ASIPP, Hefei, August 18, 2009Page 1
ITER, Overview
Songtao WU Songtao WU
Institute of Plasma Physics, CASInstitute of Plasma Physics, CASITER International Organization
18 August 2009
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ITER, OverviewITER, Overview
1. Background and Objectives2. ITER Tokamak and Major Systems3. Nowadays Situation
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ITER, OverviewITER, Overview
1. Background and Objectives2. ITER Tokamak and Major Systems3. Nowadays Situation
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1985
•
At the Geneva Superpower Summit Meeting on 21st
November, a proposal was made by the then Soviet Union to build a next generation tokamak experiment on a collaborative basis involving the world's four major fusion programmes in Europe, Japan, Soviet Union, and USA.
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1986-1988 - Discussion and Negotiation•
The ensuing discussions resulted in the establishment of a collaboration under the auspices of the IAEA known as ITER - the International Thermonuclear Experimental Reactor - and also meaning "The Way" in Latin.
•
Representatives of the four parties developed a detailed proposal for cooperation on the Conceptual Design Activities (CDA) for ITER.
1988-1991 - (CDA) Conceptual Design Phase•
Start of common activities among EU,RF, USA and JA. Selection of machine parameters and objectives
•
The ITER CDA began in April 1988 and were successfully completed in December 1990.
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1992-1998 - (EDA) Engineering Design Phase•
In July 1992, in Washington D.C., the four Parties signed an Agreement under the auspices of the IAEA, which established EDA of ITER.
•
Developed design capable of ignition - large and expensive.
1998 – USA withdrew•
By the end of its 1999 fiscal year, USA withdrew.
•
At the time of the FDR’s acceptance, the Parties recognized that they might be unable, for financial reasons, to construct the device.
•
A Special Working Group (SWG) was set up for reducing the cost by reducing ITER’s technical objectives and decreasing the technical margins while maintaining the overall objective of ITER.
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1999 - 2001•
The EDA was subsequently extended to July 2001.
•
New design: moderate plasma power reduction at about half the cost.
•
The complete and fully integrated documentation of the ITER design to make a decision on construction was completed and approved by the ITER Council in July 2001.
1998 2001Plasma major radius (m) 8.1 6.2
Plasma half width at mid-plane (m) 2.8 2.0
Plasma elongation (95% flux surface) 1.6 1.7
Toroidal magnetic field on axis (T) 5.6 5.3
Nominal maximum plasma current (MA) 21 15
Nominal fusion power (MW) 1500 500
Nominal inductive pulse length (s) >1000 >400
Average neutron wall load (MW/m2) ~1.0 0.57
Estimated direct construction cost (1989 US $) 5460 3013
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2001 - 2002•
Coordinated Technical Activities (CTA) underpinning Negotiations on the joint implementation of ITER.
•
The CTA terminated in December 2002, the CTA work being continued under ITER Transitional Arrangements (ITA).
•
By the middle of 2002, four possible sites for ITER had been proposed, at Cadarache, Vandellòs, Rokkasho-mura and Clarington.
ITER Candidate Sites
FranceSpainCanada Japan
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2003-2004•
In January 2003 China joined ITER as a full Party, and the USA rejoined in February 2003. The Republic of Korea joined ITER in June 2003.
•
Cadarache, France selected as European candidate site on November 26th, 2003.
•
Deadlock on site decision - December 20th, 2003. •
Canada left ITER – Jan. 7th , 2004.
2005•
Cadarache was selected as ITER site on 28, Jun. 2005.
•
Final NSSG/N meeting was held in Jeju, Korea from 1 to 9 Dec. 2005. The India joined ITER.
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2005•
The ITER Joint Work Site in Cadarache was inaugurated on Thursday 15 December 2005 by a ribbon-cutting and olive- tree-planting ceremony, in the presence of regional politicians and representatives of the embassies and consulates of the ITER Parties.
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2006•
“ITER Joint Implementing Agreement (JIA)” initiated in Brussels in May 2006.
•
On 21 Dec. 2006, the signature of the JIA took place at a ceremony at the Elysée Palace in Paris and was hosted by the President of the French Republic M. Jacques Chirac and by the President of the European Commission, M. José Manuel Durão Barroso.
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2007•
On Wednesday, 24 October 2007, the ITER Organization formally entered into force.
