The 1-D Cryogenic Implosion Campaign on OMEGA

Size: px
Start display at page:

Download "The 1-D Cryogenic Implosion Campaign on OMEGA"

Transcription

1 The 1-D Cryogenic Implosion Campaign on OMEGA Yield Exp (#1 14 ) D campaign neutron yields.2 R. Betti University of Rochester Laboratory for Laser Energetics LILAC 4 8. V MLILAC imp stag Tmin 45. # 113 d n d n 4. 1 d T n max (#1 14 ) 59th Annual Meeting of the American Physical Society Division of Plasma Physics Milwaukee, WI October 217 1

2 Summary High-adiabat (a. 6 to 7) implosions achieved the highest fusion yields of on OMEGA with high predictability using a statistical mapping model The ongoing 1-D campaign is building an experimental database of high-adiabat, low-convergence implosions (CR* ~ 12 to 14) The highest fusion yield of (tripled in the past year) is achieved by increasing the target outer diameter and reducing the DT ice thickness Based on these recent results, a roadmap is being developed to find the optimum target and laser pulse TC1374a * CR: convergence ratio 2

3 Collaborators V. Gopalaswamy, J. P. Knauer, A. R. Christopherson, D. Patel, K. M. Woo, A. Bose, K. S. Anderson, T. J. B. Collins, S. X. Hu, D. T. Michel, C. J. Forrest, R. Shah, P. B. Radha, V. N. Goncharov, V. Yu. Glebov, A. V. Maximov, C. Stoeckl, F. J. Marshall, M. J. Bonino, D. R. Harding, R. T. Janezic, J. H. Kelly, S. Sampat, T. C. Sangster, S. P. Regan, and E. M. Campbell University of Rochester Laboratory for Laser Energetics M. Gatu Johnson, J. Frenje, C. K. Li, and R. Petrasso Plasma Science and Fusion Center Massachusetts Institute of Technology 3

4 The 1-D Campaign Implosions 4

5 The 1-D Campaign developed a database of more-predictable, lower-convergence, high-adiabat implosions 43 nm OMEGA CD DT ice DT gas 8 nm 5 nm 372 nm Power (TW) a Time (ns) 7768 (a 3) 882 (a 7) Density (g/cm 3 ) a Time (ns) CR = 18 TC1396b 2 CR = Radius (nm) 5

6 Systematic hydro-stability, convergence, shock-timing, and preheat tests are conducted to assess degradation mechanisms and proximity to stability cliffs Shock-timing test SSD* on/off (RT** test) Power (TW) Time (ns) Time (ns) Convergence test Hot electrons on/off Power (TW) 2 1 CR = 12 CR = 16 Power (TW) TC1395b Time (ns) Time (ns) * SSD: smoothing by spectral dispersion ** RT: Rayleigh Taylor 6

7 To date, high-adiabat, low-convergence implosions achieved the highest fusion yields on OMEGA with areal densities up to ~65% of the highest compression shots Yield Exp (#1 14 ) High a > 5 Low a # 4 tr exp (mg/cm 2 ) High a > 5 Low a # Calculated CR (LILAC*) Calculated CR (LILAC) TC13677b * LILAC is the LLE 1-D hydrodynamics code 7

8 As expected, the main dependence of the yield is on the implosion velocity Yield Exp (#1 14 ) a # 4 a > 5 Yield Exp (#1 14 ) a # 4 a > Calculated V imp (km/s) Calculated IFAR 2/3 OMEGA implosions are testing the IFAR* limits. TC13678a * IFAR: in-flight aspect ratio 8

9 The Statistical Mapping Model as a Predictive Tool V. Gopalaswamy and R. Betti, CO8.1, this conference. 9

10 A reliable predictive capability is required to find the optimum implosion Conventional predictive capability is based on using simulations to design future experiments Despite advances in simulations, codes are still not predictive enough to enable quick progress in improving implosion performance Target specifications TC13679a Yield 43 nm CD DT ice DT gas 8 nm 5 nm 372 nm Power (TW) Implosion experiments a Time (ns) Good predictive capability tr Optimum implosion Limited predictive capability Laser pulse Implosion performance figure of merit Lawson parameter * Experimental ignition threshold factor (ITFx)** ITFx and scale with yield tr 2 # mass ^DTh * R. Betti et al., Phys. Plasmas 17, 5812 (21). ** B. K. Spears et al., Phys. Plasmas 19, (212). 1

