Nuclear Fusion – Status and Perspectives...Nuclear Fusion – Status and Perspectives Hartmut Zohm...
Transcript of Nuclear Fusion – Status and Perspectives...Nuclear Fusion – Status and Perspectives Hartmut Zohm...
![Page 1: Nuclear Fusion – Status and Perspectives...Nuclear Fusion – Status and Perspectives Hartmut Zohm Max-Planck-Institut für Plasmaphysik 85748 Garching GRS Fachgespräch 2013 Köln,](https://reader033.fdocuments.us/reader033/viewer/2022042317/5f06676f7e708231d417d30c/html5/thumbnails/1.jpg)
Nuclear Fusion – Status and Perspectives
Hartmut ZohmMax-Planck-Institut für Plasmaphysik
85748 Garching
GRS Fachgespräch 2013Köln, 19.02.2013
![Page 2: Nuclear Fusion – Status and Perspectives...Nuclear Fusion – Status and Perspectives Hartmut Zohm Max-Planck-Institut für Plasmaphysik 85748 Garching GRS Fachgespräch 2013 Köln,](https://reader033.fdocuments.us/reader033/viewer/2022042317/5f06676f7e708231d417d30c/html5/thumbnails/2.jpg)
Outline
What is the basic idea of Nuclear Fusion on Earth?
Where do we stand today?
What are the next steps?
Summary and conclusions
![Page 3: Nuclear Fusion – Status and Perspectives...Nuclear Fusion – Status and Perspectives Hartmut Zohm Max-Planck-Institut für Plasmaphysik 85748 Garching GRS Fachgespräch 2013 Köln,](https://reader033.fdocuments.us/reader033/viewer/2022042317/5f06676f7e708231d417d30c/html5/thumbnails/3.jpg)
Outline
What is the basic idea of Nuclear Fusion on Earth?
Where do we stand today?
What are the next steps?
Summary and conclusions
![Page 4: Nuclear Fusion – Status and Perspectives...Nuclear Fusion – Status and Perspectives Hartmut Zohm Max-Planck-Institut für Plasmaphysik 85748 Garching GRS Fachgespräch 2013 Köln,](https://reader033.fdocuments.us/reader033/viewer/2022042317/5f06676f7e708231d417d30c/html5/thumbnails/4.jpg)
A simplistic view on a Fusion Power Plant
The ‚amplifier‘ is a thermonuclear plasma burning hydrogen to helium
Centre of the sun: T ~ 15 Mio K, n 1032 m-3, p ~ 2.5 x 1011 bar
Pin = 50 MW(initiate and controlburn)
Pout = 2-3 GWth(aiming at 1 GWe)
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A bit closer look…
Fusion reactor: magnetically confined plasma, D + T → He + n + 17.6 MeV
Centre of reactor: T = 250 Mio K, n = 1020 m-3, p = 8 bar
3.5 MeV 14.1 MeV-heating wall loading
Pin = 50 MW(initiate and controlburn)
Pout = 2-3 GWth(aiming at 1 GWe)
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Toroidal systems avoid end losses along magnetic field
Need to twist field lines helically to compensate particle drifts
Plasma can be confined in a magnetic field
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'Stellarator': magnetic field exclusively produced by coils
Example: Wendelstein 7-X (IPP Greifswald)
Plasma can be confined in a magnetic field
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'Tokamak': poloidal field component from current on plasma
Simple concept, but not inherently stationary!
Example: ASDEX Upgrade (IPP Garching)
Plasma can be confined in a magnetic field
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'Tokamak': poloidal field component from current on plasma
Simple concept, but not inherently stationary!
Example: ASDEX Upgrade (IPP Garching)
Plasma can be confined in a magnetic field
![Page 10: Nuclear Fusion – Status and Perspectives...Nuclear Fusion – Status and Perspectives Hartmut Zohm Max-Planck-Institut für Plasmaphysik 85748 Garching GRS Fachgespräch 2013 Köln,](https://reader033.fdocuments.us/reader033/viewer/2022042317/5f06676f7e708231d417d30c/html5/thumbnails/10.jpg)
Plasma can be confined in a magnetic field
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Outline
What is the basic idea of Nuclear Fusion on Earth?
