Hydrodynamic instability measurements in DTlayered ICF capsules using the layered-hgr platform

Similar documents
Hydrodynamic growth experiments with the 3-D, native-roughness modulations on NIF

Progress in detailed modelling of low foot and high foot implosion experiments on the National Ignition Facility

The Ignition Physics Campaign on NIF: Status and Progress

Journal of Physics: Conference Series PAPER OPEN ACCESS. To cite this article: T J Murphy et al 2016 J. Phys.: Conf. Ser.

The Pursuit of Indirect Drive Ignition at the National Ignition Facility

ICStatus and progress of the National Ignition Facility as ICF and HED user facility

High-density implosion via suppression of Rayleigh Taylor instability

Inertial Confinement Fusion

Analysis of Laser-Imprinting Reduction in Spherical-RT Experiments with Si-/Ge-Doped Plastic Targets

The Near Vacuum Hohlraum campaign at the NIF: a new approach

Where are we with laser fusion?

Inertial Confinement Fusion DR KATE LANCASTER YORK PLASMA INSTITUTE

The National Ignition Facility: Transition to a User Facility

Update on MJ Laser Target Physics

First Results from Cryogenic-Target Implosions on OMEGA

Experimental Demonstration of X-Ray Drive Enhancement with Rugby-Shaped Hohlraums

Exploration of the Feasibility of Polar Drive on the LMJ. Lindsay M. Mitchel. Spencerport High School. Spencerport, New York

Science and code validation program to secure ignition on LMJ

BEAM PROPAGATION FOR THE LASER INERTIAL CONFINEMENT FUSION-FISSION ENERGY ENGINE. S. C. Wilks, B. I. Cohen, J. F. Latkowski, and E. A.

What is. Inertial Confinement Fusion?

Modeling Laser-Plasma Interactions in MagLIF Experiment on NIF

The Magnetic Recoil Spectrometer (MRSt) for time-resolved measurements of the neutron spectrum at the National Ignition Facility (NIF)

A Vortex Model for Studying the Effect of Shock Proximity on Richtmyer-Meshkov Instability at High Mach Number

High Gain Direct Drive Target Designs and Supporting Experiments with KrF )

Direct-Drive, High-Convergence-Ratio Implosion Studies on the OMEGA Laser System

A Model of Laser Imprinting. V. N. Goncharov, S. Skupsky, R. P. J. Town, J. A. Delettrez, D. D. Meyerhofer, T. R. Boehly, and O.V.

Experiments on Dynamic Overpressure Stabilization of Ablative Richtmyer Meshkov Growth in ICF Targets on OMEGA

GA A25658 PRECISION X-RAY OPTICAL DEPTH MEASUREMENTS IN ICF SHELLS

High Energy Density Plasmas & Fluids at LANL

Diagnosing OMEGA and NIF Implosions Using the D 3 He Spectrum Line Width

Rayleigh-Taylor Growth Rates for Arbitrary Density Profiles Calculated with a Variational Method. Jue Liao

Analysis of a Direct-Drive Ignition Capsule Design for the National Ignition Facility

The National Ignition Campaign: Status and Progress

Laser absorption, power transfer, and radiation symmetry during the first shock of ICF gas-filled hohlraum experiments

Development of a WDM platform for chargedparticle stopping experiments

The MIT Accelerator for development of ICF diagnostics at OMEGA / OMEGA-EP and the NIF

Polar Drive on OMEGA and the NIF

The 1-D Campaign on OMEGA: A Systematic Approach to Find the Path to Ignition

ICF ignition and the Lawson criterion

Fukuoka, Japan. 23 August National Ignition Facility (NIF) Laboratory for Laser Energetics (OPERA)

Modeling the Effects Mix at the Hot Spot Surface in 1-D Simulations of Cryogenic All-DT Ignition Capsule Implosions

Inertial Confinement Fusion Experiments & Modeling

High-Performance Inertial Confinement Fusion Target Implosions on OMEGA

An Overview of Laser-Driven Magnetized Liner Inertial Fusion on OMEGA

Physics of Laser-Plasma Interaction and Shock Ignition of Fusion Reactions

Measurements of Magneto-Rayleigh-Taylor Instability Growth in Solid Liners on the 20 MA Z Facility

Polar Direct-Drive Simulations for a Laser-Driven HYLIFE-II Fusion Reactor. Katherine Manfred

FPEOS: A First-Principles Equation of State Table of Deuterium for Inertial Confinement Fusion Applications

Supporting Online Material for

Observations of the collapse of asymmetrically driven convergent shocks. 26 June 2009

Direct-drive fuel-assembly experiments with gas-filled, cone-in-shell, fast-ignitor targets on the OMEGA Laser

