ITER - ATS

Transcription

ITER - ATS
Status of the ITER project
– role of F4E Maurizio Gasparotto
F4E Chief Engineer
13/10/2011
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Outline
• ITER – Introduction: the agreement, the aims, the
sharing, the procurement allocation.
• ITER schedule.
• F4E the European Domestic Agency.
• The EU contribution: components and systems
present status.
• Conclusions.
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The ITER Agreement
•
•
Involvement of 7 parties representing over half of the world’s
population – the largest R&D project ever!
ITER Agreement signed in Paris on 21 November 2006
European Union
Japan
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USA
Russia Fed
India
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Korea
China
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What is ITER?
ITER
•Pl. vol.: 1000 m3
•R=6 m
•Ip=15 MA
It is a “Big” Step!!
JET
•Pl. vol.: 100 m3
•R=3 m
•Ip=4 MA
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ITER – the aims
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•
Produce and study inductively-driven, burning plasma at Q
10 (400-500 MW) for an “extended” time, 300 s.
•
Aim at producing and studying “steady-state”, burning
plasma with non-inductive drive Q 5.
•
Demonstrate the availability and integration of essential
fusion reactor technologies (superconducting magnets,
plasma facing materials, remote handling, tritium plant).
•
Test components for a future reactor including tritium
breeding module concepts.
•
First plasma in 2019 / 2020.
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ITER main components
Toroidal
Field Coil
Nb3Sn, 18 coils
Blanket Module and
First Wall
421 modules
Cryostat
Vacuum Vessel
9 sectors
24 m high x 28 m dia
Additional
Heating
IC, EC, NBI
Port Plug
Central
Solenoid
Nb3Sn,
6 modules
+ Diagnostics
Remote Handling
Tritium Plant
Pumping/Fuelling
Power Supplies…
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Torus
Cryopump 8
Inner Divertor
54 cassettes
Poloidal Field Coil
Nb Ti,6 coils
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ITER–Quick Mass Comparison
ITER Machine mass:
ITER Machine mass:
~23000 t
28 m diameter x 29 m tall
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Charles de Gaulle Aircraft Carrier:
~38000 t (empty)
261 m long
(Commissioned 2001)
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ITER Sharing
• Some procurement packages will be shared among
several parties (e.g. superconducting strands and cables,
divertor, first wall, blanket, TF, PF, vacuum vessel).
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Procurement Arrangements - Status
13/10/2011Meeting 11-12 Nov 2010
TAP/ExCo
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Summary of the IO Level-0 Schedule
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Overview of the proposed structure of the ITER
Research Plan adapted to the revised IO Level-0 OPS
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ITER Organization
Governing
Board
STAC
ITER
COUNCIL
Fusion Laboratories
MAC
ITER Organizatin
IO
Cadarache (FR)
European DA
F4E
Fusion for Energy
Barcelona (SP)
Domestic Agencies
DAs
Other DAs
US, JPN, IN, CN,
KO, RF
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Indiustries
Universities
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F4E Governance
Governing Board
(58 members)
representatives from all 27 EU Member States,
Switzerland and Euratom
Bureau
Technical
Advisory Panel
(13 members)
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Executive
Committee
(13 members)
Administration
and Finance
Committee
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Audit
Committee
(5 members)
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Fusion for Energy: Objectives
The European Domestic Agency for ITER (“Fusion for Energy” – F4E)
was established in April 2007.
Provide Europe’s
contribution to
the ITER
international
fusion energy
project
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F4E
Prepare for the
construction of
demonstration
fusion reactors
(DEMO)
Implement the
Broader Approach
(BA) agreement
between Euratom
and Japan
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MAGNETS
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ITER Magnet System
48 Superconducting Coils:
–
–
–
–
–
18 TF coils
6 CS modules
6 PF coils
9 pairs of CC
Feeders
T
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Toroidal Field Coil –
Quick Mass Comparison
TF Coils
Caterpillar Bulldozer
~35 t
Mass of (1) TF Coil:
~360 t
16 m Tall x 9 m Wide
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X 10
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Conductor Manufacture
3rd Stage
1st Stage
Conductor
Cu Wire
Luvata
Sub-Wrap
5th Stage
2nd Stage
Cable
4th Stage
Strand
Cu Core Cable
6th Stage
Wrap
OST,
BEAS
Cu Sub-Cable
Jacket Assy
Jacket
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Central Spiral
ICAS
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Magnets:
TF coils main manufacturing steps
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Regular radial plate prototype fully
machined in August 2011!
