High-density carbon ablator ignition path with low-density gas-filled rugby hohlraum

Size: px
Start display at page:

Download "High-density carbon ablator ignition path with low-density gas-filled rugby hohlraum"

Transcription

1 High-density carbon ablator ignition path with low-density gas-filled rugby hohlraum Peter Amendt, Darwin D. Ho and Ogden S. Jones Lawrence Livermore National Laboratory, Livermore CA A recent low gas-fill density (0.6 mg/cc 4 He) cylindrical hohlraum experiment on the National Ignition Facility has shown high laser-coupling efficiency (>96%), reduced phenomenological laser drive corrections, and improved high-density carbon capsule implosion symmetry [Jones et al., BAPS 59 (15), 66 (2014)]. In this Letter an ignition design using a large rugby-shaped hohlraum [Amendt et al., Phys. Plasmas (2014)] for high energetics efficiency and symmetry control with the same low gas-fill density (0.6 mg/cc 4 He) is developed as a potentially robust platform for demonstrating thermonuclear burn. The companion high-density carbon capsule for this hohlraum design is driven by an adiabat-shaped [Betti et al., Phys. Plasmas 9, 2277 (2002)] 4-shock drive profile for robust high gain (>10) 1-D ignition performance and large margin to 2-D perturbation growth. Efforts to demonstrate thermonuclear energy breakeven with indirect drive on the National Ignition Facility (NIF) continue in earnest [1]. Indirect drive uses a laser-heated hohlraum (or high-z enclosure) for generating soft x rays that irradiate and implode a centrally located capsule filled with deuterium (D) and tritium (T) fuel. The first ignition attempts used a 4- shock low-adiabat drive in cylinder hohlraums at moderate gas-fill density (ρ=0.96 mg/cc) and large outer-to-inner laser cone wavelength separation to control time-integrated x-ray drive symmetry, leading to good compression [2] but lower neutron yield than expected [3]. Significant fuel self-heating has been recently demonstrated for a higher adiabat 3-shock high-foot laser power drive history in cylinder hohlraums at higher gas-fill density (ρ=1.6 mg/cc) and still large outer-to-inner laser cone wavelength separation Δλ>5Å [4]. The high gas fill is used to constrain the inward motion of the ablating Au or U hohlraum wall plasma, which can lead to large x-ray drive symmetry swings in time. These symmetry variations result in residual (non-radial) kinetic energy at peak compression [5] and degraded implosion yield. A large wavelength separation (~8Å) is required to compensate for inhibited inner-cone laser propagation at late time and to achieve time-integrated 2 nd Legendre mode (P2) drive symmetry. The combination of high gas-fill density and large cross-beam energy transfer (CBET)[6] from the imposed large Δλ provides for a computationally challenging hohlraum environment, involving 3-D effects and significant plasma-induced laser backscatter (~40-50%) on the inner cones. An additional feature is the prevalence of 20-25% unaccounted drive energy according to high-flux model [7] comparisons with the database that collectively encompasses (1) shock-tuning experiments [8], (2) 1-D streaked radiography experiments for direct measurement of the capsule implosion trajectory [9], and (3) observed x-ray and neutron peak emission bang times [10]. The origin of this missing energy is not known, possibly involving mixing of the high-z hohlraum material with the low-z gas fill [11] and the role of numerical mesh management [12] in mainline radiation-hydrodynamic (RH) simulations [13]. At the other end of hohlraum gas-fill studies is the near-vacuum hohlraum (NVH) platform (ρ=0.032 mg/cc of 4 He) that was successfully used to drive exploding pusher or thin plastic (CH) ablators [14]. Due to the short laser pulse length used (~4 ns), good agreement with RH simulations was achieved without the need for phenomenological drive multipliers [10,15], i.e., no missing energy was inferred. These results have served as the impetus for recent 2- and 3- shock high-density carbon (HDC) ablator studies on the NIF [16, 17]. The strategy is to combine the intrinsically short laser power histories of HDC with the NVH platform for acceptable drive symmetry control without depending on large CBET at high Δλ. A HDC capsule requires an early-time high foot in laser drive to ensure melting of the ablator after first shock passage, thereby avoiding the crystalline diamond phase that can seed hydrodynamic instability growth [16]. To date HDC implosion experiments in NVHs have shown a strong bias towards equator high implosion drive asymmetry, in contrast to RH simulation results [18]. The origin of this difference is