Polar-Drive Hot-Spot Ignition Design for the National Ignition Facility

The effect of shock dynamics on compressibility of ignition-scale National Ignition Facility implosions

Monochromatic 8.05-keV Flash Radiography of Imploded Cone-in-Shell Targets

Target Design Activities for Inertial Fusion Energy at Lawrence Livermore National Laboratory 1. Introduction

Theory and simulations of hydrodynamic instabilities in inertial fusion

Charles Cerjan. Nuclear Data Needs and Capabilities for Applications. Lawrence Berkeley National Laboratory. May 28, 2015

Los Alamos National Laboratory Hydrodynamic Methods Applications and Research 1 LA-UR

PROGRESS OF INDIRECT DRIVE INERTIAL CONFINEMENT FUSION IN THE US

Mitigation of Cross-Beam Energy Transfer in Direct-Drive Implosions on OMEGA

Integrated Modeling of Fast Ignition Experiments

ICF Burn-History Measurements Using 17-MeV Fusion Gamma Rays

Adiabat Shaping of Direct-Drive OMEGA Capsules Using Ramped Pressure Profiles

ON THE PATH TO IGNITION

MIT Research using High-Energy Density Plasmas at OMEGA and the NIF

Analysis of Experimental Asymmetries using Uncertainty Quantification: Inertial Confinement Fusion (ICF) & its Applications

High Convergence, Indirect Drive Inertial Confinement Fusion Experiments at Nova

Monoenergetic proton backlighter for measuring E and B fields and for radiographing implosions and high-energy density plasmas invited

Classical and ablative Richtmyer-Meshkov instability and other ICF-relevant plasma flows diagnosed with monochromatic x-ray imaging

T T Fusion Neutron Spectrum Measured in Inertial Confinement Fusion Experiment

X-ray optics for Laboratory Astrophysics

Improved target stability using picket pulses to increase and shape the ablator adiabat a

Polar-Direct-Drive Experiments on the National Ignition Facility

The 1-D Cryogenic Implosion Campaign on OMEGA

Laboratory experiments on the formation and recoil jet transport of aerosol by laser ablation

Ion Acceleration from the Interaction of Ultra-Intense Laser Pulse with a Thin Foil

Proton Radiography of a Laser-Driven Implosion

Molecular Pillars in the Sky and in the Lab

Progress in Direct-Drive Inertial Confinement Fusion Research at the Laboratory for Laser Energetics

New developments in the theory of ICF targets, and fast ignition with heavy ions

High-resolution measurements of the DT neutron spectrum using new CD foils in the Magnetic Recoil

Imploded Shell Parameter Estimation Based on Radiograph Analysis. George Liu. Pittsford Sutherland High School. LLE Advisor: Reuben Epstein

Advanced Ignition Experiments on OMEGA

An Overview of Laser-Driven Magnetized Liner Inertial Fusion on OMEGA

Laser Inertial Confinement Fusion Advanced Ignition Techniques

Two-Dimensional Simulations of Electron Shock Ignition at the Megajoule Scale

Design of Magnetized, Room-Temperature Capsule Implosions for NIF

Measuring the Refractive Index of a Laser-Plasma System

Downloaded 11 Oct 2012 to Redistribution subject to AIP license or copyright; see

The MIT Nuclear Products Generator for development of ICF diagnostics at Omega / Omega EP and the NIF

Improving hot-spot pressure for ignition in high-adiabat inertial confinement fusion implosion

Laser Inertial Fusion Energy

Measurements of the Deuterium-Tritium Branching Ratio Using ICF Implosions

NIF-scale hohlraum asymmetry studies using point-projection radiograph of thin shells

Capsule-areal-density asymmetries inferred from 14.7-MeV deuterium helium protons in direct-drive OMEGA implosions a

Critical Path to Impact Fast Ignition Suppression of the Rayleigh-Taylor Instability

Experimental Initiatives in Nuclear Astrophysics

Numerical simulation of supernova-relevant laser-driven hydro experiments on OMEGA

Deconstructing Integrated High Energy Density Physics Experiments into Fundamental Models for Validation

Status and Prospect of Laser Fusion Research at ILE Osaka University

Transcription:

Journal of Physics: Conference Series PAPER OPEN ACCESS Hydrodynamic instability measurements in DTlayered ICF capsules using the layered-hgr platform Related content - Mix and hydrodynamic instabilities on NIF V.A. Smalyuk, H.F. Robey, D.T. Casey et al. To cite this article: C Weber et al 2016 J. Phys.: Conf. Ser. 717 012057 View the article online for updates and enhancements. This content was downloaded from IP address 37.44.194.8 on 05/12/2017 at 10:35

