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Device schedules / Programme Elements in 2005 compiled by O. Gruber

Operations. Engineering Break. Restart. Device schedules / Programme Elements in 2005 compiled by O. Gruber 3rd Joint WS of IEA Implementing Agreements on “Implementation of the ITPA Coord. Research Recommendations” Eynsham Hall, UK, 8 – 10 Dec 2004. Device schedules.

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Device schedules / Programme Elements in 2005 compiled by O. Gruber

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  1. Operations Engineering Break Restart Device schedules / Programme Elements in 2005 compiled by O. Gruber 3rd Joint WS of IEA Implementing Agreements on “Implementation of the ITPA Coord. Research Recommendations” Eynsham Hall, UK, 8 – 10 Dec 2004 Device schedules

  2. 81 shifts 3 3 2 weeks 75 shifts 2005

  3. 2. Critical issues for ITER 1. Bring new systems to full performance (divertor, diagnostics, LH launcher) (potentially impacting detailed design of ITER components, e.g. first wall, heating & current drive systems, diagnostics…) • Design tolerable ELMs • Commissioning of the MkII HD divertor • Characterise ELM behaviour and edge pedestal in ELMy H-mode • Characterise disruptions • Commissioning of new/upgraded diagnostics and systems • Measure tritium retention and migration • High-level commissioning of theLH system to full power • Establish level of off-axis current with off-axis NBI and/or MC-ICRH) and quantify degree of rotation achieved with low momentum input Strong focus in 2005 on preparing ITER detailed design and ITER exploitation • Exploit fully the LH system • Quantify physics governing rotational stabilisation of RWMs • Control core MHD (fishbones) typical of hybrid regimes Programme Elements in 2005 EFDA-JET Workprogramme 2005:Basis for the Scientific Programme

  4. 4. Specific physics issues of direct relevance to ITER(exploiting unique features of JET) 3. Preparation of ITER operating scenarios • Extend ELMy H-mode operation at high triangularity to high current • Determine transport physics implications for ITER • Explore new burning plasma physics • Extend scaling of ELMy H-mode confinement at low d to lowest r*, ne* and highest b • Develop a robust steady-state non-inductive scenario with acceptable edge / confinement making full use of real-time control • Demonstrate portability, fuelling and b limits of the hybrid scenario Programme Elements in 2005 EFDA-JET Workprogramme 2005:Basis for the Scientific Programme Balance of programme Headlines 1/2/3/4 - approx. 8/68/39/21 sessions - contingency: 20 sessions Proposals being analysedRun-time subject to change

  5. FY 2001 FY 1999 FY 2000 Resume MG FY 2003 MG trouble FY 2004 FY 2002 Modification to long pulse 4T,15s FY 2007 FY 2005 FY 2006 3.3T,30s Ripple reduction 2.7T,60s Nov. 05- Sept.06 -30s Programme Elements in 2005 Recent operational schedules of JT-60U • Major cut from FY2002. • - 16 weeks (one shift) of operation in two years • JT-60U program focus on well-thought, selected key topics • For example ; long sustainment of high beta for 03-04 campaign 46MW

  6. 1.4% 0.4% Buffle 0.2% 1.1% 0.6% Programme Elements in 2005 Key implementation during Dec.04 to Oct. 05 shut down (Note; budget for 05 not fixed yet.) Toroidal field ripple at plasma surface will be reduced less than 1/2 by inserting ferritic plates inside the VV. Ferritic insert distribution

  7. Programme Elements in 2005 Tentative run schedule of JT-60U for FY05-06 campaign (Note; budget for 05 will be fixed in late Dec. ,06 not foreseen.) JT-60 would operate from Dec.05 to Sept. 06