2 not firmly established, but may involve ion diffusive effects from interpenetrating low-z HDC ablator and high-z hohlraum ions that are not captured in mainline fluid-based modeling tools. According to RH simulations of these NVHs the stopping length for a fully ionized ablated carbon ion (~ 350 µm/ns) into the expanding gold wall (~ -250 µm/ns) is on the order of 500 µm, based on a Au mass density of ~1 mg/cc and temperature of ~3 kev just before collision onset. Such long mean free paths challenge the use of RH simulations in a physical regime where kinetic effects are important [19]. For example, ion mixing from kinetic processes may modify the high-z density and temperature distribution above the capsule compared with RH simulations and allow for more efficient inner-cone laser propagation after the stagnation time of C/Au because of reduced inverse bremsstrahlung absorption or enhanced inner-beam refraction. A successful HDC ignition campaign based on the NVHs will require a predictive capability for informing studies of high-convergence implosion symmetry. Low gas-fill densities are attracting interest for potentially simplified hohlraum dynamics: high laserhohlraum coupling efficiency through minimal backscatter and unaccounted energy, reduced need for CBET, and calculable implosion symmetry. In this Letter recent experimental results with a 0.6 mg/cc 4 He gas fill that achieved close to optimal cylinder hohlraum performance in driving a 2-shock HDC capsule form the basis for a novel ignition path. The associated design uses a 4-shock drive profile with a comparatively low fuel adiabat (for high ignition margin) and applies the technique of adiabat shaping [20, 21] for ablation front instability control. The capsule is driven by an oversized rugby-shaped gold hohlraum [22] for high drive efficiency and robust symmetry control that is filled with the same 0.6 mg/cc 4 He gas. The 4-shock HDC ablator design has high 1-D simulated ignition margin (for achieving >1 MJ yield) and good tolerance to ablator and ice surface roughness, according to capsule-only high-resolution 2-D RH simulations. Hohlraum simulations that integrate laser propagation, x-ray transport and capsule/hohlraum hydrodynamics give a 2-D yield of nearly 15 MJ for only ~1.5 MJ absorbed laser energy. Based on demonstrated efficient hohlraum performance at low gas-fill densities and RH simulations that suggest strong 1- and 2-D 4-shock HDC implosion performance, an ignition design leveraging this unexplored parameter space is described and proposed as an alternate path for demonstrating ignition on the NIF. The recent low gas-fill density target that was fielded on the NIF combined the benefits of high efficiency of NVHs and the inherent symmetry control of gas-filled hohlraums for the purpose of driving a 2- shock HDC design over a ~7 ns laser pulse length [23]. The recognized challenges with the 2-shock ignition design are suitable control of implosion symmetry and the low 1-D ignition margin due to the intrinsically high fuel adiabat. Late time symmetry control is challenging because of significant wall motion and the ensuing laser absorption close to the hohlraum symmetry axis. To reduce the risk of excessive hohlraum filling with high-z wall material, the low gas-filled cylindrical hohlraum was enlarged to 6.72 mm diameter from the standard 5.75 mm. The larger hohlraum results in greater geometric smoothing of intrinsic hohlraum radiation modes at the capsule ablation front and ensures greater laser clearance at the laser entrance holes (LEHs). The incident laser energy was 1.5 MJ with a peak power of 370 TW, and no wavelength separation (Δλ=0) was chosen. The demonstrated backscatter was <4%, the effective x-ray drive was inferred to lie much closer to high-flux model predictions for typical gas-filled hohlraums (ρ= mg/cc 4 He), and improved imploded core symmetry in good agreement with modeling was observed [23]. Remarkably, increasing the gas fill for HDC implosions did not incur a drive penalty compared with NVHs. The early experimental success with a low gas-fill hohlraum platform opens up a promising ignition path for HDC ablators that is now described. The three main design challenges are ensuring (1) high 1-D performance margin, (2) robustness to instability growth at the ablation front and fuel-ablator and DT gas-ice interfaces, and (3) favorable hohlraum energetics with robust symmetry and preheat control. The demonstrated favorable symmetry control and energetics with a low gas-filled hohlraum density mean that 4-shock capsule designs with their ignitionrelevant low 1-D fuel adiabats α (or ratio of pressure to Fermi degenerate pressure) now become viable. Reference 17 compared the relevant 1-D implosion properties between 2- and 4-shock HDC designs, but without the potential benefit of adiabat shaping from laser pickets [20, 21]. Both capsule designs have comparable peak implosion speeds υ of ~380 µm/ns, but with a significantly higher adiabat for the 2-shock design (3.7 vs 1.5 for the 4-shock design). The ignition threshold factor ITF=M+1, is related to the ignition

3 Yield P stag υ α At GF [MJ] [Gbar] [µm/ns] Table 1: Calculated 1-D capsule yield, peak fuel stagnation pressure (with burn turned off), peak implosion speed υ, maximum fuel adiabat α, Atwood number of DT-ice/HDC interface At, and associated peak linear growth factor (GF) at peak implosion speed (l 80) for HDC 4-shock capsule [see Fig. 1a]. performance margin M and scales as α 2.6 υ 8 [24], giving more than a 10 higher margin for the 4-shock design. The current 2-shock design in a cylinder NVH uses undoped HDC [18], allowing for larger ablationfront stabilization of Rayleigh-Taylor instability growth but low 1-D margin. Table 1 lists the key properties of the 4-shock design used in the integrated hohlraum tune [described below]. However, adiabat shaping of the drive history may significantly reduce the exposure of the 4-shock target to ablation front instability growth. Adiabat shaping refers to the launch of a decaying first shock with a strong laser picket [see Figs. 2a, 3a] to potentially raise the adiabat of the outer ablator for ablation front stability control while keeping the fuel on a low adiabat. The shock pressure is designed to remain above 7 Mbars at the ablator-fuel interface, minimizing the risk of instability seeding from multi-phase HDC. The linear growth factor ~1200 for the 4-shock HDC design with adiabat shaping is 2 lower compared with the 4-shock lowadiabat CH design [17]. Figure 1b shows the simulated perturbation growth for the 4-shock design at the time of maximum shell kinetic energy using the ( 1 ) Fig. 2a-b: (a) Total requested laser power for 4-shock HDC ignition hohlraum design; (b) requested laser cone fraction with 300 ps outer cone delay at t=0. measured surface roughness spectra on all material interfaces from an as-built (undoped) HDC capsule. Up to ~2.5 the measured roughness on all surfaces is predicted to still lead to ignition, according to RH simulation parameter scans. The simulated clean fuel fraction defined as the fraction of DT fuel with less than 5.0 at.% of carbon at the time of maximum shell kinetic energy is a favorable 80% and lies above the threshold for onset of important 3-D effects. The tradeoff between capsule robustness and hohlraum performance is best illustrated by considering the drive duration. Fuel adiabat control benefits from longer pulse lengths [24], but hohlraum symmetry control and coupling efficiency (through reduced laser backscatter and x-ray drive corrections) favor shorter pulses. In order to accommodate the ~9 ns drive history of the optimized 4-shock capsule tune, added margin is sought by using a rugby-shaped Au hohlraum with a 7 mm diameter, 1.09 cm length and a comparatively large LEH fraction of ~60% [See Fig. 4]. The use of a rugby hohlraum over a cylinder allows for a greater volume above the capsule while preserving the hohlraum drive efficiency through a nearly fixed wall surface area. Added benefits of the rugby hohlraum include potentially benign (gold) M- Fig. 1a-b: (a) Diagram of HDC 4-shock design with indicated materials, dopant and dimensions; (b) 2-D highresolution (l = ) multi-mode capsule-only simulation at time of peak implosion speed with left (right) panel showing materials (density). Fig. 3a-b: (a) Uncompensated (for LEH closure) Dante radiation temperature T rad versus time with a viewing angle of 37 to the hohlraum symmetry axis; (b) Dante gold M- band (>1.8 kev) fraction of spectral flux versus Dante T rad for 4-shock ignition HDC design.

