TORE SUPRA : 2011

X LITAUDON on behalf of TORE SUPRA TEAM
CEA-IRFM, Institute for magnetic fusion research (IRFM)
CEA Cadarache
F-13108 St Paul Lez Durance. France
e-mail: xavier.litaudon@cea.fr
ITPA-IOS group, Kyoto, 18-21 October 2011

X. Litaudon on behalf of Tore Supra team1

2011 Experimental Campaign
 21 April up to end July 2011
 Overall Coordination– Experiments & physics programme B. Saoutic & Y.
Corre
– Technical coordination M. Houry Three Task forces– Qualification of new CW LHCD system ( ITER launcher
and transmitter): A. Ekedahl– Development of long pulse scenario : R. Dumont– ITER operation preparation: S. Bremond

ITPA-IOS group, Kyoto, 18-21 October 2011

X. Litaudon on behalf of Tore Supra team2

Scenario development: extended domain ofsteady-state operation2011 Scenario
Development:
High energy with LHCD
5MW LHCD 400s

High energy with ICRH
4MW LHCD + 3MW ICRH 200s

High power discharges
6MW LHCD + 9MW ICRH 30s

ITPA-IOS group, Kyoto, 18-21 October 2011

+ Physics thrusts
on MHD, transport,
rotation
X. Litaudon on behalf of Tore Supra team3

TORE SUPRA 2011
 LHCD: Recent large upgrade

TED 2103C Klystrons– 2009: Installation of PAM launcher– 2010-11: 8 new klystrons on FAM
 ICRH:– up to 9MW during 30 s (3antennae)– or 3MW long pulse– New Faraday screen (one antenna)
 ECRH:– 700kW during 5s
 IR monitoring:– for RF operation & to protect fully
actively cooled tokamak
 Upgrade diagnostics– Reflectometry
ITPA-IOS group, Kyoto, 18-21 October 2011

X. Litaudon on behalf of Tore Supra team4

New CW klystrons validated on plasma operation
Coupled power: 3.8MW (> 4.0MW at klystrons) with Full
Active Multi-junction launcher (FAM), fed by a set ofeight 700 kW/3.7GHz CW klystrons.
TH2013C: 700kW CW on matched load

#48081<ne> (1019 m-3)
PLH = 3MW

L. Delpech et al., 19th RF Conf., Newport (2011)
G. Berger-by et al., 19th RF Conf., Newport (2011)
ITPA-IOS group, Kyoto, 18-21 October 2011

X. Litaudon on behalf of Tore Supra team5

Long pulse operation with both LHCD launchers
Both LHCD launchers together  4.5MW/150s obtained(650MJ injected energy)
Opens new operational space (ne, IP) for long pulse operation

Total PLHCD
PAM, FAM

Slow increase in density due to nonoptimised feedback control
A. Ekedahl et al., 19th RF Conf., Newport (2011)
ITPA-IOS group, Kyoto, 18-21 October 2011

X. Litaudon on behalf of Tore Supra team6

Control improvements for long pulse operation:transition to feedback controlled loop voltage
Issue: jump in Lower Hybrid power during transition from Ip
control to (VG0, PLH) <-> (Ip, Vloop) control
Development : Multi Input Multi Output feedback control

1

Ph Moreau

TS#38488

Flux (Wb)

0.5
0

8
6
4
2
0
1.5
1
0.5
0
-0.5
3
2
1
0

Plh (MW)Vg0 (kV)

Typicalsituation
beforeIp (MA)

Control oriented model development, feedback control design andtest on simplified model and on METIS code, experimental validation

0

5

10

15

20

25

30

0

5

10

15

20

25

30

0

5

10

15

20

25

30

0

5

10

15

20

25

30

New MIMO control now in routine operation

ITPA-IOS group, Kyoto, 18-21 October 2011

X. Litaudon on behalf of Tore Supra team7

Measurements of Density Profile in the Scrape-off-Layer with
Reflectometer Embedded in the LHCD Full Active Multijunction Antenna

