Accelerator Technology and Power Plant Design for Fast ... · two-sided beam irradiation, ... = 2/3 E beam 150 GeV Bi209-> Pb (11.3 g/cc) full range = 1.21 cm d E /d z (G eV /cm)

Accelerator Technology and Power Plant Design Accelerator Technology and Power Plant Design for Fast Ignitionfor Fast Ignition

Heavy Ion Fusion EnergyHeavy Ion Fusion EnergyBoris Sharkov (ITEP-Moscow)M.Basko,M.Churazov,, D.Koshkarev, S.Medin, Yu.Orlov, Parshikov A. N., Suslin V.M.

ITEP-MoscowIHED RASKeldysh IAM RAS

20th IAEA FEC Villamoura 2004

OutlineOutline•• Basic principlesBasic principles•• Target for FI IFETarget for FI IFE•• Energy release partitionEnergy release partition•• HI Accelerator HI Accelerator –– DriverDriver•• Reactor ChamberReactor Chamber•• Chamber Wall ResponseChamber Wall Response•• Power Plant Power Plant •• ITEPITEP--TWAC facilityTWAC facility•• ConclusionsConclusions

Driver efficiency ≥ 25%High repetition rate ~ 1-10 HzHigh reliability based on developed accelerator technologies

Principal motivation for cylindrical targets

Near-relativistic heavy ions with energies ≥ 0.5 become an interesting alternative driver option for heavy ion inertial fusion (D.G. Koshkarev).

Bi ions with energies 100-200 GeV have relatively long ranges of ~7-18 g/cm2 in cold heavy metals. Such ranges can be naturally accommodated in cylindrical targets with axial beam propagation.

Direct drive may become a competitive target option whenazimuthal symmetry is ensured by fast beam rotation around the target axis,axial uniformity is controlled by discarding the Bragg peak, and (possibly) by

two-sided beam irradiation,a heavy-metal shell (liner) is used to compress the DT fuel.

0.0 0.2 0.4 0.6 0.8 1.0

100

150

200

Axial profile of the beam energy deposition rate

Edep = 2/3 Ebeam

150 GeV Bi209 -> Pb (11.3 g/cc)full range = 1.21 cm

dE/d

z (G

eV/c

m)

z (cm)

ion beam

DT

M.Basko et al., HIF 2002

M.Basko et al., HIF 2002

Fast ignition with heavy ions: assembled configuration M.Basko et al., HIF 2002

With a heavy ion energy ≥ 0.5 GeV/u, we are compelled to use cylindrical targets because of relatively long ( ≥ 6 g/cm2 ) ranges of such ions in matter.

The ion pulse duration of 200 ps is still about a factor 4 longer than the envisioned laser ignitorpulse. For compensation, it is proposed to use a massive tamper of heavy metal around the compressed fuel:

Assembled configuration Ignition and burn propagation

t = 0 t = 0.2 ns

DT = 100 g/ccρ

100 GeVBi ions

100 mµ

0.6 mm

Pb

Pb

100 GeVBi ions

DT= 100 g/ccρ

Pb

Pb

Fuel parameters in the assembled state: ρDT = 100 g/cc, RDT = 50 µm, (ρR)DT = 0.5 g/cm2.

2-D hydro simulations (ITEP + VNIIEF) have demonstrated that the above fuel configuration is ignited by the proposed ion pulse, and the burn wave does propagate along the DT cylinder!

Slide 10: M.Basko, EPS2003.