4 Fig. 4: Rugby-shaped (quarter) hohlraum geometry and laser ray geometry at peak power (6.5 ns; see Fig. 2a) for HDC 4- shock design (capsule not shown). Ray bundles as shown include only rays with greater than 50% of the peak (central) intensity for clarity. band x-ray preheat [See Fig. 3b] from reduced laser intensity at the curved wall, less hot electron generation, greatly reduced time-dependent drive symmetry variations in time, reduced exposure to specular laser glint and a reduced gold bubble feature in the wall blow-off that is typically seen in cylinder hohlraum experiments [25] and simulations [11]. The peak M-band fraction shown in Fig. 3b is predicted to remain below 20%, which compares favorably with the measured and simulated ~21% level in NVHs. A lower level of M-band preheat translates into smaller dopant concentrations that are needed in the ablator for higher ablation velocities and, in turn, higher performance and stability margins. The gold bubble may lead to impaired inner beam propagation at late time, but the curvature of a rugby-shaped wall distributes the incident laser energy over a larger area for a reduced risk of non-uniform wall ablation. Figure 4 shows the laser propagation at peak laser power, indicating robust inner cone (23 and 30 ) propagation past the incipient (small) gold bubble produced by the outer cones (44 and 50 ). However, the NIF rugby hohlraum database for 4-shock low-adiabat CH implosions (~20 ns laser pulse length) has shown some symmetry anomalies compared with RH simulations using the high-flux model - unless the outer laser cones are significantly displaced inward toward the capsule [11]. The origin of this anomaly is not established, but may involve hydrodynamic mix or ion diffusion across the gold-helium interface near the LEH. To minimize this risk (beyond the benefit of a ~2 shorter laser pulse with HDC), a comparatively larger LEH (~60% vs 50.6% for low-foot rugby hohlraums with 1.2 mg/cc 4 He fill [11]) is used in the 4-shock design [See Fig. 4]. Figure 2a-b depicts the requested laser power history and cone fraction. Use of an early time high (inner) cone fraction is intended to appreciably ablate the Fig. 5a-b: (a) Normalized 2 nd Legendre coefficient of simulated instantaneous ablation pressure asymmetry for HDC 4-shock capsule in rugby hohlraum (green) and HDC 2-shock in cylinder NVH [shot N140702] (blue) versus time; (b) fuel density map before (~9 kev) ignition onset (~12 kev) with rugby hohlraum symmetry axis along vertical. P2/P0 and P4/P0 distortion of maximum fuel density [ρ~900 g/cc] contour ~16% and 1.2%. window before onset of the ~70 TW picket in order to suppress hot electron generation by the two-plasmon decay instability. There is the potential for generating (non-azimuthal) CBET during the picket from the expanding LEH window even for low Δλ. However, use of just the 44 cones to drive the picket pulse can be shown to remove this risk. By removing CBET on the picket the usual hohlraum modeling uncertainties arising from choice of density saturation parameter are bypassed. There is also some CBET near peak laser power at Δλ=0, but a nominally small value of Δλ can largely suppress this contribution to hohlraum symmetry. Figure 5a shows the associated simulated capsule ablation pressure asymmetry history (P2/P0), indicating very low symmetry swings on the order of ±2% compared with the 2-shock HDC capsule in cylinder NVHs (~ ±5%). For low-adiabat implosions in rugby hohlraums, the relatively low level of P2 symmetry swings compared with cylinders has been experimentally confirmed [11]. The key figure-ofmerit is the degree of symmetry control at the end of the laser pulse. Effective inner-cone laser propagation at late time is predicted because of the large volume between the capsule and rugby equator and the large LEH fraction. Figure 5b shows the imploded fuel just before ignition, suggesting keen symmetry control without relying on late time CBET from large Δλ as in higher density gas-filled hohlraums. The energy output is over 15 MJ, corresponding to a gain of ~10. The low gas-fill hohlraum design also benefits from remaining in the fluid regime, which facilitates modeling with mainline RH simulation methods. The