Hydrodynamic instability measurements in DT-layered ICF capsules using the layered-hgr platform C Weber 1, T Döppner 1, D Casey 1, T Bunn 1, L Carlson 2, R Dylla-Spears 1, B Kozioziemski 1, A G MacPhee 1, J Sater 1, A Nikroo 1,2, H Robey 1 and V Smalyuk 1 1 Lawrence Livermore National Laboratory, Livermore, California, USA 2 General Atomics, San Diego, California, USA E-mail: weber30@llnl.gov Abstract. The first measurements of hydrodynamic instability growth at the fuel-ablator interface in an ICF implosion are reported. Previous instability measurements on the National Ignition Facility have used plastic capsules to measure ablation front Rayleigh-Taylor growth with the Hydro.-Growth Radiography (HGR) platform. These capsules substituted an additional thickness of plastic ablator material in place of the cryogenic layer of Deuterium- Tritium (DT) fuel. The present experiments are the first to include a DT ice layer, which enables measurements of the instability growth occurring at the fuel-ablator interface. Instability growth at the fuel-ablator interface is seeded differently in two independent NIF experiments. In the first case, a perturbation on the outside of the capsule feeds through and grows on the interface. Comparisons to an implosion without a fuel layer produce a measure of the fuel s modulation. In the second case, a modulation was directly machined on the inner ablator before the fuel layer was added. The measurement of growth in these two scenarios are compared to 2D rad-hydro modeling. 1. Introduction Understanding and mitigating the hydrodynamic instability growth that occurs during the implosion of an inertial confinement fusion (ICF) capsule is important for improving performance in experiments on the National Ignition Facility (NIF). This has been the focus of an experimental campaign using face-on radiography to measure the in-flight growth of pre-imposed perturbations[1, 2]. Thus far, good agreement between simulations and the observed growth has been found at several mode numbers and using several pulse shapes. These hydro-growth radiography (HGR) measurements were made on gas-filled plastic capsules (called symmetry capsules or symcaps ), where the thickness of the ablator is increased to compensate for the missing DT fuel mass. It is expected that ablation front growth is similar between a symcap and a capsule with a DT ice layer, but this has not been experimentally verified. Additionally, the fuel-ablator interface can be unstable and mix ablator material into the fuel. Recently the first experiments directly measuring instability growth in the presence of a DT ice layer have been conducted[3] and are reported here. Content from this work may be used under the terms of the Creative Commons Attribution 3.0 licence. Any further distribution of this work must maintain attribution to the author(s) and the title of the work, journal citation and DOI. Published under licence by IOP Publishing Ltd 1

Figure 1. (a) Experimental setup of the hydro.-growth radiography platform. (b) Layered capsules are used with perturbations either on the outer surface or on the fuel-ablator interface. A symcap was also used with identical perturbations on the outer surface. (c) Target image for the experiment with an interface perturbation viewed through the laser entrance hole during cryogenic layering. The capsule, the cone, and the ice layer can be seen. Below shows the same image unrolled into radius vs. angle. 2. Experimental Setup These experiments have perturbations on two separate surfaces. The first set of experiments uses perturbations on the outer surface of the ablator. This perturbation feeds through to the fuelablator interface and grows through the Rayleigh-Taylor and Richtmyer-Meshkov instabilities. The effect on the interface is identified by comparison to a separate experiment using a symcap with identical outer-surface perturbations. In the second experiment, a perturbation is machined directly on the inner ablator surface, between the DT ice and the CH plastic. The setup for these experiments is shown in Fig. 1(a). The capsule is placed on an Au cone, centering it within the Au hohlraum. Of NIF s 192 laser beams, 184 are directed into the hohlraum, with the remaining 8 laser beams pointed towards a scandium backlighter, creating 4.5 kev x-rays. The backlighter x-rays pass down the axis of the cone, through half the shell of the capsule as it is imploding, out a high-density carbon (HDC) window in the wall of the hohlraum, through a 12 µm wide slit, and finally are recorded by the gated x-ray detector (GXD). The GXD is timed to record images at four times as the capsule is imploding. These targets are similar to the ignition-scale design[4] used during the National Ignition Campaign (NIC), but scaled down by 0.8 in order to be hydrodynamically similar yet operate at reduced laser energy (and reduced laser damage). The laser pulse has 0.9 MJ of energy and a peak power of 230 TW. The capsule for the DT layered experiment is 909 µm in radius with a 153 µm thick CH ablator and a DT ice layer that is 55 µm thick in the field of view. The ablator contains graded silicon dopant of up to 2.5% to block high-energy x-ray preheat. The symcap contains 10 µm of additional CH to account for the absent DT mass. The target for the inner-surface perturbation experiment is shown in the Fig. 1(c). The ice layering process was precisely controlled so that the ice would be a uniform 55 µm thickness over ±90 and have minimal grooves within the field of view. The perturbation at the interface can be seen in the radiograph. This perturbation was imposed through a new technique using laser ablation[5]. After the hole for the Au cone was cut into the capsule, a UV laser was used to remove individual spots to create a sinusoidal mode 60 pattern. This technique also left higher-mode features the size of the laser spot (mode 500). Because of these higher mode 2

