Mitigation of Cross-Beam Energy Transfer in Direct-Drive Implosions on OMEGA
|
|
- Linette Stephens
- 5 years ago
- Views:
Transcription
1 Mitigation of Cross-Beam Energy Transfer in Direct-Drive Implosions on OMEGA In-flight aspect ratio OMEGA cryogenic ignition hydro-equivalent design tr = 3 mg/cm 2, V imp = cm/s m = 48 ng a = R t (CH) Zooming (CH) m = 6 ng Hydro-equivalent a = 3.2 curve CBET No CBET Ablation pressure (Mbar) D. H. Froula Plasma and Ultrafast Physics Group Leader University of Rochester Laboratory for Laser Energetics Current stability threshold th Annual Meeting of the American Physical Society Division of Plasma Physics Denver, CO 11 November 13
2 Summary Reducing cross-beam energy transfer (CBET) on OMEGA will allow for more stable ignition-relevant implosions CBET can be mitigated by reducing the diameter of the laser beams Mitigating CBET increases the ablation pressure, allowing for thicker shelled targets and higher adiabats Two approaches are being investigated on OMEGA to reduce the laser beams smaller laser spots reduced beam-to-beam overlap two-state zooming increased single-beam imprint Experiments to validate these schemes are underway. E22428
3 Collaborators T. J. Kessler, I. V. Igumenshchev, V. N. Goncharov, H. Huang, S. X. Hu, E. Hill, J. H. Kelly, D. T. Michel, D. D. Meyerhofer, A. Shvydky, J. D. Zuegel, and R. Epstein University of Rochester Laboratory for Laser Energetics
4 CBET reduces the energy coupled to the fusion capsule CBET is spatially limited near M ~ 1 k 1 k 2 k a Energy is transferred between beams by ion-acoustic waves Target E19971d CBET reduces the most hydrodynamically efficient portion of the incident laser beams.
5 CBET modeling is required to match the experimental observables (scattered light, implosion velocity, and bang time)* 76 nm 122 ps 128 ps 133 ps 138 ps 182 ps 188 ps 193 ps 198 ps** 2 Simulations (Nonlocal + CBET models) Simulations (Nonlocal + CBET models) 2 4 Simulations (Nonlocal + CBET models) 2 P (TW) R (nm) 4 3 Data P (TW) V (km/s) 3 Data P (TW) t (ns) t (ns) t (ns) CBET reduces the ablation pressure by ~4%. E22473a * I. V. Igumenshchev et al., Phys. Plasmas 19, 6314 (12). ** D. T. Michel et al., Rev. Sci. Instrum. 83, E3 (12).
6 Experiments have demonstrated that CBET can be mitigated by reducing the radius of laser beams Scattered-light fraction.3 CBET model R beam /R target Absorption fraction OMEGA cryogenic hydro-equivalent design tr = 3 mg/cm 2, V imp = cm/s In-flight aspect ratio CBET m = 48 ng a = 1.7 Hydroequivalent curve.8 R t (CH) No CBET Ablation pressure (Mbar) Current stability threshold* m = 6 ng a = 3.2 Reducing the radius of the beams will allow the thickness of the shell and the adiabat to be increased in a hydro-equivalent design but the reduced overlap uniformity may increase the imprint. E14g *D. H. Froula et al., Phys. Rev. Lett. 8, 123 (12). *V. N. Goncharov, GI3.1, this conference (invited).
7 Simulations suggest that reducing the beam diameters by % (R b /R t =.8) will have minimal impact on the hotspot symmetry 2-D DRACO simulations (low-order nonuniformities only) 4 3 R b /R t = 1.7 YOC = R b /R t =.8 YOC = R b /R t =.7 YOC =.62 t (g/cm 3 ) t (g/cm 3 ) t (g/cm 3 ) z (nm) z (nm) z (nm) Reducing the beam diameters by more than % significantly degrades the target performance. TC9894 I. V. Igumenshchev et.al., Phys. Plasmas 19, 6314 (12).
8 Reducing the diameter of the laser beams beyond % after a sufficient conduction zone is generated ( zooming ) is predicted to maintain good low-mode uniformity rms deviation from round (v) R b /R t =.7 3 v - 17 nm 3 4 Power ( 12 W) Time (ns) R b /R t = 1. 3 v < 3 nm 3 4 t (g/cm 3 ) E21317l *I. V. Igumenshchev et al., Phys. Rev. Lett. 1, 141 (13).
9 Reducing the diameter of the laser beams beyond % after a sufficient conduction zone is generated ( zooming ) is predicted to maintain good low-mode uniformity rms deviation from round (v) R b /R t =.7 3 v - 17 nm 3 4 Power ( 12 W) R b /R t = 1. R b /R t = Time (ns) Zooming from R b /R t = 1. to.7 R b /R t = 1. 3 v < 3 nm 3 4 t (g/cm 3 ) v - 12 nm 1 E21317m 3 4 *I. V. Igumenshchev et al., Phys. Rev. Lett. 1, 141 (13).