•
On Tuesday, 27 November 2007, for the first time in the history of the new International Organization the ITER Council convened in the Château de Cadarache, France.
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On 24 October 2007, following ratification by all Members, the ITER Agreement entered into force and officially established the ITER Organization.
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2008•
The (IAEA), Vienna, Austria, and the ITER Organization sign a Cooperative Agreement on 13 October 2008 to enhance research on fusion and strengthen the working relationship between the two organizations.
2009•
Work on the impressive ITER platform comes to an end in April, 2009. The platform is now ready to receive the scientific buildings and facilities of the ITER project.
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ITER ObjectivesProgrammatic•
Demonstrate the scientific and technological feasibility of fusion energy for peaceful purposes.
Technical•
Demonstrate extended burn of DT plasmas, with steady state as ultimate goal.
•
Integrate and test all essential fusion power reactor technologies and components.
•
Demonstrate Safety & Environmental acceptability of fusion.
Strategic•
A single device answering, in an integrated way, all feasibility
issues needed to define a subsequent DEMO except for material development and to provide low activation and larger 14 MeV
n-resistance at least for in-vessel components.
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Project Costs
Magnet SystemsCryogenie
& VesselInternals
Others
Power SuppliesDistribution &
& DiagnosticsCODAC
Cooling WaterSystems
Buildings
Assembly & R/H Cryostat & TS
Construction Cost:
Total procurement value : 3021 kIUA
Staff: 477 kIUAR&D: 80 kIUATotal amount: 3578 kIUA (5365 Mil € / 2008 )Overall contingency : 358 kIUA ( 10% of total )
Operations Cost for 20 years : 188 kIUA / year
Deactivation and Decommissioning: 281 + 530 kIUA
IUA: ITER Units of Account1 IUA is equivalent to 1 kUS$ in 1998
European Union (5/11)
RF(1/11)CN
(1/11)KO
(1/11)JA
(1/11)IN
(1/11) US(1/11)
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ITER Main ParametersTotal fusion power 500 MW (700 MW)Q = fusion power/auxiliary heating power ≥10 (inductive)Average neutron wall loading 0.57 MW/m2 (0.8 MW/m2)Plasma inductive burn time ≥ 300 s Plasma major radius 6.2 mPlasma minor radius 2.0 mPlasma current (inductive, Ip ) 15 MA (17.4 MA)Vertical elongation @95% flux surface/separatrix 1.70/1.85Triangularity @95% flux surface/separatrix 0.33/0.49Safety factor @95% flux surface 3.0Toroidal field @ 6.2 m radius (max. conductor) 5.3 T (≤12 T)Plasma volume 837 m3
Plasma surface 678 m2
Installed auxiliary heating/current drive power 73 MW (100 MW)
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ITER, OverviewITER, Overview
1. Background and Objectives2. ITER Tokamak and Major Systems3. Nowadays Situation
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Central Solenoid
Toroidal Field Coils
Poloidal Field Coils
Machine Gravity Supports
Blanket Modules
Vacuum Vessel
Cryostat
Port
Divertor
Magnet Supports
ITER Tokamak Machine 29 m high × 28 m dia. & ~23000 tons
Correction Coils
Plasma
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Facts- 48 superconducting coils - Operation temperature – 4.5 K- ~ 187 km of conductor- 11.8 T (peak TF field)- 68 kA (peak current)- Stored energy – 51 GJ- ~ 9800 tons
ITER Magnet System Status
6 PF Coils (EU & RF)
CS Coils – Stack of 6 (US)
31 Feeders (CN)9 Pairs of Correction Coils (CN)
18 TF Coils (EU & JP)
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TF Coil TF Coil –– Mass ComparisonMass Comparison
Mass of (1) TF Coil: 16 m Tall x 9 m Wide, ~360 t
Boeing 747-300 (Maximum Takeoff Weight) ~377 t
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ITER Magnet Field
ITER magnetic Field ~10 Tesla or 200,000 x Higher
Earths Magnetic Field ~ 0.5 gauss or 0.5x10-4 Tesla
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VV & In-vessel components mass: ~8000 t19.4 m outside diameter x 11.3 m tall
Eiffel Tower mass: ~7300 t324 m tall
(Completed 1889)
ITER Vacuum VesselFacts - First safety barrier for ITER- SS 316 LN-IG- ~5300 tons (VV, ports, shielding only)- 19.4 m (63 ft) torus outer diameter- 11.3 m (37 ft) torus height
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Divertor
In-vessel Components – Blanket & Divertor
Blanket Vacuum Vessel
Port Plug
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The blanket and diverter