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Poloidal Field (PF) Coils
• 6 PF coils independently powered, wound in double pancakes to:
Confine and shape the plasma
PF1 & PF6 control plasma vertical displacement
• Conductor field limited to 6 T: NbTi sufficient
• Coils are large (24 m diameter) but use of NbTi simplifies construction
PF1
PF2
PF3
PF4
PF5
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PF6
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Buildings – Work in Progress
PF Coils Manufacturing Building
PF Coils Manufacturing Building Contract (signed in January 2010)
Construction from Aug 2010 until Dec 2011
27th of September 2011
PF Coils
Manufacturing
Building
13/10/2011
• Length: 257 m
• Width: 49 m
• Height: 17 m
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VACUUM VESSEL
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ITER–Quick Mass Comparison
Vacuum Vessel
VV & In-vessel components mass: ~8000 t
19.4 m outside diameter x 11.3 m tall
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Eiffel Tower mass: ~7300 t
324 m tall (Completed 1889)
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Vacuum Vessel Prototype
•
The reference VV fabrication route includes the use of heavy jigs to limit the
deformations linked to the high concentration of welded zones.
Courtesy Ansaldo
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FIRST WALL
and
DIVERTOR
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First Wall Fabrication Technology
Hot Isostatic Pressing (HIP)
fabrication route
proposed for the manufacture
of First Wall (FW) panels
316L Stainless Steel / CuCrZr alloy HIP joining
Step 1:
316L(N) SS / CuCrZr HIP joining
1040 C, 140 MPa, 2 hrs.
Post HIP Solution Annealing
heat treatment with fast cooling.
Step 2:
CuCrZr / Beryllium HIP joining
580 C, 140 MPa, 2 hrs.
CuCrZr alloy / Beryllium HIP joining
Full scale FW panel prototypes
with HIPped Be tiles
Full scale FW panel prototypes
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Divertor
Plasma Facing Components’ technologies
Divertor
•
Three inner vertical target qualification prototypes have successfully passed all the
fabrication acceptance tests and the high heat flux test requirements (CFC up to 20
MW/m2 – W up to 5 MW/m2 for 1000 cycles) performed at the Efremov Institute (RF).
The EU, Japan and Russia passed the ITER qualification test programme and have
started the procurement of the components.
Courtesy Ansaldo
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Courtesy Plansee
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REMOTE HANDLING
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Divertor Remote Handling
Divertor RH: the Divertor Test Platform 2 is becoming operational with
the delivery of the Cassette Multifunctional Mover prototype in Finland.
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Cask and plug remote handling
system
Casks will transport the in-vessel components from the VV to the
Hot Cell and vice-versa.
Cask from VV to lift
Upper plug
cask
Divertor cask
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In Vessel Viewing System
Six laser-based IVVS probes will
have to make inspections
(viewing and metrology) under
vacuum, temperature, magnetic
field and gammas
Target specifications:
• Metrology accuracy: 0.5mm @
5m
• Viewing spatial resolution
1mm @ 0.5m-4m
3mm @ up to 10m
Self-illumination (no external
light source)
6 IVVS inserted during an
inspection
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TEST BLANKET MODULE
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The functions of the breeder blanket
Production of the Tritium consumed in the
fusion reaction (closed cycle)
• Tritium “breeding” blanket (breeder
materials enriched with 6Li)
4He + n +
Fusion (plasma):
T+D
17.6 MeV
4He + T
Breeding (blanket): n + 6Li
+ 4.8 MeV
Heat generation and extraction
• Heat generation in blanket (Heat flux, nuclear
reactions)
• Heat extraction and transport (coolant)
Protection of vacuum vessel and
superconducting magnets against
nuclear heating and neutron damages
• Radiation shielding (neutrons, gammas)
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Breeder blanket modules
Stiffening
grid
HCPB
He collector
system
HCLL
Ceramic pebble
bed
Breeder unit
He collector
system
Breeder
cooling unit
Be pebble bed
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Fuel Cycle:
Vacuum pumping
&
Tritium Processing
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Vacuum Pumping Systems
Vacuum Pumping:
•
•
8 Torus-, 2 cryostat cryopumps
3 HNB-, 1 DNB cryopumps
Purpose: Pumping Torus (153 Pa
m3/s), cryostat and HNB and DNB
facilities.