10 Reducing the diameter of the laser beams beyond % after a sufficient conduction zone is generated ( zooming ) is predicted to maintain good low-mode uniformity rms deviation from round (v) R b /R t =.7 3 v - 17 nm 3 4 Power ( 12 W) R b /R t = 1. R b /R t = Time (ns) Zooming from R b /R t = 1. to.7 R b /R t = 1. 3 v < 3 nm 3 4 t (g/cm 3 ) v - 12 nm v - 3. nm E21317n *I. V. Igumenshchev et al., Phys. Rev. Lett. 1, 141 (13).
11 Reducing the diameter of the laser beams beyond % after a sufficient conduction zone is generated ( zooming ) is predicted to maintain good low-mode uniformity rms deviation from round (v) R b /R t =.7 3 v - 17 nm 3 4 Power ( 12 W) R b /R t = 1. R b /R t = Time (ns) Zooming from R b /R t = 1. to.7 R b /R t = 1. 3 v < 3 nm 3 4 t (g/cm 3 ) v - 12 nm v - 3. nm v < 1. nm E21317o *I. V. Igumenshchev et al., Phys. Rev. Lett. 1, 141 (13).
12 Zooming can be implemented on OMEGA using a radially varying phase plate and a dynamic near field Power ( 12 W) Time (ns) Dynamic near field Picket pulse Zooming phase plate (ZPP) Main pulse E239b D. H. Froula et al., Phys. Plasmas, 8274 (13).
13 Implementing zooming on OMEGA will provide a more-robust implosion to hydrodynamic instabilities In-flight aspect ratio OMEGA cryogenic ignition hydro-equivalent design tr = 3 mg/cm 2, V imp = cm/s Current stability threshold 14 m = 48 ng a = R t (CH) Zooming (CH) m = 6 ng Hydro-equivalent a = 3.2 curve CBET No CBET Ablation pressure (Mbar) In-flight aspect ratio Hydro-equivalence for current implosions Unstable Current threshold Adiabat tr/tr 1-D > <. Data Both CBET mitigation strategies on OMEGA will allow the mass of the shell and the adiabat to be increased while maintaining ignition-relevant conditions. E22229b T. C. Sangster et al., Phys. Plasmas, 6317 (13).
14 Summary/Conclusions Reducing cross-beam energy transfer (CBET) on OMEGA will allow for more stable ignition-relevant implosions CBET can be mitigated by reducing the diameter of the laser beams Mitigating CBET increases the ablation pressure, allowing for thicker shelled targets and higher adiabats Two approaches are being investigated on OMEGA to reduce the laser beams smaller laser spots reduced beam-to-beam overlap two-state zooming increased single-beam imprint Experiments to validate these schemes are underway. E22428
Polar Drive on OMEGA and the NIF
Polar Drive on OMEGA and the NIF OMEGA polar-drive geometry 21.4 Backlit x-ray image OMEGA polar-drive implosion 21.4 58.2 77.8 42. 58.8 CR ~ 5 R = 77 nm 4 nm 4 nm P. B. Radha University of Rochester Laboratory
More informationPolar-Drive Hot-Spot Ignition Design for the National Ignition Facility
Polar-Drive Hot-Spot Ignition Design for the National Ignition Facility At ignition, Gain=40 T. J. B. Collins University of Rochester Laboratory for Laser Energetics International Shock-Ignition Workshop
More informationAnalysis of Laser-Imprinting Reduction in Spherical-RT Experiments with Si-/Ge-Doped Plastic Targets
Analysis of Laser-Imprinting Reduction in Spherical-RT Experiments with Si-/Ge-Doped Plastic Targets v rms of tr (mg/cm )..6 Si [4.%] Si [7.4%] Ge [.9%] DRACO simulations..4 Time (ns) S. X. Hu University
More informationThe 1-D Cryogenic Implosion Campaign on OMEGA
The 1-D Cryogenic Implosion Campaign on OMEGA Yield Exp (#1 14 ) 1.4 1.2 1..8.6.4 1-D campaign neutron yields.2 R. Betti University of Rochester Laboratory for Laser Energetics.2.4.6.8 1. 1.2 LILAC 4 8.
More informationThe 1-D Campaign on OMEGA: A Systematic Approach to Find the Path to Ignition
The 1-D Campaign on OMEGA: A Systematic Approach to Find the Path to Ignition Normalized intensity 1..8.6.4.2 R. Betti University of Rochester Laboratory for Laser Energetics Core self-emission. 3 2 1
More informationFirst Results from Cryogenic-Target Implosions on OMEGA
First Results from Cryogenic-Target Implosions on OMEGA MIT 1 mm 1 mm 100 µm C. Stoeckl University of Rochester Laboratory for Laser Energetics 43rd Annual Meeting of the American Physical Society Division
More informationCross-Beam Energy Transport in Direct-Drive-Implosion Experiments
Cross-Beam Energy Transport in Direct-Drive-Implosion Experiments 35 3 Laser pulse Power (TW) 25 2 15 1 Modeled scattered light Measured 5 D. H. Edgell University of Rochester Laboratory for Laser Energetics.5
More informationTwo-Dimensional Simulations of Electron Shock Ignition at the Megajoule Scale
Two-Dimensional Simulations of Electron Shock Ignition at the Megajoule Scale Laser intensity ( 1 15 W/cm 2 ) 5 4 3 2 1 Laser spike is replaced with hot-electron spike 2 4 6 8 1 Gain 2 15 1 5 1. 1.2 1.4
More informationAn Investigation of Two-Plasmon Decay Localization in Spherical Implosion Experiments on OMEGA
An Investigation of Two-lasmon Decay Localization in Spherical Implosion Experiments on OMEGA 1 12 50 23 14 27 18 32 J. F. Myatt University of Rochester Laboratory for Laser Energetics 24 56th Annual Meeting
More informationModeling the Effects Mix at the Hot Spot Surface in 1-D Simulations of Cryogenic All-DT Ignition Capsule Implosions
Modeling the Effects Mix at the Hot Spot Surface in 1-D Simulations of Cryogenic All-DT Ignition Capsule Implosions 14 Time = 1.4 ns 25 Ion temperature (kev) 12 1 8 6 4 2 22.2 8.7 1.5 Gain =.45 2 15 1
More informationIon-Acoustic-Wave Instability from Laser-Driven Return Currents
Ion-Acoustic-Wave Instability from Laser-Driven Return Currents 3.0 3~ beam 2.5 4~ TS beam 60 100 100-nm TS volume Thomsonscattered light 5 0 5 Wavelength shift (Å) 0.5 0.0 D. H. Froula University of Rochester
More informationWhere are we with laser fusion?