5 carbon stopping length in the helium gas fill is on the order of 20 microns, largely preventing the carbon blow off from penetrating the Au plasma. In addition, the low gas fill density delays deceleration onset of the classical Au/ 4 He interface compared with high gas-fill platforms [11], lessening the amount of Rayleigh- Taylor instability growth after (wall/gas) stagnation onset. The alternate ignition path described herein is the culmination of promising early data with low-density gas-filled (cylindrical) hohlraums [23], recent capsule designs that both exploit adiabat shaping for improved stability control and optimize performance margin [21], and rugby-shaped hohlraum simulations for improved efficiency and symmetry control. However, the path to ignition is justifiably fraught with uncertainty over the fidelity of the mainline simulation tools, thereby requiring a careful and long-term experimental plan to benchmark the calculations and iterate on the design as necessary. In summary, a low density gas-filled hohlraum regime shows promise towards a novel ignition path that combines the energetics benefits of a NVH and the symmetry control advantages of a gas-filled hohlraum. A 4-shock HDC capsule design uses an oversized rugby-shaped hohlraum filled with the same 4 He density for greater margin to impaired laser propagation and potential symmetry anomalies. Further energetics margins can be obtained with depleted uranium hohlraums and the associated ~6% improvement in energy coupling [26]. Useful input from O.L. Landen and J. Milovich is gratefully acknowledged. The suggestions of L. Berzak-Hopkins, S. Khan, S. Nagel, R.J. Rygg and D. Turnbull are appreciated. Work performed under the auspices of Lawrence Livermore National Security, LLC (LLNS) under Contract DE-AC52-07NA2734. [1] J.D. Lindl, P. Amendt, R.L. Berger, S.G. Glendinning, S.H. Glenzer, S.W. Haan, R.L. Kauffman, O.L. Landen, and L.J. Suter, Phys. Plasmas 21, (2004). [2]H.F. Robey, B.J.MacGowan, O.L. Landen, K.N. LaFortune, C. Widmayer, P.M. Celliers, J.D. Moody, J.S. Ross, J. Ralph, S. LePape et al., Phys. Plasmas 20, (2013). [3] M.J. Edwards, P.K. Patel, J.D. Lindl, B.K. Spears, S.V. Weber, L.J. Atherton, D.L. Bleuel, D.K. Bradley, D.A. Callahan, C.J. Cerjan et al., Phys. Plasmas 20, (2013). [4] O.A. Hurricane, D.A. Callahan, D.T. Casey, P.M. Celliers, C. Cerjan, E.L. Dewald, T.R. Dittrich, T. Doppner, D.E. Hinkel, L.F. Berzak Hopkins et al., Nature 506, 343 (2014). [5] R.P.J. Town, D.K. Bradley, A. Kritcher, O.S. Jones, J.R. Rygg, R. Tommasini, M. Barrios, L.R. Benedetti, L.F. Berzak Hopkins, P.M. Celliers et al., Phys. Plasmas 21, (2014); A.L. Kritcher, R. Town, D. Bradley D. Clark, B. Spears, O. Jones, S. Haan, P.T. Springer, J. Lindl, R.H.H. Scott, et al., Phys. Plasmas 21, (2014). [6] P. Michel, W. Rozmus, E.A. Williams, L. Divol, R.L. Berger, S.H. Glenzer and D.A. Callahan, Phys. Plasmas 20, (2013). [7] M.D. Rosen, H.A. Scott, D.E. Hinkel, E.A. Williams, D.A. Callahan, R.P.J. Town, L. Divol, P.A. Michel, W.L. Kruer, L.J. Suter et al., High Energy Density Physics 7, 180 (2011). [8]H.F. Robey, T.R. Boehly, P.M. Celliers, J.H. Eggert, D. Hicks, R.F. Smith, R. Collins, M.W. Bowers, K.G. Krauter, P.S. Datte et al., Phys. Plasmas 19, (2012). [9] D.G. Hicks, N.B. Meezan, E.L. Dewald, A.J. MacKinnon, R.E. Olson, D.A. Callahan, T. Doppner, L.R. Benedetti, D.K. Bradley, P.M. Celliers et al., Phys. Plasmas 19, (2012). [10] D.S. Clark, D.E. Hinkel, D.C. Eder, O.S. Jones, S.W. Haan, B.A. Hammel, M.M. Marinak, J.L. Milovich, H.F. Robey, L.J. Suter and R.P.J. Town, Phys. Plasmas 20, (2013). [11] P. Amendt, J.S. Ross, J.L. Milovich, M. Schneider, E. Storm, D.A. Callahan, D. Hinkel, B. Lasinski, D. Meeker, P. Michel, J. Moody and D. Strozzi, Phys. Plasmas 21, (2014). [12] C.A. Thomas (private communication, 2014). [13] G.B. Zimmerman and W.L. Kruer, Comments Plasma Phys. Controlled Fusion 2, 51 (1975); M.M. Marinak, R.E. Tipton, O.L. Landen, T.J. Murphy, P. Amendt, S.W. Haan, S.P. Hatchett, C.J. Keane, R. McEachern and R. Wallace, Phys. Plasmas 3, 2070 (1996). [14] S. Le Pape, L. Divol, L. Berzak Hopkins, A. MacKinnon, N.B. Meezan, D. Casey, J. Frenje, H. Herrmann, J. McNaney, T. Ma et al., Phys. Rev. Lett. 112, (2014). [15] O.S. Jones, C.J. Cerjan, M.M. Marinak, J.L. Milovich, H.F. Robey, P.T. Springer, L.R. Benedetti, D.L. Bleuel, E.J. Bond, D.K. Bradley et al., Phys. Plasmas 19, (2012). [16] D. Ho, Bull. Am. Phys. Soc. 52(16), 273 (2007). [17] A.J. MacKinnon, N.B. Meezan, J.S. Ross, S. Le Pape, L. Berzak Hopkins, L. Divol, D. Ho, J. Milovich, A. Pak, J. Ralph et al., Phys. Plasmas 21, (2014). [18] L. Berzak-Hopkins, S. Le Pape, L. Divol, N. Meezan, A. MacKinnon, D. Ho, O. Jones, S. Khan, J. Milovich, J. Ross, P. Amendt, D. Casey, A. Pak, J. Peterson, J. Ralph and J. Rygg, Near-vacuum hohlraums for driving fusion