Where do we stand today?
What are the next steps?
Summary and conclusions
![Page 12: Nuclear Fusion – Status and Perspectives...Nuclear Fusion – Status and Perspectives Hartmut Zohm Max-Planck-Institut für Plasmaphysik 85748 Garching GRS Fachgespräch 2013 Köln,](https://reader033.fdocuments.us/reader033/viewer/2022042317/5f06676f7e708231d417d30c/html5/thumbnails/12.jpg)
The road to Fusion Energy holds many challenges
Fusion plasma physics
• heat insulation of the confined plasma
• exhaust of heat and particles
• magnetohydrodynamic (MHD) stability of configuration
• self-heating of the plasma by fusion born -particles
Fusion specific technology
• plasma heating and diagnostics
• fuel cycle including internal T-breeding from Li
• development of suitable materials in contact with plasma
• development of suited low activation structural material
![Page 13: Nuclear Fusion – Status and Perspectives...Nuclear Fusion – Status and Perspectives Hartmut Zohm Max-Planck-Institut für Plasmaphysik 85748 Garching GRS Fachgespräch 2013 Köln,](https://reader033.fdocuments.us/reader033/viewer/2022042317/5f06676f7e708231d417d30c/html5/thumbnails/13.jpg)
The road to Fusion Energy holds many challenges
Fusion plasma physics
• heat insulation of the confined plasma
• exhaust of heat and particles
• magnetohydrodynamic (MHD) stability of configuration
• self-heating of the plasma by fusion born -particles (ITER)
Fusion specific technology
• plasma heating and diagnostics
• fuel cycle including internal T-breeding from Li (DEMO)
• development of suitable materials in contact with plasma
• development of suited low activation structural material
![Page 14: Nuclear Fusion – Status and Perspectives...Nuclear Fusion – Status and Perspectives Hartmut Zohm Max-Planck-Institut für Plasmaphysik 85748 Garching GRS Fachgespräch 2013 Köln,](https://reader033.fdocuments.us/reader033/viewer/2022042317/5f06676f7e708231d417d30c/html5/thumbnails/14.jpg)
The road to Fusion Energy holds many challenges
Fusion plasma physics
• heat insulation of the confined plasma
• exhaust of heat and particles
• magnetohydrodynamic (MHD) stability of configuration
• self-heating of the plasma by fusion born -particles (ITER)
Fusion specific technology
• plasma heating and diagnostics
• fuel cycle including internal T-breeding from Li (DEMO)
• development of suitable materials in contact with plasma
• development of suited low activation structural material
![Page 15: Nuclear Fusion – Status and Perspectives...Nuclear Fusion – Status and Perspectives Hartmut Zohm Max-Planck-Institut für Plasmaphysik 85748 Garching GRS Fachgespräch 2013 Köln,](https://reader033.fdocuments.us/reader033/viewer/2022042317/5f06676f7e708231d417d30c/html5/thumbnails/15.jpg)
Power Ploss needed to sustain plasma
• determined by thermal insulation: E = Wplasma/Ploss (‘energy confinement time’)
Fusion power increases with Wplasma
• Pfus ~ nDnT<v> ~ ne2T2 ~ Wplasma
2
Presently: Ploss compensatedby external heating systems
• Q = Pfus/Pext Pfus/Ploss ~ nTE
Reactor: Ploss compensated by -(self)heating
• Q = Pfus/Pext =Pfus/(Ploss-P) (ignited plasma)
Figure of merit for fusion performance nT
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R
Energy confinement time determined by transport
collision
Transport to the edge
B
Experimental finding:
• ‚Anomalous‘ transport, much largerheat losses
• Tokamaks: Ignition expected for R = 7.5 m
Simplest ansatz for heat transport:
• Diffusion due to binary collisions
• table top device (R 0.6 m) should ignite!
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Energy Transport in Fusion Plasmas
Anomalous transport determined by gradient driven turbulence
• linear: main microinstabilities giving rise to turbulence identified
• nonlinear: turbulence generates ‘zonal flow’ acting back on eddy size
• (eddy size)2 / (eddy lifetime) is of the order of experimental values
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Energy Transport in Fusion Plasmas
Anomalous transport determined by gradient driven turbulence
• temperature profiles show a certain ‘stiffness’
• ‘critical gradient’ phenomenon – increases with Pheat (!)
increasing machine size will increase central T as well as E
N.B.: steep gradient region in the edge governed by different physics!
