Otto Gruber for the ASDEX Upgrade Team

21st IAEA 2006, Chengdu, China, 17 Oct .2006 O. Gruber 1

Otto Gruber for the ASDEX Upgrade Team

Overview of ASDEX Upgrade Results

Max-Planck-Institut für Plasmaphysik, EURATOM Assoc.-IPP

Presented at the 21st IAEA Conferenceat Chengdu (China), 16 – 21 Oct 2006


ASDEX Upgrade Team:

C. Angioni1, C.V. Atanasiu2, M. Balden1, G. Becker1, W. Becker1, K. Behler1, K. Behringer1, A. Bergmann1,T. Bertoncelli1, R. Bilato1, V. Bobkov1, T. Bolzonella3, A. Bottino1, M. Brambilla1, F. Braun1, A. Buhler1,A. Chankin1, G. Conway1, D.P. Coster1, T. Dannert1, S. Dietrich1, K. Dimova1, R. Drube1, R. Dux1, T. Eich1, K. Engelhardt1, H.-U. Fahrbach1, U. Fantz1, L. Fattorini4, R. Fischer1, A. Flaws1, M. Foley5, C. Forest6,P. Franzen1, J.C. Fuchs1, K. Gál7, G. Gantenbein8, M. García Muñoz1, L. Giannone1, S. Gori1, S. da Graça1,H. Greuner1, O. Gruber1, S. Günter1, G. Haas1, J. Harhausen1, B. Heinemann1, A. Herrmann1, J. Hobirk1,D. Holtum1, L. Horton1, M. Huart1, V. Igochine1, A. Jacchia9, F. Jenko1, A. Kallenbach1, S. Kálvin7, O. Kardaun1,M. Kaufmann1, M. Kick1, G. Koscis7, H. Kollotzek1, C. Konz1, K. Krieger1, H. Kroiss1, T. Kubach8, T. Kurki-Suonio10, B. Kurzan1, K. Lackner1, P.T. Lang1, P. Lauber1, M. Laux1, F. Leuterer1, J. Likonen11, A. Lohs1,• Lyssoivan12, C. Maggi1, H. Maier1, K. Mank1, A. Manini1, M.-E. Manso4, P. Mantica9, M. Maraschek1,P. Martin3, M. Mayer1, P. McCarthy5, H. Meister1, F. Meo13, P. Merkel1, R. Merkel1, V. Mertens1, F. Merz1,H. Meyer14, F. Monaco1, H.-W. Müller1, M. Münich1, H. Murmann1, Y.-S. Na1, G. Neu1, R. Neu1, J. Neuhauser1,J.-M. Noterdaeme1, M. Pacco-Düchs1, G. Pautasso1, A.G. Peeters1, G. Pereverzev1, S. Pinches1, E. Poli1,M. Püschel1, T. Pütterich1, R. Pugno1, E. Quigley5, I. Radivojevic1, G. Raupp1, M. Reich1, T. Ribeiro4, R. Riedl1,V. Rohde1, J. Roth1, M. Rott1, F. Ryter1, W. Sandmann1, J. Santos4, K. Sassenberg5, G. Schall1, H.-B. Schilling1,J. Schirmer1, A. Schmid1, W. Schneider1, G. Schramm1, W. Schustereder15, J. Schweinzer1, S. Schweizer1,B. Scott1, U. Seidel1, M. Serbu1, F. Serra4, Y. Shi16, A. Silva4, A.C.C. Sips1, E. Speth1, A. Stäbler1, K.-H. SteuerJ. Stober1, B. Streibl1, D. Strintzi1, E. Strumberger1, W. Suttrop1, G. Tardini1, C. Tichmann1, W. Treutterer1,C. Tröster1, M. Tsalas17, L. Urso1, E. Vainonen-Ahlgren11, P. Varela4, L. Vermare1, D. Wagner1, M. Wischmeier1,E. Wolfrum1, E. Würsching1, Q. Yu1, D. Zasche1, T. Zehetbauer1, M. Zilker1, H. Zohm1.