 Crucial to study LH coupling and SOL physics
 Strong increase of density gradient in the SOL
during LHCD

C. Bottereau et al. 2011
ITPA-IOS group, Kyoto, 18-21 October 2011

X. Litaudon on behalf of Tore Supra team8

Ray-tracing modelling of full current drive discharge
Full CD regime (PAM alone) for 50sn//spectrum(ALOHA) n// spectrum from ALOHA code (using

measured values of power, phase andedge density) Hillairet et al Nucl. Fusion 50
125010 Ray tracing code, C3PO, using 36
Y Peysson and J Decker. EPS 2011 &rays (6 n//-values x 6 waveguide rows) PPCF
ITPA-IOS group, Kyoto, 18-21 October 2011

X. Litaudon on behalf of Tore Supra team9

Good agreement with modelling, in this example
LH current profile for #45534

Line integrated HXR emission

IPlasma exp: 510kA
ILH LUKE: 508kA
ILH Cronos/HXR: 443kA

Experiment
Modelling

Dfast = 0.1m2/s

C3PO/LUKE reproduce well the HXR
profile and the driven current.

Synthetic diagnostic models well
the line integrated HXR emission.

Y Peysson and J Decker, Phys. Plasmas (2008)
J Decker et al., 19th RF Conf., Newport (2011)
Although good agreement in this example, robustness in LHCD
modelling is still required.
Y Peysson et al., 19th RF Conf., Newport (2011)
ITPA-IOS group, Kyoto, 18-21 October 2011

X. Litaudon on behalf of Tore Supra team

10

ITPA-IOS experiment: LHCD modelling vs HXR
measurement
TS#45155

PLH =2MW
At first order

IHXR ~ nenfastZeff f(Z)~η Zefff(Z)~Te Zefff (Z)~ne-2
IHXR, experimental ~ <ne> -2.5, -3.5

ILH~η ne-1~Tene-1~ne-2
ILH, computed ~ ne-3

Experimental HXR scaling (ne-2.5,-3.5) is consistent with
RT/FP computation of ILH

Goniche et al and Oosako et al RF 2011 conf.

ITPA-IOS group, Kyoto, 18-21 October 2011

X. Litaudon on behalf of Tore Supra team

11

ITPA-IOS experiment, LHCD experiments at High Density :Gas vs. Pellet Fuelling and role of edge fluctuation• HXR emission stronger with pellets when ne>4×1019m-3• Faster decay of HXR correlated to strong increase of
SOL density fluctuation
Goniche et al RF & EPS 2011 conf.
ITPA-IOS group, Kyoto, 18-21 October 2011

X. Litaudon on behalf of Tore Supra team12

High density long pulse operation with LHCD &ICRH: new GJ discharges in 2011 !!
• ~1GJ (~6.3MW/150s) injected/extracted energy• Non-inductive fraction ~80% with sustained e-ITB!
Bo~ 3.8T, nl = 4.1x1019m-3, Ip = 0.7MA
βp ~0.6, βN ~ 0.7 PLHCD = 2-6MW PICRH = 1-3MW
Tore Supra # 47979

ICRF reduced by RT
protection: overheating of
LHCD coupler

R. Dumont et al
ITPA-IOS group, Kyoto, 18-21 October 2011

X. Litaudon on behalf of Tore Supra team13

ICRF power stabilizes MHD activity
in non-inductive LHCD discharges as expected
MHD activity ~500ms after
ICRH swith-off
Tore Supra # 47319

2011 discharges[ M. Zabiego et al, PPCF 2001 ]R. Dumont et al
ITPA-IOS group, Kyoto, 18-21 October 2011

X. Litaudon on behalf of Tore Supra team14

q-profile & improved confinement sustainedin the GJ discharges
 electron ITB:
 Global confinement–

Low magnetic shear incore– High magnetic shear in
confinement domain

Tore Supra # 47979

R. Dumont et al
ITPA-IOS group, Kyoto, 18-21 October 2011

Ph . Lotte et al
X. Litaudon on behalf of Tore Supra team15

Large central temperature variations: couplingq & transport (through bootstrap current ?)Tore Supra # 48161