T(0.4)T(0.8)
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Anomalous transport determines machine size
ITER (Q=10)
DEMO (ignited)
• ignoition (self-heated plasma) predicted at R = 7.5 m
• at this machine size, the fusion power will be of the order of 2 GW
ITER (N=1.8)
DEMO (N=3)
Major radius R0 [m] Major radius R0 [m]
Fusi
on P
ower
[MW
]
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The road to Fusion Energy holds many challenges
Fusion plasma physics
• heat insulation of the confined plasma
• exhaust of heat and particles
• magnetohydrodynamic (MHD) stability of configuration
• self-heating of the plasma by fusion born -particles (ITER)
Fusion specific technology
• plasma heating and diagnostics
• fuel cycle including internal T-breeding from Li (DEMO)
• development of suitable materials in contact with plasma
• development of suited low activation structural material
![Page 21: Nuclear Fusion – Status and Perspectives...Nuclear Fusion – Status and Perspectives Hartmut Zohm Max-Planck-Institut für Plasmaphysik 85748 Garching GRS Fachgespräch 2013 Köln,](https://reader033.fdocuments.us/reader033/viewer/2022042317/5f06676f7e708231d417d30c/html5/thumbnails/21.jpg)
Plasma wall interface – from millions of K to 100s of K
• plasma wall interaction in well defined zone further away from core plasma
• allows plasma wall contact without destroying the wall materials
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• plasma wall interaction in well defined zone further away from core plasma
• allows plasma wall contact without destroying the wall materials
Plasma wall interface – from millions of K to 100s of K
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The perfect wall material: Low-Z or High-Z?
High-Z materials (W, Mo) promise low erosion rates and fuel retention
• if edge temperature is low enough…
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ASDEX Upgrade: operation with fully W-coated wall
First successful demonstration of use of W with reactor relevant plasma
• capitalises on low divertor temperatures that lead to negligible erosion
• plasma performance can be equal to that with C-wall
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Additional cooling by impurity seeding
Injecting adequate impurities can significantly reduce divertor heat load
• impurity species has to be ‘tailored’ according to edge temperature
• edge radiation beneficial, but core radiation (and dilution) must be avoided
No impurityseeding
With N2seeding
Bolometry of total radiated power Discharge with P/R = 13 MW/m (ASDEX Upgrade)
19
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Additional cooling by impurity seeding
No impurityseeding
With N2seeding
19
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The road to Fusion Energy holds many challenges
Fusion plasma physics
• heat insulation of the confined plasma
• exhaust of heat and particles
• magnetohydrodynamic (MHD) stability of configuration
• self-heating of the plasma by fusion born -particles (ITER)
Fusion specific technology
• plasma heating and diagnostics
• fuel cycle including internal T-breeding from Li (DEMO)
• development of suitable materials in contact with plasma
• development of suited low activation structural material
![Page 28: Nuclear Fusion – Status and Perspectives...Nuclear Fusion – Status and Perspectives Hartmut Zohm Max-Planck-Institut für Plasmaphysik 85748 Garching GRS Fachgespräch 2013 Köln,](https://reader033.fdocuments.us/reader033/viewer/2022042317/5f06676f7e708231d417d30c/html5/thumbnails/28.jpg)
Tokamaks have made Tremendous Progress
• figure of merit nTE doubles every 1.8 years
•JET tokamak in Culham (UK) has produced 16 MW of fusion power
• present knowledge has allowed to design a next step tokamakto demonstrate large scale fusion power production: ITER
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Outline
What is the basic idea of Nuclear Fusion on Earth?
Where do we stand today?
What are the next steps?