Cylindrical FIHIF Target

Pb shell

DT fuel

L=8mm

Ignition

beamIgnition

beam

E=0.4MJ

t=0.2ns�

E=0.4MJ

t=0.2ns�

Compressing

hollow beam

E=7.1MJ, t=75ns�

Compressing

hollow beam

E=7.1MJ, t=75ns�

R=8mm

Slide № 6 Medin S.A. et al

Density distribution in compressed cylindrical target for FIHIF (t=30ns) M.Churazov 2004, 2D hydro


FIHIF Driver Scheme The Third IAEA TM 11-13.10.04, Daejon, Korea

RFQRFQIS

Wideroe

Alvarez

Main linac

Pt+198 }

Pt 196+ }

Pt+194 }

Pt+192 }

Pt-198 }

Pt-196 }

Pt-194 }

Pt-192 }

Storage rings

IS=ionsource

compressing

1 2 3 4 5 6 7 8

Pt +192

beam

ReactorChamber


Beam parameters of HIF driver for fast ignition fusionStation

number

Ion energ

y (GeV

)

RF frequen

cy (MHz)

Bunch current

(A)

Momentum spread (x104)

Emittance(µm)

β=v/c

1 10-4 0.04 ±300 0.3 0.001

2 10-3 6.25 0.16 ±180 0.9 0.003

3 10-2 12.5 0.4 ±36 0.9 0.010

4 0.1 50 1 ±37 0.9 0.033

5 0.2 200 4 ±75 0.95 0.047

6 100 1000 230 ±2 1 0.745

7 100 Single bunch

20000 ±30 1 0.745

8 100 Single bunch

1600 ±20 1 0.745



−+,Pt 198,196,194,192

HIGH POWER HEAVY ION DRIVERIons

Ion energy (GeV) 100Compression beam

Energy (MJ) 7.1 (profiled)Duration (ns) 75Maximum current (kA) 1.6Rotation frequency (GHz) 1Rotation radius (mm) 2

Duration (ns) 0.2Maximum current (kA) 20

Ignition beamEnergy (MJ) 0.4

Focal spot radius (µm) 50

Main linac length (km) 10Repetition rate (Hz) 2x4 (reactor)Driver efficiency 0.25

−+,Pt 198,196,194,192

Ground plan outlinefor FIHIF power plant

Reactor andturbogenerator building

Reactor andturbogenerator building

Transfer lines for ignitionbeam

Transfer lines for ignitionbeam

Storagering

Storagering

Compressionring

Compressionring

Auxiliarylinac

Auxiliarylinac Transfer line for compressing beam, P

+

192Transfer line for compressing beam, P+

192

Ion sources andlow energy linac tree

Ion sources andlow energy linac tree

Main linacMain linac

10 km10 km

Storagerings

Storagerings

+

Pt

192

-19

8P

t1

92

-19

8

Pt

192

-19

8P

t1

92

-19

8

-


REACTOR CHAMBER FOR FIHIF POWER PLANT


REACTOR CHAMBER CHARACTERISTICSFusion energy per shot (MJ) 750

Repetition rate (Hz) 2

Li/Pb atom density (cm-3) 1012

Coolant temperature (oC) 550

Explosion cavity diameter (m) 8

Number of beam penetrations 2

First wall material SiC (porous)

Coolant tubes material V-4Cr-4Ti

Blanket energy multiplication 1.1


CYLINDRICAL TARGETDT fuel mass (g) 0.006

Total mass (g) 4.44

Length (mm) ~8.0

ρR parameter (g/cm2) 0.5

Burn fraction 0.39

Gain 100

Fusion yield (MJ) 750

Energy release partitionX-ray (MJ) 17

Ion debris (MJ) 153

Neutrons (MJ) 580

The Third IAEA TM 11-13.10.04, Daejon, Korea


Temporal profiles of X-radiation characteristics for FIHIF cylindrical target

2 00 4 00 6 00 8 00 10 00 12 000

1 0

2 0

3 0

4 0

5 0

X-r ay ener gy

P ow er

Te m pe rature

X-ra

y en

ergy

, MJ;

Pow

er, T

W;

Tem

pera

ture

, eV

T im e, n s


Pressure distribution in liquid film at different times

0.0e0 5.0e0 1.0e1 1.5e1 2.0e1Lagrangian coordinate, kg m-2

0.0e0

1.0e8

2.0e8

3.0e8

4.0e8

Pres

sure

,Pa

t=100 nst=500 nst=1000 ns

Shock wave profiles generated by X-ray radiation in liquid film at the first wall




