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Fusion mit Laser und Teilchenstrahlen für die Stromerzeugung - Stand und Perspektiven
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30.01.10 01:58BBC News - Laser fusion test results raise energy hopes
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ONE-MINUTE WORLD NEWS
INERTIAL CONFINEMENT FUSION
By Jason Palmer Science and technology reporter, BBC News
The experiment focuses 192 high-power laser beams to a tiny target
A major hurdle to producing fusion energy using lasers hasbeen swept aside, results in a new report show.
The controlled fusion of atoms - creating conditions like those in ourSun - has long been touted as a possible revolutionary energysource.
However, there have been doubts about the use of powerful lasersfor fusion energy because the "plasma" they create could interruptthe fusion.
An article in Science showed the plasma is far less of a problem thanexpected.
The report is based on the first experiments from the NationalIgnition Facility (Nif) in the US that used all 192 of its laser beams.
Along the way, the experiments smashed the record for the highestenergy from a laser - by a factor of 20.
Star power
Construction of the National Ignition Facility began at LawrenceLivermore National Laboratory in 1997, and was formally completedin May 2008.
The goal, as its name implies, is to harness the power of the largestlaser ever built to start "ignition" - effectively a carefully controlledthermonuclear explosion.
It is markedly different fromcurrent nuclear power, whichoperates through splitting atoms -fission - rather than squashingthem together in fusion.
Proving that such a lab-basedfusion reaction can release more
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Page last updated at 23:12 GMT, Thursday, 28 January 2010
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Laser fusion test results raise energy hopesA D V E R T I S E M E N T
A D V E R T I S E M E N T
SEE ALSOGiant laser experiment powers up 31 Mar 09 | Science & Environment
Laser heats up the fusion future 19 May 08 | Science & Environment
Europe seeks fusion power 06 Oct 08 | Science & Environment
Man-made star to unlock cosmic secrets 22 May 09 | Science & Environment
Giant laser experiment powers up 30 Mar 09 | Technology
Europe follows fusion twin track 07 Oct 08 | Science & Environment
How to build a star on Earth 16 Feb 09 | Science & Environment
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A D V E R T I S E M E N TA D V E R T I S E M E N TAktualität
BBC- ONLINE 28.1.2010
NIF Fertiggestellt 2009 Beginn Experimente 2009
Erste Kampagne 2010
Ende der ersten Kampagne 2012
Workshop Science for Ignition @ NIF
High-Foot Kampagne 2013
Adiabate shaping 2015
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Trägheitsfusion
Bestrahlung der Oberfläche
Kompression (Raketen- prinzip)
Zentrale Zündung Burn
3
Magnetic Confinement Fusion Dichte = 1014 cm-3 Einschlusszeit = 1 Sekunde
Inertial Confinement Fusion Dichte = 1025 cm-3 Einschlusszeit = 10 Pikosekunden
Plasma Einschlussbedingung: Lawson Kriterium: nτ = 1014
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Einige Zahlen
Bei ρR=3 g/cm2 i.e. fb=30% Y=100 MJ/mg
1 mg DT muss komprimiert werden zu 336 g/cm3 oder 1680 x Festkörperdichte (0.2 g/cm3) für ρR=3 g/cm2.
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Lawrence Livermore National Laboratory 3
Rosen APS/DPP 10/14/14 LLNL-PRES-662854
Three approaches to ignition are being pursued, with implosions that are Laser, Magnetically or X-ray driven
This talk deals exclusively with x-ray driven implosions, aka “Indirect Drive”
Laser: Directly Driven (Spherical on Ω, Polar on NIF) led by URLLE PO L A R DR I V E IG N I T I O N CA M P A I G N CO N C E P T U A L DE S I G N
12
Figure 3: PD pointing configuration showing the four rings of NIF beams and five PD beam groups or rings, yielding irradiation at three different latitudes on the target.
Ignition experiments with PD require that each of the five PD beam rings have a unique pulse shape, and continuous phase plate. The combination of these components, coupled with single-beam smoothing provided by the MultiFM 1D SSD on the pickets and polarization smoothing, provide the required drive uniformity to achieve ignition conditions. Figure 4 illustrates the pulse power vs. time (a) and the resultant beam intensity profiles (b) (obtained from the requisite phase plate) for each ring of NIF beams. The use of the triple-picket pulse (Figure 4a) represents a quantitative change from the strategy employed in previous PD ignition designs.7 OMEGA experiments have shown that picket pulses can be experimentally tuned for optimal shock timing.26 Furthermore, adiabat shaping and increased shell stability can be realized by adjusting the strength of the shocks launched by the pickets. A step pulse at the start of the main drive launches a fourth shock giving further control over the adiabat. Shock tuning of this four-shock design will be conceptually identical to the tuning performed for indirect-drive targets. A cone-in-sphere target design either filled with liquid D2 or using a thick ablator design (to appropriately spread the shock arrival times at the inner shell wall) will be used. Due to the inherent asymmetry of PD, these shock timing experiments will rely on the dual-axis target design employed by the NIC campaign and currently under development for PD experiments on OMEGA.