11 By assuming that the 1-D codes do not accurately reproduce the 1-D implosion dynamics, we look for statistical correlations between experimental and simulated data 1-D physics models (LILAC) Laser pulse and target specifications are inputs to both the code and the experiment 43 nm OMEGA CD DT ice DT gas 8 nm 5 nm 372 nm Power (TW) a Time (ns) Implosion experiment: real physics Assuming 1-D implosions Code output: LILAC imp LILAC LILAC i LILAC LILAC LILAC Yield, V, tr,t, x,r Mapping Measurable parameters: Exp Exp imp Exp Exp i Exp Exp Yield, V, tr,t, x,r TC1368a Example: YieldExp = FV _ LILAC, tr LILAC, T LILAC, x LILAC i imp i New predictive capability (also valid for 3-D systematic nonuniformities) Instead of comparing each simulated parameter with its measured value, we map each measurement onto all simulated parameters through nonlinear correlations. 11

12 The combination of 1-D simulations and mapping relations provides a predictive capability as long as its validity can be extrapolated TC13681a Yield Exp (#1 14 ) Mapping onto 1-D simulated parameters 1-D campaign a ~ 6 to 7 Shots used to generate prediction LILAC Extrapolation LILAC 65. Vimp Mstag 43. # 113 d n d 4 1. Shots used to generate prediction Predicted shots Predictive capability: 1-D simulations + mapping relations n (#1 14 ) V M LILAC imp = stag LILAC = LILAC implosionvelocity LILAC stagnation mass 12

13 The higher yields were achieved through CD ablators, thinner ice, 4/6 DT mixture, modified pulse shapes, and larger diameter shells 43 nm OMEGA 5/5 DT CH DT ice DT gas 8 nm 53 nm Power (TW) nm OMEGA 4/6 DT CD DT ice DT gas 7.5 nm 42 nm 882 Y = 3.2 #1 13 tr = 126 mg/cm 2 T i = 2.6 kev Time (ns) Y = 1.2 to 1.4 #1 14 tr = 11 to 13 mg/cm 2 T i = 4.3 to 4.6 kev TC13687b 13

14 Systematic changes to the target specifications and laser pulse resulted in the expected increase in yield 1.1 Four shot days (Feb. to July 217) Yield (#1 14 ) Measured yield Prediction from mapping VLILAC MLILAC imp stag 43. # 113 d n d n 4 1. No change Power (TW) Time shift 1 2 Time (ns) D DT = constant No change Power (TW) D DT = 3 nm 2 1 Ramp change 1 2 Time (ns) D DT = constant No change OD = +4 nm D DT = constant Foot delay 1 2 Time (ns) D DT = 48 nm Outer diameter (OD) = 87 nm TC13688b D DT = 3 nm Sequential shot number D DT = 42 nm OD = 91 nm 14

15 In the last two shot days (ten shots), an ~2% yield variability is observed between repeats and also between the measured yield and prediction of mapping model 1.4 Without T i asymmetries T max /T min = With T i asymmetries TC1394 Yield Exp (#1 14 ) T max /T min = 1.2 OD = 98 nm repeats T max /T min = 1.23 T max /T min = 1.18 Sept. and Oct. 217 shots (not included in mapping) (#1 14 ) (#1 14 ) LILAC V MLILAC imp stag V MLILAC 43. # 113 imp stag d n T d n min 47. # 113 d n d n d T n Yield Exp (#1 14 ) LILAC Large temperature asymmetries suggest nonsystematic distortions possibly caused by the large DT ice rms (~1.5 nm) or target offsets max 15