Where are we with laser fusion? R. Betti Laboratory for Laser Energetics Fusion Science Center Dept. Mechanical Engineering and Physics & Astronomy University of Rochester HEDSA HEDP Summer School August
More informationThe Effect of Laser Spot Shapes on Polar-Direct-Drive Implosions on the National. Ignition Facility. 250 East River Road, Rochester, NY 14623
The Effect of Laser Spot Shapes on Polar-Direct-Drive Implosions on the National Ignition Facility F. Weilacher, 1,2 P. B. Radha, 1,* T. J. B. Collins, 1 and J. A. Marozas 1 1 Laboratory for Laser Energetics,
More informationPolar-Drive Implosions on OMEGA and the National Ignition Facility
Polar-Drive Implosions on OMEGA and the National Ignition Facility Introduction Polar drive (PD) 1 provides the capability to perform directdrive ignition experiments on laser facilities like the National
More informationHigh-Intensity Shock-Ignition Experiments in Planar Geometry
High-Intensity Shock-Ignition Experiments in Planar Geometry Low intensity High intensity 4 nm CH 3 nm Mo 138 nm quartz VISAR SOP Simulated peak pressure (Mbar) 1 5 Laser backscatter 17.5 kev Mo K a Hard
More informationAnalysis of a Direct-Drive Ignition Capsule Design for the National Ignition Facility
Analysis of a Direct-Drive Ignition Capsule Design for the National Ignition Facility R (mm) 1 8 6 4 End of acceleration phase r(g/cc) 7.5 3.5.5 Gain 4 3 2 1 1 2 2 s (mm) 5 25 25 5 Z (mm) P. W. McKenty
More informationA 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.
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. Gotchev Laboratory for Laser Energetics, U. of Rochester The control of
More informationThe Ignition Physics Campaign on NIF: Status and Progress
Journal of Physics: Conference Series PAPER OPEN ACCESS The Ignition Physics Campaign on NIF: Status and Progress To cite this article: M. J. Edwards and Ignition Team 216 J. Phys.: Conf. Ser. 688 1217
More informationMonochromatic 8.05-keV Flash Radiography of Imploded Cone-in-Shell Targets
Monochromatic 8.5-keV Flash Radiography of Imploded Cone-in-Shell Targets y position (nm) y position (nm) 2 3 4 5 2 3 4 66381 undriven 66393, 3.75 ns 66383, 3.82 ns Au Al 66391, 3.93 ns 66386, 4.5 ns 66389,
More informationDirect-Drive, High-Convergence-Ratio Implosion Studies on the OMEGA Laser System
Direct-Drive, High-Convergence-Ratio Implosion Studies on the OMEGA Laser System F. J. Marshall, J. A. Delettrez, R. Epstein, V. Yu. Glebov, D. D. Meyerhofer, R. D. Petrasso,P.B.Radha,V.A.Smalyuk,J.M.Soures,C.Stoekl,R.P.J.Town,
More informationProgress in Direct-Drive Inertial Confinement Fusion Research
Progress in Direct-Drive Inertial Confinement Fusion Research Ignition and Gain Total GtRH n (g/cm 2 ) 2 1.5.2.1 IAEA 21 DT, 22 kj IAEA 28 DT, 16 kj NIF.5 MJ NIF point design 1.5 MJ 1-D marginal ignition
More informationThree-Dimensional Studies of the Effect of Residual Kinetic Energy on Yield Degradation
Threeimensional Studies of the Effect of Residual Kinetic Energy on Yield Degradation Kinetic energy density for single-mode, = 1, m = 6 1. YOC model = (1 RKE) 4.4 1 3 to ( Jm / ) 5.797 1 15 1.44 1 1 z
More informationAdiabat Shaping of Direct-Drive OMEGA Capsules Using Ramped Pressure Profiles
Adiabat Shaping of Direct-Drive OMEGA Capsules Using Ramped Pressure Profiles a r Lagrangian coordinate K. Anderson University of Rochester Laboratory for Laser Energetics 44th Annual Meeting of the American
More informationAdvanced Ignition Experiments on OMEGA
Advanced Ignition Experiments on OMEGA C. Stoeckl University of Rochester Laboratory for Laser Energetics 5th Annual Meeting of the American Physical Society Division of Plasma Physics Dallas, TX 17 21
More informationFramed X-Ray Imaging of Cryogenic Target Implosion Cores on OMEGA
Framed X-Ray Imaging of Cryogenic Target Implosion Cores on OMEGA KBFRAMED optic assembly KBFRAMED core image OMEGA cryogenic DT target implosion shot 77064 F. J. Marshall University of Rochester Laboratory
More informationX-Ray Spectral Measurements of Cryogenic Capsules Imploded by OMEGA
X-Ray Spectral Measurements of Cryogenic Capsules Imploded by OMEGA 1 15 1 14 F. J. Marshall University of Rochester Laboratory for Laser Energetics kt =.65 kev 48386 (v ice = 1.5 nm) 2 48385 (v ice =
More informationMeasurement of Long-Scale-Length Plasma Density Profiles for Two-Plasmon Decay Studies
Measurement of Long-Scale-Length Plasma Density Profiles for Two-Plasmon Decay Studies Plasma density scale length at 10 21 cm 3 (nm) 350 300 250 200 150 100 0 Flat foil 2 4 6 8 10 100 Target diameter
