InteBoris Sharkov, Boris Sharkov, (ITEPITEP--Moscow),Moscow), : : HIF E HIF E –– activities in Europe and in Russiaactivities in Europe and in Russia

Outline

1. HI IFE (introduction) 2. RU IFE concept and respective activities3. International FAIR4. HED Physics with Intense HIB at FAIR

basic experimentsresults of numerical simulationsrelevance to HI IFErequirements for performance of experimental campaignspecific diagnostic methodscurrent experimental activities towards FAIR

5. Outlook

B. Sharkov 2

Basic motivations for HI IFEBasic motivations for HI IFE

• Intrinsic efficiency• High repetition rate ~1 - 10 Hz• Reliability / durability to last billions of shots• Final focusing magnets tolerant to neutrons

and target debris• Compatibility of beams to propagate through the poor vacuum of fusion chamber• Effective beam-target coupling• Mature driver technology

A.W.Mashke 1979

Consideration of HIFE leads to special Consideration of HIFE leads to special driver driver -- and and -- target combinationstarget combinations

Drivers Targets determined by target tailored specifically

requirements for acceleratorsChallenging aspect : short pulse length < 10ns Challenging aspect : short pulse length < 10ns –– i.e. 10E4 compression i.e. 10E4 compression

small focal spot ~ 1small focal spot ~ 1--2 mm2 mm@ large distance ~ 5 m@ large distance ~ 5 m

Two complimentary accelerator scenarios as potential IFE drivers :

1. The RF linac & storage ring approach – HIBALL, HIBALL-II (R.Bock 1984, GSI Darmstadt)- ITEP-Moscow (Koshkarev, V.Imshennik,

P.Zenkevich -1987)

2. The induction linear accelerator concept – US (LBNL, LLNL, Princeton)

“Russian” target M.Basko, V.Vatulin 19978 (10) converters 1.7 mm each,Energy deposiion 4.5 MJ/6ns

J.Maruhn 1997

Heavy ion targets with hydrodynamic ignitionHeavy ion targets with hydrodynamic ignitionIndirect drive option is considered to be feasible for heavy ion targets in

the hydrodynamic ignition mode. The fusion capsule can be similar to those of laser-driven hohlraums

R.Ramis 1998

2 converters3 MJ/6 ns

(IAEA-2004) Russian studies of fast ignition using 100 GeV heavy-ion synchrotrons: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.

HI IFE Concept Ground plan for HIF power plant

B.Y. Sharkov BY, N.N. Alexeev, M.M. Basko et al., Nuclear Fusion 45(2005) S291-S297.

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

-

Slide № 3 Medin S.A. et al

Slide № 4 Medin S.A. et al

−+,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

Ignition beamEnergy (MJ) 0.4Duration (ns) 0.2Maximum current (kA) 20Focal spot radius (µm) 50

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

−+,Pt 198,196,194,192

• 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.

HIF Power Plant HIF Power Plant 1 1 GWGW ++ accelerator accelerator 100 100 GeVGeV Pt+Pt+

Principal motivation for cylindrical targets

Near‐relativistic heavy ions with energies  ≥ 0.5 GeV/U 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 when

azimuthal 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 ignitor pulse. 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 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 ~120

Fusion energy (MJ) 750

Energy release partition

X-ray (MJ) 17

Ion debris (MJ) 153

Neutrons (MJ) 580

Target irradiation by rotating ion beam

1cm

DTfuelPorousP

babsorberPbShell

IgnitionBeam

E=0.4MJ

Dt=0.2ns

Compressing

hollowbeam

E=4.6MJ

Dt=60ns

Pbpusher

0.00 2.00 4.00 6.00

0.00

1.00

2.00

3.00

4.00

5.00

ρ ≥ 100 g/cm3 ,

ρR ≥ 0.5 g/cm2

E = 6.3 MJ (instead 7.1 MJ )

Fusion – Fission - Fusion

Au

Pb

U238

DT

• 10 MJ Heavy Ion Driver -> directly driven cylindrical target

• Cylindrical implosion of DT fuel -> DT-neutrons generation

• DT-neutrons -> fission of U238pusher material

• Better confinement, additional compression of DT

• Burn fraction & energy gain enhancement

10 MJ ion beamRotation ~1 GHz

REACTOR CHAMBER CHARACTERISTICS

Fusion 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 ports 2

First wall material SiC (porous)

Coolant tubes material V-4Cr-4Ti

Blanket energy multiplication 1.1

REACTOR CHAMBER REACTOR CHAMBER FOR HIF POWER PLANT:FOR HIF POWER PLANT:

wetted first wall designwetted first wall design

INJECTIONTARGET

SHIELD

STRUCTURALWALL

FOCUSING LENS

IGNITION BEAMWETTED WALL

BLANKET

DISPERSED JETS

COOLANT POOL

TO HEATEXCHANGER

COMPRESSING HOLLOW

TO V

ACU

UM

PU

MP

BEAM

REACTOR CHAMBER FOR FAST IGNITION HEAVY ION FUSION 0 5 10 m

Pb83Li17

Orlov Yu.N., Basko M.M., Churazov M.D. et al.,Nuclear Fusion 45 (6) , 531 – 536, (2005).

