Integrated simulations of fast ignition of inertial fusion targets

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Integrated simulations of fast ignition of inertial fusion targets Javier Honrubia School of Aerospace Engineering Technical University of Madrid, Spain 11 th RES Users Meeting, Santiago de Compostela, Spain, 28 th Sep, 2017

Inertial Confinement Fusion 1-2 mm radius 10 14-10 15 W/cm 2 a few ns Hot plasma expands into vacuum causing shell to implode with high velocity Material is compressed to ~1000 gcm -3 Hot spark formed at the centre of the fuel by convergence of accurately timed shock waves Lasers or X-rays symmetrically irradiate pellet

National Ignition Facility (NIF)

Central ignition vs. Fast ignition

Fast ignition can be achieved with lower drive energies Separation between implosion and ignition phases. Courtesy of M. Key

Fast ignition schemes R.R. Freeman, Fast Ignition Review, National Academy of Sciences, March, 2011

Our simulation work The research projects carried out on Marenostrum and Magerit HPC have been focused to analyse alternative ignition schemes of inertial confinement fusion capsules with the aim of lowering the ignition threshold. The following schemes have been explored so far: - Electron-driven fast ignition of inertial fusion targets, where an electron jet is generated by the interaction of an ultra-high intensity (UHI) laser with the cone tip. The electrons deposit their energy in the compressed core triggering the fusion reaction. - Ion-driven fast ignition the same but driven by UHI laser-accelerated ions. - Magnetized inertial fusion targets. Just started. The simulation codes used have been as follows: - The Particle-In-Cell (PIC) codes PICLS [Sentoku & Kemp, JCP 227, 6846 (2008)] and EPOCH [Arber et al., PPCF 57, 113001 (2015)]. - The hybrid code PETRA [Honrubia et al., Phys. Plasmas 12, 052708 (2005)]. - The magneto-hydrodynamic code ATHENA [Stone & Gardiner, J. Comput. Phys. 205, 209 (2005)].

The first integrated FI experiment was very successful 0.5 PW Kodama et al., Nature 412, 798 (2001) and Kodama et al., Nature 418, 933 (2002) GEKKO laser 9 beams, 0.53 mm, 1.2 kj / 1ns 1000x increased DD neutrons 20% coupling efficiency to imploded CD

Beam collimation by density effects: Experiment on fast electron transport in high density plasmas Experimental setup 4 long pulse beams Experiment carried out at RAL Pérez, Honrubia et al., Phys Rev. Lett. 107, 065004 (2011) 1ns 40-50J each at 2w 0 160µm focal spots (1/e) Gold shield Short pulse beam 12 ps 160 J at w 0 20µm FWHM spot 4x10 18 W/cm 2 Ni foil to produce the hot electrons Copper foil Target description Polyimide shell 1.1g/cc, 20µm thick CH foam r m =0.1, 0.3 or 1g/cc 200µm long foam diameter = 180µm Polyimide hollow cylinder containing CH foam of 3 densities: 0.1, 0.3 and 1g/cc Foams polymerized by W. Nazarov (Univ. St. Andrews) Targets assembled at RAL (Ch. Spindloe et al.) 200 µm

Simulation strategy 3-D radiation-hydrodynamics for the cylinder implosion and compression. 2D PIC simulations to characterize the fast electrons generated by the short pulse laser. Hybrid simulations for simulation of fast electron transport in the compressed cylinder including self-generated electromagnetic fields. 3-D hydrodynamic simulations of target compression 1 g/cm 3 foam. 0.1 g/cm 3 foam. Temperature (K)

First experimental evidence of e-beam collimation Pérez et al., Phys. Rev. Lett. 107, 065004 (2011) 1 g/cc, t = 1.5 ns 1 g/cc, t = 2.0 ns 0.1 g/cc, t = 1.5 ns

Integrated simulations of ignition-scale targets

y [mm] PIC simulations of electron acceleration in a double cone Cone parameters: q = 15º, d int = 10 mm, d ext =20 mm, n e = 80 n c and Z* = 40 [Debayle, Honrubia et al., Phys. Rev. E 82, 036405 (2010)]. Numerical parameters: Dx = Dy = /50, 40 electron/cell. 10 million cells, 400 million particles. laser beam 2x10 20 W/cm 2 p - polarized = 1 mm pulse length 1 ps focal spot = 24 mm beam density n e 2r 0 =24 mm pre-plasma L = 1mm 10 mm x [mm] n e = 40 n c fast electron source (E > 255 kev) time integrated spectrum f(g) f(g) = A exp[-(g 1)m e c 2 /kt e ] kt e = 8.2 MeV f(g) = A (g-1) a, a ~ -1.2 0 radial current Dq 0 q r 20 40 60 75 X (mm) f (q) Aexp q q (y,t) 2 r Dq 0 (y,t)