Magnetically: Magnetized Liner Inertial Fusion at Sandia Nat’l Lab
X-ray: Produced by NIF laser at LLNL with an Internt’l team
Lawrence Livermore National Laboratory 5 Rosen APS/DPP 10/14/14
A hohlraum indirectly drives capsule implosions at the 1.8 MJ National Ignition Facility (NIF)
It needs to Provide Sufficient Radiation Drive:
After ~ 0.2 MJ LPI losses, ~ 1.6 MJ of laser energy couples to the hohlraum wall. It converts
to ~ 1.3 MJ of x-rays. A ~ 300 eV x-ray bath ablates outside of the capsule, (using ~ 150 kJ), driving the rest inward: a 15 kJ, 370 km/s rocket.
It needs to Provide that Drive Symmetrically:
Symmetrically compress the capsule as it implodes. Short λ modes smooth geometrically.
P2,P4 controlled via inner vs. outer beam balance, & Cross Beam Energy Transfer (CBET)
The kinetic energy of the rocket payload is reconverted to internal
energy upon stagnation in the round imploded core.
inners
outers
at NIF
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Um die enormen Anforderungen an die Symmetrie zu gewährleisten wird in der ersten Kampagne die indirekte Zündung versucht
indirectIllumination
by x-rays
fuel capsulecompression
(200-1000 g/cc)
fusionignition
(~ 10 keV)fusionburn
High-Z hohlraumDT fuel
capsule
mid(low)-Z fill slows
down wall motion
laser
backscattering
Wall losses
LEH losses
x-rays
Zündung bedarf der Optimierung von:• Hohlraum Design:
- Laserabsorption/ -propagation, backscattering- Laser Konversionseffizienz in X-rays- Hohlraum Re-emissionseffizienz (Wand+LEH Verluste)
• Implosiondynamik der Kompression - shock timing, EOS ablator studies
• Kompressionssymmetrie der Kapsel
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This work performed under the auspices of the U.S. Department of Energy by Lawrence Livermore National Laboratory under Contract DE-AC52-07NA27344
NIF
7Aufgabe: Verlässliche Zündung einer Fusionsreaktion mit Gain bei niedrigster möglicher Laserenergie
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NIF-0506-11956
10
Eine von zwei Laserbays
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Targetkammer
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NIF hat bislang keine Zündung erreicht was ging schief? wo stehen wir?….
LLNL-PRES-645894 This work was performed under the auspices of the U.S. Department of Energy by Lawrence Livermore National Laboratory under contract DE-AC52-07NA27344. Lawrence Livermore National Security, LLC
APS DPP Meeting QI3.00004 Nov. 13, 2013
Omar A. Hurricane Distinguished Member of the Technical Staff
Progress Toward Ignition at the
National Ignition Facility Presentation to
European Physical Society Meeting Espoo, Finland
July 1, 2013
D. E. Hinkel
LLNL-PRES-640041
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2014 NIF performance
NIF hat seine Designparameter inzwischen weit übertroffen
alle drei Monate wird das bislang stärkste Lasersystem der Welt (NOVA) addiert
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NIF Tests erfüllen (und oft übertreffen) die Design Spezifikationen, die für die Zündung erwartet werden
18
NIF ist das zuverlässigste Lasersystem das je gebaut wurde
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The principal issues on ignition performance deficit
Performance deficit likely due to combination of low mode X-ray drive asymmetry / cold fuel shape, and higher than simulated hydrodynamic instability
Mix Fuel shape
Vermutete Hauptgründe für das Versagen bei der Zündung
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New radiography capabilities used to measure low mode fuel asymmetry (Oct 2012 - Mar 2013)
Ge (~10 keV)
Pinhole array
Gated images N121004
Imploded THD fuel scatters X-rays
60-200 keV
30 µm tilted Au wire
Gated MCP
THD shot N121005
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Preliminary data!
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Erstmals gute Übereinstimmung mit den Rechnungen (YOC)
Lawrence Livermore National Laboratory LLNL-PRES-645894 15
0 2 4 6 8 10 12 14
0.01
0.1
1
111215
120131
120205
120213
120311120321
120405
120422
130501
130530
130710
130802
130812
130927
CH mix fraction (at%)
1D Y
OC
LFHF
N130530: out of spec ice (large m=1 mode) N130802: longer +700 hohlraum
Using a hohlraum drive that is "calibrated" to tuning experiments (shock, shape, trajectory, etc.)