  8. Programme Elements in 2005 DIII-D 2005

  9. Programme Elements in 2005 DIII-D 2005

  10. Programme Elements in 2005 DIII-D 2005

  11. Programme Elements in 2005 • ASDEX Upgrade 2005 • Task Force I: "Improvement of H-mode and integrated scenarios" • 1. Improved / hybrid H-mode • - further exploration of hybrid scenario operation space • (early NBI heating and radiation control, q , b, performance, high density,...) • - extend hybrid scenarios with dominant ICRH • (document performance, exchange off-axis NBI by off-axis ICRH, high density) • - establish full non-inductive current drive scenarios • (ITER reference scenario with ECCD and q > 1.5) • 2. Current drive • - document NBCD threshold (power, shape, electron heating, ITB influence) • - find evidence for radial fast ion redistribution • maximize bootstrap current for steady state operation (high b at Ip = 0.6 MA) • 3. Core physics • test ITER hybrid reference scenario with positive ion based NBI • Zeff profiles with on- an d off-axis ICRH • - scaling of geodesic acoustic mode (GAM) frequency ( Doppler reflectometry) • 4.Heating scenarios • - EC heating of high density plasmas using 2nd harmonic O-mode (>1.2 1020 m-3) • - comparison of power limits of 2 & 4 ICRH antenna straps • - influence of the ICRH spectrum on H-mode formation • - ICRH H/D mode conversion heating scenario

  12. Programme Elements in 2005 • ASDEX Upgrade 2005 • Task Force I: "Improvement of H-mode and integrated scenarios" • 5. Core transport: electrons, ions, momentum, particles, impurities • transport dependence on magnetic shear • characterization of transport improvement at low n • - effect of Te / Ti on electron ITB: • - threshold and stiffness of Ti -profile • - momentum transport • angular momentum diffusion and pinch • coupling of momentum / ion heat transport • plasma rotation with pure ICRH • - particle transport • density profile peaking in H-mode • thermodiffusion effects • pellet fuelled disch. • - impurity transport • impurity density profiles at diff. neff • diffusion and pinch coefficients in ITG and TEM dominated discharges • transport coefficients for r/a > 0.7 by sinusoidal impurity gas injection • 6. Diagnostic improvements

  13. Programme Elements in 2005 ASDEX Upgrade 2005 Task Force II: Pedestal and tolerable ELMs 1. H-mode confinement and operation space · triangularity dependence of density limit, type I-III boundary at high d · scaling of pedestal parameters · strong effect of small shape changes (squareness, DIII-D) · toroidal rotation can dramatically affect pedestal and ELMs (JT-60U) 2. ELM physics and ELM structure · scaling of ELM losses with pedestal parameters from large data set · shape dependence of ELM toroidal structure · ICRH coupling asymmetry · bursty transport (burst mode TS, ICRH) 3. ELM control Goals: Quantify and compare ELM size reduction Study physics mechanism Extend range of plasma regimes where techniques applicable Tools: Pellets (so far HFS centrifuge) Electron cyclotron current drive (of edge current) Fast vertical plasma displacement (“wobbling”) Supersonic gas jet injection Laser-blow off from micro-target (KFKI collaboration)

  14. Programme Elements in 2005 ASDEX Upgrade 2005 Task Force II: Pedestal and tolerable ELMs 4. ELM-free regimes, QH-mode · Higher QH-mode densities by shaping · Power dependence of pedestal and confinement · EHO & HFO frequencies · Er / Er shear measurements 5. Small ELM regimes . Focus on Type II / Grassy ELMs · Type III / type I ELM boundary · parameter space: - mixed type I/II ELMs, in different configurations - JT-60U “grassy” ELM regime accessibility (q95, d) · type II ELMs in hydrogen 6. Edge transport, radial electrical field, flow shear Improved diagnostics for inter-ELM transport: · proximity to Double Null changes H-mode properties (MAST) · theory tests for E (r) 7. H-mode access Centered around transition at low density: · electron or ion temperature critical? · can neutral friction and CX viscosity determine threshold? · is there an effect of X-point proximity to roof baffle?