Contributing Institutes

1 Max-Planck-Institut für Plasmaphysik, EURATOM Association-IPP, Garching, Germany2 Institute of Atomic Physics, EURATOM Association-MEdC, Romania,3 Consorzio RFX, EURATOM Association-ENEA, Padova, Italy, 4 CFN, EURATOM Association-IST Lisbon, Portugal, 5 Physics Dep., University College Cork, Association EURATOM-DCU, Ireland, 6 University of Wisconsin, Madison, USA. 7 KFKI, EURATOM Association-HAS, Budapest, Hungary, 8 Institut für Plasmaforschung, Stuttgart University, Germany, 9 IFP Milano, EURATOM Association-ENEA, Italy, 10 HUT, EURATOM Association-Tekes, Helsinki, Finland, 11 VTT, EURATOM Association-Tekes, Espoo, Finland, 12 LPP-ERM/KMS, EURATOM Association-Belgian State, Brussels, Belgium, 13 NL Risǿ, EURATOM Association-RISØ, Roskilde, Denmark, 14 UKAEA Culham, EURATOM Association-UKAEA, United Kingdom, 15 University of Innsbruck, EURATOM Association-ÖAW, Austria 16 IPP, CAS, Hefei, China, 17 NCSR Demokritos, EURATOM Association-HELLAS, Athens, Greece


Main aim is to establish the physics base for ITER (and DEMO): - consolidation of the 'standard' H-mode scenario - exploration of ‚advanced' modes beyond the standard scenario

Understanding of physics elements

- transport

- fast particles and NBCD

- H-mode edge and ELM tailoring

- disruption mitigation

- MHD control with ECCD

- tungsten wall and divertor operation

Integration into improved scenario beyond reference - Improved H-mode (ITER Hybrid scenario) - ITER relevant digital CODAC system

Direct influence on ITER component design: PFC material, heating/CD systems, ECRF system

Strategy: in close collaboration within EU fusion programme, ITPA TGs

AUG programme to prepare / in parallel to ITER


towards a tungsten first wall: 36 m2 or 85% of PFC area) 2005: - all LFS limiters (water cooled) - roof baffle with thin W coating (<4 m PVD) 2006: lower divertor target plates (200 m W VPS)

guard/

ICRHlimiter

aux.limiter

hor.plate

lower PSL

roofbaffle

2006/2007(planned)

W-coating startingwith campaign

2003/2004

2004/2005

2005/2006

guard/

ICRHlimiter

aux.limiter

hor.plate

lower PSL

roofbaffle

2006/2007(planned)


2003/2004

2004/2005

2005/2006

AUG enhancements 2004-2006:


AUG enhancements: Towards a full W machine 2005

● in 2005 “thin” W coating of - 4 guard limiters at LFS (water cooled) - 8 ICRH antenna side limiters - top of bottom PSL - roof baffle

● in 2006 - upper and lower ICRH limiters - W coated bottom target tiles (200 m)

full tungsten machine

ITER start-up configuration ?


towards a tungsten first wall: 36 m2 or 85% of PFC area) 2005: - all LFS limiters (water cooled) - roof baffle with thin W coating (<4 m) 2006: lower divertor target plates (200 m W)

4 steerable ECRH mirrors installed

first two-frequency gyrotron: leak after commissioning (≤1 MW / 10 s / 105 & 140 GHz)

guard/

ICRHlimiter

aux.limiter

hor.plate

lower PSL

roofbaffle

2006/2007(planned)


2003/2004

2004/2005

2005/2006

guard/

ICRHlimiter

aux.limiter

hor.plate

lower PSL

roofbaffle

2006/2007(planned)


2003/2004

2004/2005

2005/2006

AUG enhancements 2004-2006:

pellet injection systems - centrifuge (HFS launch capability, variable pellet size,< 1200 m/s) - blower gun (optimized for decoupling ELM pacing and refuelling)

new CODAC commissioned - reduced cycle time <1.5ms - extended regime recognition & performance control - real-time diagnostics replaces CAMACs


Understanding of anomalous transport predictions

- response of different transport channels on heat and momentum input- comparison with gyrokinetic simulations TEM and ITG turbulence dominate in different parameter regimes

