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ITERThe past, present and future
1985 to 2007
Garry McCracken
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What is ITER?• ITER is a design for a nuclear fusion experiment to demonstrate the feasibility of a fusion power plant. • First proposed as a collaboration between the
US and the Soviet Union by Ronald Reagan and Mikhail Gorbachev at a Summit meeting Geneva 1985
• The experiment is jointly funded by China, Europe, India, Japan, Korea, Russia and the US
representing more than half the population of the world
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What is Nuclear Fusion?• Nuclear fusion is the reaction between two nuclei to form
a larger one. When the mass of the product nucleus is less than the mass of the two original nuclei the excess mass is released as energy
»
+ 4 MeV
+ 3.3 MeV
+ 17.6 MeV Key reaction
+ 18.3 MeV
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Nuclear Fusion Power Plants
• Assuming that the problem of plasma confinement would be solved the design of fusion power plants was considered very early in the international fusion program
• A patent for a fusion power plant was filed in 1946 by GP Thomson and M Blackman of Imperial college London.
• In the 1950’s Lyman Spitzer at Princeton NJ considered the design of a fusion reactor
• In the late 1960’s after the success of the Soviet tokamaks there were many attempts to design tokamak reactors, particularly in the US and the UK
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Conceptual fusion reactor
Deuterium
Lithium blanketTritium
D+T plasma
Steam Generator
Turbine Generator
Lithium
Primary Fuels
Vacuum
Deuterium Tritium
Reprocessing of gases
Heat exchanger
Fusion Reactor
Electricity grid
Helium + hydrogen waste gases
Exhaust Gases -- Deuterium, tritium hydrogen , helium
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Attempts to produce fusion power on earth
• Fusion reaction occur in the sun because gravity holds the reacting particles close enough together for the reaction to occur
• On earth man first succeeded in producing the reaction in the hydrogen bomb in 1952 This destructive approach is of no use for generating useful power
• Instead we have tried to produce the reaction in a controlled manner by using magnetic and electric fields. Experiments started in the late 1940’s and have continued to the present day.
• Early successes were the Soviet tokamaks (1960’s)• The first demonstration of controlled DT fusion reactions was
in 1991 on the European tokamak JET. About 1 MW was produced for aver 1 second
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Tokamak PrinciplesConfinement is produced by the combination of toroidal field produced by external coils and a poloidal field produced by a current in the plasma
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Experimental fusion power production
JET and TFTR have demonstrated fusion reactions.
The maximum power achieved was 16 MW
The value of
Q=Power out/power in =0.6
Q in ITER is planned to be 10
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The INTOR programme
• INTOR was the first international attempt to design a fusion reactor
• In the late 1970’s 3 large tokamaks were being designed JET, TFTR and JT60
• IAEA proposed a workshop in Vienna with US, USSR, JA and EU
• This defined a reactor design with S/C magnets, T breeding, remote handling and materials testing, 1980
• DESIGN had R=5m, a=1.2m Ip=8-10 MA
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Scaling confinement time from experiments to ITER
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Origins of ITER
• Velikhov, Gorbachev and Mitterand
• Regan -Gorbachev summit, Geneva Nov 1985
• Japan and Europe invited to join a 4 party programme to build a reactor
• IAEA invitation to Vienna workshop March 1987. Report produced and Joint Working site at Garching(Germany) agreed
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President Reagan, GorbachevGeneva Summit, 1985
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Designing ITER
• Conceptual design 1988-90
• Engineering design 1992-94 (Rebut)
• Engineering design 1994-98 (Aymar)
• Redesign 1998-2001 (Aymar)
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Problems over siting design team
• 3 sites proposed
• Japan Naka (External components)• Europe Garching, Germany (Internal comp.)• USA San Diego (Integration)
Three joint sites agreed. This led to a complicated structure and a lot of travelling
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Engineering Design 1992-94
Director Paul-Henri Rebut (centre)Deputy directors(from left) Valery Chuyanov (RF), Michel Huguet (EU) Ron Parker (US), Yasuo Shimomura (JA)
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Robert AymarDirector (1994-2003)
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Comparison of JET and ITER
JETR=3mIp=4MA
ITERR=6.2mIp=15MA
JET is the largest presently existing tokamak
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The 2001 ITER design
Toroidal Field CoilNb3Sn, 18, wedged
Central SolenoidNb3Sn, 6 modules
Poloidal Field CoilNb-Ti, 6
Vacuum Vessel9 sectors
Port Plug heating/current drive, test blanketslimiters/RHdiagnostics
Cryostat24 m high x 28 m dia.