  15. Programme Elements in 2005 • ASDEX Upgrade 2005 • Task Force III: SOL & Divertor Physics and First Wall Materials • 1. ELM structure and heat loads • - Radiation Losses and Energy Balance during Type I ELMs • - ELM particle and energy transport during impurity seeded pellet pace making • Small ELM structure on the divertor target plates • 2. Erosion, deposition and material migration • - Carbon erosion/deposition in the lower divertor • - Deposition and migration of tungsten • - Long term erosion/deposition • - Temperature dependence of hydrocarbon layer growth in sub-divertor region • - Material transport in SOL: Carbon migration by 13C puffing • - Hydrocarbon injection: impurity influxes and chemical sputtering yield • - Deposition of carbon and deuterium in gaps of divertor target surfaces • - Hydrogen gas balance with dominat ICRH injection • - Reduction of a:C-H layer growth by N Puffing • - Stability investigation of erosion morphologies of doped fine-grain graphites

  16. Programme Elements in 2005 ASDEX Upgrade 2005 Task Force III: SOL & Divertor Physics and First Wall Materials 3. SOL profiles and transport incl. drifts, flows and particle influx Exploration of SOL and Divertor plasmas, transport and drifts Fluctuations in the in the edge region and SOL Divertor heat flux profiles, ELM resolved Methane Screening in ELM mitigated plasmas 4. Tungsten first wall (operation regimes, impurity sources and migration, substitution of C divertor radiation, W diagnostics, impact from fast particle losses) Erosion in the upper W-divertor Tungsten migration at the outer SOL Compatibility of ICRF antenna with tungsten limiter for different plasma shapes Tungsten Influx from ICRH and Guard Limiters 5. Modeling Modelling of plasma surface interaction on AUG divertor with ERO code Divertor characterisation by B2E modeling Modelling of tungsten erosion, transport and formation of mixed W-C layers with ERO CD4 -puff: experiments modeling 6. Machine conditioning Assessment of Wall Conditioning Efficiency with the ICRF-DC Carbon removal by He/O glow discharge

  17. Programme Elements in 2005 • ASDEX Upgrade 2005 • Task Force IV: MHD instabilities and their active control • 1. NTMs • - NTM avoidance by early application of ECCD • - NTM Stabilisation of (3/2) NTM with ECCD - modulated and non-modulated • - implementation of the feedback controlled (3/2) and (2/1)-NTM stabilisation /ECCD • - Scaling of βp,marg for the (3/2) and (2/1)-NTM ( inter-machine scaling) • - (3/2) and (2/1)-NTM stabilisation: βN extension with narrow deposition • - (3/2) and (2/1)-NTM stabilisation with reduced q95 = 3.3 • - (3/2)-NTM stabilisation in the improved H-mode • 2. Sawtooth Control • - Sawteeth stabilization with ECCD • - Sawtooth Stabilization via mode converted waves (He3 in H) • 3. VDEs and disruptions • - power deposition profiles on the inner wall and upper divertor during disruptions • - measurements of the vertical displacement time constant of different configurations. • disruption mitigation by massive gas puffs • 4. TAEs and fast particle MHD • - Excitation of TAE modes with ICRH and ICRH beatwaves • - Measurements of fast ion losses (incl. during MHD instabilities) • - Excitation of Alfven Cascades with NBI and ICRH

  18. Programme Elements in 2005 AlcC-MOD 2005 Experimental Campaign (1) For most regimes: equilibrated electrons and ions; no external momentum drive; RF current drive; all-metal PFC's Transport Core turbulence diagnostic upgrades: PCI, reflectometry Electron and ion scale ITB mechanisms, control (ITG, TEM, classical and anomalous particle pinches) Pedestal physics (small ELM regimes, type I ELM regimes) Edge/Divertor Fluctuations, Flows, Transport Tungsten brush technology MHD Alfven Eigenmode studies (active and passive, RF tail driven, weak and negative shear) NTM's (beta thresholds, LH stabilization) ELM stability Advanced tokamak Hybrid scenarios Weak and reverse shear ITBs (with lower hybrid) High bootstrap + LHCD, non-inductive scenarios

