Презентация - Nuclear Fusion and ITER
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21
Carlos Alejaldre 2 Julio 2007
Blanket
Blanket
• 440 blanket modules with
detachable faceted first wall (FW)
with Be armour on a water-cooled
copper substrate, attached to a SS
shielding block.
• Blanket cooling channels are
mounted on the vessel.
• Design strongly affected by need to
resist electromagnetic forces.
• Initial blanket acts solely as a
neutron shield, and tritium breeding
experiments are carried out on test
blanket modules inserted and
withdrawn at radial equatorial ports.
Inlet/outlet
manifolds
First wall
panel
Hole to fit
flexible support
Flexible
supports
Vessel
Shield
block
Shear
key
Gripping
hole
Electrical strap
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Carlos Alejaldre 2 Julio 2007
Vacuum
Vessel
Blanket
Divertor
Carlos Alejaldre 2 Julio 2007
ITER Physics R&D
ITER Physics R&D
The World Tokamak Research
Efforts Have Been Concentrated
on Establishing ITER Physics
Basis.
Energy
Confinement
Scaling
Current Drive
Halo Current
Characteristics
Review paper ”ITER Physics Basis” (500 pages,NF1999)
http://www.iop.org/EJ/abstract/0029-5515/39/12/301)
“Progress in ITER Physics Basis” (500 pages, NF2007)
H-mode Transition
Threshold Scaling
Carlos Alejaldre 2 Julio 2007
Plasma energy confinement
Plasma energy confinement
Carlos Alejaldre 2 Julio 2007
Antenna
protection
Main Limiter
Outer
Limiter
Inner waal
protection
e.g. Tore Supra (CEA-Cadarache)
Actively cooled Plasma Facing Components
tested up to 10 MW/m
2
World records (over 6 minute pulses)
AMC tiles
(CFC/Cu)
Copper
Carbon-Fiber
composite
Long pulses
Long pulses
–
–
Current Drive
Current Drive
Tore Supra results
Tore Supra results
Neutron (x10
10
/s)
Z
eff
~2
T
i
(0) =1.6 keV
Line density (x10
19
m
-2
)
LH Power (MW)
Transformer flux (Wb)
T
e
(0) = 4.8 keV
Long pulse non inductive discharges (V~0, Ip = 0.5 MA,
feed back control of plasma current on LH power, 360 s,
1 GJ):
• Constant wall temperature
• New Physics with ITER relevance …
26
Carlos Alejaldre 2 Julio 2007
Technology Challenges
Technology Challenges
• Unprecedented size of the super-
conducting magnet and structures.
• Remote Handling systems.
• Extremely high heat fluxes in first
wall components
• Materials under neutron irradiation
• Plasma Heating Systems
Carlos Alejaldre 2 Julio 2007
CENTRAL SOLENOID MODEL COIL
REMOTE MAINTENANCE
OF DIVERTOR CASSETTE
Attachment Tolerance ± 2 mm
DIVERTOR CASSETTE
Heat Flux 20 MW/m
2
Height 4 m
Width 3 m
B
max
=7.8 T
4 t Blanket Sector
Attachment Tolerance ±0.25 mm
Double-Wall, Tolerance ± 5 mm
HIP Joining Tech
Size : 1.6 m x 0.93 m x 0.35 m
REMOTE MAINTENANCE OF BLANKET
BLANKET MODULE
VACUUM VESSEL SECTOR
Completed R&D Activities by July 2001.
ITER Design and Technology have been developed
TOROIDAL FIELD MODEL COIL
Radius 3.5 m
Height 2.8m
B
max
=13 T
0.6 T/sec
Carlos Alejaldre 2 Julio 2007
ITER Vacuum Vessel
ITER Vacuum Vessel
Electron Beam welding on the inner shell
Carlos Alejaldre 2 Julio 2007
ITER Central Solenoid
ITER Central Solenoid
CS conductor (Incoloy
jacket)
Carlos Alejaldre 2 Julio 2007
ITER Divertor Remote Handling
ITER Divertor Remote Handling
JET