More informationProgress Toward Demonstration of Ignition Hydro-equivalence on OMEGA
Progress Toward Demonstration of Ignition Hydro-equivalence on OMEGA Hot-spot pressure (Gbar) 12 1 8 6 4 2 1 1-D LILAC calculations Convergence ratio Inferred from measurements 12 14 16 18 2 3-D ASTER
More informationCapsule-areal-density asymmetries inferred from 14.7-MeV deuterium helium protons in direct-drive OMEGA implosions a
PHYSICS OF PLASMAS VOLUME 10, NUMBER 5 MAY 2003 Capsule-areal-density asymmetries inferred from 14.7-MeV deuterium helium protons in direct-drive OMEGA implosions a C. K. Li, b) F. H. Séguin, J. A. Frenje,
More informationProgress in Direct-Drive Inertial Confinement Fusion Research at the Laboratory for Laser Energetics
1 Progress in Direct-Drive Inertial Confinement Fusion Research at the Laboratory for Laser Energetics R.L. McCrory 1), D.D. Meyerhofer 1), S.J. Loucks 1), S. Skupsky 1) R.E. Bahr 1), R. Betti 1), T.R.
More informationMeasuring the Refractive Index of a Laser-Plasma System
Measuring the Refractive Index of a Laser-Plasma System 1 dh ( 10 4 ) 0 1 J (dh) R (dh) 3 2 1 0 1 2 3 D. Turnbull University of Rochester Laboratory for Laser Energetics Dm (Å) 58th Annual Meeting of the
More informationControlling Laser Beam Speckle with Optimized Illumination of Zooming Phase Plates. Adeeb Sheikh
Controlling Laser Beam Speckle with Optimized Illumination of Zooming Phase Plates Adeeb Sheikh Advisor: Dr. Reuben Epstein Laboratory for Laser Energetics, University of Rochester Rochester, New York
More informationHigh-Performance Inertial Confinement Fusion Target Implosions on OMEGA
High-Performance Inertial Confinement Fusion Target Implosions on OMEGA D.D. Meyerhofer 1), R.L. McCrory 1), R. Betti 1), T.R. Boehly 1), D.T. Casey, 2), T.J.B. Collins 1), R.S. Craxton 1), J.A. Delettrez
More informationPolar-drive implosions on OMEGA and the National Ignition Facility
Polar-drive implosions on OMEGA and the National Ignition Facility P. B. Radha, F. J. Marshall, J. A. Marozas, A. Shvydky, I. Gabalski et al. Citation: Phys. Plasmas 20, 056306 (2013); doi: 10.1063/1.4803083
More informationLaser Plasma Interactions in Direct-Drive Ignition Plasmas
Laser Plasma Interactions in Direct-Drive Ignition Plasmas Introduction Two approaches to inertial confinement fusion (ICF) 1 employ megajoule-class laser beams,3 to compress a fusion capsule to thermal
More informationAn Overview of Laser-Driven Magnetized Liner Inertial Fusion on OMEGA
An Overview of Laser-Driven Magnetized Liner Inertial Fusion on OMEGA 4 compression beams MIFEDS coils B z ~ 1 T Preheat beam from P9 1 mm Ring 3 Rings 4 Ring 3 Target support Fill-tube pressure transducer
More informationDirect-Drive Ignition Designs with Mid-Z Ablators
Direct-Drive Ignition Designs with Mid-Z Ablators Introduction In laser-driven inertial confinement fusion (ICF), 1, a spherical capsule filled with deuterium tritium (DT) is irradiated by direct laser
More informationExperiments on Dynamic Overpressure Stabilization of Ablative Richtmyer Meshkov Growth in ICF Targets on OMEGA
Experiments on Dynamic Overpressure Stabilization of Ablative Richtmyer Meshkov Growth in ICF Targets on OMEGA Contributors: V. N. Goncharov P. A. Jaanimagi J. P. Knauer D. D. Meyerhofer O. V. Gotchev
More informationScaling Hot-Electron Generation to High-Power, Kilojoule-Class Lasers
Scaling Hot-Electron Generation to High-Power, Kilojoule-Class Lasers 75 nm 75 75 5 nm 3 copper target Normalized K b /K a 1.2 1.0 0.8 0.6 0.4 Cold material 1 ps 10 ps 0.2 10 3 10 4 Heating 2.1 kj, 10
More informationDetermination of the Flux Limiter in CH Targets from Experiments on the OMEGA Laser
Determination of the Flux Limiter in CH Targets from Experiments on the OMEGA Laser f = 0.070 Neutron rate (1/s) Exp. f = 0.065 f = 0.060 J. A. Delettrez et al. University of Rochester Laboratory for Laser
More informationAn Overview of Laser-Driven Magnetized Liner Inertial Fusion on OMEGA
An Overview of Laser-Driven Magnetized Liner Inertial Fusion on OMEGA 4 compression beams MIFEDS coils B z ~ 1 T Preheat beam from P9 1 mm Ring 3 Rings 4 Ring 3 Target support Fill-tube pressure transducer
More informationImproved target stability using picket pulses to increase and shape the ablator adiabat a
PHYSICS OF PLASMAS 12, 056306 2005 Improved target stability using picket pulses to increase and shape the ablator adiabat a J. P. Knauer, b K. Anderson, R. Betti, T. J. B. Collins, V. N. Goncharov, P.
