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17 October 2006 121st IAEA Fusion Energy Conference, Chengdu
TORE SUPRAAssociationEuratom-Cea
M. Chatelier
Integration of High Power, Long Pulse Operation in Tore Supra in preparation of ITER
TORE SUPRA
TORE SUPRA
M. Chatelier, on behalf of Equipe Tore Supra
17 October 2006 221st IAEA Fusion Energy Conference, Chengdu
TORE SUPRAAssociationEuratom-Cea
M. Chatelier
Tore Supra, large superconducting tokamak devoted to long-duration, high performance discharges
• 3rd largest tokamak• Operation of the cryo-magnetic system for 18 years• All PFCs actively cooled
• 6 min discharges (2003) with 1 GJ injected/exhausted energy
PLHCD = 3 MW Ip = 0.5 MA ne0 = 2.5 1019m-3
Neutron (x1010/s)
Zeff
Ti(0) (keV)Line averaged density (x1019m-2)
LHCD Power (MW)
Transformer flux (Wb)
Te(0) (keV)
17 October 2006 321st IAEA Fusion Energy Conference, Chengdu
TORE SUPRAAssociationEuratom-Cea
M. Chatelier
Injected power9.5 MW
Large margin towards higher power long discharges
• Convective losses routinely handled by the TPL (3-5 MWm-2)• H/CD systems initially designed for 30 sec operation; ongoing upgrade (see Beaumont et al., IT/2-5)
towards 10-12 MW for 1000 sec, near Greenwald
• Tore Supra current program: Investigation NI dischargesPreparation scenarios &
techniques for high power long pulse operation (based on LHCD & ICRH)
17 October 2006 421st IAEA Fusion Energy Conference, Chengdu
TORE SUPRAAssociationEuratom-Cea
M. Chatelier
CIEL project
(2003, active cooling)
CIMES project(2008, continous Current drive)
Tore Supra
17 October 2006 521st IAEA Fusion Energy Conference, Chengdu
TORE SUPRAAssociationEuratom-Cea
M. Chatelier
Outline
• Safely operating Tore Supra at multi-MW level• Multi-MW long duration discharges results• Integrating operational controls for steady-state scenarios• Turbulence measurements and local transport analysis• Plasma wall interaction during long discharge operation• Technological developments for long discharge operation follow-up• Conclusions and prospects
17 October 2006 621st IAEA Fusion Energy Conference, Chengdu
TORE SUPRAAssociationEuratom-Cea
M. Chatelier
Safely operating Tore Supra at multi-MW level
17 October 2006 721st IAEA Fusion Energy Conference, Chengdu
TORE SUPRAAssociationEuratom-Cea
M. Chatelier
10 MW in TS representative of ITER operation in term of averaged power density & heat exhaust
150 MW
(100 α)Pnom
Convectedpower30 MW
Pinj / R0(4.4 MWm-1)
Radiatedpower130 MW
Pinj / Surf(0.16 MWm-2)
Power density360 MWPinj / Vol
(0.43 MWm-3)
ITER
17 October 2006 821st IAEA Fusion Energy Conference, Chengdu
TORE SUPRAAssociationEuratom-Cea
M. Chatelier
Handling localized heat loads
• LHCD launcher A: fast electrons B: fast ion direct losses
C: Arcing
• ICRH antenna A: fast electrons B: fast ion direct losses
C: Rectified sheath
(see Goniche et al. EX/P6-12)
C (800°)A (1000°)
B’ (1000°)
B (800°)B(600°)
A(800°)
CA(800°)
17 October 2006 921st IAEA Fusion Energy Conference, Chengdu
TORE SUPRAAssociationEuratom-Cea
M. Chatelier
Safely operating Tore Supra at 10 MW level
• 20 areas monitored delivering Real Time IR signals• Each used in RT controller with specific safety strategy
LHCD launcher zone B LHCD launcher zone A
17 October 2006 1021st IAEA Fusion Energy Conference, Chengdu
TORE SUPRAAssociationEuratom-Cea
M. Chatelier
Multi-MW long duration discharges results
17 October 2006 1121st IAEA Fusion Energy Conference, Chengdu
TORE SUPRAAssociationEuratom-Cea
M. Chatelier
Significant ion heating at high Greenwald fraction
• Ip = 0.9 MA; ne0 = 5 1019 m-3; 8.4 MW H/D minority• Ti close to Te
• HITER-L = 1.3
#33612
17 October 2006 1221st IAEA Fusion Energy Conference, Chengdu
TORE SUPRAAssociationEuratom-Cea
M. Chatelier
Toroidal rotation observed with ICRH
• Suggests sheared rotation• Could explain confinement improvement through ITG and TE modes stabilization (Kinezero)
17 October 2006 1321st IAEA Fusion Energy Conference, Chengdu
TORE SUPRAAssociationEuratom-Cea
M. Chatelier
Long sawteeth-free discharges with ICRH & LHCD
• Ip = 0.6 MA; ne0 = 4 1019 m-3; q(0) above 1
PICH = 6.3 MWPLH = 3.1 MW
ββββN = 0.83
Greenwald fract. = 0.93