SS..АА..MedinMedin¹¹,, ММ..ММ..BaskoBasko²²,, Yu.N.OrlovYu.N.Orlov³³

¹¹Joint Joint Institute forInstitute for High Temperatures High Temperatures ²²Institute for Theoretical and Experimental Physics Institute for Theoretical and Experimental Physics

³³Keldysh Institute forKeldysh Institute for Applied MathematicsApplied Mathematics

Response of the first wetted wall of Response of the first wetted wall of an IFE reactor to the energy release an IFE reactor to the energy release

from a directfrom a direct--drive DT capsuledrive DT capsule

GOAL OF RESEARCHGOAL OF RESEARCH

Hydrodynamics of IFE reactor chamber Hydrodynamics of IFE reactor chamber induced by the capsule explosion:induced by the capsule explosion:

(a) DT capsule implosion and burn,(a) DT capsule implosion and burn,(b) X(b) X--ray and charged particles stopping,ray and charged particles stopping,(c) Radiation transport in the chamber,(c) Radiation transport in the chamber,(d) Liquid film ablation,(d) Liquid film ablation,(e) Neutron deposition in blanket.(e) Neutron deposition in blanket.

COMPUTED EVENTS IN REACTOR CHAMBER COMPUTED EVENTS IN REACTOR CHAMBER

t = 0

DT implosion starts

3,5 ns

DT ignition

4.16 ns

Fireball expansion sets in

X-rays arrival

16,7 ns

95,9 ns

Neutrons arrival

Debris impact on vapor layer

Helium ions arrival 1000 ns

384 ns

Computation of the liquid film response to Computation of the liquid film response to XX--ray,ray, neutron and helium ions heatingneutron and helium ions heating

Physics of the RAMPHY radiation-hydrodynamics code

* 1D-2T Lagrangian (spherical, cylindrical, planar)

* Plasma thermal conduction and viscosity

* Radiation diffusion and relaxation between plasma and radiation temperatures

* Mean Rosseland and Planckian opacities

* Neutron diffusion and heating (MCNP)* Condensed matter strength and spallation

* Wide-range equation of state, phase transitions and ionization

* Applied energy sources: X-ray and fast ions volumetric energy deposition

XX--ray emission from the HIF cylindrical ray emission from the HIF cylindrical targettarget.

• X-ray prepulse is generated by shock arriving at the target surface at t=104ns.

• Prepulse FWHM equals 0.5ns.

• X-ray main pulse starts at t=300ns. Its FWHM equals 360ns.

100 200 300 400 500 600

0

50

100

150

200

250

Wx,

TW

; T x

, eV

Time, ns

Tx Wx

Slide № 7 Medin S.A. et al

XX--ray, N and Ion Debris Impact on the First Wetted ray, N and Ion Debris Impact on the First Wetted Wall of IFE ReactorWall of IFE Reactor

TTargetarget history after fuel microexplosionhistory after fuel microexplosion• The first maximum

of Eint corresponds to the fusion flare at t=95 ns

• The second maximum of Eint corresponds to the shock arrival at the target surface at t=104 ns

• The Eint pulsation is caused by the shock refraction in non-uniform shell.0 100 200 300 400 500 600

0

20

40

60

80

100

120

140

E kin

, Ein

t, E r

ad, M

J

Time, ns

Ekin Eint Erad

Slide № 8 Medin S.A. et al

XX--ray impact on the liquid film at the first wallray impact on the liquid film at the first wall

0,2 0,4 0,6 0,8 1,0 1,2 1,4 1,6 1,8 2,0-80

-40

0

40

80

120

160

200 80 ns 50 ns 20 ns

Pres

sure

, MPa

Lagrangian coordinate, kg/(4πR2)

0 2 4 6 8 10 12 14 16 18 20-10

0

10

20

30

40

50

60 400 ns 900 ns

Pres

sure

, MPa

Lagrangian coordinate, kg/(4πR2)

Pressure profiles in the liquid film at various times for the X-rays prepulse impact. R=5m.