More informationStimulated Raman Scattering in Direct-Drive Inertial Confinement Fusion
Stimulated Raman Scattering in Direct-Drive Inertial Confinement Fusion View ports 5 FABS Experiments carried out at the National Ignition Facility FABS power (arbitrary units) Plasma-producing beams (
More informationAn Alternative Laser-Speckle-Smoothing Scheme for the NIF
An Alternative Laser-Speckle-Smoothing Scheme for the NIF 1.5-MJ CH-foam target; end of acceleration 1-D SSD, 1.8 Å 1-D MultiFM, 8 Å 2-D SSD, 11 Å 1-D SSD 1-D, multiple-fm SSD 2-D SSD Density (g cm 3 )
More informationNumerical Study of Large-Scale, Laser-Induced Nonuniformities in Cryogenic OMEGA Implosions
Numerical Sudy of Large-Scale, Laser-Induced Nonuniformiies in Cryogenic OMEGA Implosions 1 nm Offse = 2.56 ns 3-D ASTER simulaions of sho 78378 22 16 8 T i (kev) 3 2 1 4- o 8-keV x ray 17% Maximum Minimum
More informationOMEGA Laser-Driven Hydrodynamic Jet Experiments with Relevance to Astrophysics
OMEGA Laser-Driven Hydrodynamic Jet Experiments with Relevance to Astrophysics Astronomical jets Experimental jets Instabilities 1.4 light years Ambient shocks Jet/ambient material interface 2.8 mm Collimated
More informationShock-Ignition Experiments on OMEGA at NIF-Relevant Intensities
Shock-Ignition Experiments on OMEGA at NIF-Relevant Intensities Shock ignition is a two-step inertial confinement fusion (ICF) concept in which a strong shock wave is launched at the end of the laser pulse
More informationCrossed-Beam Energy Transfer in Inertial Confinement Fusion Implosions on OMEGA
Crossed-Beam Energy Transfer in Inertial Confinement Fusion Implosions on OMEGA Inertial confinement fusion (ICF) uses the energy of multiple laser beams to implode a millimeter-scale capsule containing
More informationMultiple-FM Smoothing by Spectral Dispersion An Augmented Laser Speckle Smoothing Scheme
Multiple-FM Smoothing by Spectral Dispersion An Augmented Laser Speckle Smoothing Scheme Introduction Polar-drive (PD) 1 4 implosions on the National Ignition Facility (NIF) require smoothing of the laser-imposed
More informationICF ignition and the Lawson criterion
ICF ignition and the Lawson criterion Riccardo Betti Fusion Science Center Laboratory for Laser Energetics, University of Rochester Seminar Massachusetts Institute of Technology, January 0, 010, Cambridge
More informationMonochromatic Backlighting of Direct-Drive Cryogenic DT Implosions on OMEGA
Monochromatic Backlighting of Direct-Drive Cryogenic DT Implosions on OMEGA Introduction Layered cryogenic DT targets are the baseline approach to achieving ignition in direct-drive inertial confinement
More informationThe National Direct-Drive Program
The National Direct-Drive Program Ignition hydro-equivalence on OMEGA 1.8 MJ 26 kj Verify laser plasma interaction scaling at the National Ignition Facility T. C. Sangster University of Rochester Laboratory
More informationExploration of the Feasibility of Polar Drive on the LMJ. Lindsay M. Mitchel. Spencerport High School. Spencerport, New York
Exploration of the Feasibility of Polar Drive on the LMJ Lindsay M. Mitchel Spencerport High School Spencerport, New York Advisor: Dr. R. S. Craxton Laboratory for Laser Energetics University of Rochester
More informationAreal-Density-Growth Measurements with Proton Spectroscopy on OMEGA
Areal-Density-Growth Measurements with Proton Spectroscopy on OMEGA Areal density (mg/cm ) 5 15 1 5 4 atm D 3 He 1.6 1... 1 1 1 1 19 1 1 Neutron rate (s 1 ) V. A. Smalyuk Laboratory for Laser Energetics