6 implosions with high density carbon ablators, Phys. Plasmas (submitted). [19] M.J. Rosenberg, H.G. Rinderknecht, N.M. Hoffman, P.A. Amendt, S. Atzeni, A.B. Zylstra, C.K. Li, F.H. Seguin, H. Sio, M. Gatu Johnson et al., Phys. Rev. Lett. 112, (2014). [20] R. Betti, K. Anderson, V.N. Goncharov, R.L. McCrory, D.D. Meyerhofer, S. Skupsky and R.P.J. Town, Phys. Plasmas 9, 2277 (2002). [21] D. Ho, P. Amendt, D. Clark, S. Haan, J. Milovich, J. Salmonson, G. Zimmerman, L. Berzak Hopkins, J. Biener, N. Meezan et al., Bull. Am. Phys. Soc. 59(15), 199 (2014). [22] P. Amendt, C. Cerjan, A. Hamza, D.E. Hinkel, J.L. Milovich and H.F. Robey, Phys. Plasmas 14, (2007); M. Vandenboomgaerde, J. Bastian, A. Casner, D. Galmiche, J.-P. Jadaud, S. Lafitte, S. Liberatore, G. Malinie and F. Philippe, Phys. Rev. Lett. 99, (2007). [23] O. Jones, N. Izumi, L.Berzak-Hopkins, D.J. Strozzi, P.A. Amendt, G.N. Hall, D.D. Ho, S.F. Khan, N.B. Meezan, J.D. Moody et al., Hohlraum fill gas density scaling of x-ray drive, symmetry and laser coupling backscatter in 6.72-mm NIF hohlraums, Bull. Am. Phys. Soc. 59(15), 66 (2014). [24] J. Lindl, O. Landen, J. Edwards and E. Moses, Phys. Plasmas 21, (2014). [25] S.A. MacLaren, M.B. Schneider, K. Widmann, J.H. Hammer, B.E. Yoxall, J.D. Moody, P.M. Bell, L.R. Benedetti, D.K. Bradley, M.J. Edwards et al., Phys. Rev. Lett. 112, (2014). [26] D.A. Callahan, N.B. Meezan, S.H. Glenzer, A.J. MacKinnon, L.R. Benedetti, D.K. Bradley, J.R. Celeste, P.M. Celliers, S.N. Dixit, T. Doppner et al., Phys. Plasmas 19, (2012).

7

8

9

10

11

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

The Near Vacuum Hohlraum campaign at the NIF: a new approach The Near Vacuum Hohlraum campaign at the NIF: a new approach S. Le Pape, 1 L. F. Berzak Hopkins, 1 L. Divol, 1 N. Meezan, 1 D. Turnbull, 1 A. J. Mackinnon, 2 D. Ho, 1 J.S. Ross, 1 S. Khan, 1 A. Pak, 1

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

Design of a Peanut Hohlraum with Low Gas-Fill Density for the Laser Megajoule

Design of a Peanut Hohlraum with Low Gas-Fill Density for the Laser Megajoule Design of a Peanut Hohlraum with Low Gas-Fill Density for the Laser Megajoule X. Li ( 李欣 ) *, C. S. Wu ( 吴畅书 ), Z. S. Dai ( 戴振生 ), D. G. Kang ( 康洞国 ), W. D. Zheng ( 郑无敌 ), P. J. Gu ( 古培俊 ), P. Song ( 宋鹏

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

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

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

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

Demonstrated high performance of gas-filled rugby-shaped hohlraums on Omega

Demonstrated high performance of gas-filled rugby-shaped hohlraums on Omega Demonstrated high performance of gas-filled rugby-shaped hohlraums on Omega F. Philippe, V. Tassin, S. Depierreux, P. Gauthier, P. E. Masson-Laborde, M. C. Monteil, P. Seytor, B. Villette, B. Lasinski,

More information

In-flight observations of low-mode R asymmetries in NIF implosions

In-flight observations of low-mode R asymmetries in NIF implosions In-flight observations of low-mode R asymmetries in NIF implosions The MIT Faculty has made this article openly available. Please share how this access benefits you. Your story matters. Citation As Published

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

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

Laser absorption, power transfer, and radiation symmetry during the first shock of ICF gas-filled hohlraum experiments Laser absorption, power transfer, and radiation symmetry during the first shock of ICF gas-filled hohlraum experiments A. Pak, 1 E. L. Dewald, 1 O. L. Landen, 1 J. Milovich, 1 D. J. Strozzi, 1 L. F. Berzak

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

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

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

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

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

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

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

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

PROGRESS OF INDIRECT DRIVE INERTIAL CONFINEMENT FUSION IN THE US

PROGRESS OF INDIRECT DRIVE INERTIAL CONFINEMENT FUSION IN THE US PROGRESS OF INDIRECT DRIVE INERTIAL CONFINEMENT FUSION IN THE US J. L. KLINE, 1 S. H. BATHA, 1 L. R. BENEDETTI, 2 D. BENNETT, 2 S. BHANDARKAR, 2 L. F. BERZAK HOPKINS, 2 J. BIENER, 2 M. M. BIENER 2, R BIONTA,