  19. Programme Elements in 2005 AlcC-MOD 2005 Experimental Campaign (2) ICRF Minority heating in weak single pass regimes MCCD MC flow drive LHRF Far off-axis current drive Burning Plasma Disruption mitigation (massive gas puff), high absolute pressure plasmas all metal PFC's, tungsten brush locked mode physics

  20. Programme Elements in 2005 TCV Scientific programme 2004-2005: - investigation of methods for improving the plasma performance in term of ß, including studies of electron heat transport in shaped plasmas, of plasma rotation, of methods to heat high density plasmas and to control edge localized instabilities - physics of the interaction between waves and particles in the EC frequency range, for the optimisation of ECH and ECCD (recently installed top-launched third harmonic ECH) - physics of enhanced confinement regimes, in particular in the presence of ITB´s, ( barrier formation, plasma response to inductive current perturbation, MHD activity) - physics of energy and particle transport, including particle pinch mechanisms, - divertor and edge physics (incl. density / potential fluctuations in SOL, anomalous plasma detachment observed on TCV). Investigations are conducted in ohmic and ECH-ECCD plasmas, both with X2 and X3. Scientific programme 2005-2006: discussed in autumn 05

  21. Programme Elements in 2005 MAST priorities for 2005 (1) Performance optimisation - H-mode optimisation (fuelling, magnetic configuration, ELM/pedestal characteristics) - formation & sustainment of ITBs Confinement studies - expansion of database to higher power, plasma current.. - dimensionless scaling (beta, A, *..) - particle confinement studies incl. pellet injection Transport - assessment of the relative roles of electron & ion transport and the impact of micro-instabilities - impact of plasma rotation * Studies will incorporate a counter-NBI campaign incl. QH mode studies

  22. Programme Elements in 2005 MAST priorities for 2005 (2) Plasma Exhaust - ELM characteristics and impact on PFCs - energy distribution to first wall & divertor during transient events - SOL transport and impact of drifts on SOL flows High beta operation - development of sustained high normalized beta regimes - impact of performance-limiting instabilities (e.g. NTMs) NBCD - assessment of NBCD efficiency & comparison with theory Non-solenoid start-up - development of effective start-up schemes without use of central solenoid

  23. FY05 FY06 FY07 Exp. Run-Weeks: 17 17 17 1) Transport & Turbulence: Physical processes that govern heat, particle & momentum confinement (05-1) Characterize q’ effects (06-1) Measure high-k (07-1) Compare spectrum with on electron transport turbulence local electron transport 2) Macroscopic Stability: Role of magnetic structure on plasma pressure & bootstrap current (05-2) Study plasmas  “wall- (06-2) Identify tearing (07-2) Characterize effectiveness stabilized” pressure limit mode & onset conditions of active RWM control 3) Wave-Particle Interaction: Use of electromagnetic waves to sustain and control high-temperature plasmas (05-3) Assess EBW (06-3) Optimize HHFW CD H&CD requirements properties (06-5) Characterize HHW- plasma edge interactions 4) Start-up, Ramp-up and Sustainment: Physical processes of magnetic flux generation (07-3) Test solenoid-free ramp-up to high current 5) Boundary Physics: Interface between fusion plasmas and normal temperature surroundings (05-5) Characterize edge of (06-4) Characterize Li pellet (07-4) Assess long-pulse heat high-performance plasmas & coating effectiveness & particle control requirements 6) Integration: Integration of external control and self-organization physics (05-4) Characterize high-bs (07-5) Evaluate VL = 0 & low-induction plasmas plasmas for tskin Programme Elements in 2005 NSTX:Proposed FY05-07 Research Milestones Aim to Establish Control Science of Sustained High fBS-bN-tE Plasmas