16 What are the Results Telling Us? 16

17 Hydro stability SSD on/off tests show modest degradation in performance but no proximity to a stability cliff Yield (SSD off) Yield (SSD on) tr (SSD off) tr (SSD on) Yield (#1 13 SSD on) Yield (#1 13 SSD on) 15 < higher IFAR < < higher IFAR < 34 TC13685a 17

18 Including lower-adiabat implosions shows the yield increase from convergence is less than 1-D predictions while the areal density scales as 1-D 1-D theory 17. CR 1 b 13 l tr (MRS*) (mg/cm 2 ) Areal density CR 1 c 13 Exp 15. m Yield Exp (#1 14 ) Neutron yield: experiment versus LILAC param +CR Exp a # 4 a > (#1 14 ) LILAC 4 7. V MLILAC imp stag CRExp 4# 113 d n d n c m D theory CR 2 In experiments, a higher CR leads to a very modest increase in yield. TC13739a * MRS: magnetic recoil spectrometer 18

19 The shape of the hot-spot self-emission profile is used as a measure of proximity to 1-D behavior; the 1-D Campaign targets are more 1-D than high-cr targets y (nm) D DRACO simulations* : Y = : Y = 3.9 # 1 13 tr = 13 mg/cm 2 tr = 225 mg/cm 2 GMXI** GMXI** TC1394a Normalized intensity x (nm) x (nm) 1. Core self-emission lineouts Radius (nm) 2 Arbitrary untis SGfit exp = GMXI lineouts SGfit exp = 2.1 Radius (nm) 2 4 * R. Nora, Laboratory for Laser Energetics, private communication (214). ** F. J. Marshall and J. A. Oertel, Rev. Sci. Instrum. 68, 735 (1997). GMXI: gated monochromatic x-ray imager 19

20 OMEGA Roadmap and Extrapolation to NIF* Laser Energies * NIF: National Ignition Facility 2

21 A systematic approach is being used to find the optimum implosion on OMEGA Hydro-stability or laser-energy boundary Larger yield by increasing OD, better coupling, larger V imp, larger IFAR Velocity campaign Increase DT thickness Optimum implosion Tuning campaign increase tr October 3 shots: as predicted Y = 1.4 # 1 14, tr = 11 to 13 mg/cm 2 April 4 shots: as predicted Y = 7.8 # 1 13, tr = 11 mg/cm 2 TC13691a Ice thickness 21

22 OMEGA highest-yield shots extrapolate to fusion yields L23 kj at 1.9 MJ of symmetric illumination Density (g/cm 3 ) 1-D profiles from OMEGA/NIF-symmetric used in the extrapolation TC R/R() Pressure (Gbar) t (OMEGA) t (NIF) P (OMEGA) P (NIF) Shot 8726 OMEGA 28 kj.86 mm T i (kev) Hydrodynamic scaling R 17 (nm) x (ps) GPH (Gbar) Direct drive NIF 1.9 MJ 3.6 mm Yield Experiment Simulation (degraded** in 2-D to YOC =.75) 1.9-MJ extrapolation Hydro-equivalent extrapolation* V imp = const, a = const, mass ~ volume ~ E L no a kj * R. Nora et al., Phys. Plasmas 21, (214). ** A. Bose et al., Phys. Plasmas 24, 1274 (217). YOC: yield-over-clean 22

23 Summary/Conclusions High-adiabat (a. 6 to 7) implosions achieved the highest fusion yields of on OMEGA with high predictability using a statistical mapping model The ongoing 1-D campaign is building an experimental database of high-adiabat, low-convergence implosions (CR* ~ 12 to 14) By mapping the experimental results onto the simulation database, an accurate predictive tool is developed that enables the design of targets with improved performance The highest fusion yield of is achieved by increasing the target outer diameter and reducing the DT ice thickness Based on these recent results, a roadmap is being developed to find the optimum target and laser pulse Hydro-equivalent extrapolation to 1.9 MJ symmetric illumination shows fusion yields $23 kj for best performing implosions TC1374b * CR: convergence ratio 23

