Instituto de Plasmas e Fusão Nuclear
Instituto Superior Técnico
Lisbon, Portugal
http://www.ipfn.ist.utl.pt
C Silva | March 2015 | IST
.
Carlos Silva
Instituto de Plasmas e Fusão Nuclear
Controlled Nuclear Fusion
Author’s name | Place, Month xx, 2007 | Event C Silva | March 2015 | IST 2
Nuclear Fusion
Author’s name | Place, Month xx, 2007 | Event C Silva | March 2015 | IST 3
Nuclear Fusion Nuclear fusion involves the merging of light elements
Nuclear fusion could provide a safe energy source with abundant reserves and
low environmental impact
Author’s name | Place, Month xx, 2007 | Event C Silva | March 2015 | IST 4
Fusion reactions
MeVHHeHeD
MeVHTDD
MeVnHeDD
MeVnHeTD
3.18
03.4
27.3
6.17
43
4
4
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Advantages of nuclear fusion
Fuel Years
Deuterium 3x1011
Lithium
Earth 30 000
Oceans 30x106
Clean Abundant
= +
45 l 40 t 1 unit
Waste free
~200 000 kW h
Author’s name | Place, Month xx, 2007 | Event C Silva | March 2015 | IST 6
Advantages of nuclear fusion
Low Activation Competitive
Safe
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Plasma Confinement
gravitational magnetic inertial
Magnetic confinement is the most promising for
energy production
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Author’s name | Place, Month xx, 2007 | Event C Silva | March 2015 | IST 9
Nuclear Fusion history September 1958 “Atoms for Peace” (IAEA, Geneva)
Plasma physics is very difficult. A
worldwide collaboration is
necessary for progress
Fusion technology is very complex.
It's almost impossible to build a
fusion reactor in this century
L.A.Artsimovich E.Teller
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Nuclear Fusion history
B-3 stellarator
Princeton University
Initial results very disappointing (1950 - 1965)
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Nuclear Fusion history
1968 - A turning point for fusion (Tokamak)
IAEA Novosibirsk
(August 1968)
T3 reaches 1 keV
Confirmed in 1969: mission from
Culham (UK) to Moscow
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Tokamak | early 1960’s
World's first tokamak device Russian T1 Tokamak @ Kurchatov Institute in Moscow
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TOKAMAK
From Russian: toroidalnaya kamera,
magnitnaya katushka : Toroidal chamber
with magnetic coil
Tokamak is a toroidal plasma confinement
system comprising:
External coils that generate the toroidal
magnetic field
Transformer that produces a toroidal
current
The plasma current creates the poloidal
magnetic field lines resulting in a helical
field
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Tokamak
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R&D magnetic confinement
Tokamak Stellarator
EU is world leader
Tokamak configuration is favored
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Author’s name | Place, Month xx, 2007 | Event C Silva | March 2015 | IST 17
Major radius: 5.5 m
Minor radius: 0.53 m
Plasma volume: 30 m3
Stelarators | Wendelstein 7-X
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Joint
European
Torus
(JET)
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Vacuum vessel
Toroidal filed coils
(cooled)
Support
structure
(2600t)
Poloidal coils
…etc
Fusion device | JET
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Unique in the world with a capacity of
Nuclear fusion
Joint European Torus (JET) 1980’s-2015?
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Demonstration fusion power
Q = 0.65
1.7 MW (World First)
16.2 MW
(World Record)
25 MW
16 MW
Heating
Fusion Energy
Q=0.65
Q = 0.2
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Plasma turbulence affects the energy confinement time
Plasma energy confinement
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International Thermonuclear Experimental Reactor
Mission
• Prove scientific and technical feasibility of fusion energy
P = 500 MW, D = 300 s, Q = 10 – 20
• Test the integration of all the
technologies needed for a
nuclear fusion power plant
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International Thermonuclear Experimental Reactor
Mega-project de R&D
15000 M€
30 years 10 years construction
20 years operation
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JET allowed extrapolation of performance for baseline regime of operation of ITER
Fusion research profits from a step ladder approach based
on devices of different size but similar magnetic configuration
≈30 years
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ITER is a necessary step
ITER JET DEMO
6 m
80 m3
~ 16 MWth
12 m
800 m3
~ 500 MWth
Diameter (torus)
Plasma volume
Fusion power
Present Future
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WHEN?
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Significant progress
1968
Uma década
após T3
Progresso
impressionante
Anos 80-90
T
n T
E
ITER
Comparable with computers and accelerators progress
1980-1990
One decade
after T3
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Fusion energy | When?
- Classical approach: 60 years
- “Fast Track”: 40 years
Graphics by Prof. Sir Chris Llewellyn Smith, IAEA
Fusion Energy Conference, Vilamoura, 2004
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Fusion: Multidisciplinary Research
Power electronics
Superconductors
Control (plasmas, engineering)
Materials
Nuclear engineering
Remote handing
Simulation - numerical models
Diagnostics
Theoretical and experimental
physics
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ISTTOK @ IST
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ISTTOK
In operation since 1991 at IST
Density < 5 1018 m-3, Temperature < 200 eV
Fusion: 1 1020 m-3 , 20 keV
Objectives:
Training students and engineers
Development of diagnostics and new concepts: flexible, low
cost, short development time scales (collaboration with
several European laboratories)
Research in Plasma Physics (edge plasma)
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Activities in Magnetic Confinement | Main thrusts
ISTTOK
Collaboration in EU devices
• MAST
• ASDEX-Up
• TJ-II
• W7-X
• COMPASS
• Tore-Supra
• TCV