Pump connection
flange
Valve
pneumatic
actuator
80K
louvre
baffles
Cryopump prototype successfully
tested.
Integral inlet valve
4.5K
hydroformed
cryosorption
panel circuit
Prototype Torus Cryopump
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Simplified ITER Fuel Cycle
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Introduction to Cryoplant Project:
ITER Cryoplant Layout
EU in-kind components indicated in red
GN2 storage
Heaters
Purifier
LN2 plant
cold boxes
Quench tanks
80 K He loop
cold boxes
LN2 storage
LHe storage
Building # 52
He warm storage tanks
Area # 53
(160 m x 13,35 m)
Dryers
LN2 plant compressors
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Building # 51
(75 m x 45 m)
80K loop compressors
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ITER
Heating & Current Drive Systems
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ITER Heating and Current Drive
Systems (H&CD)
The H&CD systems are essential for ITER operation, e.g.:
• to heat of plasma to temperatures required for fusion burn
• to achieve steady-state operation (non-inductive current
drive)
• vessel wall conditioning and plasma start-up assist
Three systems foreseen for ITER: Neutral Beam (NB), Ion
Cyclotron (IC), Electron Cyclotron (EC).
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RF Heating Systems
Ion Cyclotron
Heating &
Current Drive
IC Antenna
Upper Launcher
Electron
Cyclotron
Heating &
Current Drive
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RF Power
Sources
Power Supplies
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The 2MW coaxial cavity gyrotron
for ITER
The specifications for ITER go beyond capabilities of the
gyrotrons installed in existing facilities
EU is developing the 2MW coaxial cavity gyrotron
- Highest power 1st prototype
1.4MW – few ms (2008)
- KIT pre-prototype 2.2MW –
1ms (2009)
EU proto1
EU proto2
EU proto3
110GHz tubes
Installed in existing facilities
ITER
target
ITER
target
RF
JA’08
W7X tubes
JA’05
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View of NB injector
• Test Facility in construction in Padua.
• Collaboration with JA – Domestic Agency.
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DIAGNOSTICS
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Diagnostics
F4E will be responsible for procurement of 11 diagnosticrelated systems for ITER .
Diagnostics
Magnetics
Neutron Systems
Optical Systems
Bolometry
Spectroscopic
Microwave
Operational Systems
Standard Diagnostics
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BUILDINGS
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Site view
The ITER
worksite in
September
2011
Architect
view of the
future
buildings
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Buildings:
Two areas of construction
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Buildings:
Work in Progress Tokamak Complex
Implementation of 500 Seismic Isolators since September 2011
3D view of a plinth and an isolator
on top
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Conclusions
• 7 Parties (EU, JA, US, RF, KO, CN, IN) signed the ITER Agreement on
21st November 2006.
• The European Domestic Agency (Fusion for Energy) was established
in April 2007 in Barcelona and it is based on the EURATOM Treaty.
• EU is responsible for 45% of the “Capital Value” established in 2001.
• A new baseline will be presented to the ITER Council at the end of
this year. The construction phase will be completed in 2020 with the so
called “first plasma” planned in November 2020.
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Conclusions
• 46 Procurement Arrangements between IO and F4E defines the
activities to be implemented by EU in kind; 16 already signed.
• A number of construction contracts have been launched in the
Magnet and Vacuum Vessel areas. Building construction started.
• R&D activity still needed in RH, Diagnostics, H&CD systems and
TBMs.
•Finalization of design and prototype testing in progress in Fuel Cycle,
Cryoplant, FW, Divertor and Tritium Processing areas.
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Thank you for your attention
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