C. Bourdelle 2011, Giruzzi et al PRL 2003, Imbeaux et al PRL 2005
ITPA-IOS group, Kyoto, 18-21 October 2011

X. Litaudon on behalf of Tore Supra team16

First Observation of Turbulence Dynamics
in the Scrape-off-Layer (SOL) with Ultra-Fast Sweep Reflectometry

 Strong intermittent behaviour into the SOL
Spatial origin of “Blob-like” structures well identified radially New plasma physics issues

Blob-like structure observed in
the SOL of plasmas heated by
ICRH
F. Clairet, 38th EPS Strasbourg

June 201117

2011: New Faraday Screen for ICRH Antenna Designed to minimize RF  Leak tests validated: jan. 2011
sheath potential & RF tests on new test bed facility: 03/11
mechanical constraint on
 Experiments on Tore Supra: RF
FS Bars
sheath physics, power coupling, impurity
production, thermal cooling; withparticipation of ITER-IO & ICRH experts
Simulated RF potentials

new concept

L. Colas, K. Vulliez

R&D aspects relevant for ITER

ITPA-IOS group, Kyoto, 18-21 October 2011

X. Litaudon on behalf of Tore Supra team18

Measurement of the DC floating potential with RF fields(Tunnel probes)

0.5

Probe

Ref.
plane 0.5
IC ant.
Z(m)θ /πq(a)=7.5

0

Probe
IC
ant.

q(a)=7.50q(a)=3.2q(a)=3.2

-0.5
-0.5
0

0.5

φ1/π

1.5

2

2

ITPA-IOS group, Kyoto, 18-21 October 2011

2.5
R(m)

3

J. Gunn, M. Kubic EPS 2011

X. Litaudon on behalf of Tore Supra team19

Thermo-mechanical calculation andcomparison to experiments
MesuretempératureantenneQ5barreau8- 47204- Q2=2MWQ5=2MWIp=1MA

400

15.0%

 Thermo-mechanicalTexp- moyennesur profil avecécart type12.5%
modelling reproduces
experiments
Tsimulation- h13000W/m²K- 10kW/m² / 690kW/m² +350

claquages0kW/m²

300

10.0%

T (°C )

Ecart typerelatif actively cooled
Faraday screen: goodthermal response

250

7.5%

200

 But the local heat flux
is 10 times higher
5.0%
compared to standard
FS

150

2.5%

 consequences for
0.0%
ITER design

t (s)
100
0

5

10

– 375-690 kW/m2

15

20

25

M. Firdaouss
ITPA-IOS group, Kyoto, 18-21 October 2011

X. Litaudon on behalf of Tore Supra team20

Other issues related to ITER operation
preparation
 Disruption runaway electrons suppression by highpressure fast gas injection
 Event / Exception handling High density/high radiation Operation
 EC assisted plasma start-up :assistance to plasma start-up by 2nd harmonic
X-mode ECRH with 20° tangential injection (ITER at
half magnetic field)
 Effect of local gas puffing on IC/ LHCD power
coupling Heat flux pattern on leading edge of misaligned tile
 Characterisation of the SOL near limiter plasmatangency point Wall conditioning by low frequency glow discharges
and by Ion Cyclotron
ITPA-IOS group, Kyoto, 18-21 October 2011

X. Litaudon on behalf of Tore Supra team21

Runaway electron mitigation by high pressure fast gaz
injection
 Motivation : suppression of runaway electron in ITER
by fast injection of dense gas jet in the current
quench (alternative to massive material injection)

FIRE setup (Fast Injection by
Rupture disk Explosion) sucessfully
developped (ITER contract)
HV
conductor
Cartridge
body
Springelectric arc

F. St Laurent
ITPA-IOS group, Kyoto, 18-21 October 2011

Rupture disk
X. Litaudon on behalf of Tore Supra team22

First results: neon gas flow observed by fast camera
Propagation of the Neon gas injected by Fire from the
top of the machine during plasma current quench
TS#47373 @ -8.01ms / Ip = 820 kA