More information

hohlraum directly and reduce the effect of the beam phasing technology. A crossed-beam energy transfer (CBET) [1] technique is used to maintain the re

hohlraum directly and reduce the effect of the beam phasing technology. A crossed-beam energy transfer (CBET) [1] technique is used to maintain the re A new ignition hohlraum design for indirect-drive inertial confinement fusion Xin Li( 李欣 ) 1, Chang-Shu Wu( 吴畅书 ) 1, Zhen-Sheng Dai( 戴振生 ) 1,, Wu-Di Zheng( 郑无敌 ) 1, Jian-Fa Gu( 谷建法 ) 1, Pei-Jun Gu( 古培俊

More information

arxiv: v2 [physics.plasm-ph] 29 Dec 2016

arxiv: v2 [physics.plasm-ph] 29 Dec 2016 Interplay of Laser-Plasma Interactions and Inertial Fusion Hydrodynamics D. J. Strozzi, D. S. Bailey, P. Michel, L. Divol, S. M. Sepke, G. D. Kerbel, C. A. Thomas, J. E. Ralph, J. D. Moody, M. B. Schneider

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

Performance of beryllium targets with full-scale capsules in low-ll 6.72-mm hohlraums on the National Ignition Facility

Performance of beryllium targets with full-scale capsules in low-ll 6.72-mm hohlraums on the National Ignition Facility Performance of beryllium targets with full-scale capsules in low-ll 6.72-mm hohlraums on the National Ignition Facility A. N. Simakov, 1,a) D. C. Wilson, 1 S. A. Yi, 1 E. N. Loomis, 1 J. L. Kline, 1 G.

More information

Simulations of indirectly driven gas-filled capsules at the National Ignition Facility

Simulations of indirectly driven gas-filled capsules at the National Ignition Facility Simulations of indirectly driven gas-filled capsules at the National Ignition Facility S. V. Weber, 1 D. T. Casey, 1 D. C. Eder, 1 J. D. Kilkenny, 5 J. E. Pino, 1 V. A. Smalyuk, 1 G. P. Grim, 2 B. A. Remington,

More information

Electron Temperature Measurements inside the Ablating Plasma of Gas-Filled. Hohlraums at the National Ignition Facility

Electron Temperature Measurements inside the Ablating Plasma of Gas-Filled. Hohlraums at the National Ignition Facility Electron Temperature Measurements inside the Ablating Plasma of Gas-Filled Hohlraums at the National Ignition Facility M.A. Barrios 1, D.A. Liedahl 1, M.B. Schneider 1, O. Jones 1, G.V. Brown 1, S.P. Regan

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

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

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

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

Gamma Reaction History ablator areal density constraints upon correlated diagnostic modeling of NIF implosion experiments

Gamma Reaction History ablator areal density constraints upon correlated diagnostic modeling of NIF implosion experiments Gamma Reaction History ablator areal density constraints upon correlated diagnostic modeling of NIF implosion experiments C. Cerjan, 1, a) D. B. Sayre, 1 O. L. Landen, 1 J. A. Church, 1 W. Stoeffl, 1 E.

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

arxiv: v2 [physics.plasm-ph] 8 Oct 2015

arxiv: v2 [physics.plasm-ph] 8 Oct 2015 Under consideration for publication in J. Plasma Phys. 1 arxiv:1508.00803v2 [physics.plasm-ph] 8 Oct 2015 Imposed magnetic field and hot electron propagation in inertial fusion hohlraums DAVID J. STROZZI

More information

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

BEAM PROPAGATION FOR THE LASER INERTIAL CONFINEMENT FUSION-FISSION ENERGY ENGINE. S. C. Wilks, B. I. Cohen, J. F. Latkowski, and E. A. BEAM PROPAGATION FOR THE LASER INERTIAL CONFINEMENT FUSION-FISSION ENERGY ENGINE S. C. Wilks, B. I. Cohen, J. F. Latkowski, and E. A. Williams Lawrence Livermore National Laboratory L-211, Livermore, CA,

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

Simultaneous measurement of the HT and DT fusion burn histories in inertial fusion implosions

Simultaneous measurement of the HT and DT fusion burn histories in inertial fusion implosions Simultaneous measurement of the HT and DT fusion burn histories in inertial fusion implosions A.B. Zylstra,, a) H.W. Herrmann, Y.H. Kim, A.M. McEvoy,, b) M.J. Schmitt, G. Hale, C. Forrest, V.Yu. Glebov,

More information

Science and code validation program to secure ignition on LMJ

Science and code validation program to secure ignition on LMJ Journal of Physics: Conference Series PAPER OPEN ACCESS Science and code validation program to secure ignition on LMJ Related content - Inertial fusion with the LMJ C Cavailler To cite this article: E

More information

The 1-D Cryogenic Implosion Campaign on OMEGA

The 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 information

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

Target Design Activities for Inertial Fusion Energy at Lawrence Livermore National Laboratory 1. Introduction Target Design Activities for Inertial Fusion Energy at Lawrence Livermore National Laboratory MAX TABAK, DEBRA CALLAHAN-MILLER,MARK HERRMANN,STEPHEN HATCHETT,JOHN D. LINDL, L.JOHN PERKINS, Lawrence Livermore