Plot from P. Patel
Lawrence Livermore National Laboratory LLNL-PRES-645894 19
EDT = Ehs +Efuel + 12 e
−τ fuel EBrems − 12 Eα
Compression yield (kJ)
Tota
l yie
ld (k
J)
0 1 2 3 4 5 6 7 8 9 100
2
4
6
8
10
12
14
16
18
20
N130927
N130812
N130710
N130501
" = High-foot " = Low-foot = Range of EDT,total
Ytotal = 14.4 kJ
Ehs = 3.5 – 4.8 kJ Phs = 129 - 150 Gbar
Eα = 1.8 – 2.5 kJ
ρhs = 34 – 49 g/cm3
= 8.8-11.7 kJ
Efuel = 5.8 – 6.8 kJ ρfuel = 442 – 462 g/cm3
α = 2.2 – 2.6
EBrems = 2.5 – 4.6 kJ τfuel = 0.7 – 1.3
Eablator absorbed = 150 kJ
Beginn der alpha-Teilchen Heizung wird sichtbar
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NIS zeigt Hotspot Form und Lage
13-17 MeV
6-12 MeV
primary downscattered
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Resultat seit der NATURE Veröffentlichung
0
5
10
15
20
25
30
1106
0811
0615
1106
2011
0826
1109
0411
0908
1109
1411
1103
1111
1211
1215
1201
2612
0131
1202
0512
0213
1202
1912
0311
1203
1612
0321
1204
0512
0412
1204
1712
0422
1206
2612
0716
1207
2012
0802
1208
0812
0920
1303
3113
0501
1305
3013
0710
1308
0213
0812
1309
2713
1119
1312
1213
1219
1401
20
Yiel
d (k
J)
Yield from fuel compression Yield from self heating
Lawrence Livermore National Laboratory LLNL-PRES-645894 2
0
5
10
15
ShotID
Yield (
kJ)
110608
110615
110620
110826
110904
110908
110914
111103
111112
111215
120126
120131
120205
120213
120219
120311
120316
120321
120405
120412
120417
120422
120626
120716
120720
120802
120808
120920
130331
130501
130530
130710
130802
130812
130927
Yield from fuel compression Yield from self heating
NIC (Low-foot)
High-foot N130927 [390 TW, 1.8 MJ] Energycompression = 7.7 kJ Energyalpha_heating = 6.6 kJ
Plot from P. Patel
Joint WCI/NIF Team: D. Callahan, E. Dewald, T. Dittrich,T. Doeppner, D. Hinkel, L. Berzak Hopkins, O. Hurricane, P. Kervin, J. Lee Kline (LANL), S. LePape, T. Ma, J. Milovich, J. Moody, A. Pak, H.-S. Park, B. Remington, H. Robey, J. Salmonson, NIF operations, NIF cryo, NIF targets, GA, LLE, & M.I.T.
9.3 x 1015 n mit 11.5 kJ Kompression und 14.5 kJ Selbstheizung NIF betritt das Gebiet der selbstheizungs-dominierten Physik
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Cross-beam energy transfer results in a spatially non-uniform, time-dependent intensity distribution
14
Schematic of Ignition Hohlraum
wall"
30o"quad"LEH"
(Laser"Entrance"Hole)"
Beam before xbt, refraction, absorption
Beam after xbt, refraction, absorption
• Cross Beam Energy Transfer (CBET):
laser forward scatters off ion acoustic waves (P. A. Michel et al., PoP, May 2010)
energy transfer
IAW
D. E. Hinkel -- EPS 2013 -- Espoo, Finland
• CBET ~ I x ne/Te – occurs at peak power (where laser intensity I is maximum) – occurs when laser beams burn through gas to wall (when Te is low)
Drive
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Lawrence Livermore National Laboratory 10
Rosen APS/DPP 10/14/14 LLNL-PRES-662854
We’re ~ 2x away from required ignition conditions
At the end of NIC in 2012, we were > 10x lower in Yield, and Pstag ~ 130 Gbar Lawrence Livermore National Laboratory P611468.ppt – Edwards– NIF DRC, 05/06/14
13
Conditions are currently ~ factor 2 from ignition
UR = Areal density
~ 500 g/cc
~ 40 g/cc
~ 180 Gbar
~ 0.75 g/cm 2
Best simultaneous performance on single shot
~ 27kJ
Eignition ~ UR3T ~
UR� �3T 3Pstag2Shell ρR provides
inertial confinement
60 µm
alph
50 million degrees achieved
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Weitergehende Ansätze
Verbessertes Hohlraum Design (Rugby Hohlraum) Optimierter Energietransfer äussere zu innere Strahlen -> Form der Implosion Optimierte Adiabate (zwischen 2.6und 1.5) Diamant- Ablator, dünnerer Ablator Optimierte, isobarische Zündung (e.g. mit 2ω) Double shell (non-cryo solution?) Elektronen Fast Ignition (mit oder ohne Cone) Protonen Fast Ignition (2016?)