Pure electron heating: threshold for TEM at R/LTe3

power balance and heat pulse propagation show a transition through threshold

Angioni EX/8-5Rb


Transport: Er transitions at plasma edge

negative Er well increases

with confinement improvement

- coincides with H-mode barrier gradient

- Doppler reflectometry

Conway EX/2-1

H98(y,2)


Fast particle interactions with large scale instabilities

- New: Fast Ion Loss Detector (FILD) with bandwidth of 1 MHz

- frequency / phase correlations of fast ions with TAEs (ICRH, ICRH beatwave)

- fast particle losses correlated with low frequency MHD activity: NTMs, double tearing modes, ELMs

- slow MHD activity like NTM (+harmonics) induces fast particle losses

- FILD signal is modulated with rotating mode in fixed phase relation

- modulated NBI sources with different injection geometry origin of fast particles- time scale of losses >100 toroidal orbit transits due to stochasticity of overlapping drift islands caused by the NTM

- NTM stabilization decrease of losses

Günter EX/6-1

(2,1)

Fast ion losses trackthe details of the mode

f (kHz)

time (s)


Unexpected broadening of NBI driven currents

Switch on / off-axis at 4.1 s

UL(V)

4.2 s 0.1 s

3.5-4.0 s

- beyond a certain heating power, measured and predicted distributions of NBI driven currents deviate (MSE, TRANSP)

- electric field changes cannot be explained by current diffusion

Günter EX/6-1, McCarthy TH/P3-7





Günter EX/6-1, McCarthy TH/P3-7


UL(V)

4.2 s 0.1 s

3.5-4.0 s

4.3 s 4.4 s 4.5 s





energetic particle diffusion driven by small-scale turbulence (gyrokinetic code)

redistribution of injected ions

with Dfast0.5 m2/s

Günter EX/6-1


UL(V)

4.2 s

3.5-4.0 s

4.3 s 4.4 s 4.5 s


ELMs and disruptions

Neuhauser EX/P8-2

• most of the ELM and disruption energy is deposited in the divertor• a smaller fraction goes to the main chamber wall

ELMs:- helical field aligned structures with a 3-6 cm spatial width and 3-6 km/s rotation velocity - move radially far into the SOL (LFS)- heat flux decay length 2-3 cm- particle flux decay length comparable

- consistent with convective loss along field lines

ITER: small ELM regimes / ELM pacemaking & disruption mitigation mandatory


ELMs and disruptions

Pautasso EX/P8-7

• most of the ELM and disruption energy is deposited in the divertor• a smaller fraction goes to the main chamber wall

Disruptions:- mitigation by puffing of noble gases (Ne)

regularly used at AUG

- significant reduction of force loads on all structures- divertor heat load mainly reduced by broader radiation and heat deposition profiles in divertor- further optimization needed: higher gas pressure and amount

ITER: small ELM regimes / ELM pacemaking & disruption mitigation mandatory

Erad (kJ)

vertical bolometer channels

w/o gas puff

w. gas puff


NTM stabilization: Influence of ECCD deposition width d

narrow deposition W>2d: - IECCD counts for helical CD

- full stabilisation with dc ECCD of (3,2) and (2,1) NTMs

- no advantage of phased ECCD

broad deposition W<2d:

- mimics ITER Wmarg~pol

- IECCD/d2 counts for dc ECCD

- only partial dc stabilization

- required current increases significantly ⇒ modulated ECCD required

(at mode frequency / O-point injection)

tor


NTM stabilization: Modulated ECCD with broad deposition

narrow deposition W>2d: - IECCD counts for helical CD

- full stabilisation with dc ECCD of (3,2) and (2,1) NTMs

- no advantage of phased ECCD

broad deposition W<2d:

- mimics ITER Wmarg~*

- IECCD/d2 counts for dc ECCD

- only partial dc stabilization

- required current increases significantly ⇒ modulated ECCD required

(at mode frequency / O-point injection)

Zohm EX/4-1RbYu TH/P3-13

17

184 X-point modulation

O-point modulation

tor


NTM stabilization: Modulated ECCD with broad deposition

Confinement improvement

j~IECCD/dW<2dITER

W>2d

O-point modulation

X-point modulation

Zohm EX/4-1Rb


High-Z wall and divertor in ITER / DEMO

pro: - tritium co-deposition with carbon - erosion of low-Z material - neutron bombardment destructs graphite

con: - central radiation losses sets limit cW< some 10-5

ITER DEMO

Dux EX/3-3RaSputtering source mainly from LFS limiters

- CX neutrals Te(edge)