TS#47373 @ -7.85ms / Ip = 786 kA

TS#47373 @ -7.61ms / Ip = 736 kA

TS#47373 @ -7.37ms / Ip = 686 kA

TS#47373 @ -7.21ms / Ip = 656 kA

TS#47373 @ -6.97ms / Ip = 607 kA

TS#47373 @ -6.73ms / Ip = 566 kA

TS#47373 @ -6.57ms / Ip = 541 kA

Fast visible camera images filtered for Ne I line. Front moves with v ~500 m/s for
Ne and 1200 for He (1/2 of gas velocity in vacuum)

F. St Laurent
ITPA-IOS group, Kyoto, 18-21 October 2011

X. Litaudon on behalf of Tore Supra team23

Modelling of Event / Exception handling
0.6

4

Nl (x 10+19 m-2)

0.4

Ip

0.2
0
8

2

Vloop/5

0
2.0

Power
(MW)

6
ICRH

4

ROG (cm)
2.2

LHCD#2

2

LHCD#1
2.4

0Temperature
(°C)

LH#2

600
LH#1

400
200
0

10
LH#1 unavailable

20

LH#2 Temp threshold

Missing power redistribu- ROG is increased,
ted on LH#2 to ensure Vloop≠0 during transient
Vloop=0(Ip maintained)

30

Time (s)LH#2 unavailable

Vloop=0 not recovered

Vloop≠0 tomaintain Ip

Soft Stop is
triggered

Local E/E report

Orange

Red

Red

Red

Global E/E report

Green

OrangeRed

Red

R. Nouailletas
ITPA-IOS group, Kyoto, 18-21 October 2011

X. Litaudon on behalf of Tore Supra team24

ne/nGr=1.4 maintained for several τE in RF
heated plasmas with 90% radiated power Regime similar to ‘high recycling’ regime inaxisymmetrix X-pt divertors
 No degradation of global energy confinement
TS47346

1.2

4

1.4

1.4
gnl%4

1.2

Pfci
3

1.0

1.0

0.8
0.6
0.48

2

0.8
Wdia (MJ)

0.6 ne/nGr

0.46
0.44

Prad/Ptot

1

0.4

0.42
0.40
0.7

0.8

0.9

1.0

1.1

0.2

6

7

8

9

10

0
11

gnl%8

tps (s)
ITPA-IOS group, Kyoto, 18-21 October 2011

X. Litaudon on behalf of Tore Supra team25

Tore Supra: prepare ITER long pulse operation
 Plasma operation restarts in Sept. 2012
– Shutdown: modification of HV 400kV network for ITER Full H&CD CW capability & 2012 upgrade– 6-7MW LHCD (CW) + 3MW ICRH on more than ~200s– Assess power limit of CW ITER-PAM– Antenna & machine protection upgrade– Diagnostics upgrade: fast core reflectometry– ECRH antenna upgrade (in collaboration with FOM): Mirror
mouvement for real time control
 Master long pulse operation: minimising risks for ITER
– fully non-inductive plasmas at higher Ip and density– Disruption mitigation– real time control for machine protection & performance
optimisation: IR control of hot spots, ripple fast losses...
– Physics of evanescent Vloop plasma on time scale much longer
than current diffusion: MHD, intrinsic rotation, ...
ITPA-IOS group, Kyoto, 18-21 October 2011

X. Litaudon on behalf of Tore Supra team

26

WEST : minimising risks for ITER operation
Use Tore Supra assets to prepare ITER exploitation

ITPA-IOS group, Kyoto, 18-21 October 2011

X. Litaudon on behalf of Tore Supra team27

WEST : extending H mode towards steady stateand exploring PWI with actively cooled W

ITPA-IOS group, Kyoto, 18-21 October 2011

X. Litaudon on behalf of Tore Supra team28

Thanks for your attention !

