device schedules / programme elements in 2005 compiled by o. gruber

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

Operations

Engineering Break

Restart

Device schedules

Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec

JET

JT-60U

DIII-D

AUG

AlcC-MOD

TCV

JFT-2M

MAST

NSTX

TS

Textor

FTU

T-10

T-11

Globus-M

TUMAN-3M

FT-2

HT-7

TRIAM

2005

3 3 2 weeks

81 shifts

75 shifts

EFDA-JET Workprogramme 2005:Basis for the Scientific Programme

2. Critical issues for ITER

• Characterise disruptions

• Characterise ELM behaviour and edge pedestal in ELMy H-mode

• Measure tritium retention and migration

• Establish level of off-axis current with off-axis NBI and/or MC-ICRH) and quantify degree of rotation achieved with low momentum input

• Quantify physics governing rotational stabilisation of RWMs

• Control core MHD (fishbones) typical of hybrid regimes

• Design tolerable ELMs

(potentially impacting detailed design of ITER components, e.g. first wall, heating & current drive systems, diagnostics…)

• Exploit fully the LH system

• Commissioning of the MkII HD divertor

• Commissioning of new/upgraded diagnostics and systems

1. Bring new systems to full performance (divertor, diagnostics, LH launcher)

• High-level commissioning of the LH system to full power

Strong focus in 2005 on preparing ITER detailed design

and ITER exploitation

Programme Elements in 2005

4. Specific physics issues of direct relevance to ITER (exploiting unique features of JET)

• Explore new burning plasma physics

• Determine transport physics implications for ITER

3. Preparation of ITER operating scenarios

• Extend ELMy H-mode operation at high triangularity to high current

• Extend scaling of ELMy H-mode confinement at low to lowest *, e* and highest

• Develop a robust steady-state non-inductive scenario with acceptable edge / confinement making full use of real-time control

• Demonstrate portability, fuelling and limits of the hybrid scenario

Balance of programme

Headlines 1/2/3/4

- approx. 8/68/39/21 sessions

- contingency: 20 sessions

Proposals being analysedRun-time subject to change

EFDA-JET Workprogramme 2005:Basis for the Scientific Programme


Recent operational schedules of JT-60U

46MW

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

4T,15s

-30s

3.3T,30s

2.7T,60s

FY 1999 FY 2000 FY 2001

FY 2002 FY 2003 FY 2004MG trouble Resume MG

Modification to long pulse

FY 2006 FY 2007FY 2005

Ripple reduction Nov. 05- Sept.06


Key implementation during Dec.04 to Oct. 05 shut down(Note; budget for 05 not fixed yet.)

Buffle

Toroidal field ripple at plasma surface will be reduced less than 1/2 by inserting ferritic plates inside the VV.

0.2%

1.1%

1.4%

0.6%

0.4%

Ferritic insert distribution


Tentative run schedule of JT-60U for FY05-06 campaign(Note; budget for 05 will be fixed in late Dec. ,06 not foreseen.)

Maintenance

Exp. Operation

Cond. Operation

JT-60 would operate from Dec.05 to Sept. 06

FY2005

M S M T W T F S Expwk

11 30 31 1 2 3 4 5

6 7 8 9 10 11 12

13 14 15 16 17 18 19

20 21 22 23 24 25 26

27 28 29 30 1 2 3

12 4 5 6 7 8 9 10 E1/05

11 12 13 14 15 16 17 E2/05

18 19 20 21 22 23 24 E3/05

25 26 27 28 29 30 31

1 1 2 3 4 5 6 7

8 9 10 11 12 13 14 E4/05

15 16 17 18 19 20 21 E5/05

22 23 24 25 26 27 28 E6/05

2 29 30 31 1 2 3 4

5 6 7 8 9 10 11

12 13 14 15 16 17 18 E7/05

19 20 21 22 23 24 25 E8/05

3 26 27 28 1 2 3 4

5 6 7 8 9 10 11

12 13 14 15 16 17 18

19 20 21 22 23 24 25

26 27 28 29 30 31 1

FY2006

M S M T W T F S Expwk

4 2 3 4 5 6 7 8

9 10 11 12 13 14 15

16 17 18 19 20 21 22

23 24 25 26 27 28 29

5 30 1 2 3 4 5 6

7 8 9 10 11 12 13

14 15 16 17 18 19 20

21 22 23 24 25 26 27

28 29 30 31 1 2 3

6 4 5 6 7 8 9 10

11 12 13 14 15 16 17 E1/06

18 19 20 21 22 23 24 E2/06

25 26 27 28 29 30 1 E3/06

7 2 3 4 5 6 7 8

9 10 11 12 13 14 15

16 17 18 19 20 21 22 E4/06

23 24 25 26 27 28 29 E5/06

8 30 31 1 2 3 4 5 E6/06

6 7 8 9 10 11 12

13 14 15 16 17 18 19

20 21 22 23 24 25 26 E7/06

27 28 29 30 31 1 2 E8/06

9 3 4 5 6 7 8 9

10 11 12 13 14 15 16

17 18 19 20 21 22 23

24 25 26 27 28 29 30


Programme Elements in 2005DIII-D 2005

ASDEX Upgrade 2005Task 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 , , 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 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


