behavior in L and ELM-free H modes. Presented invited paper at the Centennial Mtg of the Am. Phys. Soc. Carried out analysis of radiative rates and profiles during killer pellet disruption experiments. Made first measurements of the fast timescale radiated power behavior during disruption thermal quenches using an array of AXUV diodes Found that boronized carbon in the divertor does not contribute to the core impurity level during detached divertor experiments. Results modeled in collaboration with SNL and ANL A newly developed digital harmonic detection technique was used to measure SOL electron temperature fluctuations with a bandwidth of up to 200 khz and estimate the turbulent heat flux

9 Sandia has provided with: Two reciprocating Langmuir probes SNL COLLABORATION Dr. J.G. Watkins, SNL Physicist onsite Measure upper divertor plasma conditions with 28 new upper divertor target plate probes Temperature (ev) Density ( 10 m 3 ) 56 target plate Langmuir probes (3 shown in graphite tile) Target plate density and temperature profiles in the lower divertor R Rsep Optimize plasma performance with inner/outer leg pumping for particle control Study divertor physics issues of inner/outer leg pumping Study target erosion, redeposition, and impurity sources as part of the DiMES team Perform reciprocating probe studies (with UCSD) Te fluctuations, flow in divertor, SOL and divertor physics Collaborate with LLNL and Univ. of Toronto (Stangeby) on SOL model comparison and probe theory /rs

10 JT 60U JET MAJOR INTERNATIONAL COLLABORATIONS Advanced Tokamak (AT) scenarios edge stability and pedestal, high density operation, divertor modeling, ECH and ECCD Optimized shear, neoclassical tearing modes, RI mode experiments ASDEX (AUG) Neoclassical tearing modes, edge physics, transport comparisons TEXTOR RI mode Russia Theory, participation in experiments, modeling of dynamic operational scenarios China Participation in experiments KSTAR Development and design of AT scenarios, diagnostic/device interface /KHB/wj

11 RESPONSE TO 1999 PROGRAM ADVISORY COMMITTEE RECOMMENDATIONS 1999 Membership R. Hazeltine (U. Texas), Chair C. Baker (UCSD) J. Drake (U. Maryland) R. Fonck (U. Wisconsin) R. Hawryluk (PPPL) S. Ishida (JAERI) M. Mauel (Columbia U.) J. Neuhauser (AUG) W. Nevins (LLNL) G. Vlases (U. Washington) M. Watkins (JET) S. Wolfe (C Mod) Meeting February 8 9, 1999 Positive on 1998 results and three-year plan Recommendations Develop better AT metrics 3 Snowmass, SEAB, FESAC,... Improve milestones 3 Improved with FFCC Assess core impurities with internal transport barriers 3 M. Wade, Helium Workshop 10/99 Improve understanding of off-axis ECCD efficiency 3 T. Luce PRL paper More emphasis on edge ELM/kink control of NCS discharges 3 J. Ferron invited APS 3 Initiating edge current profile diagnostics

12 HIGHLIGHTS OF THE 1999 PLASMA PHYSICS RESEARCH PROGRAM ON THE TOKAMAK Good progress on our primary advanced tokamak scenario (β N H 89P ~ 9 for 2 s) First results using smart conducting shells around the plasma to increase plasma stability Increased physics understanding of edge and internal plasma instabilities, gained through new and more precise measurements and theoretical modeling A scientific basis for the choice of the optimum shape of the plasma Detailed exploration of the so-called transport barriers responsible for the remarkable radial regions of super quality heat insulation, including the variety of the phenomena and the implications of the theoretical model Exciting new work probing building better heat insulation using impurity atoms New discoveries of high confinement quality plasmas with steady-state potential and high confinement quality at unusually high densities Studies of transport fundamentals seeking to show whether transport arises from many small events like a dust storm or more infrequent large events like avalanches Visual reconstruction of edge-plasma turbulence from plasma fluctuation measurements

13 β N H89p IN 1999 SIGNIFICANT IMPROVEMENT IN LONG-PULSE ADVANCED TOKAMAK PERFORMANCE HAS BEEN ACHIEVED Future emphasis is on increasing the duration of high performance and increasing the fraction of bootstrap current β N H = 9 for 16 τ E DIII-D Advanced Tokamak Target Progress Conventional Tokamak τ duration /τ E ARIES-RS β N 4 l i H 89 β N H 89 P NBI I P D α 2 s 1.2 MA 11 MW f bs = ~ 50% ARIES-RS SSTR ARIES-RS SSTR ARIES-RS SSTR Time (ms)