More information

High Convergence, Indirect Drive Inertial Confinement Fusion Experiments at Nova

High Convergence, Indirect Drive Inertial Confinement Fusion Experiments at Nova UCRL-JC-119536 PREPRNT High Convergence, ndirect Drive nertial Confinement Fusion Experiments at Nova R. A. Lerche, M. D. Cable, S. P. Hatchett, J. A. Carid, J. D. Kilkenny, H. N. Kornblum, S. M. Lane,

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

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

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

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

Journal of Physics: Conference Series PAPER OPEN ACCESS. To cite this article: T J Murphy et al 2016 J. Phys.: Conf. Ser. Journal of Physics: Conference Series PAPER OPEN ACCESS Progress in the development of the MARBLE platform for studying thermonuclear burn in the presence of heterogeneous mix on OMEGA and the National

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

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

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

On thermonuclear ignition criterion at the National Ignition Facility

On thermonuclear ignition criterion at the National Ignition Facility On thermonuclear ignition criterion at the National Ignition Facility Baolian Cheng, Thomas J. T. Kwan, Yi-Ming Wang, and Steven H. Batha Los Alamos National Laboratory, Los Alamos, New Mexico 87545, USA

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

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

Response to Comment on "The National Ignition Facility Laser Performance Status"

Response to Comment on The National Ignition Facility Laser Performance Status UCRL-JRNL-237304 Response to Comment on "The National Ignition Facility Laser Performance Status" C. A. Haynam, R. A. Sacks, E. I. Moses, K. Manes, S. Haan, M. L. Spaeth December 17, 2007 Applied Optics

More information

Integrated Modeling of Fast Ignition Experiments

Integrated 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 information

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

Downloaded 11 Oct 2012 to Redistribution subject to AIP license or copyright; see PHYSICS OF PLASMAS VOLUME 11, NUMBER 2 FEBRUARY 2004 REVIEW ARTICLE The physics basis for ignition using indirect-drive targets on the National Ignition Facility John D. Lindl, Peter Amendt, Richard L.

More information

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 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 information

Effects of fuel-capsule shimming and drive asymmetry on inertial-confinement-fusion symmetry and yield

Effects of fuel-capsule shimming and drive asymmetry on inertial-confinement-fusion symmetry and yield PSFC/JA-16-43 Effects of fuel-capsule shimming and drive asymmetry on inertial-confinement-fusion symmetry and yield F. H. Séguin, 1 C. K. Li, 1 J. L. DeCiantis, 1 J. A. Frenje, 1 J. R. Rygg, 1 R. D. Petrasso,

More information

The National Ignition Facility: Transition to a User Facility

The National Ignition Facility: Transition to a User Facility Journal of Physics: Conference Series PAPER OPEN ACCESS The National Ignition Facility: Transition to a User Facility To cite this article: E. I. Moses et al 2016 J. Phys.: Conf. Ser. 688 012073 View the

More information

Measurements of collective fuel velocities in deuterium-tritium exploding pusher and cryogenically layered deuterium-tritium implosions on the NIF

Measurements of collective fuel velocities in deuterium-tritium exploding pusher and cryogenically layered deuterium-tritium implosions on the NIF Measurements of collective fuel velocities in deuterium-tritium exploding pusher and cryogenically layered deuterium-tritium implosions on the NIF M. Gatu Johnson, D. T. Casey, J. A. Frenje, C.-K. Li,

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

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

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

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

Analysis of Experimental Asymmetries using Uncertainty Quantification: Inertial Confinement Fusion (ICF) & its Applications Analysis of Experimental Asymmetries using Uncertainty Quantification: Inertial Confinement Fusion (ICF) & its Applications Joshua Levin January 9, 2009 (Edited: June 15, 2009) 1 Contents 1. Uncertainty

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

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

arxiv: v1 [physics.plasm-ph] 12 Oct 2016

arxiv: v1 [physics.plasm-ph] 12 Oct 2016 Simulation and assessment of ion kinetic effects in a direct-drive capsule implosion experiment A. Le, T. J. T. Kwan, M. J. Schmitt, H. W. Herrmann, and S. H. Batha arxiv:60.078v [physics.plasm-ph] Oct

More information

Using multiple secondary fusion products to evaluate fuel ρr, electron temperature, and mix in deuterium-filled implosions at the NIF

Using multiple secondary fusion products to evaluate fuel ρr, electron temperature, and mix in deuterium-filled implosions at the NIF Using multiple secondary fusion products to evaluate fuel ρr, electron temperature, and mix in deuterium-filled implosions at the NIF H. G. Rinderknecht, M. J. Rosenberg, A. B. Zylstra, B. Lahmann, F.

More information

Inertial Confinement Fusion Experiments & Modeling

Inertial Confinement Fusion Experiments & Modeling Inertial Confinement Fusion Experiments & Modeling Using X-ray Absorption Spectroscopy of Thin Tracer Layers to Diagnose the Time-Dependent Properties of ICF Ablator Materials David Cohen (Swarthmore College,

More information

Design of Magnetized, Room-Temperature Capsule Implosions for NIF

Design of Magnetized, Room-Temperature Capsule Implosions for NIF Design of Magnetized, Room-Temperature Capsule Implosions for NIF 48 th Anomalous Absorption Conference Bar Harbor, Maine 11 July 2018 D. J. Strozzi, J. D. Moody, J. M. Koning, J. D. Salmonson, W. A. Farmer,

More information

Modeling Laser-Plasma Interactions in MagLIF Experiment on NIF

Modeling Laser-Plasma Interactions in MagLIF Experiment on NIF Modeling Laser-Plasma Interactions in MagLIF Experiment on NIF Anomalous Absorption Meeting 5 May 2016 D. J. Strozzi, R. L. Berger, A. B. Sefkow, S. H. Langer, T. Chapman, B. Pollock, C. Goyon, J. Moody