More informationPolar-Direct-Drive Experiments on the National Ignition Facility
Polar-Direct-Drive Experiments on the National Ignition Facility M. Hohenberger, 1 P. B. Radha, 1 J. F. Myatt, 1 S. LePape, 2 J. A. Marozas, 1 F. J. Marshall, 1 D. T. Michel, 1 S. P. Regan, 1 W. Seka,
More informationNational direct-drive program on OMEGA and the National Ignition Facility
Plasma Physics and Controlled Fusion PAPER National direct-drive program on OMEGA and the National Ignition Facility To cite this article: V N Goncharov et al Plasma Phys. Control. Fusion 00 Manuscript
More informationMultibeam Laser Plasma Interactions in Inertial Confinement Fusion
Multibeam Laser Plasma Interactions in Inertial Confinement Fusion Polar drive X-ray drive 1 n e /n c n e /n c 1 mm.25. n e /n c 3.5 mm J. F. Myatt University of Rochester Laboratory for Laser Energetics
More informationObservations of the collapse of asymmetrically driven convergent shocks. 26 June 2009
PSFC/JA-8-8 Observations of the collapse of asymmetrically driven convergent shocks J. R. Rygg, J. A. Frenje, C. K. Li, F. H. Seguin, R. D. Petrasso, F.J. Marshalli, J. A. Delettrez, J.P. Knauer, D.D.
More informationTwo-Plasmon-Decay Hot Electron Generation and Reheating in OMEGA Direct-Drive-Implosion Experiments
Two-Plasmon-Decay Hot Electron Generation and Reheating in OMEGA Direct-Drive-Implosion Experiments r 1/4 ~500 nm Ne To sheath e Laser r e To core 20 nm J. F. Myatt University of Rochester Laboratory for
More informationTwo-Plasmon Decay Driven by Multiple Incoherent Laser Beams
Two-Plasmon Decay Driven by Multiple Incoherent Laser Beams 2 # # E^xyt,, h dy dy^arbitrary h n Two coherent e /n c plane waves Dm = 8.8 Å Dm = 17.6 Å.19.21.23.25.27.19.21.23.25.27.19.21.23.25.27 2 Arbitrary
More informationTime-Resolved Compression of a Spherical Shell with a Re-Entrant Cone to High Areal Density. for Fast-Ignition Laser Fusion
Time-Resolved Compression of a Spherical Shell with a Re-Entrant Cone to High Areal Density for Fast-Ignition Laser Fusion The compression of matter to a very high density is of general interest for high-energy-density
More informationT T Fusion Neutron Spectrum Measured in Inertial Confinement Fusion Experiment
T T Fusion Neutron Spectrum Measured in Inertial Confinement Fusion Experiment V. Yu. Glebov University of Rochester Laboratory for Laser Energetics 48th Annual Meeting of the American Physical Society
More informationInitial Experiments on the Shock-Ignition Inertial Confinement Fusion Concept
Initial Experiments on the Shock-Ignition Inertial Confinement Fusion Concept Introduction Shock ignition is a concept for direct-drive laser inertial confinement fusion (ICF) 1 3 that was recently proposed
More informationInertial Confinement Fusion DR KATE LANCASTER YORK PLASMA INSTITUTE
Inertial Confinement Fusion DR KATE LANCASTER YORK PLASMA INSTITUTE In the beginning In the late fifties, alternative applications of nuclear explosions were being considered the number one suggestion
More informationPhysics of Laser-Plasma Interaction and Shock Ignition of Fusion Reactions
Modelisation and Numerical Methods for Hot Plasmas Talence, October 14, 2015 Physics of Laser-Plasma Interaction and Shock Ignition of Fusion Reactions V. T. Tikhonchuk, A. Colaïtis, A. Vallet, E. Llor
More informationCharged-Particle Spectra Using Particle Tracking on a Two-Dimensional Grid. P. B. Radha, J. A. Delettrez, R. Epstein, S. Skupsky, and J. M.