Pressure profiles in the liquid film at various times for the X-rays main pulse impact. R=5m.

Slide № 9 Medin S.A. et al

FIHIF target neutron pulse

9 4 9 5 9 6 9 7 9 8 9 9 1 0 01 E 2 01 E 2 11 E 2 21 E 2 31 E 2 41 E 2 51 E 2 61 E 2 71 E 2 81 E 2 91 E 3 01 E 3 1

2 . 4 5 M e V

1 4 M e V

Neu

tron

on fl

uenc

e, n

/s

T i m e , n s

MCNP code, spherical approximation, 2D neutron transport Medin S.A., Orlov Yu.N., Suslin V.M. Preprint of KIAM of RAS 62 (2004)

Average neutron energy ~12.2 MeVTritium breeding ratio (TBR) of the blanket ~ 1.112blanket multiplication factor ~ 1.117total energy release per shot ~ 818 MJ

Slide № 10 Medin S.A. et al

Pressure distribution in FIHIF blanket at various times1D hydrodynamic equations in cylindrical geometry

(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=0µsPr

essu

r e,M

Pa

Radial distance, m

(b)

Liquid wall response

0,0 0,2 0,4 0,6 0,8 1,0 1,2 1,4 1,6 1,8 2,00

100

200

300

400

500

600

700 10 ns

30 ns

50 ns

Pres

sure

, MP

a

Lagrange coordinate in the film, kg/m2

0 2 4 6 8 10 12 14 16 18 200

20

40

60

80

100

120

140 250 ns 900 ns

Pres

sure

, MP

a

Lagrange coordinate in the film, kg/m2

liquid film of eutectic Li17Pb83real equation of state for Pb,ionization processes (Saha) ,heat conductivity (Rosseland mfp)

Shock wave propagation in the liquid film from the main X-ray pulse

Vs ~ 2000 m/s

Pre-pulse shock wave propagation

Input data for computation of the first wall response Input data for computation of the first wall response to to XX--ray,ray, neutron and helium ions heatingneutron and helium ions heating

Initial conditions for the liquid Pb filmT0 = 823 K, P0 = 0, ρ0 = 10.55 g cm-3

3,4 3,5 3,6 3,7 3,8

103

104

105

106

107

Leak

ing

pow

er W

n, W

He,

Wr,

TW

Time, ns

Wr

WHe

Wn

3,2 3,3 3,4 3,5 3,6 3,7 3,8 3,9 4,00,0

0,5

1,0

1,5

2,0

2,5

Rad

iatio

n te

mpe

ratu

re, k

eV

Time, ns

Boundary conditions for the liquid Pb filmFree surface: P = 0, dT/dr = 0, krgradTr = -σTr^4Liquid-wall interface: dU/dr = 0, dP/dr = 0, dT/dr = 0

,

Deposited energy sourcesTemporal energy profiles deposited by X-rays, neutronsand fast He4 ions

X-ray temperature at the DT fireball surface Neutron spectra

0 4 8 1210-3

10-2

10-1

100

Target First wall Fourth channel

Neu

tron

s pe

r ene

rgy

grou

p

Neutron energy, MeV

SUMMARYSUMMARY--11• Heavy ion beams are well adjusted to a massive

cylindrical target.

• X-ray emission profile with short intense prepulse and low-amplitude extended main pulse.

•• The vapor layer generated by the prepulse The vapor layer generated by the prepulse shields the liquid film from the main Xshields the liquid film from the main X--ray pulse.ray pulse.

•• The target ion debris is absorbed by the vapor The target ion debris is absorbed by the vapor layer as well, and vapor reradiation leads to layer as well, and vapor reradiation leads to revaporization of the liquid film. revaporization of the liquid film.

SummarySummary--22• mechanical loading of the first wall material

turns out to be tolerable to X-ray impact of the first wall

• relaxation of the fog atmosphere of the reactor chamber to the initial conditions is fast enough (from 1 to 10 ms): not a limiting factor for the repetition rate,

• fast condensation of vapor is well accomplished, when an array of dispersed jets is employed,

• 2D neutron transport in the reactor chamber determines tritium breading ratio (1.112) and blanket energy multiplication factor (1.117) and provides data on thermal energy density distribution for the blanket design,

• The problem of vapor fog/droplets inside the chamber - major concern for the reactor design.