  24. MHD Mode Stabilization(Draft) Opportunity Areas are Shaping and RWM Controls. Plasma Operations FY 06 FY 07 FY 05 Wall-mode sensors (Columbia) • Base milestone MHD Diagnostics & Analysis Tools Ultra-soft x-ray arrays (JHU) • Base plan Fast MHD sensors • Available Improved magnetics EFIT with Plasma Rotation (Columbia/GA) Fast X-ray camera (PSI) Shape Control Higher Elongation Real Time EFIT (GA) PF 1A Upgrade for high  &  Coil Fabrication / Install Res. Field & RWM Control System (Columbia) Six-Element RWM External Coils with a preprogrammed SPA Supply Active Resonant Field Correction Coil Fab./Install Switching Power Amp

  25. Plasma Operations FY 06 FY 07 FY 05 4 21 21 (Run Weeks) Confinement and Transport Exciting Opportunities For Advanced Fluctuation Diagnostics • Base milestone Edge Pol CHERS Tor. CHERS (51 ch) • Base plan Profile Diagnostics Edge Rotation Diagnostic ERD Upgrade • Available MPTS 30 ch MPTS Third laser FIReTIP 6 ch (UCD) MSE / LIF (Nova) MSE / CIF 14 ch (Nova) MSE/CIF 8 ch (Nova) Energetic Particles Neutron Collimator Fast Loss Ion Probe Low k Reflectometer (UCLA) Fluctuation Diagnostics Low k Imaging Reflectometer Gas-puff Imaging(LANL, PSI) Reciprocating probe (UCSD) High k Microwave Scattering( UCD)

  26. Non-Inductive CD Systems Plasma Operations FY 06 FY 07 FY 05 4 21 21 (Run Weeks) Enhancement Opportunity areas are EBW and Solenoid-free Start-up • Base milestone Feed-back Phase Control HHFW (6MW) • Base plan Antenna side-limiter upgrade • Available RF Wave Reflectometer (ORNL) • Incremental Antenna Loading Control Prelim Design Begin Site Prep 1 MW EBW System Decision Point EBW -E / -CD Complete Site Prep Procure 1st Tube Transient CHI Capacitor Bank(U. Washington) CHI (IT = 0.5 MA) ECH/Gas Injection Upgrade Dynamo-head-probe(UCSD) PF Coil Start-up PF 5 Bi-Polar Power Supply PF 4 Energization

  27. Plasma Operations FY 06 FY 07 FY 05 4 21 21 (Run Weeks) Boundary Physics Exciting Enhancement Opportunity in Core Fueling and Boundary Physics Li Pellet Injector Wall Conditioning • Base milestone Lithium Evaporator Hot-boronization • Base plan • Available Between-shots boronization (Gas/plasma Boronization, Between-shot GDC) • Incremental Moveable GDC probe Power/Particle Exhaust System Decision Point Power / Particle Control Divertor IR Camera (ORNL) Fast IR Camera (ORNL) Horiz. Divertor Bolometer Div. Spectrometer Divertor Probe Vert. Divertor Bolometer Fueling Supersonic Gas injector Pellet injector in "suitcase” (ORNL) (In-board gas injectors CT injector Lab. Test

  28. Programme Elements in 2005 • Tore Supra 2005 • Program not yet decided… but should look like : • Steady state plasmas control, safety • Current profile control (LHCD, ECRH) • « High bootstrap » scenario development • PFCs hot spots, LH coupler arc control • Particle transport • Deuterium retention and C migration • SOL transport (heat deposition, transport physics) • + Disruption mitigation (runaway suppression) • Wide band matching ICRH antenna test • Tore Supra can now provide steady-state conditions, for studying: • - Regimes where Te ~ Ti and @ Greenwald limit without momentum injectio • (Advanced Scenario: ITB, Hybrid…) • - Heat / Turbulent Particle Transport (namely vs Ti/Te, beta scaling) • - C release, D retention with actively cooled CFC • + Sol Transport • Disruption mitigation

