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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

RELATED INTERNET LINKSNational Ignition Facility

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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

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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)

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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

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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!!!