0.0e0 2.0e-3 4.0e-3 6.0e-3 8.0e-3

Lagrangian coordinates, kg m-2

1.1e3

3.0e3

8.1e3

2.2e4

6.0e4

1.6e5

4.4e5

1.2e6

3.3e6

8.9e6

Tem

pera

ture

, K t = 100 nst = 500 nst =1000 ns

Temperature profile in liquid protecting layer of the first wall


Vaporization rate of liquid film on the first wall

Temporal evolution of the evaporated mass

0 1 0 0 2 0 0 3 0 0 4 0 0 5 0 0 6 0 0 7 0 00 ,0

0 ,2

0 ,4

0 ,6

0 ,8

1 ,0

1 ,2

1 ,4

Vap

oriz

ed m

ass,

kg

T im e , n s


Evaporation-condensation dynamics

0,00 0,02 0,04 0,06 0,08 0,100,0

0,2

0,4

0,6

0,8

1,0

Tem

pera

ture

, 3.5

x105 K

Time, µs0,0 0,5 1,0 1,5 2,00

2

4

6

8

10

Den

sity

, 1.2

3x10

23m

-3

Time, msSlide № 16 Medin S.A. et al


FIHIF target neutron pulse

94 95 96 97 98 99 1001E201E211E221E231E241E251E261E271E281E291E301E31

2.45 MeV

14 MeV

Neu

tron

on fl

uenc

e, n

/s

Time, ns

Pressure distribution in FIHIF blanket at different times

(a)

PbLi

PbLi

PbLi

SiC VCrTi

Ht-9

PbLi

Firs

t wal

l

4,0 4,1 4,2 4,3 4,4 4,5-40

-20

0

20

40

60

300µs

200µs100µs

time=0µs

Pres

sur e

,MPa

Radial distance, m

(b)


FIHIF Blanket Structure and Neutron Energy DepositionMaterial ofblanket zones

R, cm ∆R, cm ρ, g/cm3

M, 103 kg

Q/V,MJ/m3

Q, MJ

1. PbLi2. PbLi3. SiC/PbLi4. PbLi5. V/4Cr/4Ti6. PbLi7. V/4Cr/4Ti8. PbLi9. V/4Cr/4Ti10. PbLi11. V/4Cr/4Ti12. PbLi13. V/4Cr/4Ti14. PbLi15. V/4Cr/4Ti16. PbLi17. V/4Cr/4Ti18. HT-919. Concrete

400,0400,0400,2401,0407,0407,4413,4413,8419,8420,2426,2426,6432,6433,0439,0439,4445,4446,4452,0

4000,20,86,00,46,00,46,00,46,00,46,00,46,00,46,01,06,0400

3,4⋅10-10

9,05,79,05,99,05,99,05,99,05,99,05,99,05,99,05,97,92,0

10-7

3,39,3110,84,9113,65,0116,15,1119,75,2123,75,4128,85,6133,014,5112,2-

5⋅10-9

23,820,718,58,912,26,16,52,84,11,11,50,80,90,20,30,10,07-

1,3⋅10-6

8,833,7237,77,4164,05,288,82,455,50,923,60,713,30,24,40,21,0Total:647,8


∆T, K

66,613,05,111,12,87,31,74,00,92,00,50,90,20,40,10,20,050,01


Pressure distribution in FIHIF blanket at different times

4 ,0 4,1 4,2 4 ,3 4,4 4,5-40

-20

0

20

40

60

3 0 0 µ s

2 0 0 µ s1 0 0 µ s

t=0

Pres

sure

, MPa

R a d ia l d ist an ce , m



Pressure, Temperature and Radial stresstemporal evolution in FIHIF blanket



Von Mises fluidity criteriumDetermination of material state in blanket design under neutron pulse impact

Temporal variation of equivalent stress normalized by yield stress Y (Y= 35 MPa for SiC/PbLi and 280 MPa for V-Cr-Ti).

The von Mises criterion determines elastic/plastic material behaviour.