- fast ions from NBI: depends on injection geometry

antenna limiters with ICRH: 60-90% of W influx - sheath rectified E-fields accelerate impurities- drastic enhancement of all sources during ELMs

Impurity transport- H-mode barrier ELM frequency control by pellet injection- neoclassical inward pinch- anomalous outward impurity transport enhanced by central heating (ICRH, ECRH) 0 0.1 0.2

1

10

100

pea

kin

g o

f c W

PECRH/Ptot


W wall: Long term evolution of W concentration

- wide distribution depending on plasma conditions:

increase with W coverage, saturation of mean value around 10-5

- reduced cW at relevant central heating power and higher densities (ITER!)


W wall: Indications for transitions to W device

reduction of C plasma content

(standard H-mode discharge)

Migration / transport model

- slow evolution due to strong C recycling

- C ‚leaking‘ out of divertor important

11019 atoms/s

remaining strong net erosion zone

Noble gas retention / release:Schmid EX/3-3Rb

Dux EX/3-3Ra


Improved H-mode: Characterization of „advanced scenarios

Reversed shear, ITB discharges: hollow current profile

high NH/q952>0.25 only transient

• control of pressure and current delicate • high bootstrap fraction > 60% ss• transport bifurcation

0

1

2

3

4

5

0 0.5 1r/a

strong

weak

q

Standard H-mode

~ zero shear

Reversedshear

Zero shear, ‘hybrid’ discharges: elevated q(0) above 1 desirable

stationary with NH/q952 up to 0.4

• high -limit close to no wall limit• substantial bootstrap fraction 50%• no bifurcation, smooth evolution

r/a 1

pla

sm

a p

ress

ure

0 0.5

Standard H- mode

~zero shear

Reversed shear


Improved H-mode: Performance and operational range

N = 2-3.3 and H98(y,2) =1-1.5

N above 3 achievable at q95=3-5

operating at ITER collisionality and at densities close to Greenwald stationary on several current diffusion times

similar correlation of density peaking to *

Sips EX/1-1, Weisen EX/8-4

DEMO


heat transport given by TEM/ITG turb.

- stiff temperature profile

- plasma energy connected with pedestal pressure (pedestal energy) confinement improvement weakly correl. with more peaked density profiles

pedestal top pressure enhanced

- increases stronger than Padd0.3

- predominantly Te,i rise

due to broader barrier width

- pbarrierconst.

Improved H-mode: Confinement

Suttrop EX/8-5, Maggi IT/P1-6,


Improved H-mode: Influence of q-profile

Scenarios with limiter /divertor ramp-up, early / late heating: effect on q profile

H98(y,2)=1.5, N=2.9

q954

H98(y,2)=1.2, N=2.3

q954

Stober EX/P1-7


different MHD behaviour: both clamp the current profile

slightly peaked current profile flat central current profile

influence on transport: - theory tells us R/LTi~s/q

- both quantities up to 25% enhanced for flat q-profile

- in agreement with threshold from GS2 (max=ExB)

edge pressure increased in case with flatter q-profile

Improved H-mode: Influence of q-profile

sawteeth

toroidalmodenumber n

freq

uenc

y (k

Hz)

time (s)

Stober EX/P1-7


Improved H-mode:(3,2) NTM suppression with ECCD

q95=2.9

N2.6

H98(y,2)1.2

dc, W/(2d)=0.6

- at low q95<3.5 large (3,2) NTM can develop strong impact on confinement- after stabilization transition to fishbone activity enhanced performance

Sips EX/1-1Zohm EX/4-1Rb


Substantial progress for the benefit of ITER was achieved.