Summary and conclusions
![Page 30: Nuclear Fusion – Status and Perspectives...Nuclear Fusion – Status and Perspectives Hartmut Zohm Max-Planck-Institut für Plasmaphysik 85748 Garching GRS Fachgespräch 2013 Köln,](https://reader033.fdocuments.us/reader033/viewer/2022042317/5f06676f7e708231d417d30c/html5/thumbnails/30.jpg)
A stepladder of tokamak experiments
JET6 m
80 m3
~ 16 MWth
(D-T)
ITER12 m
800 m3
~ 500 MWth
(D-T)
Diameter VolumeFusion power
ASDEX Upgrade3.3 m14 m3
1.5 MW(D-T equivalent)
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The ITER Design
Major RadiusMinor Radius
Plasma currentMagnetic field
Power amplification Q
Fusion powerDuration of burnExternal heating
ITER6.2 m2.0 m15 MA5.3 T
(Supercond.)
10
400 (800)MW 400 (3000) s 73 (110) MW
ITER
Cost: ~ 15 Billion €Requires world-wide effort
ITER will be built in Cadarache (F) as joint effort – Cn, EU, In, Jp, Ko, RF, US
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ITER operational scenarios
ITER operational scenarios aim at fulfilling several physics missions
• demonstrate self heating by -particles (close the loop)
• provide long pulse -heated discharges in reactor-regime to testtechnology elements (e.g. T-breeding) for the next step (DEMO)
Scenario: Standard Low q Hybrid AdvancedIp [MA] 15 17 13.8 9Bt [T] 5.3 5.3 5.3 5.18N 1.8 2.2 1.9 3Pfus [MW] 400 700 400 356Q 10 20 5.4 6tpulse [s] 400 100 1000 3000
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ITER = proof of principle for dominantly -heated plasmas
DEMO = proof of principle for reliable large scale electricity productionwith self-sufficient fuel supply
DEMO must be larger: 6.2 m 8.5 m, 400 MW ~ 2 GW
First scoping studies indicate that further advances in physics and technology could be very beneificial
The step from ITER to DEMO
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DEMO Challenges: Blanket
Breeding blanket must provide self-sufficient T-supply for fuel cycle
• breeding ratio > 1 needed (1 neutron per fusion reaction n-multiplier)
Blanket also crucial for providing high grade heat (the hotter the better)
He sub-systems
cold shield
SiCf/SiC channel inserts
EUROFER Structure (FW+Grids)
ODS Layers plated to the FW
hot shield
coolant manifold
He-2
He-1 Pb-17Li
Pb-17Li1
2
rad.
tor.
pol.
“Dual Coolant” He-PbLi LM Blanket DesignTmax ≥ 650°C, 80-150 dpa in DEMO (KIT)
EU Power Plant ConceptualDesign Study (PPCS)
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DEMO Challenges: structural materials
Progress in materials development needed to fully use fusion advantages
• issue: structural stability at high temperature under 14 MeV neutron-flux
• EUROFER steel up to 550o C (but not below 300 oC), better: ODS
• also reduce waste issues (fuel/burn products itself have short 1/2 12 yrs)
1 hr 1 day 1 year 100 yearstime (log scale)
Spec
ific
activ
ity (B
q/kg
)
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2010 2015 2020 2025 2030 2035 2040 2045 2050 2055
DEMO-relevant technology
ITER
Plas
map
hysi
cs
IFMIF
Tokamak physics
Firstcommercialpower plant
Stellarator physics
ITER-relevant technology
First electricityfrom fusion
DEMO
Faci
litie
sTe
chno
logy
A Road Map to Fusion Energy
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Outline
What is the basic idea of Nuclear Fusion on Earth?
Where do we stand today?
What are the next steps?
Summary and conclusions
![Page 38: Nuclear Fusion – Status and Perspectives...Nuclear Fusion – Status and Perspectives Hartmut Zohm Max-Planck-Institut für Plasmaphysik 85748 Garching GRS Fachgespräch 2013 Köln,](https://reader033.fdocuments.us/reader033/viewer/2022042317/5f06676f7e708231d417d30c/html5/thumbnails/38.jpg)
Summary and Conclusions
Fusion energy research has made tremendous progress in recent years
• existing database enabled design of next-step device: ITER
Strategy towards fusion energy comprises 3 major facilities:
• ITER to study burning plasma physics and fusion specific technology
• IFMIF to qualify materials (in parallel to ITER)
• DEMO to demonstrate viability of integrated reactor concept
Fusion power plants could be ready to supply energy by 2050
• they will not be too late
• their development will need continuous effort, also in funding