24 Backup 24

25 The time history of the hot-spot radius R 17% monitors deviations from 1-D behavior 6 5 Low modes (, ~2) increase the hot-spot size Intermediate modes (, ~1) decrease the size 1-D bang time, = 2 R 17% (nm) Clean, = 2, YOC = 6%, = 1, YOC = 6% Clean, = Time (ps) The time history of the hot-spot radius reveals which modes are dominant. TC1393 * A. Bose, R. Betti, and D. Shvarts, JO7.7, this conference. 25

26 The hydrodynamic scaling holds in three dimensions In-flight scaling: R+ E 13 / P + E 23 / x + E / L L L pulse V imp + const a + const RT growth factors+ const 13 L Stagnation scaling: P + const T + R 2. V + R x burn + R tr tot + R hs 3 z (nm) YOC NIF = 6% YOC X = 61% 3 NIF 2 1 OMEGA t (g/cm 2 ) Yield Y Y no a no a a no a + +. E E 145. L 35. L 1 ^ no a h TC1975e r (nm) r (nm) A. Bose et al., Phys. Plasmas 22, 7272 (215); R. Nora et al., Phys. Plasmas 21, (214). 26

27 The hydro-equivalent extrapolation uses the results of 1-D simulations combined with 2-D degradation to match the experimental observables P n /P n 1-D , = 1, = 2 T n /T n 1-D V GhsH /V GhsH 1-D Y/Y 1-D.8 1. x/x 1-D Y/Y 1-D TC1325 * A. Bose, Ph.D. thesis, University of Rochester, 217; A. Bose et al., Phys. Plasmas 24, 1274 (217). 27

28 The yield predictive capability of the mapping relations applies over a wide range of extrapolations 1. Yield Exp (#1 14 ) Shots used to generate prediction Predicted shots (#1 14 ) LILAC 43. V MLILAC imp stag 43. # 113 e o e o TC13682a 28

29 The yield s unique dependence on 1-D simulated parameters persists in 3-D as long as the 3-D dynamics are affected by dominant systematic nonuniformities Y exp = Y 1-D (1-D parameters) YOC (distortion) A = initial nonuniformities (target and/or laser) f (1-D) = amplifications of distortion caused by implosion (RT, RM*, BP**) systematic YOC= YOC A f 1D Arandom 8u ^ - h+ u f ^1-DhB s If systematic nonuniformities are dominant: Au r Au systematic random & systematic Y = Y ^1-DparametershYOC 8Au f ^1- D parametershb exp 1-D If Au systematic = constant, the yield depends only on 1-D parameters even in distorted implosions s Y exp = Y 1-D (1-D parameters) For 1-D implosions or 3-D with dominant systematic nonuniformities TC13683a *RM: Richtmyer Meshkov ** BP: Bell Plesset 29

30 A convergence test on the thin 42-nm ice targets did not show proximity to stability cliffs for low and mid modes TC13686a 43 nm 8566 CR = 12 CD DT ice Power (TW) DT gas nm 42 nm 8566 CD E L = 27.7 kj V LILAC imp = 45 km/s Time (ns) 43 nm 8529 CH E L = 26.4 kj VLILAC imp = 397 km/s CR = CH DT ice DT gas 7.5 nm 42 nm Higher-CR targets performed better than low-cr targets at the same predicted velocity. Yield Exp (#1 14 ) Shot 8529 CR = 16 tr = LILAC 42. Vimp Mstag 43. # 113 e o e 4 1. LILAC Shot 8566 CR = 12 tr = 113 o (#1 13 ) 65. 3

31 Simulated trajectories compare favorably with experimental measurements 5 Shot Shot Shot R (nm) P (#1 2 TW) t (ps) t (ps) t (ps) TC13725a 31

The 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 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 information

Polar Drive on OMEGA and the NIF

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 information

First Results from Cryogenic-Target Implosions on OMEGA

First 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 information

Three-Dimensional Studies of the Effect of Residual Kinetic Energy on Yield Degradation

Three-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 information

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

Mitigation of Cross-Beam Energy Transfer in Direct-Drive Implosions on OMEGA 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 = 3.7 7 cm/s 3 3 2 14 m = 48 ng