AUG focuses on integrated ITER scenarios and performance beyond reference

Understanding of anomalous transport and turbulence (TEM,ITG) proceeds: ITER: peaked density profiles and benign high-Z accumulation to be expected

Fast ions: - losses caused by MHD and anomalous diffussion important

- off-axis NBCD above a certain turbulence level questionable

Modulated ECCD needed for NTM stabilization of ITER reference scenario

ELM (pacemaking) and disruption mitigation (gas injection) schemes evolve

high-Z walls compatible with tokamak operation modes - impurity sputtering source by ICRF accelerated impurities critical - accumulation control by ELMs and central heating (-particles) afforded

Improved H-mode / Hybrid scenario guides ITER beyond reference scenario

- ITER parameter range achieved (q95, *, ne/nGW)

at H98(y,2)=1.1-1.5 and N=2.5-3.5

- Q and prolonged pulse length at full current (q95=3)

- Q=10 and 1 h pulses at reduced current (q954)

- heating power of 73 MW may not be sufficient to achieve N3 for IPB98(y,2)


Main aim is to establish the physics base for ITER (and DEMO): - consolidation of the 'standard' H-mode scenario - exploration of ‚advanced' modes beyond standard scenario

Understanding of physics elements

- transport Angioni EX/8-5Rb, Conway EX/2-1, Jenko EX/8-5Ra, Weisen EX/8-4

- fast particles and NBCD Günter EX/6-1, McCarthy TH/P3-7

- H-mode edge and ELM tailoring

- disruption mitigation Pautasso EX/P8-7

- MHD control with ECCD Zohm EX/4-1Rb, Yu TH/P3-13, Merkel TH/P3-8

- tungsten wall and divertor Dux EX/3-3Ra, Schmid EX/3-3Rb

Integration into improved scenario beyond reference - Improved H-mode (Hybrid scenario)

Pereverzev FT/P5-23

Sips EX/1-1, Suttrop EX/8-5,Stober EX/P1-7, Maggi IT/P1-6,

Neuhauser EX/P8-2, Chankin TH/P6-15, Scott TH/1-1

AUG contributions to this conference


Technical incident with EZ4 at 27.04.06

flywheel generator EZ4 damaged

construction 1986,power 220 MVA,total weight ca. 160 tnumber of pulses est. 75.100,operated for est. 7.900 h

- eperimental campaign terminated- extent of damage: overhauling of generator rotor, new generator stator- operation in 2007 with EZ2 & 3 with only limited restrictions:

60% of all pulses possible with reduced coil voltages- full W machine will start with limited wall loads and discharge parameters

- in medium-term the full power/energy supply is needed for all relevant ITER work


ASDEX Upgrade, JETand ITER: a stepladder

similarity to ITER in coil system and divertor configuration - similar in geometrical configuration (linear dimensions scale 1:2:4) - different in size and therefore in dimensionless parameter * similarity in cross-section - size scaling and extrapolation to ITER


AUG uses three flywheel generators as power/energy source EZ2 (1.45 GJ / 167 MVA): toroidal field EZ3 (500 MJ /144 MVA) + EZ4 (650MJ/220MVA): OH, pol.field, add. heating

Present settings for PF coils: reduced power and energy with EZ3 alone allow only 15 % of the last 2000 # (Ip<800 kA, Padd<5 MW, <5 s)

Reduced max. coil voltages (except divertor coils) reduced reactive power consumption (speed)

about 60% of the last 2000 # are still possible Ip=800 kA, 5-10 MW, 5 s Ip= 1 MA, 5-7.5 MW, 3-4 s at lower dens.& triang.

W program (highest priority in 2007) nearly without restriction full ELM and disruption control program restricted high- discharges at low * and *

strongly reduced NTM stabilization schemes

the planned short-term investigations can be done with only minor restrictions medium-term the full power/energy supply is needed for all relevant ITER

work

Operation with reduced generator capacity (EZ2, EZ3)

0

5

10

15

20

EZ

3 (k

A)

0.4 0.6 0.8 1.0 1.2Ip(MA)

EZ3 > 11 kAEZ3 ≤ 11 kA

Limit: 11 kA

A.C. Sips, W. Suttrop


Integrated evaluation of core and edge data:- state-of-art core diagnostic suite - multi-system, good resolution SOL & divertor diagnosticsNew or extended diagnostics:

Doppler reflectometry edge Ti and impurity densities from Li beam ultrafast (ns) Thomson digitisation for filament detection fast ion loss detector (new FILD at fixed positions) fast pellet observation (KFKI, Budapest) combined Langmuir and magnetic probes