non-inductive fract. ~ 50%
q(0)
#33898
Ptot
• Reminiscent of hybrid scenarios, but q profile controlled by LHCD
17 October 2006 1421st IAEA Fusion Energy Conference, Chengdu
TORE SUPRAAssociationEuratom-Cea
M. Chatelier
Integrating operational controls for steady-state scenarios
17 October 2006 1521st IAEA Fusion Energy Conference, Chengdu
TORE SUPRAAssociationEuratom-Cea
M. Chatelier
Optimising plasma performance reliability
• Fully NI long discharges prone to MHD activity• Small MHD free operating window (see Maget et al. EX/P8-21)
• RT current profile control:Actuator LHCD n//
Sensor HXR width
• Combined with control of: Ip (LHCD power) Flux consumption (primary)
• Triple control at low loop voltage (< 10 mV) (see Joffrin et al., EX/1-6)
#36133
17 October 2006 1621st IAEA Fusion Energy Conference, Chengdu
TORE SUPRAAssociationEuratom-Cea
M. Chatelier
• RT IR safety + triple control• Discharges 70 sec / 7MW controlled in MHD free window
• Pioneers integration work for ITER when combining:
global performance profile shaping plasma stabilityPFCs protection
Integrating plasma optimisation and safe operation
17 October 2006 1721st IAEA Fusion Energy Conference, Chengdu
TORE SUPRAAssociationEuratom-Cea
M. Chatelier
Turbulence measurements and local transport analysis
17 October 2006 1821st IAEA Fusion Energy Conference, Chengdu
TORE SUPRAAssociationEuratom-Cea
M. Chatelier
Neoclassical level pinch observed inside q=1 in Ω Ω Ω Ω plasma
• Progressive density build-up during sawtooth recovery
• Inward pinch ≈ 0.1 ms-1 ≈ Ware pinch• Low diffusion ≈ 0.1 ms-2 coherent with low ñ level• Vanishes with high CD and/or heating power
see Hennequin et al., EX/P4-36
17 October 2006 1921st IAEA Fusion Energy Conference, Chengdu
TORE SUPRAAssociationEuratom-Cea
M. Chatelier
ββββ scaling experiments in L mode
• Two sets of discharges βn= 0.5 / BT= 3.8T & βn= 0.2 / BT= 3.2T with matched ν*, ρ* & q profiles• Weak β degradation. β exponent:
Global confinement -0.2 ±±±± 0.15Effective diffusivity -0.2 ±±±± 0.4 ITER L-mode scaling -1.4
• Supported by density fluctuation measurements
• Bias in extraction of dimensionless scaling law extraction?
Supported by density fluctuation measurements
17 October 2006 2021st IAEA Fusion Energy Conference, Chengdu
TORE SUPRAAssociationEuratom-Cea
M. Chatelier
Plasma wall interaction issues during long discharge operation
17 October 2006 2121st IAEA Fusion Energy Conference, Chengdu
TORE SUPRAAssociationEuratom-Cea
M. Chatelier
NoPermanentCodeposition
NoPermanentBulk diffusion & trapping
YesPermanentImplantation
YesTransientAdsorption in C porosity
Saturat.Type of
retentionMechanism
NoPermanentCodeposition
NoPermanentBulk diffusion & trapping
YesPermanentImplantation
YesTransientAdsorption in C porosity
Saturat.Type of
retentionMechanism
NoPermanentCodeposition
NoPermanentBulk diffusion & trapping
YesPermanentImplantation
YesTransientAdsorption in C porosity
Saturat.Type of
retentionMechanism
• Long term constant retention rate observed (50-80% injected flux)• Repetitive behaviour on 3 consecutive shots (15 min)
NoPermanentCodeposition
NoPermanentBulk diffusion & trapping
YesPermanentImplantation
YesTransientAdsorption in C porosity
Saturat.Type of
retentionMechanism
Fuel retention in Carbon walls
Time (s)
D r
eten
tion
rate
(D
/s)
D/C = 0.1
17 October 2006 2221st IAEA Fusion Energy Conference, Chengdu
TORE SUPRAAssociationEuratom-Cea
M. Chatelier
Bulk diffusion, a credible retention mechanism
• Evidenced in laboratory experiments at high fluence (fl)• Key parameter: exposure time
• Retained fraction ∝ (fluence)0.5
Time (s)
D r
eten
tion
rate
(D
/s)
D/C = 0.1
• Simple model: implantation up to saturation + evolution retained fraction ∝(fluence)0.5
• Needs to be refined
• Extrapolation to ITER:Bulk diff. possible, but ∝ fl0.5
Codeposition (∝ fl) still major concern
Detritiation difficult for both
17 October 2006 2321st IAEA Fusion Energy Conference, Chengdu
TORE SUPRAAssociationEuratom-Cea
M. Chatelier
Flows in the SOL: a common physics for divertor and limiter machine
• Half recycling at each strike zone + uniform radial outflux from core => nearly stagnant flow at Mach probe