14 EXPERIMENT PLANNING PROCESS FOR 2000 September Year-End Review of 99 Campaign September Research Council set thrusts for 2000 Campaign Proposals solicited for Brainstorming Meeting October Brainstorming Meeting ~200 Proposals November Proposals collected into and prioritized by thrust and topical area groups December 14 Thrust and topical area plans and runtime presented to Research Council December Deputy Director for Research, with advice of RC, allocated runtime on target for scheduled Feb. 7 startup

15 RUN TIME ALLOCATIONS FOR THE 2000 EXPERIMENT CAMPAIGN No. Acronym Day Plan Day Plan 1 Edge stability 6 2 Advanced Tokamak scenario Neoclassical tearing mode 3 4 Resistive wall mode Optimum edge 9 6 High l i 0 7 Internal transport barrier Advanced Tokamak divertor 8 9 Electron cyclotron systems 6 Thrust totals Stability topical area 2 6 Confinement topical area Boundary topical area 5 5 Heating and current drive topical area 3 0 Topical area sum Percentage of total days Contingency Sum 73 69

16 RESEARCH PLANNING GENERALLY CAN FORESEE 2 3 YEARS OF RESEARCH AHEAD OF US Year 2000 Runtime Allocation to Highest Priority Thrust and Topical Area Needs Additional/contingency highest priority requests from thrust and topical areas Brainstorming submissions not included in either category above Request from three thrusts allocated no time and fast wave research Edge stability Neoclassical tearing modes High l i Fast wave Total estimated backlog 55 Days 40 Days 115 Days 30 Days Days 2 3 years

17 THE 2000 ADVANCED TOKAMAK RESEARCH THRUSTS FOR INTERNAL TRANSPORT BARRIER PHYSICS RESISTIVE WALL MODE FEEDBACK AT DIVERTOR RWM STABILIZATION AT AND RADIATIVE DIVERTOR OPTIMAL MODE SPECTRUM ITB AT LARGE RADIUS ADVANCED METHODS HIGH BOOTSTRAP FRACTION ADVANCED TOKAMAK (INTERMEDIATE SCENARIOS) SUSTAIN OPTIMIZE MODERATE PULSE ADVANCED TOKAMAK FESAC ASSESS- MENT ECH/ECCD VALIDATION EDGE STABILITY STUDIES NEOCLASSICAL TEARING- AFFECT MODE EDGE STABILITY CONTROL NTM-CONTROL MODE GROWTH NTM-STABILIZE MODE HIGH l i SCENARIO PHYSICS INTERMEDIATE SCENARIO DEMONSTRATION /RDS/rs

18 ADVANCED TOKAMAK 5 YEAR RESEARCH PLAN Physics Development β N H 89 ~9 for 2s (16τ E ) ITB Physics Edge Stability Neoclassical Tearing Resistive Wall Mode AT Divertor ECCD Physics Validation Physics Integration Integrated long duration scenarios (10 seconds) with high normalized beta, confinement enhancement, bootstrap fraction, and radiative divertor Increased stability limits Use and optimization of transport barriers at high beta Non-inductive current sustainment with high bootstrap current fraction Divertor power and particle control Progress Checkpoint FESAC Checkpoint CY Operation Periods Current Drive (EC) Fueling and Edge Control Resistive Wall Mode Control Diagnostics Other Options Inside launch pellet Upper Divertor Divertor Improvement Central Thomson 6 Coil Feedback 4 Gyrotrons Upper Divertor Diagnostics 6 Gyrotrons 8 Gyrotrons 9.5 MW Long Pulse Edge J(r) 18 Coil Feedback Electron Transport 3-D Equilibrium Counter NBI Liquid Jet In-vessel wall stabilization systems Diagnostics = Completed = Planned = Option /RDS/rs

19 THE FUTURE OF THE EC PROGRAM ON IS THE (1 MW) 10 S TUBES NOW BEING DELIVERED BY CPI AND THE (1.5 MW) TUBE BEING DEVELOPED BY THE VIRTUAL LABORATORY FOR TECHNOLOGY Scarecrow diamond window 110 GHz gyrotron 550 kw, 10 s at CPI RDS/rs

20 CY99 Katya 2 s Dorothy Boris Natasha 0.7 MW, 2 s 0.7 MW, 2 s 0.7 MW, 2 s 0.7 MW, 1 s EC SYSTEM PLAN CY00 CY01 CY02 CY03 CY04 10 s Toto Scarecrow 0.7 MW, 10 s 1.0 MW, 10 s Tin Man Lion 1.0 MW, 10 s 1.0 MW, 10 s CPI #4 LP CPI #5 LP 1.0 MW, 10 s 1.0 MW, 10 s VLT #1 VLT #2 VLT #3 1.5 MW, 10 s 1.5 MW, 10 s 1.5 MW, 10 s Nominal Tube Power Power into Plasma (MW) /RDS/jy