are needed to …
The blanket
-
Provide shielding for the superconducting coils
-
Provides high heat flux component to face the plasma (protect the VV)
The divertor
-
Provide shielding for the superconducting coils
-
Extract heat and helium ash form the plasma (allows a high performance plasma)
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Blanket System
Facts• 440 blanket modules at ~4 ton each• ~40 different blanket modules
Issues• Thermal and mechanical loads very high• Manufactured by 6 Parties• QA/QC of components (at 6 Parties)• Remote handling
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Divertor SystemFacts- 54 Divertor assemblies- 4320 Heat flux elements
Issues• Thermal and mechanical loads very high• QA/QC of components (at 6 Parties)• Remote handling
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CryostatThe magnet system is installed inside a cylindrical cryostat, held under vacuum. This, plus thermal shields, minimizes the heat in-
leak to the magnet system from the warm components and the surrounding environment .The Cryostat is 29 metres tall and 28 metres in diameter.The Cryostat is 29 metres tall and 28 metres in diameter.
Jefferson Memorial (Washington DC)~29 m Tall (floor to top of dome)
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Machine Assembly
TF Coil / Sector Assembly TF Coil / Sector Assembly ~1400 ton ~1400 ton
TokamakTokamak and Assembly Buildingand Assembly Building
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Transfer Cask Systems (EU+CN)Blanket RH System (JA)
Many Remote Handling SystemsMany Remote Handling Systems
1
2
456
7891 0
3θ1
θ2θ
3θ4
α1α
2α3
θ5
+/- 90°
+/- 100°
+/- 90°
+/- 180°
0°180°
+/- 180°
+/- 90°
+/- 90°
0 6200mm
0 4500mm
limits
Pitc h 5
1 0
Roll 3
9Pitc h 4
8Roll
27
Pitc h 3
6Roll
15
Pitc h 2
4Pitc h 1
3Tra nsla tion
2
2Tra nsla tion
1
1Na me
D O F
In-Vessel Viewing System
Multi Purpose Deployer
Cassette Toroidal MoverHot Cell RH Equipment
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Initially: 73 MW Upgrade: possibility for 130 MW
ITER Heating & Current Drive
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Neutron Beam InjectionUnit H DT
NB H&CD injection power MW 27 33 - 50
NB H&CD beam energy MeV 0.87 1
NB H&CD beam on time s 3600 3600
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Electron Cyclotron Heating & CDSCOPE
f= 170 GHz, 20 MW : heating & current drivef= ~127 GHz, 3 MW: plasma breakdownEquatorial Launcher :1Heating for Q>10 and L-H transition Current drive for Steady State operation, Upper Launcher : 4Stabilisation of MHD instabilities
Start-up gyrotrons
170 GHz gyrotrons
Upper launchers
Equatorial launcher
Corrugated waveguide
27 gyrotrons ( each to 2 MW )
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Straps
Front Housing
Removable Vacuum Transmission Line
Core Conductors
Vacuum Windows
Equatorial IC LauncherComposed of 24 straps grouped in 8 triplets (only one visible here)
SCOPEf= 40-55 MHz, 20 MW : Heating & current driveEquatorial Launcher :1Heating for Q>10 and L-H transition Current drive for Steady State operation ( 1 MA ) Assist in Plasma Startup
Ion Cyclotron Heating & CD
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Cryogenic System
•
LHe
cryoplant:
65 kW equivalent @ 4.5 K–
Cooling of the superconducting magnet system, HTS current leads
–
Cooling of cryo-pumps with high regeneration frequency and small users
•
LN2
cryoplant:
1300 kW @ 80 K–
Thermal shielding, LHe
cryoplant
pre-
cooling
•
Helium inventory:
24 t
Cryoplant
Cryo distribution boxes and cryolines
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DiagnosticsAbout 45 different diagnostic systems will be installed around the ITER tokamakThree categories: •
necessary for machine protection or basic control•
necessary for advanced performance control •
for evaluating the plasma performance and for understanding important physical phenomena
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ITER I&C
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Hot Cell blanket & divertor RH refurbishment area layout
Divertor cassette RH refurbishment & testing equipment
Hot Cell Remote Handling
The hot cell provides space and handling facilities for the reception, dispatch, decontamination, storage, repair, refurbishment and testing of highly radioactive and, or contaminated in-vessel components and materials (divertor cassettes, blanket modules, and other in-vessel component such as diagnostics and port plugs).