More information

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

Direct-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 information

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

Two-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 information

High-Performance Inertial Confinement Fusion Target Implosions on OMEGA

High-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 information

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

Polar-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 information

Modeling 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 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 information

Framed X-Ray Imaging of Cryogenic Target Implosion Cores on OMEGA

Framed 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 information

Progress in Direct-Drive Inertial Confinement Fusion Research

Progress 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 information

Analysis 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 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 information

Advanced Ignition Experiments on OMEGA

Advanced 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 information

Analysis 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 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 information

Progress Toward Demonstration of Ignition Hydro-equivalence on OMEGA

Progress 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 information

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

Monochromatic 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 information

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

Progress 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 information

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

Observations 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 information

Where are we with laser fusion?

Where 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 information

Areal-Density-Growth Measurements with Proton Spectroscopy on OMEGA

Areal-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 information

Determination 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 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 information

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

Adiabat 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 information

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

Capsule-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 information

Monochromatic Backlighting of Direct-Drive Cryogenic DT Implosions on OMEGA

Monochromatic 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 information

X-Ray Spectral Measurements of Cryogenic Capsules Imploded by OMEGA

X-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 information

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

An 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 information

Bulk Fluid Velocity Construction from NIF Neutron Spectral Diagnostics

Bulk 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 information

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

Improved 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 information

ICF ignition and the Lawson criterion

ICF 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 information

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

Diagnosing 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 information

An Investigation of Two-Plasmon Decay Localization in Spherical Implosion Experiments on OMEGA

An 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 information

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

The MIT Accelerator for development of ICF diagnostics at OMEGA / OMEGA-EP and the NIF Introduction The MIT Accelerator for development of ICF diagnostics at OMEGA / OMEGA-EP and the NIF SBDs d + or 3 He +(2+) D or 3 He target Present MIT Graduate Students and the MIT Accelerator OLUG 21

More information

Initial Experiments on the Shock-Ignition Inertial Confinement Fusion Concept

Initial 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 information

Polar-Drive Implosions on OMEGA and the National Ignition Facility

Polar-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 information

Measurements of fuel and shell areal densities of OMEGA capsule implosions using elastically scattered protons

Measurements 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 information

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

An 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 information

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.

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. 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 information

National direct-drive program on OMEGA and the National Ignition Facility

National 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 information

D 3 He proton spectra for diagnosing shell R and fuel T i of imploded capsules at OMEGA

D 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 information

The Ignition Physics Campaign on NIF: Status and Progress

The 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 information

The 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. 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 information

Shock-Ignition Experiments on OMEGA at NIF-Relevant Intensities

Shock-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 information

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

Fukuoka, 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 information

Direct-Drive Ignition Designs with Mid-Z Ablators

Direct-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 information

Experiments 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 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 information

Charged-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. 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 information

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

The Magnetic Recoil Spectrometer (MRSt) for time-resolved measurements of the neutron spectrum at the National Ignition Facility (NIF) PSFC/JA-16-32 The Magnetic Recoil Spectrometer (MRSt) for time-resolved measurements of the neutron spectrum at the National Ignition Facility (NIF) J.A. Frenje 1 T.J. Hilsabeck 2, C. Wink1, P. Bell 3,

More information

Direct-Drive Cryogenic Target Implosion Performance on OMEGA

Direct-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 information

Inertial Confinement Fusion DR KATE LANCASTER YORK PLASMA INSTITUTE

Inertial 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 information

Dual Nuclear Shock Burn:

Dual 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 information

Stimulated Raman Scattering in Direct-Drive Inertial Confinement Fusion

Stimulated 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 information

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

Physics 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 information

The National Direct-Drive Program

The 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 information

High-Intensity Shock-Ignition Experiments in Planar Geometry

High-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 information

Cross-Beam Energy Transport in Direct-Drive-Implosion Experiments

Cross-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 information

Proton Temporal Diagnostic for ICF Experiments on OMEGA

Proton 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 information

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

Direct-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 information

Polar-drive implosions on OMEGA and the National Ignition Facility

Polar-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 information

T T Fusion Neutron Spectrum Measured in Inertial Confinement Fusion Experiment

T 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 information

Update on MJ Laser Target Physics

Update 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 information

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

Hydrodynamic growth experiments with the 3-D, native-roughness modulations on NIF Journal of Physics: Conference Series PAPER OPEN ACCESS Hydrodynamic growth experiments with the 3-D, native-roughness modulations on NIF To cite this article: V A Smalyuk et al 2016 J. Phys.: Conf. Ser.

