Transcript Slide 1

ITER
The past, present and future
1985 to 2007
Garry McCracken
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
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
+ 18.3 MeV
Key reaction
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
Conceptual fusion reactor
Fusion Reactor
Lithium
Lithium blanket
Primary
Fuels
Deuterium
D+T
plasma
Tritium
Deuterium
Tritium
Reprocessing
of gases
Helium + hydrogen
w aste gases
Vacuum
Exhaust Gases -Deuterium, tritium
hydrogen , helium
Electricity
grid
Heat exchanger
Turbine
Steam Generator
G enerator
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
Tokamak Principles
Confinement is produced by the combination of toroidal field
produced by external coils and a poloidal field produced by a
current in the plasma
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
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
Scaling confinement time from
experiments to ITER
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
President Reagan, Gorbachev
Geneva Summit, 1985
Designing ITER
• Conceptual design 1988-90
• Engineering design 1992-94 (Rebut)
• Engineering design 1994-98 (Aymar)
• Redesign 1998-2001 (Aymar)
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
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)
Robert Aymar
Director (1994-2003)
Comparison of JET and ITER
JET is the largest presently
existing tokamak
JET
R=3m
Ip=4MA
ITER
R=6.2m
Ip=15MA
Central Solenoid
Nb3Sn, 6 modules
The 2001 ITER design
Cryostat
24 m high x 28 m dia.
Toroidal Field Coil
Nb3Sn, 18, wedged
Vacuum Vessel
9 sectors
Poloidal Field Coil
Nb-Ti, 6
Major plasma radius 6.2 m
Port Plug
heating/current
drive, test blankets
limiters/RH
diagnostics
Plasma Volume: 840 m3
Plasma Current: 15 MA
Typical Density: 1020 m-3
Typical Temperature: 20 keV
Fusion Power: 500 MW
Machine mass: 23350 t (cryostat + VV + magnets)
- shielding, divertor and manifolds: 7945 t + 1060 port plugs
- magnet systems: 10150 t; cryostat: 820 t
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
Magnets and Structures
Superconducting. 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.
Vessel, Blanket and divertor
The 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.
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
Parameters of the ITER designs
Conceptual ŅFinalÓ
(1990)
(1998)
P lasma major radius
(m)
6.0
P lasma width at mid-plane
(m)
2.15
Elongation (rat io of plasma height to width)
1.98
Toroidal field on plasma axis
(T)
4.85
Nominal maximum plasma current (MA)
22
Nominal fusion power
(MW) 1000
Pulse length more t han
(s)
200
Number of toroidal field coils
16
2
Neut ron wall loading
(MW/m ) 1.0
Divertor
double
8.1
2.8
1.6
5.7
21
1500
1000
20
1.0
single
Redesign
(2001)
6.1
2.0
1.7
5.3
15
500
400
18
single
The Rebut design in 1994 had 24 field coils but was otherwise similar to the
1998 design
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 approach
Agreement on the Caderache site
Signing the treaty,
Paris, 21 November 2006
The ITER buildings today
Cadarache, near Aix-en-Provence, France
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.
The ITER organization
ITER Director-General
Dr Kaname Ikeda (Japan)
Deputy Director General and Project
construction leader
Dr Norbert Holtkamp EU
Deputy Director Generals
Gary Johnson US
Tokamak
Kim KO, Engineering,
Fuel cycle
Carlos Alhedre EU
Safety, Environment
Valery Chuyanov RF
Fusion Science
Wang CN Administration,
Finance
Dhijaj Bora (IN) Control
Diagnostics and Heating
Proposed ITER Site Layout
Staff Planning
Staff Ramp Up IO Team
700
600
Number
500
400
Sum PPY: 1800
Sum Support: 2760
Sum Total
300
200
100
0
2006 2007 2008 2009 2010 2011 2012 2013 2014 2015
Calendar Year
Indicative Construction Schedule
Fig .I-4 .2 -1 Overa ll Co nstructio n Schedule
NSSR
RE GU L AT ORY A PPR OVAL
Construction
A greement
SITE LIC ENSE
M onths
C ONSTR UC TION LIC ENSE
12
0
24
36
48
60
72
84
96
108
EX C AVATE
CONST RUC T I ON
Purcha s e orde r
B UILD TOKAM AK B U ILDING
HV A C ready
SITE FAB R IC ATION B UILD IN G
OTHER B UILDIN GS
PFC s ite
fabrica tion
build.