Charged-Particle Spectra Using Particle Tracking on a Two-Dimensional Grid P. B. Radha, J. A. Delettrez, R. Epstein, S. Skupsky, and J. M. Soures Laboratory for Laser Energetics, U. of Rochester S. Cremer
More informationFukuoka, Japan. 23 August National Ignition Facility (NIF) Laboratory for Laser Energetics (OPERA)
Fukuoka, Japan 23 August 2012 National Ignition Facility (NIF) LLNL-PRES-562760 This work was performed under the auspices of the U.S. Department of Energy by Lawrence Livermore National Laboratory under
More informationProton Temporal Diagnostic for ICF Experiments on OMEGA
Proton Temporal Diagnostic for ICF Experiments on OMEGA Introduction In an inertial confinement fusion (ICF) 1 experiment, a capsule filled with deuterium (D 2 ) or a deuterium tritium (DT) fuel is heated
More informationHydrodynamic instability measurements in DTlayered ICF capsules using the layered-hgr platform
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
More informationPolar-Direct-Drive Experiments with Contoured-Shell Targets on OMEGA
Polar-Direct-Drive Experiments with Contoured-Shell Targets on OMEGA F. J. Marshall, P. B. Radha, M. J. Bonino, J. A. Delettrez, R. Epstein, V. Yu. Glebov, D. R. Harding, and C. Stoeckl Laboratory for
More informationD 3 He proton spectra for diagnosing shell R and fuel T i of imploded capsules at OMEGA
PHYSICS OF PLASMAS VOLUME 7, NUMBER 6 JUNE 2000 D 3 He proton spectra for diagnosing shell R and fuel T i of imploded capsules at OMEGA C. K. Li, D. G. Hicks, F. H. Séguin, J. A. Frenje, and R. D. Petrasso
More informationCollimation of a Positron Beam Using an Externally Applied Axially Symmetric Magnetic Field FSC
Collimation of a Positron Beam Using an Externally Applied Axially Symmetric Magnetic Field Numbers (MeV/Sr) 1 12 1 11 1 1 1 9 Electrons Positrons Reference shot (no B fields) 1 15 Shot with B fields by
More informationHiPER target studies on shock ignition: design principles, modelling, scaling, risk reduction options
HiPER target studies on shock ignition: design principles, modelling, scaling, risk reduction options S. Atzeni, A. Marocchino, A. Schiavi, Dip. SBAI, Università di Roma La Sapienza and CNISM, Italy X.
More informationDirect-Drive Cryogenic Target Implosion Performance on OMEGA
Direct-Drive Cryogenic Target Implosion Performance on OMEGA Introduction Direct-drive, cryogenic inertial confinement fusion (ICF) capsule implosion experiments under investigation using the 3-kJ OMEGA
More informationLaser Inertial Confinement Fusion Advanced Ignition Techniques
Laser Inertial Confinement Fusion Advanced Ignition Techniques R. Fedosejevs Department of Electrical and Computer Engineering University of Alberta Presented at the Canadian Workshop on Fusion Energy
More informationLaser Inertial Fusion Energy
Laser Inertial Fusion Energy presentation before the HEDLP committee at the WORKSHOP ON SCIENTIFIC OPPORTUNITIES IN HIGH ENERGY DENSITY PLASMA PHYSICS 25 August 2006 Washington DC presented by A. J. Schmitt,
More informationUpdate on MJ Laser Target Physics
Update on MJ Laser Target Physics P.A.Holstein, J.Giorla, M.Casanova, F.Chaland, C.Cherfils, E. Dattolo, D.Galmiche, S.Laffite, E.Lefebvre, P.Loiseau, M.C. Monteil, F.Poggi, G.Riazuelo, Y.Saillard CEA
More informationA Tunable (1100-nm to 1500-nm) 50-mJ Laser Enables a Pump-Depleting Plasma-Wave Amplifier
A Tunable (1100-nm to 1500-nm) 50-mJ Laser Enables a Pump-Depleting Plasma-Wave Amplifier Focused intensity (W/cm 2 ) 10 30 10 25 10 20 10 15 10 10 Nonlinear quantum electrodynamics (QED) Ultrarelativistic
More informationHigh-Resolving-Power, Ultrafast Streaked X-Ray Spectroscopy on OMEGA EP
High-Resolving-Power, Ultrafast Streaked X-Ray Spectroscopy on OMEGA EP Channel 1 Crystal chamber X-ray streak camera Chamber wall Re-entrant tube with collimators Normalized signal 0.8 0.6 0.4 0.2 Pulse
More informationBulk Fluid Velocity Construction from NIF Neutron Spectral Diagnostics
Bulk Fluid elocity Construction from NIF Neutron Spectral Diagnostics ntof-4.5 DT-Lo (64-309) ntof-3.9 DSF (64-275) ntof-4.5 BT (64-253) MRS ntof-4.5 DT-Hi (64-330) Spec E (90-174) Spec A (116-316) Spec
More informationDirect Observation of the Two-Plasmon-Decay Common Plasma Wave Using Ultraviolet Thomson Scattering
Direct Observation of the Two-Plasmon Decay Common Plasma Wave Using Ultraviolet Thomson Scattering The self-organization of nonlinearly interacting dynamic systems into coherent synchronized states has
More informationIntegrated Modeling of Fast Ignition Experiments
Integrated Modeling of Fast Ignition Experiments Presented to: 9th International Fast Ignition Workshop Cambridge, MA November 3-5, 2006 R. P. J. Town AX-Division Lawrence Livermore National Laboratory
More informationFPEOS: A First-Principles Equation of State Table of Deuterium for Inertial Confinement Fusion Applications
FPEOS: A First-Principles Equation of State Table of Deuterium for Inertial Confinement Fusion Applications S. X. Hu 1,, B. Militzer 2, V. N. Goncharov 1, S. Skupsky 1 1. Laboratory for Laser Energetics,