More information

What is. Inertial Confinement Fusion?

What is. Inertial Confinement Fusion? What is Inertial Confinement Fusion? Inertial Confinement Fusion: dense & short-lived plasma Fusing D and T requires temperature to overcome Coulomb repulsion density & confinement time to maximize number

More information

Laser Inertial Confinement Fusion Advanced Ignition Techniques

Laser 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 information

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

Experimental Demonstration of X-Ray Drive Enhancement with Rugby-Shaped Hohlraums Experimental Demonstration of X-Ray Drive Enhancement with Rugby-Shaped Hohlraums The MIT Faculty has made this article openly available. Please share how this access benefits you. Your story matters.

More information

Two-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 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 information

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

MIT 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 information

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

Monoenergetic proton backlighter for measuring E and B fields and for radiographing implosions and high-energy density plasmas invited REVIEW OF SCIENTIFIC INSTRUMENTS 77, 10E725 2006 Monoenergetic proton backlighter for measuring E and B fields and for radiographing implosions and high-energy density plasmas invited C. K. Li, a F. H.

More information

D- 3 He Protons as a Diagnostic for Target ρr

D- 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

Polar-Direct-Drive Experiments with Contoured-Shell Targets on OMEGA

Polar-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 information

X-ray driven implosions at ignition relevant velocities on the National Ignition Facilitya) Phys. Plasmas 20, (2013); /1.

X-ray driven implosions at ignition relevant velocities on the National Ignition Facilitya) Phys. Plasmas 20, (2013); /1. A Particle X-ray Temporal Diagnostic (PXTD) for studies of kinetic, multi-ion effects, and ion-electron equilibration rates in Inertial Confinement Fusion plasmas at OMEGA (invited) H. Sio, J. A. Frenje,

More information

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

Hydrodynamic 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 information

Exploration 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 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 information

A Multi-Dimensional View of the US Inertial Confinement Fusion Program

A 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 information

Inertial Confinement Fusion

Inertial Confinement Fusion Inertial Confinement Fusion Prof. Dr. Mathias Groth Aalto University School of Science, Department of Applied Physics Outline Principles of inertial confinement fusion Implosion/compression physics Direct

More information

Numerical Study of Large-Scale, Laser-Induced Nonuniformities in Cryogenic OMEGA Implosions

Numerical 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 information

Measurement 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 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 information

Multiple-FM Smoothing by Spectral Dispersion An Augmented Laser Speckle Smoothing Scheme

Multiple-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 information

An Alternative Laser-Speckle-Smoothing Scheme for the NIF

An 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 information

Time-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 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 information

Supporting Online Material for

Supporting Online Material for www.sciencemag.org/cgi/content/full/319/5867/1223/dc1 Supporting Online Material for Proton Radiography of Inertial Fusion Implosions J. R. Rygg, F. H. Séguin, C. K. Li, J. A. Frenje, M. J.-E. Manuel,

More information

The Pursuit of Indirect Drive Ignition at the National Ignition Facility

The Pursuit of Indirect Drive Ignition at the National Ignition Facility The Pursuit of Indirect Drive Ignition at the National Ignition Facility Workshop on Plasma Astrophysics: From the Laboratory to the Non-Thermal Universe Oxford, England July 3-5, 2017 Richard Town Deputy