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Fuel Cycling•
ITER will be the first fusion machine fully designed for Deuterium-Tritium operation.
•
Commissioning will happen in three phases: Hydrogen operation, followed by Deuterium operation, and finally full Deuterium-Tritium operation.
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Tritium Breeding•
Tritium in the Earth's crust is limited, estimated currently at twenty kilos.
•
A second source of Tritium fortunately exists: Tritium can be produced within the tokamak when neutrons escaping the plasma interact with a specific element — Lithium — contained in the Blanket.
•
ITER will provide a unique opportunity to test mockups of breeding blankets, called Test Blanket Modules.
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ITER, OverviewITER, Overview
1. Background and Objectives2. ITER Tokamak and Major Systems3. Nowadays Situation
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Present Structure of the ITER Organization
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Staffing Status
• By the end of July 2009, IO has a total of 391 staff, including 351 Direct Employed Staff, 35 Seconded staff and 5 Post-Doc
• 38 temporary staff, 9 Visiting Researchers.
Staff by Members by the end of June, 2009:
Total: 391
CN: 15
EU: 257
IN: 23
JP: 28
KR: 18
RU: 23
US: 27Status of Professional Staff as of end June 2009
EU 65.7%
CN 3.8%US 6.9%RU 5.9%
KR 4.6%
JP 7.2%
IN 5.9%
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ITER Staff Group Picture in May 2009
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ITER Construction Site (ITER Construction Site (FebFeb. 2009). 2009)
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ITER ITER Site after ConstructionSite after Construction
Tokamak Hall Power Supply
Permanent Office Buildings
Parkings
32 Buildings, 180 hectares10 years of construction20 years of operation
Present HQ Building
To Aix
Hot Basin & Cooling Tower
Control Building Magnet AD/DC Converter
Site Services Building
Tritium, Vacuum, Fueling & Service Building
Cryoplant, PF Coil Fabrication & Emergency Power Supply Buildings
Hot Cell Building
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Itinerary of ITER ComponentsITER Site
Itinerary of ITER ComponentsItinerary of ITER Components
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• Project Management– Tight schedule and budget– Limited resources– New organization– 7 Party coordination
• Design and Procurement– Complex design, requirement,
& interfaces– Severe QA / QC requirements– Complex procurement split– >90 procurement packages
• Superconducting magnets– Unprecedented size of the
superconducting magnets and structures
– High field performance ~12T
Why is the design of the ITER machine so challenging?
•Plasma facing components– >10 MW/m2 steady heat flux– >10000 cycles
•Remote maintenance (very complex)
•Vacuum and Tritium technology– Active recycling of tritium– Test of lithium blankets
•Cryogenic technology
•Heating and current drives– ~ 100 MW continuous– Neutral particles accelerators up to 1 MeV– Ion cyclotron, electron cyclotron
And others…
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First Plasma planned in the end of 2018
2007 2008 2009 2010 2011 2012 2013 2014 2015 2016 2017 2018 2019 2020
“Permis de Construire” Start Tokamak
Assembly Complete Tokamak
Core Construction
Issue VV PAs
1st
VV Sector at Site Last VV Sector at Site
2018 First PlasmaMinimal internal vessel components
First Plasma
Tokamak
Basic Machine
ITER Construction
Issue TF Coils PAs
1st
TF Coil at Site Last TF Coil at Site
Buildings & Site
Tokamak
Complex Excavations
Tokamak
Building Construction
Site Leveling
Tokamak Bldg 11 RFE
Tokamak
AssemblyTokamak
Basic Machine Assembly
Ex Vessel AssemblyIn Vessel Assembly
Start Torus Pump Down
Start Install CS Start Cryostat Closure
Pump Down & Integrated Commissioning
Start Assemble VV
Current Date
Issue PF Coil PAs
1st
PF Coil at Site Last PF Coil at Site
Tendering process
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The Way to the Future…