Major plasma radius 6.2 m
Plasma Volume: 840 m3
Plasma Current: 15 MA
Typical Density: 1020 m-3
Typical Temperature: 20 keV
Fusion Power: 500 MWMachine mass: 23350 t (cryostat + VV + magnets)- shielding, divertor and manifolds: 7945 t + 1060 port plugs- magnet systems: 10150 t; cryostat: 820 t
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Seven Large Projects to study manufacturing
• Central solenoid coil (Nb/Sn S/C) L1
• Toroidal field coil (Nb/Sn S/C) L2
• Sector of the vacuum vessel L3
• Blanket module L4
• Divertor cassette L5
• Blanket remote handling system L6
• Divertor remote handling system L7
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Magnets and StructuresSuperconducting. 4 main subsystems:•18 toroidal field (TF) coils produce confining/stabilizing toroidal field;
•6 poloidal field (PF) coils position and shape plasma;
•a central solenoid (CS) coil induces current in the plasma.
•correction coils (CC) correct error fields due to manufacturing/assembly imperfections, and stabilize the plasma against resistive wall modes.
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Vessel, Blanket and divertorThe double-walled vacuum vessel is lined by modular removable components, including blanket modules, divertor cassettes, and diagnostics sensors, as well as port plugs for limiters, heating antennae, diagnostics and test blanket modules. All these removable components are mechanically attached to the VV. The total vessel/in-vessel mass is ~10,000 t.
These components absorb most of the radiated heat from the plasma and protect the magnet coils from excessive nuclear radiation. The shielding is steel and water, the latter removing heat from absorbed neutrons. A tight fitting configuration of the VV to the plasma aids passive plasma vertical stability, and ferromagnetic material “inserts” in the VV located in the shadow of the TF coils reduce toroidal field ripple and its associated particle losses.
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Safety and Environmental Characteristics
•ITER will be a precedent for future fusion licensing
•Work towards internationally accepted basic principles
and safety criteria for fusion energy
•Interact with regulatory experts to ensure ITER
options can be licensed in any Party
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Parameters of the ITER designs Conceptual ŅFinalÓ Redesign (1990) (1998) (2001)
Plasma major radius (m) 6.0 8.1 6.1Plasma width at mid-plane (m) 2.15 2.8 2.0Elongation (ratio of plasma height to width) 1.98 1.6 1.7Toroidal field on plasma axis (T) 4.85 5.7 5.3Nominal maximum plasma current (MA) 22 21 15Nominal fusion power (MW) 1000 1500 500Pulse length more than (s) 200 1000 400Number of toroidal field coils 16 20 18Neutron wall loading (MW/m2) 1.0 1.0Divertor double single single
The Rebut design in 1994 had 24 field coils but was otherwise similar to the 1998 design
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Political aspects• 1998-2001 US withdrawal, no site offered• June 2001, Canadian site proposed• June 2002 JA offers Rokkasho, EU offers Caderache
and Vandellos -- now 4 sites!• EU withdraws Vandellos, CA withdraws• Jan 2003 China joins, US rejoins, KO joins• Washington meeting to decide site ends in stalemate• 2003-2006 Battle between EU and JA for site
Proposal for a broader approachAgreement on the Caderache site
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Signing the treaty, Paris, 21 November 2006
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The ITER buildings today
Cadarache, near Aix-en-Provence, France
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ITER collaboration•For its size and cost and the involvement of virtually all the most developed countries, •representing over half of today world’s population ITER will become a new reference• term for big science projects.
•The ITER project is one of the world’s biggest scientific collaboration.