ASDEX Upgrade 2005Task 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. eff diffusion and pinch coefficients in ITG and TEM dominated discharges transport coefficients for r/a > 0.7 by sinusoidal impurity gas injection6. Diagnostic improvements


ASDEX Upgrade 2005Task 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 controlGoals: Quantify and compare ELM size reduction

Study physics mechanismExtend 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)


ASDEX Upgrade 2005Task Force II: Pedestal and tolerable ELMs4. 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 hydrogen6. Edge transport, radial electrical field, flow shearImproved diagnostics for inter-ELM transport:· proximity to Double Null changes H-mode properties (MAST)· theory tests for E (r)7. H-mode accessCentered 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?



ASDEX Upgrade 2005Task 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

Programme Elements in 2005ASDEX Upgrade 2005Task Force III: SOL & Divertor Physics and First Wall Materials

3. SOL profiles and transport incl. drifts, flows and particle influxExploration of SOL and Divertor plasmas, transport and driftsFluctuations in the in the edge region and SOLDivertor heat flux profiles, ELM resolvedMethane Screening in ELM mitigated plasmas4. 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-divertorTungsten migration at the outer SOLCompatibility of ICRF antenna with tungsten limiter for different plasma shapesTungsten Influx from ICRH and Guard Limiters5. Modeling Modelling of plasma surface interaction on AUG divertor with ERO codeDivertor characterisation by B2E modeling Modelling of tungsten erosion, transport and formation of mixed W-C layers with EROCD4 -puff: experiments modeling6. Machine conditioningAssessment of Wall Conditioning Efficiency with the ICRF-DCCarbon removal by He/O glow discharge

ASDEX Upgrade 2005Task 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-mode2. 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 puffs4. 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



AlcC-MOD 2005 Experimental Campaign (1)For most regimes: equilibrated electrons and ions; no external momentum drive;

RF current drive; all-metal PFC's

TransportCore turbulence diagnostic upgrades: PCI, reflectometryElectron and ion scale ITB mechanisms, control (ITG, TEM, classical and anomalous particle pinches)

Pedestal physics (small ELM regimes, type I ELM regimes)

Edge/DivertorFluctuations, Flows, TransportTungsten brush technology

MHDAlfven Eigenmode studies (active and passive, RF tail driven, weak and negative shear)NTM's (beta thresholds, LH stabilization)ELM stability

Advanced tokamakHybrid scenariosWeak and reverse shear ITBs (with lower hybrid)High bootstrap + LHCD, non-inductive scenarios


AlcC-MOD 2005 Experimental Campaign (2)

ICRFMinority heating in weak single pass regimesMCCDMC flow drive

LHRFFar off-axis current drive

Burning PlasmaDisruption mitigation (massive gas puff), high absolute pressure plasmasall metal PFC's, tungsten brushlocked mode physics

TCVScientific 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


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


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


NSTX:Proposed FY05-07 Research Milestones Aim to Establish Control Science of Sustained High fBS-N-E Plasmas

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 withon 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 effectivenessstabilized” pressure limit mode & onset conditions of active RWM control

4) Start-up, Ramp-up and Sustainment: Physical processes of magnetic flux generation(07-3) Test solenoid-free ramp-up to high current

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 skin

3) Wave-Particle Interaction: Use of electromagnetic waves to sustain and control high-temperature plasmas

(05-3) Assess EBW (06-3) Optimize HHFW CDH&CD requirements properties

(06-5) Characterize HHW- plasma edge interactions

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 heathigh-performance plasmas & coating effectiveness & particle control requirements

17Exp. Run-Weeks:

FY05 FY07FY06

17 17


MHD Mode Stabilization(Draft)MHD Mode Stabilization(Draft)

Six-Element RWM External Coils with Six-Element RWM External Coils with a preprogrammed SPA Supplya preprogrammed SPA Supply

Opportunity Areas are Shaping and RWM Controls.