ITPA-IOS group, Kyoto, 18-21 October 2011

X. Litaudon on behalf of Tore Supra team29

Stationary electron ITBs in LHCD & ICRH
long pulse discharges
2011 discharges
Typical Te profiles

R. Dumont et al
ITPA-IOS group, Kyoto, 18-21 October 2011

X. Litaudon on behalf of Tore Supra team30

Barrier characterization with ECCD
Tore Supra # 47968

HXR signal (60-80keV)

Balanced co/cnt-ECCD (PEC ~ 0.8MW)

During ECCD

Before ECCD

G. Giruzzi et al
ITPA-IOS group, Kyoto, 18-21 October 2011

X. Litaudon on behalf of Tore Supra team31

CRONOS interpretative transport analysis:
clear e-ITB in the low magnetic shear region

C. Bourdelle

Normalised radius

ITPA-IOS group, Kyoto, 18-21 October 2011

X. Litaudon on behalf of Tore Supra team32

48161, discharge with Te oscillations

47901, with eITB

ITPA-IOS group, Kyoto, 18-21 October 2011

X. Litaudon on behalf of Tore Supra team33

After oscillations

ITPA-IOS group, Kyoto, 18-21 October 2011

X. Litaudon on behalf of Tore Supra team34

ITER context
 RF sheath modelling with RF
fields from TOPICA– Non consistent calculation
 Minimisation of RF sheath byminimising the E// (slow wave)

field line

E// RF dl

 Design of New
Faraday screen on
Tore Supra based on
the same modelling
approachc a da r a c h e

i r f mCYCLE

POLITECNICODI TORINO∆V = ∫

6 poloidal by 4 toroidal staps ,40-55MHz, 20MW
ITPA-IOS group, Kyoto, 18-21 October 2011

X. Litaudon on behalf of Tore Supra team35

Self-consistent non-linear ICRH wave
propagation and RF sheath rectification• RF sheath rectification treated as Slow Wave propagation
self-consistently coupled with DC edge plasma biasing.
Non-linear coupling is ensured via RF and DC sheathboundary conditions.

•

DC current generation:– thedifferential
biasing of adjacent
flux tubes connected
electrically via DCtransverse plasma
conductivity– asymmetricRFsolicitation at bothends of the field line

Colas EPS 2010,Jacquot RF conf 2011
ITPA-IOS group, Kyoto, 18-21 October 2011

X. Litaudon on behalf of Tore Supra team36

Event / Exception handling architecture overview

Plasma scenario

Operation limits

Desired references(pulse references)

E/E
handling
Optimized
requests

BC

E/E
handling

E/E
handling

PlasmaE/E handling

Raw data
Fault detection

Group 2A

B

Actuators

C

Diagnostic 1 Diagnostic 2

Plasmastate

Equipment
layer

A

E/E
handling

ActuatorstatusGroup 1

Desiredplasmastate

Checkedoutputs

Reports

Central control Local control
layer
layer

Overall E/E handling

Diagnostics
Plasma

ITPA-IOS group, Kyoto, 18-21 October 2011

X. Litaudon on behalf of Tore Supra team37

Implementation of an E/E handling system on a tokamak/plasma
simulator
ICRH models Solenoid +
METIS
Ref

Basic plasma models• Circuit equation (R, Li, M, constant)
ILHCD

RCS
VCS

RplasmaM

Ip

PlasmastatusOhmiccurrentsource

LHCD
modelsLocal E/E
handling

LHCD

Non inductive
current
source0-D plasma models replaced by
METIS code
• plasma evolution simulation
 Current diffusion solver
 Grad-shafranov equation solver
 Scaling law for plasma parameters(inductive/non inductive current, etc.)

ICRH
EventsLi

LCS

Op
limitsGlobal E/E
handling• ICRH strap voltage and reflected power• PFC temperature−d / dT&QiLj = K Qi nl e Qi 0 PQ1i/ 2 + K LH PLH()+ K ICRH PICRH + K H 2O TH 2O − TQiLj + δ QiLj
ITPA-IOS group, Kyoto, 18-21 October 2011

Vstrap = Z 0

2 PQi
Rc Lstrap

Rc = α (t )nl e

X. Litaudon on behalf of Tore Supra team− d Qi / dr38