0 2 4 6 8 10 12 14 16 18 200,0

0,2

0,4

0,6

0,8

1,0

Intermediate wall of VCrTi

First wall (porous SiC/liquid PbLi)(3

J 2/2Y2 )1/

2

Time, ms

( ) 2/12 2/3Jeq =σ

1/ ≤Yeqσ



• The reactor chamber with a wetted first wall has a minimum number of ports for beam injection. • A massive target significantly softens the X-ray pulse resulting from the microexplosion. • A two-chamber reactor vessel mitigates the condensation problem and partly reduces the vapor pressure loading. • Three loops in the energy conversion system make it easier to optimize the plant efficiency and to develop the thermal equipment.

ENERGY CONVERSION SYSTEM

Primary coolant loop Li17 Pb83

Max./min. temperature (oC) 550/350

Mass flow rate (ton/s) 13.1

Pump power (MW) 11.6

Intermediate coolant loop Na

Max./min. temperature (oC) 500/300

Mass flow rate (ton/s) 6.40

Pump power (MW) 3.77

Steam cycle

Steam parameters (MPa/oC/oC) 18/470/470

Net efficiency 0.417

Power plant parameters

Net power (per 1 chamber) (MW) 670

Net efficiency 0.373Slide № 23 Medin S.A. et al

ITEP-TWAC project in progress

• >10¹º C6+ accumulated• accelerated up to 4

GeV/u

B.Sharkov ITEP

Non-Liouvillian stacking process

Ni > 10^10

Процесс накопления ядер С 6+

ВЧ группировка пучка

170 нс

RFRF :: fofo == 695 695 ккHzHz, 10 , 10 ккVV

Ion accumulation С6+ in U-10 (213 MeV/u)

Линейный рост интенсивности ~ 100 c (> 30 циклов)

2·1010

Максимальная интенсивностьСнижение темпа накопление

Accelerator Technology Issues

• High current injection,

• Accumulation / stacking

• Bunch compression,

• IBS and vacuum instability

• Fast extraction

• Beam transport and focusing

• Generation of hollow beams –“wobbler”

High energy density experimental area

0 m 10 m 20 m

UK-ring

U10-ring

SM

M1

M2

9394

9192

95

9697

9899

910911

912913

915

Target

F1

Build

ing

120

ITEPITEP--TWACTWAC

ion beam

Cylindrical implosionexperiment300 MHzwobbler

Development of Diagnostic Methods

V is ib le an dU ltrav io le tD ia gnos tic

N eu tro n and ra y D ia gnos tic

γ -

Io n b eam

T arg e t

E xp erim en ta lM easu rem en ts

o f E O S P aram e te rs

X -ra y D ia gnos tic o f

T a rge t and In itia l B eam

E nerg y loss

d ia gnos tic

F o cu s in g S ys tem

B eam D iag n o s tic

X-ray back-lighting

CONCLUSIONS : - a power plant concept for fast ignition HIF is formulated, which is consistent with the newly proposed driver–target–chamber design.

- ITEP-TWAC facility is suitable for accelerator technology developments:

• Positive features :• A massive target significantly softens the X-ray pulse resulting from the microexplosion. • The reactor chamber with a wetted first wall has a minimum number of ports for beam injection. • A two-chamber reactor vessel mitigates the condensation problem and partly reduces the vapor pressure loading. • Three loops in the energy conversion system make it easier to optimize the plant efficiency and to develop the thermal equipment.

Problems of concern:

driver length,

target positioning in flight,

the of vapor fog problem in the chamber,

pressure-stress pulsations in the blanket.

Experiments in frame of IAEA CRP

HEAVY IONHEAVY IONBEAMSBEAMS

HED Ph.

Material science

MedicineAdvanced diagnostics

Rel. nuclearPh.

CBM

antique Goddess of Fertility

Roma-Tivoli 2004

AcceleratorPhysics

Post Post ScriptumScriptum

IFEIFE

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Accelerator Technology and Power Plant Design for Fast ... · two-sided beam irradiation, ... = 2/3 E beam 150 GeV Bi209-> Pb (11.3 g/cc) full range = 1.21 cm d E /d z (G eV /cm)