Diagnostics under development collective TS at 105 GHz (Risø) distribution of fast ions; radiation level? collective TS at 140 GHz (Nizhny Novgorod / WTZ) magnetic field direction extension of reflectometry bands (Q band, IST Lisboa) SXR crystal spectrometer (Moscow, ITER) tangential edge CXRS system (NBI source 3 as radial CXRS, MSE) fast ELM resolving camera SXR (48 out of 148 lines of sight)

Enhancement of equilibrium reconstruction (CLISTE, FPJ)

Diagnostic extensions 2005/ 2006


Understanding of anomalous transport predictions

Flattening of density profile with increasing collisionality: AUG, JET, TCV:- transition from dominant TEM to ITG turbulence

- decrease of Te/Ti supports (heat pulse studies)

- gyrofluid model GLF23 agrees, nonlinear gyrokinetik GS2 results disagree

Strong link between ion heat and momentum transport

- colinearity between Ti and vtor

- strong correlation between and i-i,neo: ratio decreases across radius

No anomalous central impurity accumulation with central auxiliary heating- quasi-linear estimates with GS2 - impurity outward pinch driven by ITG turbulence under experimental conditions- -heating in ITER will do the job

Robust negative well of Er at plasma edge (Doppler reflectometry)

- negative well coincides with steep H-mode barrier pressure gradient

- Er shear enhanced as well


Transport: Er transitions at plasma edge

negative Er well increases

with confinement improvement

- coincides with H-mode barrier gradient

- Doppler reflectometry

Er shear enhanced as well

- 2 channel Doppler at fixed f ~ 2GHz

- negative shear at pedestal increases with confinement

- shear width 5cm

Conway EX/2-1

H98(y,2)


- FILD signal caused by DTM- response time depends on origin- orbit drifts and slowing down determine delay

beamswitch-off

beamswitch-off

4 ms

- Fast Ion Loss Detector (FILD) with bandwidth of 1 MHz

- frequency / phase correlations of fast ions with TAEs (from ICRH beatwaves)

- FILD spectrogram shows fast particle losses correlated with

low frequency MHD activity: NTMs, double tearing modes, ELMs

Fast particle interactions with large scale instabilities

Unexpected broadening of NBI driven currents:- energetic particle diffusion driven by small-scale turbulence (gyrokinetic code)

- redistribution of injected ions with Dfast0.5 m2/s


Fast particle losses caused by MHD activity

FILD spectrogram shows fast particle losses well correlated

with TAE activity (NBI, ICRH, ICRH beat waves)

- ICRH creates trapped fast particles

- vperp/v ~0.9,

energy up to several hundreds keV

- TAEs modify orbits of fast particles

Munoz, K. Sassenberg, PhD, Cork, Ireland


NTM stabilization: Influence of ECCD deposition width d

ITER: - threshold reduces with pol

AUG: - frequently interrupted NTM (FIR) allows higher ´s

- ECCD with helical current within the island to compensate the

missing BS current: jECCD>jBS


Full stabilisation of (3,2) NTM with modulated ECCD (d>W)

ECCD modulated with phase from magn. signals with fmode < 30kHz reduced overall deposited ECCD power complete stabilisation at high N / <PECCD> ~ 4.0 MW-1

W/(2d)= 1.2


Improved H-mode: Scenario development

early versus late heating:

Te,i(0)4 keV

q954.8

ramp-up indivertor configuration

Stober EX/P1-7


NI

Improved H-mode: Scenario development

early versus late heating: performance increase

Te,i(0)4.5 keV

Te,i(0)5.2 keV

q954.8

N and H98(y,2) differences disappear at higher heating powers

ramp-up indivertor configuration

Stober EX/P1-7


heat transport given by TEM/ITG turbulence

- stiff temperature profile

- plasma energy connected with pedestal pressure (pedestal energy) confinement improvement weakly correlated with more peaked density profiles

- flatter density profiles anyway due to central heating (impurity accumulation!)