  29. Programme Elements in 2005 Tore Supra 2005 RF Heating Capability & Diagnostics • 3 ICRF antenna (3x4 MW). Best result 10MW (250 MJ injected) • 2 LH launchers (2x3.4 MW). Best result 6.4MW (1 GJ injected) • 2 ECRF antenna (2x0.5 MW). Best result 0.8 MW • Diagnostics: • Current profile by polarimetry (5 chords  10 in 2005), and MSE (4 chords  9 in 2005); LH current by Hard-X ray tomographic system • (21 vertical and 38 horizontal detectors, 20 - 200 keV) • Te profile by 32 channels of a superheterodyne radiometer; time/spatial res. 1ms / 2cm. Possibility to measure dTe • Ti and toroidal rotation profiles: CXRS • ne andfluctuation profiles by a set of reflectometers using 3 different techniques: • - X-mode fast and continuously scanning frequency, 50-110 GHz • X-mode stepped fixed frequency, 105–160 GHz • O-mode Doppler reflectometer with k-spectra determination, 50-75 GHz

  30. Programme Elements in 2005 TEXTOR work programme 2005 Main Topics: 1) Investigation and exploitation of the Dynamic Ergodic Divertor for the improvement of present concepts for heat and particle exhaust and application to basic MHD studies 2) Confinement and transport physics 3) Fundamental studies of plasma-wall interaction and properties of materials and the extrapolation to a steady-state fusion power plant

  31. Programme Elements in 2005 TEXTOR work programme 2005 • 1) Investigation and exploitation of the Dynamic Ergodic Divertor • Exploration of the DED by • varying the field strength and the location of the resonant layer producing either large ergodic zones (5cm radial width) or large laminar zones (4 cm width) • different combinations of the 16 DED - coils generating different modes m/n = 12/4, 6/2, 3/1 and mixtures of these • different phasing of the coil current producing rotating field structures varying from DC up to 10 kHz, • feed-back schemes controlling amplitude and phase of the distortion field and the location of the resonant layer. • Effects of the DED on plasma-wall interaction, especially heat deposition, particle recycling and impurity screening • Study of the excitation of modes by the external error field, in particular by using the deeply reaching m/n = 3/1 mode. Also in combination with mode stabilisation by ECRH/ECCD. • Investigation of the influence of static and dynamic perturbation fields on the stabilization of external kink modes. • Study of effects on local and global transport, in particular the influence of the near-field divertor on confinement and its relation to the island divertor in stellarators.

  32. Programme Elements in 2005 TEXTOR work programme 2005 • 2) Confinement and transport physics • Investigation of improved confinement modes, in combination with various heating schemes: NBI, ICRH, ECRH and DED • Study of the effect of local gas sources on edge turbulence and global confinement • Study of impurity transport with improved diagnostics; impurity screening with DED • Study of the beta limit imposed by neo-classical tearing modes at high collisionality and of mode-stabilisation by ECCD • Development of control techniques for neo-classical tearing modes: stabilisation by current driv and control by non-resonant helical fields generated by DED and ECRH/CD • Further development of methods for recognition and mitigation of disruptions by fast gas puffing and conduct studies of runaway generation and suppression. • Study of internal transport barriers (ITB) in particular during negative central shear discharges with special emphasis on turbulence characterisation. • Application of the DED for investigation of the effects of resonant error fields on the plasma rotation

  33. Programme Elements in 2005 TEXTOR work programme 2005 • 3) Fundamental studies of plasma-wall interaction • Studies of erosion and deposition mechanisms, in particular with graphite and tungsten • Study of the formation, thermo-mechanical properties, composition and removal of deposited layers • Degradation and erosion behaviour of PFCs under transient thermal loads in electron beam simulation tests (JUDITH) • Model development for ITER and model validation in TEXTOR and JET for erosion and deposition processes and link to other plasma transport codes • Evaluation of new plasma facing materials (B4C, Ta, doped graphites, and carbon-fiber-composites) with regard to their plasma compatibility and heat load properties • Development of in situ techniques to measure material deposition and fuel inventory: quartz microbalance techniques for remote areas, in situ Laser desorption /ablation techniques with spectroscopic detection for material deposition and fuel inventory. • Test of the performance of ITER like first mirrors in TEXTOR • Development of spectroscopic tools including improvements of the atomic and molecular data base