(mm) (mm) Simulations with standard injection electron injection without radial drift E ig = 36 kj E = 1.6 MeV q HWHM Dq 0 = 35 o Honrubia & Meyer-ter-Vehn, Plasma Phys. Control. Fusion 51, 014008 (2009) Ion temperature and density Resistive magnetic field T i T i / kev r / (100 g/cc) B q r 250 g/cm 3 B q / Tesla r strong collimating magnetic field r 100 g/cm 3 (mm) (mm)

Simulations with PIC injection (q r 0) electron injection with radial drift E ig = 40 kj E = 1 MeV Dq 0 = 22 o, q r = 20 o radial current Dq 0 q r Debayle, Honrubia et al., Plasma Phys. Control. Fusion 52, 124024 (2010) Ion temperature and density Resistive magnetic field T i T i / kev B q r 250 g/cm 3 r / (100 g/cc) B q / Tesla r weak collimating magnetic field

Experimental evidence of fast electron collimation by external magnetic fields ILE, Osaka PS shell Ta e - X ray Fujioka et al., Phys. Rev. E 91, 063102 (2015) LFEX e - GXII e - X ray Simulations by H. Nagatomo X ray r 1 mm T Spectrum, angular distribution, image of x-rays are measured.

Ion-driven fast ignition

Generation extremely bright ion beams by the TNSA scheme Target Normal Sheath Acceleration scheme [Snavely et al., PRL 85, 2945 (2000)] Fluid model: P. Mora, PRL 90, 185002 (2003) [ ( )] 2 ; t = E max = 2T hot ln t + (t 2 +1) 1/ 2 w pi t acc æ ; w [ 2exp(1) ] 1/ 2 pi = Z e i ç è e 0 m i 2 n e0 ö ø 1/ 2

classical proton FI scheme (time spread)

Proton focusing in cone-targets has been demonstrated experimentally Bartal et al., Nature Phys. 8, 139 (2012), Foord et al., Phys. Plasmas 19, 056702 (2012), Qiao et al., Phys. Rev. E 87, 013108 (2013) hemisphere p deflected by an E-field E r - p he /n he D 80 (> 9 MeV) laser hemisphere + cone focusing radial E-field at the cone wall E p > 3 MeV Fluence diameter Expanded hot e source divergent beam Au cone 20 mm!

Laser Wavelength = 1.06 mm. Peak laser intensity I 0 = 10 20 W/cm 2. Spatial profile: Super-Gaussian, FWHM = 55 mm. Temporal profile: Gaussian, FWHM = from 1 to 0.35 ps. Boundary conditions for particles and fields x : laser and thermal y : periodic PIC simulation data Open PIC code EPOCH-2D [Arber et al., PPCF 57, 113001 (2015)]. Target [ Honrubia, Morace and Murakami, MRE 2, 28-36 (2017); submitted to Phys. Plasmas (2017)]. Length (x) = 130 mm, width (y) = 90 mm. Pre-plasma: exponential profile with a scale-length = 2 mm. Grid: 15 million cells, 600 million particles. laser H n e (cm -3 ) 10 18 1.1 10 23 n e =100 n c Au 14 mm C DT 10 n c

Experimental validation

300 um Experiments carried out at ILE, Japan - Free standing cone. - Gold walls 15 mm thick. - Hemispherical shell 350 mm radius. - Pulse energy: 800 J. - Pulse duration: 1.5 ps. - Laser intensity on target 10 19 Wcm -2. after A. Morace et al. Thomson parabola RCF stack RCF stack

Confirmation of beam hollowing The experimental results confirm the effect of B-fields on free standing cones with the protons being deflected in a ring-like shape by the B-fields

30 o 50 o Confirmation of beam hollowing The experimental results confirm the effect of B-fields on free standing cones with the protons being deflected in a ring-like shape by the B-fields

Y [mm] New cone design to mitigate the B-fields near the cone walls - Double cone with a second wall isolated from the laser-to-proton converter foil. - No currents flow through the second wall because it is electrically isolated. Thus, the B-field is confined to the gap between the two cone walls. - Only the B-field generated at the rear surface of the converter foil is dragged by the quasi-neutral plasma and amplified at the cone tip. This field is much lower than that generated by the surface currents, 40 20 Electron density 1.1 10 23 cm -3 0-20 -40 0 50 100 130 0 X [mm]

Summary PIC and hybrid simulations have proven to be very useful for experiment design and interpretation. MareNostrum and Magerit super-computers allowed us to carry out realistic simulations, competitive with those performed at the large scale laser facilities. We plan to study other alternative schemes to reduce the ignition energies. Some of those schemes are shock ignition and magnetized inertial confinement fusion. Those new schemes will be analyzed in close contact with experiments and within the context of the EUROfusion projects Towards inertial fusion energy and Preparation and Realization of European Shock Ignition Experiments funded by Euratom. Thanks for your attention!