Improved H-mode: Confinement

Suttrop EX/8-5


Scenario development for ‚Improved H-Mode‘

early versus late heating

pol

pol

Reich, Stober


Improved H-mode: predictions for ITER

q95, N as in AUG, <n>/nGW=0.85, Te=Ti Pfus

Extrapolation to ITER using AUG kinetic profile shapes and IPB98(y,2) scaling

Ip=11.8 MA

q95=3.8

Paux=52 MW

Q=11.4

Improved H-modeIp=14.2 MA. q95=3.2

Paux=0

Q

Ip=9.7 MA

q95=4.6

Paux=55 MW

Q=6.5

standard H-modeIp=14.7 MA, q95=3.1

Paux=78 MW

Q=8

0

200

400

600

800

1000

1200

10 11 12 13 14 15Ip- ITER (MA)

open symbols Paux > 73 MW

closed symbols Paux ≤ 73 MW

ITER15 MA N,th 2.0

N,th = 2.5-3

Pfu

s (M

W)

Sips EX/1-1

Paux, Q


Test of W VPS coatings for divertor strike-points

200µm W VPS coatings

on graphite with adjusted

thermal expansion:

(Plansee, Sulzer Metco)

screening:

4 – 23 MW/m² cyclic loading:

10.8 MW/m², 3.5 s,

> 100 pulses

coatings are qualified for use in the lower divertor

0 2 4 6 81000

1500

2000

2500

16.2 MW/m²

6.5 MW/m²10.8 MW/m²

4.2 MW/m²

23.5 MW/m²

density 95% bulk W90% bulk W

pulse length (s)

Tsu

rf (

°C)

heat load tests in ion-beam facility GLADISH. Greuner


Scenario development for ‚Improved H-Mode‘ (Hybrid mode)


Combination of high power, flexible addititional heating, current and shaping capability, density operation up to Greenwald and long pulse length (> current diffusion time) allows unique exploration of advanced scenarios beyond ITER baseline Improved H-Mode in ITER allows Q>30 and / or pulselength above 1 h Improved H-Mode may allow even ‚steady state‘ in DEMO

Development of ‚Improved H-Mode‘ (Hybrid mode)

4

open: <10E

closed: >10E

N

ITER

ITPA

i*

JET

DIII-DAUG

JT-60U

0

1

2

3

0 5e-3 1e-2 1.5e-2


ECRF system: summary and outlook

• successful long pulse tests in factory test stand• long pulse tests at IPP hampered by load performance: few 10s pulses achieved up to 600kW at 105GHz and 800kW/140GHz• frequency drift during a gyrotron pulse within the limit for future double disc window application at intermediate frequencies (max. 150 MHz at 140 GHz)

• failure of vacuum conditions in the magnet lead to freezing of gyrotron cooling circuits;

cavity deformation prevented further operation of the gyrotron

measures for continuous, temperature controlled water circulation envisaged

• gyrotron Odissey-1 to be returned to GYCOM for repair• gyrotron Odissey-2 was successfully tested at GYCOM

planned installation as 2f gyrotron in coming weeks• after repair, Odissey-1 will be equipped with double disc window

planned operation as multi-frequency gyrotron end of the year


AUG enhancements: fast steerable ECRF launchers

ECRH launching mirrors in sector 5

launcher mirrors: W / Cu - coated graphite

Fast poloidal steering testedduring ASDEX shots withB=-2.18T, Ip=800kA:

a poloidal angle variationof 10° in 100 msec has been achieved

D. Wagner


Future AUG hardware extensions

● Internal coils - besides RWM control many other applications (f=1/10 kHz); 2007-9 - compatibility w. RWM control; - compatibility with heating systems - diagnostic access (YAG,...); - relevant diagnostic development

● ICRH antenna fitting to shell installation befor shell mounting ? LHCD 2008-10 5 MW at 3.7 GHz; 200 kA off-axis CD hardware and manpower from Associations needed

● Stabilising shell 2009-10


Consolidation of ITERStandard operation

Preparation of ITERAdvanced operation

2005 2006 2007 2008 2009 2010

LHCD (projected)

Tungsten Wall

ECRH Extension

Modular Flywheel Generator(s)

Internal Coils

Conducting shell

Design Construction Operation

Future AUG hardware extensions

Documents

Otto Gruber for the ASDEX Upgrade Team