More informationHigh-density implosion via suppression of Rayleigh Taylor instability
Journal of Physics: Conference Series PAPER OPEN ACCESS High-density implosion via suppression of Rayleigh Taylor instability Recent citations - Experimental study of shock-accelerated inclined heavy gas
More informationMultibeam Stimulated Brillouin Scattering from Hot Solid-Target Plasmas
Multibeam Stimulated Brillouin Scattering from Hot Solid-Target Plasmas Introduction We report on the first multibeam laser plasma interaction experiments with a critical density surface present at all
More informationA Multi-Dimensional View of the US Inertial Confinement Fusion Program
Photos placed in horizontal position with even amount of white space between photos and header To replace these boxes with images open the slide master A Multi-Dimensional View of the US Inertial Confinement
More informationDensity Functional Theory Methods for Transport and Optical Properties: Application to Warm Dense Silicon
Density Functional Theory Methods for Transport and Optical Properties: Application to Warm Dense Silicon 2200 Si, T = 62.5 kk K-edge position (ev) 2100 2000 1900 DFT (shifted by 50 ev) AOT Significant
More informationDual Nuclear Shock Burn:
Dual Nuclear Shock Burn: Experiment, Simulation, and the Guderley Model J.R. Rygg, J.A. Frenje, C.K. Li, F.H. Séguin, and R.D. Petrasso MIT PSFC J.A. Delettrez, V.Yu Glebov, D.D. Meyerhofer, and T.C. Sangster
More informationFirst-Principles Thermal Conductivity of Deuterium for Inertial Confinement Fusion Applications
First-Principles Thermal Conductivity of Deuterium for Inertial Confinement Fusion Applications Introduction As a grand challenge to harvest the ultimate energy source in a controlled fashion, inertial
More informationDirect-drive fuel-assembly experiments with gas-filled, cone-in-shell, fast-ignitor targets on the OMEGA Laser
INSTITUTE OF PHYSICS PUBLISHING Plasma Phys. Control. Fusion 47 (25) B859 B867 PLASMA PHYSICS AND CONTROLLED FUSION doi:1.188/741-3335/47/12b/s68 Direct-drive fuel-assembly experiments with gas-filled,
More informationRelativistic Electron Beams, Forward Thomson Scattering, and Raman Scattering. A. Simon. Laboratory for Laser Energetics, U.
Relativistic Electron Beams, Forward Thomson Scattering, and Raman Scattering A. Simon Laboratory for Laser Energetics, U. of Rochester Experiments at LLE (see abstract by D. Hicks at this meeting) show
More informationTheory and simulations of hydrodynamic instabilities in inertial fusion
Theory and simulations of hydrodynamic instabilities in inertial fusion R. Betti Fusion Science Center, Laboratory for Laser Energetics, University of Rochester IPAM/UCLA Long Program PL2012 - March 12
More informationDiagnosing OMEGA and NIF Implosions Using the D 3 He Spectrum Line Width
Introduction Diagnosing OMEGA and NIF Implosions Using the D 3 He Spectrum Line Width A. B. Zylstra, M. Rosenberg, N. Sinenian, C. Li, F. Seguin, J. Frenje, R. Petrasso (MIT) R. Rygg, D. Hicks, S. Friedrich,
More informationMeasurements of fuel and shell areal densities of OMEGA capsule implosions using elastically scattered protons
PHYSICS OF PLASMAS VOLUME 9, NUMBER 11 NOVEMBER 2002 Measurements of fuel and shell areal densities of OMEGA capsule implosions using elastically scattered protons J. A. Frenje, C. K. Li, F. H. Séguin,
More informationHigh-Intensity Laser Interactions with Solid Targets and Implications for Fast-Ignition Experiments on OMEGA EP
n n High-Intensity Laser Interactions with Solid Targets and Implications for Fast-Ignition Experiments on OMEGA EP a n n n n J. Myatt University of Rochester Laboratory for Laser Energetics 48th Annual
More informationMIT Research using High-Energy Density Plasmas at OMEGA and the NIF
MIT Research using High-Energy Density Plasmas at OMEGA and the NIF 860 μm 2.3 μm SiO 2 D 3 He gas 1 10 11 D-D 3 He D-D T Yield D-D p D- 3 He 0 0 5 10 15 Energy (MeV) D- 3 He p Hans Rinderknecht Wednesday,
More informationThe National Ignition Campaign: Status and Progress
1 The National Ignition Campaign: Status and Progress E. I. Moses Lawrence Livermore National Laboratory, Livermore, CA 94450 Abstract. The National Ignition Facility (NIF) at Lawrence Livermore National
More informationLow density plasma experiments investigating laser propagation and proton acceleration
Low density plasma experiments investigating laser propagation and proton acceleration L Willingale, K Krushelnick, A Maksimchuk Center for Ultrafast Optical Science, University of Michigan, USA W Nazarov
More informationPolar Direct-Drive Simulations for a Laser-Driven HYLIFE-II Fusion Reactor. Katherine Manfred
Polar Direct-Drive Simulations for a Laser-Driven HYLIFE-II Fusion Reactor Katherine Manfred Polar Direct-Drive Simulations for a Laser-Driven HYLIFE-II Fusion Reactor Katherine M. Manfred Fairport High
More informationD- 3 He Protons as a Diagnostic for Target ρr
D- 3 He Protons as a Diagnostic for Target ρr Areal density (ρr) is an important parameter for measuring compression in ICF experiments. Several diagnostics employing nuclear particles have been considered
More information