More information

Measurements of hohlraum-produced fast ions

Measurements of hohlraum-produced fast ions Measurements of hohlraum-produced fast ions A. B. Zylstra, C. K. Li, F. H. Séguin, M. J. Rosenberg, H. G. Rinderknecht et al. Citation: Phys. Plasmas 19, 042707 (2012); doi: 10.1063/1.4707410 View online:

More information

Theory and simulations of hydrodynamic instabilities in inertial fusion

Theory 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 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

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

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

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

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

Improving hot-spot pressure for ignition in high-adiabat inertial confinement fusion implosion Improving hot-spot preure for ignition in high-adiabat inertial confinement fusion implosion Dongguo Kang( 康洞国 ),* Shaoping Zhu( 朱少平 ), Wenbing Pei( 裴文兵 ), Shiyang Zou( 邹士阳 ), Wudi Zheng( 郑无敌 ), Jianfa

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

Development of a WDM platform for chargedparticle stopping experiments

Development of a WDM platform for chargedparticle stopping experiments Journal of Physics: Conference Series PAPER OPEN ACCESS Development of a WDM platform for chargedparticle stopping experiments To cite this article: A B Zylstra et al 216 J. Phys.: Conf. Ser. 717 12118

More information

High-density implosion via suppression of Rayleigh Taylor instability

High-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 information

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

NIF-scale hohlraum asymmetry studies using point-projection radiograph of thin shells UCRL-JC-139459 PREPRINT NIF-scale hohlraum asymmetry studies using point-projection radiograph of thin shells Steve Pollaine, David Bradley, Otto Landen, Russell Wallace, Ogden Jones, Peter Amendt, Larry

More information

Effects of Atomic Mixing in Inertial Confinement Fusion by Multifluid Interpenetration Mix Model

Effects of Atomic Mixing in Inertial Confinement Fusion by Multifluid Interpenetration Mix Model Commun. Theor. Phys. (Beijing, China) 52 (2009) pp. 1102 1106 c Chinese Physical Society and IOP Publishing Ltd Vol. 52, No. 6, December 15, 2009 Effects of Atomic Mixing in Inertial Confinement Fusion

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 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

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

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

ICStatus and progress of the National Ignition Facility as ICF and HED user facility Journal of Physics: Conference Series PAPER OPEN ACCESS ICStatus and progress of the National Ignition Facility as ICF and HED user facility To cite this article: B M Van Wonterghem et al 2016 J. Phys.:

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

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

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

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

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

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

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

New developments in the theory of ICF targets, and fast ignition with heavy ions INSTITUTE OF PHYSICS PUBLISHING Plasma Phys. Control. Fusion 45 (2003) A125 A132 PLASMA PHYSICS AND CONTROLLED FUSION PII: S0741-3335(03)68658-6 New developments in the theory of ICF targets, and fast

More information

The effect of residual kinetic energy on apparent ion temperature in ICF implosions. T. J. Murphy

The effect of residual kinetic energy on apparent ion temperature in ICF implosions. T. J. Murphy LA-UR-15-27714 The effect of residual kinetic energy on apparent ion temperature in ICF implosions T. J. Murphy National ICF Diagnostics Working Group Meeting October 6-8, 2015 Outline Basic kinetics of

More information

Effects of alpha stopping power modelling on the ignition threshold in a directly-driven Inertial Confinement Fusion capsule

Effects of alpha stopping power modelling on the ignition threshold in a directly-driven Inertial Confinement Fusion capsule Effects of alpha stopping power modelling on the ignition threshold in a directly-driven Inertial Confinement Fusion capsule M. Temporal 1, a, B. Canaud 2, W. Cayzac 2, R. Ramis 3, and R.L. Singleton Jr

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

Diagnosing magnetized liner inertial fusion experiments on Z a)

Diagnosing magnetized liner inertial fusion experiments on Z a) Diagnosing magnetized liner inertial fusion experiments on Z a) S. B. Hansen 1,b), M. R. Gomez 1, A. B. Sefkow 1, S. A. Slutz 1, D. B. Sinars 1, K. D. Hahn 1, E. C. Harding 1, P. F. Knapp 1, P. F. Schmit

More information

Kinetic mix mechanisms in shock-driven inertial confinement fusion implosionsa)

Kinetic mix mechanisms in shock-driven inertial confinement fusion implosionsa) Kinetic mix mechanisms in shock-driven inertial confinement fusion implosionsa) H. G. Rinderknecht, H. Sio, C. K. Li, N. Hoffman, A. B. Zylstra, M. J. Rosenberg, J. A. Frenje, M. Gatu Johnson, F. H. Séguin,

More information

Ignition and Burn in a Small Magnetized Fuel Target

Ignition and Burn in a Small Magnetized Fuel Target Ignition and Burn in a Small Magnetized Fuel Target Ronald C. Kirkpatrick, Los Alamos National Laboratory, Los Alamos, NM, USA E-mail: rck@lanl.gov Abstract LASNEX calculations of a small magnetized target

More information

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

Charles Cerjan. Nuclear Data Needs and Capabilities for Applications. Lawrence Berkeley National Laboratory. May 28, 2015 Charles Cerjan Nuclear Data Needs and Capabilities for Applications Lawrence Berkeley National Laboratory May 28, 2015 LLNL-PRES-670924 This work was performed under the auspices of the U.S. Department

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