  34. Programme Elements in 2005 • FTU 2005 • Electron ITBs • - plasma densities in the range of 1.5 1020 m-3, o.5 MA, input powers up to 3 MW • Disruptions • - test of disruption mitigation by real-time feedback of ECRH • at the start of thermal quench • Plasma transport • High density behaviour • Lithium limiter experiments • Debugging of MSE system

  35. Programme Elements in 2005: Russian tokamaks • T-11MTokamak (TRINITI) • Lithium limiter • Plasma confinement in case of Lithium limiter • Study of the IC heating efficiency • Fundamental IC frequency heating of the hydrogen plasma • Hydrogen and Lithium minorities in deuterium plasma • T-10Tokamak (Kurchatov Institute) • Transport • Density dependence of electron and ion heat transport at various Te/Ti • Energy transport variations under the ECRH switching on/off • Reverse-shear plasma under ECCD/ECRH (including role of RS in e-ITB formation) • Internal transport barrier formation under ECRH (TEXTOR/T-10 experiment) • Transport of impurities • Plasma biasing • Transport at plasma periphery and at SOL region • Plasma stability • Plasma turbulence • Control of the MHD-modes by externally driven halo current • NTM control by ECRH and ECCD • Plasma initiation • Breakdown at 2ce

  36. Programme Elements in 2005: Russian tokamaks • Spherical Tokamak GLOBUS-M (Ioffe Institute) • Plasma control • Development of digital system for plasma shaping control • Plasma-wall interaction • Tungsten toroidal belt limiter • NBI and ICRH heating • Optimisation of NBI heating • Optimisation of ICRH heating • Combined NBI and ICRH heating • Plasma fueling • Experiments with the plasma-beam injection (up to 150 km/s) • TUMAN-3M Tokamak (Ioffe Institute) • NBI ion heating and NBI current drive • ITB and ETB formation in presence of external momentum input by NBI • Measurements of the turbulence dynamics by Doppler reflectometry • FT-2 Tokamak (Ioffe Institute) • Lower Hybrid Heating and Current Drive • Transport-barrier formation under LH Heating • Turbulent transport control by LH heating • Study of poloidal distribution of transport in the SOL

  37. Programme Elements in 2005: Small Sized Tokamaks in JA • JFT-2M (JAERI : R~1.3m / a~0.3m) • A series of experimental program on JFT-2M was completed in March, 2004. • In 2005, at C-MOD for joint experiments (EDA and HRS comparison). • LATE (Kyoto Univ. : R~0.23m / a~0.17m) • - Spontaneous formation of Spherical Tokamak plasma by ECH(5 GHz). • Realization of diverted discharges for 2.45 GHz slow formation experiments • with molybdenum divertor plates to reduce impurity out flux. • TST-2 (The Univ. of Tokyo : R~0.38m / a~0.25m) • - Solenoidless start-up (Based on results of JT-60U collaboration) • - Reconnection physics (Internal Reconnection Event) • - Turbulence and transport (Develop fluctuation diagnostics) • - HHFW heating / current drive (21 MHz / 400 kW. Nonlinear wave physics) • - Prepare LHCD system (200MHz / 400kW (from JFT-2M)) • HYBTOK-II (Nagoya Univ. : R~0.4m / a~0.11m)) • Disruption Studies (Control of Te and search for its influence on current quench decay time. • Dynamic MHD behavior of disruption. ) • - Studies of plasma response to rotation helical magnetic perturbation. • - Effect of deep potential well (for CSTN-IV) • TRIAM-1M (Kyushu Univ. : R~0.84m / a~0.15m) • - Steady State Operation (SSO) of Tokamak Plasma • - PWI in Long Pulse/Steady State Plasmas • - High Performance (ITB, ECD (Enhanced current drive) mode) • - Current Drive (ECCD (170 GHz). Remote steering )

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