17 October 2006 2421st IAEA Fusion Energy Conference, Chengdu
TORE SUPRAAssociationEuratom-Cea
M. Chatelier
> 0≈ 0< 0< 0Measured
> 0≈ 0< 0< 0Localized outflux
> 0> 0≈ 0< 0Uniform outflux
TOPLFSBOTHFS
> 0≈ 0< 0< 0Measured
> 0≈ 0< 0< 0Localized outflux
> 0> 0≈ 0< 0Uniform outflux
TOPLFSBOTHFS
> 0≈ 0< 0< 0Measured
> 0≈ 0< 0< 0Localized outflux
> 0> 0≈ 0< 0Uniform outflux
TOPLFSBOTHFS
Evidence of strong outflux across the outboard midpl ane
• Large SOL width when unobstructed by outboard limiter• SOL fed by long range parallel bursty transport events located near the outboard midplane (see Gunn et al., EX/P4-9)
17 October 2006 2521st IAEA Fusion Energy Conference, Chengdu
TORE SUPRAAssociationEuratom-Cea
M. Chatelier
Technological developments for long discharge operation follow-up
17 October 2006 2621st IAEA Fusion Energy Conference, Chengdu
TORE SUPRAAssociationEuratom-Cea
M. Chatelier
Articulated Inspection Arm operational in 2007
• In vessel remote handling light payload carrier (10kg) able to reach all part of TS chamber without breaking
vacuum
• 8-meter long, 5 modules with 2 actuated joints each• Prototype module tested under ITER representative vacuum and temperature condition• Various use:
High definition CCD for inspection Leak testing tool Laser ablation tool for surface characterization and
codeposited layer removal (see Semerok et al., IT/P1-15)….
17 October 2006 2721st IAEA Fusion Energy Conference, Chengdu
TORE SUPRAAssociationEuratom-Cea
M. Chatelier
Conclusions and …
• After 3MW/LH 6mn discharges of 2003, Tore Supra has performed high power long pulse discharges (5-10MW, 20-60s) still far from the limits of the actively cooled pump limiter• Substantial progress in real time control of safe HF -non inductively driven and heated - discharges:
Minority ICRH & LH driven steady state discharges
Real time control of antennas temperature
Real time control of current profile
• Extensive density fluctuation measurements bring coherence in transport and stability studies• Large and continuous D absorption by the C wall suggesting large bulk diffusion process at work• Edge particle radial transport primarily on the outboard side consistently with Langmuir probe measurements
17 October 2006 2821st IAEA Fusion Energy Conference, Chengdu
TORE SUPRAAssociationEuratom-Cea
M. Chatelier
… Prospects
• Enhancement of the LH power & duration in preparation(CIMES project: 6-8MW, 1000s)
Steady state high power non inductive real time controlleddischarges
Physics of non inductive discharges
• Preparation of articulated inspection arm for several purposes Visual inspection of PFCs Vacuum leak test D recovery … under real conditions of temperature/vacuum
• Pursue building experience in integrating ITER relevant constraints for high power operation in actively cooledenvironment
Complementary of JET (& ASDEX-U) with all metal wall and high NBI
17 October 2006 2921st IAEA Fusion Energy Conference, Chengdu
TORE SUPRAAssociationEuratom-Cea
M. Chatelier
• Monday 16th
E. Joffrin et al., EX/1-6• Tuesday 17th
Semerok et al., IT/P1-15 Garbet et al., TH2-2, Beyond scale separation in gyrokinetic turbulence Bécoulet M. et al., IT/P1-29, Modelling of edge control by ergodic fields in
DIII-D, JET and ITER• Wednesday 18th
Durocher et al., FT/1-5• Thursday 19th
Hogan et al., EX/P4-8, Mechanisms for carbon migration and deuterium retention in Tore Supra CIEL long discharges
Gunn et al., EX/P4-9 Hennequin et al., EX/P4-36
• Friday 20th
Goniche et al. EX/P6-12• Saturday 21th
Libeyre et al., IT/2-1Ra, Remaining issues in superconducting magnets for ITER and associated R&D
Beaumont et al., IT/2-5 Huysmans et al., TH/P8-2, MHD stability in X-point geometry : simulation
of ELMs Maget et al. EX/P8-21
17 October 2006 3021st IAEA Fusion Energy Conference, Chengdu
TORE SUPRAAssociationEuratom-Cea
M. Chatelier
Discriminating spurious overheated zones
• High temperature measured on poorly adherent objects• Identified by follow-up of reference discharges• Spurious zones excluded from monitored area
Q1 Q2
#37421
#37193
#36970
#36854
time (s)
ICRH Q5
B4C flakes
T (
°C)
∆T ≥ 200°C
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