• Experiments required (new IAEA CRP)

Tivoli XVII century

НаучноНаучно--координационныйкоординационныйСоветСовет

ВНИИЭВ ИХПФ РАН ИТЭС РАН

НН//ТТсекретариатсекретариат

ИТЭФВНИИТФ ТРИНИТИФЭИ

РосатомРосатом (Rosatom)(Rosatom) РАНРАН (RAS)(RAS)

ЦИЭЭПЦИЭЭП

ЦентрЦентр ИсследованийИсследованийЭкстремальныхЭкстремальныхЭнергетическихЭнергетическихПроцессовПроцессовРосатомРосатом ––РАНРАН

ITEPITEP--TWAC Facility in ProgressTWAC Facility in Progress

Здание инжектора И-2

Secondary beams π, µ, ,К, p

Secondary beams π, µ, ,К, pSlow extraction: р, С,,.Fe,,.U

P+ fast extraction for Proton therapy

Fast extraction р, С,,.Fe,,.UFor HED

C6+ slow extraction

Slow extraction from UK ring: С,,.Fe,,.U

Slow extraction: р, С,,.Fe,,.UРадиоактивные ядра

Internal target C >Be

Non‐Liouvillian Injection into the storage ring 

Accumulator ring U‐10

Booster ring UK

C4+

C6+τ ∼ 7,5 min

Non‐Liouvillian stacking process

Ni > 10^10

Stacking process for 213 MeV/u C6+

RF bunch compression

170 нс

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

Laser Plasma Ion Source Laser Plasma Ion Source ––at ITEP at ITEP Capable of delivering Pb, In, Nb… ions with rep-rate 1 HzFor Pb 25+ : 7,7 mA / 3.5 mks , 0.6 10 E10 ions measured

emittance – 0.2 mm mrad (normalized)

ITEP SolutionsITEP Solutions

1:Laser ion source

2: RFQ accelerator

3: Non-Liouvillian stacking

4. RF wobbler technique

ITEPITEP‐‐TWAC project in progressTWAC project in progress

>4 10¹º C6+, Fe25+, Al13+

accumulated

accelerated 

up to 4 GeV/u

B.Sharkov ITEP

Mode of operation

Accelerators

Beam energy, MeV/u

Mode of beam extraction

Proton acceleration

I-2I-2/

U-10

25up to 230up to 3000up to 9300up to 3000

(9300)

pulse, 10 µ/smedical extraction, 200 ns,fast extraction, 800 ns,internal target, 1sslow extraction, 1s

Ion acceleration,

С, Al, Fe,(Pb,U)

I-3/UKI3/UK/U-10

1,5 - 40050 - 4000 fast extraction, 800 ns,

internal target, 1s, slow extraction, 1s

Nuclei accumulation

,С, Al,Fe,(Co,Zn)

I3/UK/U-10

200-300700-1000

fast extraction with compression to 150 ns,continues extraction of

stacking beam

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”

• Induced radioactivity issues

Layout of the new injector linac

4

RFQ

6 m 6 m

Co25+

(Al10+)

1.6 MeV/u

SP RFQ

7 MeV/u20 keV/u

Laser source

Output energy 7 – 8 MeV/uBeam pulse duration 15 µsBeam current of the main component 16 mABeam emittance 4π mrad*mmOperation frequency 81.4 MHz

Parameters of the RFQ cavity

13

Operation frequency, MHz 81.4Inner cavity diameter, m 0.56Cavity length, m 6Nearest dipole mode, MHz 98Quality factor 11000Storage energy, J 8.3RF power losses, kW 600

Assembling of the RFQ cavity with aluminum

model electrodes

31

1.4

m1.2 m

20

Пучки В511 и В512. Вид сверху.

5 4 3 2 1

2 1

5.5 m6 m6 m6 m

М II

Мишенная камера I

Складраритетов, 2 эт.

Пультоваяпучка, 1 эт.

Стеновые блоки

5.5

m

В511И11В511И12

В511Б10

27

21

28

3.6

m

6.0 m

0,7

m

3 .2

m

2 .8

m

Вход I

Вход II

Фазовращатель

В511С6

2.4 m

up5.

9m

1.15

m

33

3938

1.0

m

37

1718

19

242526

34

29

22

1314

11

10 09 08 07 06 05 04 03 02

36

01

30

23

42 41 40 39

5 3

16

up

12

4

0.6

5m

18

m

6

66 m

1.2

m

7.2 m

1.2

m

15 0.2 m

В511Б7В511Б8

В511Б9

Выключатель. Светильник.

2.1

m

12.65m

3 ,40 m

1,65m

.

В5 12Б 7

В 51 2Б 8

В512Б 9

В512Б10

1 ,65 m

Входнойколлиматор

3,5 0m

Аппертурный

коллиматор

Мишень

Оптический

стол MII

0.6m

35

32

ITEP-TWAC, Experimental Area for PP