More information

The National Ignition Campaign: Status and Progress

The 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 information

Polar-Direct-Drive Experiments on the National Ignition Facility

Polar-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 information

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

Progress in detailed modelling of low foot and high foot implosion experiments on the National Ignition Facility Journal of Physics: Conference Series PAPER OPEN ACCESS Progress in detailed modelling of low foot and high foot implosion experiments on the National Ignition Facility Related content - Capsule modeling

More information

Collimation 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 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 information

Three-dimensional hydrodynamic simulations of OMEGA implosions

Three-dimensional hydrodynamic simulations of OMEGA implosions Three-dimensional hydrodynamic simulations of OMEGA implosions I. V. Igumenshchev, D. T. Michel Laboratory for Laser Energetics, University of Rochester 250 East River Road, Rochester, NY 14623, USA R.

More information

First-Principles Thermal Conductivity of Deuterium for Inertial Confinement Fusion Applications

First-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 information

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

High Gain Direct Drive Target Designs and Supporting Experiments with KrF ) High Gain Direct Drive Target Designs and Supporting Experiments with KrF ) Max KARASIK, Yefim AGLITSKIY 1), Jason W. BATES, Denis G. COLOMBANT 4), David M. KEHNE, Wallace M. MANHEIMER 2), Nathan METZLER

More information

Measured dependence of nuclear burn region size on implosion parameters in inertial confinement fusion experiments

Measured dependence of nuclear burn region size on implosion parameters in inertial confinement fusion experiments PHYSICS OF PLASMAS 13, 082704 2006 Measured dependence of nuclear burn region size on implosion parameters in inertial confinement fusion experiments F. H. Séguin, a J. L. DeCiantis, J. A. Frenje, C. K.

More information

DIRECT DRIVE FUSION ENERGY SHOCK IGNITION DESIGNS FOR SUB-MJ LASERS

DIRECT DRIVE FUSION ENERGY SHOCK IGNITION DESIGNS FOR SUB-MJ LASERS DIRECT DRIVE FUSION ENERGY SHOCK IGNITION DESIGNS FOR SUB-MJ LASERS Andrew J. Schmitt, J. W. Bates, S. P. Obenschain, and S. T. Zalesak Plasma Physics Division, Naval Research Laboratory, Washington DC

More information

Direct-drive laser target designs for sub-megajoule energies

Direct-drive laser target designs for sub-megajoule energies Direct-drive laser target designs for sub-megajoule energies D.G. Colombant, A.J. Schmitt, S.P. Obenschain, S.T. Zalesak, A.L. Velikovich, and J.W. Bates Plasma Physics Division, Naval Research Laboratory,

More information

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

The effect of shock dynamics on compressibility of ignition-scale National Ignition Facility implosions The effect of shock dynamics on compressibility of ignition-scale National Ignition Facility implosions The MIT Faculty has made this article openly available. Please share how this access benefits you.

More information

Laser Inertial Fusion Energy

Laser 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 information

HiPER 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 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 information

Direct-Drive Implosion Experiments with Enhanced Beam Balance on OMEGA

Direct-Drive Implosion Experiments with Enhanced Beam Balance on OMEGA Direct-Drive Implosion Experiments with Enhanced Beam Balance on OMEGA Introduction Laser-driven, direct-drive inertial confinement fusion (ICF) is accomplished by near-uniform illumination of spherical

More information

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

High-resolution measurements of the DT neutron spectrum using new CD foils in the Magnetic Recoil PSFC/JA-16-15 High-resolution measurements of the DT neutron spectrum using new CD foils in the Magnetic Recoil neutron Spectrometer (MRS) on the National Ignition Facility M. Gatu Johnson, J.A. Frenje,

More information

Rayleigh Taylor Growth Measurements of 3-D Modulations

Rayleigh Taylor Growth Measurements of 3-D Modulations Rayleigh Taylor Growth Measurements of -D Modulations in a Nonlinear Regime Introduction Rayleigh Taylor (RT), instability is of critical importance in inertial confinement fusion (ICF) and astrophysics.

More information

Scaling Hot-Electron Generation to High-Power, Kilojoule-Class Lasers

Scaling 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 information

FPEOS: 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 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 information