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The ITER organization
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ITER Director-General
Dr Kaname Ikeda (Japan)
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Deputy Director General and Project construction leader
Dr Norbert Holtkamp EU
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Deputy Director Generals
Valery Chuyanov RF Fusion Science
Gary Johnson USTokamak
Carlos Alhedre EUSafety, Environment
Dhijaj Bora (IN) ControlDiagnostics and Heating
Kim KO, Engineering,Fuel cycle
Wang CN Administration,Finance
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Proposed ITER Site Layout
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Staff Planning
Staff Ramp Up IO Team
0
100
200
300
400
500
600
700
2006 2007 2008 2009 2010 2011 2012 2013 2014 2015
Calendar Year
Nu
mb
er
Sum PPY: 1800
Sum Support: 2760
Sum Total
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Indicative Construction Schedule
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Indicative Operation Schedule
2nd yr 4th yr 5th yr 8th yr3rd yr 10th yr7th yr 9th yr6th yr1st yrConstruction Phase
Mile StoneFirst Plasma Full Non-inductive
Current DriveFull Field, Current& H/CD Power
Q = 10,500 MW,400 s
Short DTBurn
Q = 10,500 MW
Installation &Commissioning
For activation phase
For high duty operation
BasicInstallation
Upgrade
- Commissioning- Achieve good vacuum & wall condition
Operation
EquivalentNumber ofBurn Pulses(500 MW x 440s*)
Fluence**
Low Duty DT
- Development of full DT high Q- Developmentt of non-inductive operation aimed Q = 5- Start blanket test
1 2500 3000300015001000750
- Commissioning w/neutron- Reference w/D- Short DT burn - Improvement of inductive and
non-inducvtive operation- Demonstration of high duty operation- Blanket test
- Machine commissioning with plasma- Heating & CD Expt.- Reference scenarios with H
High Duty DT
0.006MWa/m2
0.09MWa/m2
First DT Plasma Phase H Plasma Phase D Phase
Blanket Test
- Electro-magnetic test- Hydraulic test- Effect of ferritic steel etc.
- Short-time test of T breeding- Thormomecanics test- Preliminary high grade heat generation test, etc.
- Neutronics test- Validate breeding performance
- On-line tritium recovery- High grade heat generation- Possible electricity generation, etc.
Performance TestSystem Checkout and Charactrerization
* The burn time of 440 s includes 400 s flat top and equivalent time which additional flux is counted during ramp-up and ramp-down.** Average Fluence at First Wall (Neutron wall load is 0.56 MW/m2 in average and 0.77MW/m2 at outboard midplane.)
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Why is ITER important?
Features•Virtually inexhaustible power•No CO2 emissions •High energy density fuel
–1 gram D-T = 26000 kW·hr of electricity (~10 Tonnes of Coal !!)
•Inherently Safe Controllability–low fuel inventory, ease of burn termination, self-limiting power level–No chain reaction to control–low power and energy densities, large heat transfer surfaces and heat sinks
Issues•Fusion reaction is difficult to start and maintain
–High temperatures (Millions of degrees) required–Technically complex & LARGE devices are required
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The Broader Approach
• During the JA-EU discussions over ITER site a “Broader Approach” was suggested.
• This now has 3 parts– International Fusion Irradiation Facility (IFMIF)– International Fusion Research Centre– Advanced S/C tokamak at Naka Japan
The research centre will work on DEMO
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Provisional future programmeyear 0
2005 2010 2015 2020 2025 2030 2035 2040 2045 2050
5 10 15 20 4525 30 35 40
operation: priority materials
conceptual design
construction
construction
upgrade,construct
operateTodays
expts.
licensing
H & D operation
low-duty D-T operation
high-duty D-T operation
TBM: checkout and characterisation
TBM performance tests & post-exposure tests
second D-T operation phaseITER
EVEDA (design)
other materials testingIFMIF
engineering designconstruction phase 1
blanket construction
phase 2blanket
construction &installation
operation phase 1operation phase 2
blanket design
phase 2 blanket design
licensing
DEMO(s)
engineering designconstruction operateconceptual design
licensing
Commercial Power plants
blanket optimisation
plasma performance confirmation
materials characterisation
design confirmation
technology issues (e.g. plasma-surface interactions)
plasma issues
single beam
licensing licensing
plasma confirmation
materials optimisation
plasma optimisation
mobilis-ation
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Project Schedule (2006)
2005 2006 2007 2008 2009 2010 2011 2012 2013 2014 2015
ITER IOLICENSE TO CONSTRUCT
TOKAMAK ASSEMBLY STARTS
BidContract
EXCAVATETOKAMAK BUILDING
OTHER BUILDINGS
TOKAMAK ASSEMBLY
COMMISSIONING
MAGNET
VESSEL
Bid Vendor’s Design
Bid
Installcryostat
First sector Complete VVComplete blanket/divertor
PFC Install CS
First sector Last sector
Last CSLast TFCCSPFC TFCfabrication start
Contract
Contract
2016
Construction License Process
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The ITER site
Tokamak building
Tritium building
Cryoplant buildings
Magnet power convertors buildings
Cooling towers
TheHot cell
The site will cover about 60 ha, with buildings over 170m long