TO KAM AK ASSEM B LY
C omplete
VV torus
Pla ce firs t
TF/VV in pit
Ins ta ll cryos ta t
bottom lid
Complete B lanket/
Divertor Installation
Ins ta ll C S
Pla ce low er
PFC
SY STEM STA R TUP & TESTING
ST ART UP &
COM M I SSI ONI NG
INTEGR ATED
C OM M ISSIO NIN G
C omplete lea k
& pres s ure te s t
M agne t
excitation
1ST PLASM A
PR OCURE M E N T
PR OC UR EM ENT O F M AGNETS
Firs t purc ha s e
order
PFC fa b. s tart
TFC fa b.
s ta rt
La s t PFC complete
C S fab.
s ta rt
La s t TFC
comple te
P ROC URE ME N T OF V V S E CTORS , B LA NK E T & D IV E RTOR
VV 1s t Sec tor
La s t VV
C S fab.
comple te
Indicative Operation Schedule
C ons tr uc tio n Phas e
1st yr
2nd yr
3rd yr
4th yr
5th yr
6th yr
7th yr
8th yr
9th yr
10th yr
M i le Stone
Firs t Plas ma
Install ati on &
Commi ssioning
Bas ic
Ins talla tion - Commissioning
Full Fie ld , C ur rent
& H /C D Pow er
Sho rt D T
Bur n
Q = 10,
500 MW
Q = 10,
500 MW ,
400 s
Full No n-indu c tiv e
C ur rent D riv e
For ac tiv ation ph as e
- Achieve
good vacuum &
wall condition
For hig h duty oper ation
U pgr ade
H Plas ma Phase
D Phase
Firs t D T Pla sma Phase
O peration
- Machine commissioning
with plasma
- Heating & CD Expt.
- Reference scenarios
with H
Equi val ent
Number of
Burn P ulses
(500 M W x 440
s*)
Low D uty D T
- Development of full DT high Q
- Developmentt of non-inductive
operation aimed Q = 5
- Start blanket test
1
750
1000
- Improvement of inductive and
non-inducvtive operation
- Demonstration of high duty
operation
- Blanket test
1500
2500
3000
0.006
MW a/m2
F luence**
Blanket Test
H igh D uty D T
- Commissioning
w/neutron
- Reference w/D
- Short DT burn
Sys tem C heckout and C ha ract reriz ation
- Electro-magnetic test
- Hydraulic test
- Effect of ferritic steel etc.
- Neutronics test
- Validate breeding
performance
3000
0.09
MW a/m2
Performance Te st
- Short-time test of T breeding
- Thormomecanics test
- Preliminary high grade heat
generation test, etc.
- On-line tritium recovery
- High grade heat generation
- Possible electricity generation, etc.
* The bu rn time of 440 s inc ludes 40 0 s flat top and eq uiv alent time w hic h additio nal flux is c ounted dur ing ramp- up and r amp-d ow n.
** Av er age Fluenc e a t Firs t W all (N eu tr on w all load is 0.56 MW/m2 in a v era ge and 0.77MW /m2 at outboa rd midplane.)
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
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
Provisional future programme
year 0
5
2005
Todays
expts.
10
2010
upgrade,
construct
ITER
20
2020
H&D
operation
construction
low-duty D-T
operation
35
2035
2040
40
45
2045
2050
TBM: checkout and
characterisation
high-duty D-T operation
second D-T operation phase
TBM performance tests & postexposure tests
blanket
optimisation
plasma performance
confirmation
EVEDA
(design)
30
2030
plasma
issues
licensing
IFMIF
25
2025
operate
technology issues (e.g. plasmasurface interactions)
mobilisation
15
2015
construction
single
beam
plasma
optimisation
operation: priority materials
other materials testing
materials
characterisation
materials
optimisation
construction phase 1
DEMO(s)
conceptual design
engineering design
blanket
design
licensing
operation phase 1
blanket construction
phase 2 blanket
design
licensing
phase 2
blanket
construction
&installation
operation phase 2
licensing
design
confirmation
plasma
confirmation
Commercial
Power plants
conceptual design
engineering design
licensing
construction
operate
Project Schedule (2006)
LICENSE TO
CONSTRUCT
ITER IO
2005
2006
2007
Bid
2008
TOKAMAK
ASSEMBLY STARTS
2009
2010
2011
2012
2013
2014
2015
2016
EXCAVATE
Contract
TOKAMAK BUILDING
OTHER BUILDINGS
Construction License Process
First sector Complete VV
TOKAMAK ASSEMBLY
Install PFC
cryostat
MAGNET
Bid
Install CS
COMMISSIONING
Vendor’s Design
Contract
VESSEL
Complete
blanket/divertor
Bid
Contract
PFC
TFC CS
fabrication start
First sector
Last TFC
Last sector
Last CS
Cryoplant
buildings
Magnet power
convertors buildings
The ITER site
The
Hot
cell
Tokamak
building
Tritium
building
Cooling
towers
The site will cover about 60 ha, with buildings over 170m long