WARUM? • kleinere Infrastruktur; höherer Gain; • Verbesserte Toleranz gegen Laser/Target Nichtidealitäten • Breitere Basis für Grundlagenforschung • Möglichkeit Tritium zu vermeiden (oder zu reduzieren)
Für jeden Fall zu untersuchen: • Pros/cons • Facility (laser, targetry, delivery, reactor, waste) • Level of confidence • Compatibility between options (since confidence<1) • Required R&D plan
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Fast Ignition
Fast Ignition separates the functions of compression & ignition of the fuel; less compression is required (more fuel can be assembled) and symmetry relaxed.
Think – Hot-Spot ignition = Diesel Engine, Fast-Ignition = Gas Engine (spark-plug)
29
Atmosphere formation
Compression Ignition Burn
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0 -200 -400 200 400z (µm)
r (µ
m)
0
-200
-400
200
400
0.01
35ρ (g/cm3)
Als Fast Ignitor wird untersucht: Elektronen, Protonen und Ionen, mit Konus und Schock-Ignition
Honrubia et al
r (µ
m)
0
-200
-400
200
400
0 -200 -400 200 400z (µm)
log10 ρ (g/cm3) 3
-1
30
GIFI
MADEIRA_01
A
B
B
CB AC
B
6.4 mm
Au beam window: 10 microns
Au lateral walls: 40 microns
Fusion capsule 0.14 cm of radius with 0.8mg of DTShort pulse laser beam
Conversion foil
Shield
Heavy ion beamsBi+ at 3.5 GeV
Au 0.3 gr/ccBe dopped with Au 0.02 gr/ccBe 0.02 gr/cc
Foam convertersA)B)C)
10 mm
Fusion capsule is driven by thermal radiation inside a "hohlraum" target irradiated by heavy-ion beams
2-D Simulations: Gain~60, IFAR=18 Target
- 400 (250+150)kJ. Gain ~70
- NIF 2D SSD
- Modes l=4-100
- Normal incid. ray trace
- Thomas-Fermi EOS
- no radiation
- + 12-group radiation
- 500kJ
2D Simulations: Robustness to Laser Imprint Hydro
Instabilities Can be Assessed via the Ignition Window
2-D
2-D
1-D
Ignition Occurs Despite Large Nonuniformities in Ignitor Shock
Densitycontours attime ofshockcollisionReturn shock
Ignitor shock
Densitycontours atignition onset(T~6keV)
Gain~70
FSCLLE
r (µ
m)
0
-200
-400
200
400
0 -200 -400 200 400z (µm)
FSC
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LIFE der nächste Schritt?
Fusion Fission Hybrid burns nuclear Waste low fusion gain needed (500 MW) boosted to 3000 GW (thermal)
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Neutron transport affects a varietyof components and raises a set of issues
Capsule
Hohlraum
Liquid blanket
FinalFocus Magnets
Blanket
First Structural Wall
Radius
Folgeabschätzungen: Aktivierung und Sicherheit
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Displacement/atom (dpa)
Displacement per atom (dpa) für 30 Jahre Betrieb als Funktion der Dicke der flüssigen Wand. Ein Wert von 100 dpa ist das ungefähre Limit für Edelstahl. Bei der Magnetfusion wird dieser nach zwei Jahren erreicht. Abschätzungen basieren auf 3m Radius, 2700 MW Fusionsenergie und 80% Verfügbarkeit.
Folgeabschätzungen: Reaktorlebenszeit
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Radioaktivität (t) nach 30Jahren Betrieb
Radioaktivität eines 1 GW (el) Fusionsreaktors (CASCADE) als Funktion der Zeit nach 30 Jahren bBetrieb. Im Vergleich zu einem MCF Fusionsreaktor ist sie zu jeder Zeit mindestens 3 Größenordnungen kleiner.
Spätfolgen
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Folgeabschätzungen
Es gibt eine Vielzahl von neutroneninduzierten Problemen die beachtet werden müssen:
Neutronenwechselwirkung im Target Neutronenaktivierung & Transmutationsreaktionen Isochores Heizen der Wand Strahlungsschäden
Diese Herausforderungen beeinflussen den Bau und die Akzeptanz eines Kraftwerkes:
Chamber clearing Radiologische Sicherheit Verlässlichkeit der Komponenten & Performance Abfallmanagement Wirtschaftlichkeit
35
Hier ist noch viel zu tun, besonders die Materialfrage ist hier entscheidend!
ICF bietet mehr Möglichkeiten durch die Trennung von Treiber und Reaktor, aber die Eigenschaften funktionaler Materialien unter diesen Bedingungen sind weitgehend unerforscht!!!