Figure 2. Outer-surface perturbation HGR experiments, comparing a layered capsule (solid) to a symcap (dashed). (a) Radiograph results converted to optical depth. The initial condition amplitude is shown at the bottom. (b) Single mode amplitudes vs. radius. Markers represent experimental data and lines represent simulations. features and the small amplitude growth expected at the interface, only a single wavelength was included on this experiment to simplify the analysis. While high modes ( 1000) are of the most interest at this interface because they reflect the in-flight Atwood number, those small scales are challenging to measure. Mode 60 was chosen because it is expected to grow to a measurable size and can be compared to the outer-surface experiment. The outer-surface perturbations for the comparison between the symcap and the layered capsule were made using a lathe technique, similar to past HGR experiments. Side-by-side perturbations of modes 60 and 90 and amplitude of 0.7 µm are used, chosen because modes near 60 are expected to grow the fastest. These perturbations are shown at the bottom of Fig. 2(a). The perturbation amplitudes for all experiments are chosen so that the radiograph has sufficient contrast (optical depth modulation of 0.1 during the measurement), requiring perturbations that are much larger than those that natively appear on NIF capsules. 3. Results The results from outer-surface perturbation experiments are shown in Fig. 2(a). The images from the GXD were processed to show optical depth and the spatial dimension was converted to angle around the capsule by aligning individual perturbations. A similar amplitude is observed between the symcap (dashed) and layered capsule (solid) at the earliest time, but later in time the symcap appears to grow larger. This effect is reproduced in post-shot modeling and occurs when the ablation front growth feeds through to the interface. In the simulations, both capsules have the same ablation front perturbation amplitude and the same ρr ( ρ dr) modulation, but the low opacity of the DT fuel to the x-ray backlighter compared to the CH results in less observed optical-depth ( κρ dr) modulation. The single mode amplitudes from these experiments are shown in Fig. 2(b) and compared with post-shot simulations using HYDRA[6]. Here the transfer function of the imaging system has been corrected for. Good agreement is found between the simulations and the data, with the simulation falling within the error bars of most data points. Both the experiments and the simulations show the optical depth modulation amplitude growing larger in the symcap than in the layered capsule. As mentioned previously, this is consistent with both the ablation front amplitude and the ρr amplitude being similar between the two capsules, but a lower optical 3

Figure 3. Inner-surface perturbation HGR experiment. (a) The initial condition is shown in black (not to scale) and the optical depth at four times is shown in blue. (b) Single mode amplitudes vs. radius. Simulations with and without the high-mode roughness are shown and images of the opacity (κρ) are inset. depth modulation due to feed-through of growth to the interface and the low DT opacity. Results from the experiment with a perturbation at the interface are shown in Fig. 3(a). The 2.2 µm amplitude mode 60 perturbation is shown at the bottom of this figure. The phase of the perturbation was expected to invert from the initial condition, but this cannot be constrained given the uncertainty in angle between the initial condition and the in-flight radiographs. In the data, moderate amplitude growth can be observed between the earliest and latest time. There are also variations in the modulations further from the center of the target (the spike at θ=10-15 appears larger than in the center). This is an effect also observed in simulations and appears to be due to the curvature of the capsule - rays going at an angle (rather than radially, as with θ=0 ) have a longer path length (and optical depth). The sinusoidal amplitude from the center three waves are shown in Fig. 3(b). Two post-shot calculations are also shown in this figure. When only mode 60 is included in the calculation and higher modes are filtered out, the simulation shows good agreement with the earlier time data but over-predicts the late-time growth. The high-mode structure, resulting from the laserablation process used to create the perturbation, is included in the multimode calculation. The growth in this case saturates later in time, with high modes coupling to lower modes. This case shows good agreement with all of the experimental data. This suggests that high-mode features may be influencing current measurements. Future experiments will seek to directly measure the growth of these small wavelengths. Acknowledgements This work was performed under the auspices of the U.S. Department of Energy by Lawrence Livermore National Laboratory under Contract No. DE-AC52-07NA27344. References [1] Raman K S et al. 2014 Phys. Plasmas 21 072710 [2] Smalyuk V A et al. 2014 Phys. Rev. Lett. 112 185003 [3] Weber C R et al. 2016 Phys. Rev. Lett. in review [4] Haan S W et al. 2011 Phys. Plasmas 18 051001 [5] Carlson L et al. 2015 Fusion Sci. Tech. 67 [6] Marinak M M et al. 2001 Phys. Plasmas 8 2275 4