21 NEW CRYOPUMP AND BAFFLE STRUCTURE ADDED TO UPPER DIVERTOR REGION /RDS/jy

22 THE OVERALL MISSION OF THE PROGRAM IS To establish the scientific basis for the optimization of the tokamak approach to fusion energy production. Working with the Research Council, this mission has been elaborated in three additional research goal statements: 1. The Program s primary focus is the Advanced Tokamak Thrust that seeks to find the ultimate potential of the tokamak as a magnetic confinement system 2. Where it has unique capabilities, the Program will undertake the resolution of key enabling issues for advancing various magnetic fusion energy concepts 3. The Program will advance the science of magnetic confinement on a broad front, utilizing its extensive facility and national team research capability

23 FESAC FIVE-YEAR GOALS FESAC Goal 1: Advance fundamental understanding of plasma, the fourth state of matter, and enhance predictive capabilities, through comparison of experiments, theory and simulation Turbulence and Transport: Advance understanding of turbulent transport to the level where theoretical predictions are viewed as more reliable than empirical scaling in the berst understood systems Macroscopic Stability: Develop detailed predictive capability for macroscopic stability, including resistive and kinetic effects Wave-Particle Interactions: Develop predictive capability for plasma heating, flow and currrent drive, as well as energetic particle driven instabilities, in power-plant relevant regimes Multi-Phase Interfaces: Advance the capability to predict detailed multiphase plasma-wall interfaces at very high power- and particle-fluxes FESAC Goal 2: Resolve outstanding scientific issues and establish reducedcost paths to more attractive fusion energy systems by investigating a broad range of innovative magnetic confinement configurations

24 FESAC FIVE-YEAR GOALS (Continued) FESAC Goal 3: Advance understanding and innovation in highperformance plasmas, optimizing for projected power-plant requirements; and participate in a burning plasma experiment Assess profile control methods for efficient current sustainment and confinement enhancement in the Advanced Tokamak, consistent with efficient divertor operation, for pulse length >> τ E Develop and assess high-beta instability feedback control methods and disruption control/amelioration in the Advanced Tokamak, for pulse length >> τ E FESAC Goal 4: Develop enabling technologies to advance fusion science; pursue innovative technologies and materials to improve the vision for fusion energy; and apply systems analysis to optimize fusion development

25 FESAC HIGHEST LEVEL MAPPING Goals Science 1. FESAC Goals Fundamental Understanding 2. Reduced cost path... attractive... innovative Advanced Tokamak 3. Understanding and innovation in high Performance plasmas, optimizing... burning plasma Fusion Energy 4. Enabling technologies... improve the vision /RDS/jy

26 AND FESAC GOAL #1 1 Advance fundamental understanding... through comparison of well-diagnosed experiments, theory, and simulation FESAC Sub-Goals Turbulence and transport Macroscopic stability Wave-particle interaction Multi-phase interface Topical Science Areas Confinement Macroscopic stability Heating and current drive Boundary Research Thrusts Internal transport barrier Edge stability Neo classical tearing mode Resistive wall mode ECH validation Optimum edge AT divertor validation AT scenario /RDS/jy

27 AND FESAC GOAL #3 3 Advance understanding and innovation in high performance plasmas, optimizing for projected power-plant requirements Advanced Tokamak High beta instability feedback AT scenario Optimum edge Internal transport barrier AT divertor validation ECH validation Edge stability Neo classical tearing mode Resistive wall mode Advanced Tokamak Thrusts Topical Science Areas Confinement Macroscopic stability Heating and current drive Boundary /RDS/jy

28 FESAC GOAL 2 Goal: Resolve outstanding scientific issues and establish reduced-cost paths to more attractive fusion energy systems by investigating a broad range of innovative magnetic confinement configurations The Advanced tokamak vision of the ultimate potential of the tokamak is a new and innovative magnetic confinement configuration. Studies have shown that these modes, if realized, can halve the cost of electricity in tokamak fusion power systems research elements of generic value across magnetic confinement concepts: Micro-turbulence suppression Wall stabilization Energetic particle density gradient driven instabilities Current drive by waves and beams Parallel field line physics

29 FESAC GOAL 4 Goal: Develop enabling technologies to advance fusion science; pursue innovative technologies and materials to improve the vision for fusion energy; and apply systems analysis to optimize fusion development The will deploy, and thereby foster, the development of a number of enabling and innovative technologies: Advanced methods for plasma heating and current drive (microwave ECRF) Disruption mitigation by solid, liquid, or gas injection Plasma fueling (inside pellet launch) Plasma flow control (neutral beam, ECRF, ICRF) Investigation of novel divertor concepts Feedback technologies for wall stabilization Studies of surface erosion Small-sample testing of low activation materials in plasma environment