MHD MHD DiagnosticsDiagnostics

&&Analysis Analysis

ToolsTools

PlasmaOperations FY 05 FY 06 FY 07

Wall-mode sensors (Columbia)Wall-mode sensors (Columbia)

Ultra-soft x-ray arrays Ultra-soft x-ray arrays (JHU)(JHU)

Fast MHD sensorsFast MHD sensorsImproved magnetics Improved magnetics

Fast X-ray camera Fast X-ray camera (PSI)(PSI)

Res. Field & Res. Field & RWM Control RWM Control

SystemSystem(Columbia)(Columbia)

Real Time EFIT Real Time EFIT (GA)(GA)

Switching Power AmpCoil Fab./Install

Shape ControlShape ControlHigher Higher

ElongationElongationPF 1A Upgrade for high PF 1A Upgrade for high & &

Coil Fabrication / Install

EFIT with Plasma Rotation (Columbia/GA) EFIT with Plasma Rotation (Columbia/GA)

- Base milestone

- Available

Active Resonant FieldActive Resonant FieldCorrection Correction

- Base plan

Confinement and TransportConfinement and TransportExciting Opportunities For Advanced Fluctuation Diagnostics


(Run Weeks) 4 21 21

High k Microwave Scattering( UCD)

Tor. CHERS (51 ch) Edge Pol CHERS

Profile Profile DiagnosticsDiagnostics

Energetic Energetic ParticlesParticles

Fluctuation Fluctuation DiagnosticsDiagnostics

Fast Loss Ion Probe

FIReTIP 6 ch ch (UCD)(UCD)

MPTS 30 ch MPTS Third laser

Edge Rotation Diagnostic

Low k Reflectometer (UCLA)

Reciprocating probe (UCSD)

Gas-puff Imaging(LANL, PSI)

ERD Upgrade

Neutron Collimator

MSE / CIF14 ch (Nova)

MSE/CIF8 ch (Nova)

MSE / LIF(Nova)

Low k Imaging Reflectometer

- Base milestone

- Available

- Base plan

Non-Inductive CD SystemsNon-Inductive CD SystemsEnhancement Opportunity areas are EBW and Solenoid-free Start-up


(Run Weeks) 4 21 21

CHICHI(I(ITT = 0.5 MA) = 0.5 MA)

HHFWHHFW(6MW)(6MW)

Feed-back Phase ControlFeed-back Phase Control

EBW -E / -CDEBW -E / -CD

Dynamo-head-probeDynamo-head-probe(UCSD)(UCSD)

Transient CHI Capacitor BankTransient CHI Capacitor Bank((U. Washington)U. Washington)

PF CoilPF CoilStart-upStart-up

PF 4 EnergizationPF 4 Energization PF 5 Bi-Polar PF 5 Bi-Polar Power SupplyPower Supply

Prelim DesignPrelim DesignBegin Site PrepBegin Site Prep

Complete Site Prep Complete Site Prep Procure 1st TubeProcure 1st Tube

- Incremental

- AvailableAntenna side-limiter upgradeAntenna side-limiter upgrade

ECH/Gas Injection UpgradeECH/Gas Injection Upgrade

RF Wave Reflectometer RF Wave Reflectometer (ORNL)(ORNL)

Antenna Loading Antenna Loading ControlControl

1 MW EBW 1 MW EBW SystemSystemDecision PointDecision Point

- Base milestone

- Base plan

Boundary PhysicsBoundary PhysicsExciting Enhancement Opportunity in Core Fueling and Boundary Physics


(Run Weeks) 4 21 21

FuelingFueling

Wall Wall ConditioningConditioning

Supersonic Gas injectorSupersonic Gas injector

Power / Power / Particle Particle ControlControl

Li Pellet InjectorLi Pellet Injector

(Gas/plasma (Gas/plasma Boronization,Boronization,Between-shot GDC)Between-shot GDC)

(In-board gasinjectors

Pellet injector in "suitcase”(ORNL)

Fast IR Camera(ORNL)

Divertor IR Camera(ORNL)

Lithium EvaporatorLithium EvaporatorHot-boronizationHot-boronization

Between-shots boronizationBetween-shots boronization

CT injector Lab. Test

Divertor Probe

Vert. Divertor Bolometer

Horiz. Divertor BolometerDiv. Spectrometer

Moveable GDC probeMoveable GDC probe

Power/ParticlePower/ParticleExhaust SystemExhaust SystemDecision PointDecision Point

- Incremental

- Available

- Base milestone

- Base plan

Tore Supra 2005Program not yet decided… but should look like :Steady state plasmas control, safety

Current profile control (LHCD, ECRH)« High bootstrap » scenario developmentPFCs hot spots, LH coupler arc controlParticle 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


Tore Supra 2005RF 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. 1s / 2cm. Possibility to measure Te

Ti and toroidal rotation profiles: CXRS

ne and fluctuation 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



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


TEXTOR work programme 20051) 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.



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



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

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


T-11M Tokamak (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-10 Tokamak (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 2ce

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

Programme Elements in 2005: Russian tokamaks

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 )

Programme Elements in 2005: Small Sized Tokamaks in JA

device schedules / programme elements in 2005 compiled by o. gruber

Documents

campaignprogramme elements

operation plan

years jt

shift of operation

operation hydrogenshotjt

tentative run schedule

balance of programme

key topics