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Dive into the research topics where David C. Eder is active.

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Featured researches published by David C. Eder.


Physics of Plasmas | 1994

Tabletop X-ray Lasers

David C. Eder; Peter A. Amendt; L. B. DaSilva; Richard A. London; B. J. MacGowan; Dennis L. Matthews; B. M. Penetrante; M. D. Rosen; S. C. Wilks; T. D. Donnelly; R. W. Falcone; G. L. Strobel

Details of schemes for two tabletop size x‐ray lasers that require a high‐intensity short‐pulse driving laser are discussed. The first is based on rapid recombination following optical‐field ionization. Analytical and numerical calculations of the output properties are presented. Propagation in the confocal geometry is discussed and a solution for x‐ray lasing in Li‐like N at 247 A is described. Since the calculated gain coefficient depends strongly on the electron temperature, the methods of calculating electron heating following field ionization are discussed. Recent experiments aimed at demonstrating lasing in H‐like Li at 135 A are discussed along with modeling results. The second x‐ray laser scheme is based on the population inversion obtained during inner‐shell photoionization by hard x rays. This approach has significantly higher‐energy requirements, but lasing occurs at very short wavelengths (λ≤15 A). Experiments that are possible with existing lasers are discussed.


Physics of Plasmas | 2013

Detailed implosion modeling of deuterium-tritium layered experiments on the National Ignition Facilitya)

D. S. Clark; D. E. Hinkel; David C. Eder; O. S. Jones; S. W. Haan; B. A. Hammel; M. M. Marinak; J. L. Milovich; H. F. Robey; L. J. Suter; R. P. J. Town

More than two dozen inertial confinement fusion ignition experiments with cryogenic deuterium-tritium layers have now been performed on the National Ignition Facility (NIF) [G. H. Miller et al., Opt. Eng. 443, 2841 (2004)]. Each of these yields a wealth of data including neutron yield, neutron down-scatter fraction, burn-averaged ion temperature, x-ray image shape and size, primary and down-scattered neutron image shape and size, etc. Compared to 2-D radiation-hydrodynamics simulations modeling both the hohlraum and the capsule implosion, however, the measured capsule yield is usually lower by a factor of 5 to 10, and the ion temperature varies from simulations, while most other observables are well matched between experiment and simulation. In an effort to understand this discrepancy, we perform detailed post-shot simulations of a subset of NIF implosion experiments. Using two-dimensional HYDRA simulations [M. M. Marinak, et al., Phys. Plasmas 8, 2275 (2001).] of the capsule only, these simulations repre...


Physics of Plasmas | 2012

Shock timing experiments on the National Ignition Facility: Initial results and comparison with simulation

H. F. Robey; T. R. Boehly; Peter M. Celliers; Jon H. Eggert; Damien G. Hicks; R.F. Smith; R. Collins; M. W. Bowers; K. Krauter; P. S. Datte; D. H. Munro; J. L. Milovich; O. S. Jones; P. Michel; C. A. Thomas; R.E. Olson; Stephen M. Pollaine; R. P. J. Town; S. W. Haan; D. A. Callahan; D. S. Clark; J. Edwards; J. L. Kline; S. N. Dixit; M. B. Schneider; E. L. Dewald; K. Widmann; J. D. Moody; T. Döppner; H.B. Radousky

Capsule implosions on the National Ignition Facility (NIF) [Lindl et al., Phys. Plasmas 11, 339 (2004)] are underway with the goal of compressing deuterium-tritium (DT) fuel to a sufficiently high areal density (ρR) to sustain a self-propagating burn wave required for fusion power gain greater than unity. These implosions are driven with a carefully tailored sequence of four shock waves that must be timed to very high precision in order to keep the DT fuel on a low adiabat. Initial experiments to measure the strength and relative timing of these shocks have been conducted on NIF in a specially designed surrogate target platform known as the keyhole target. This target geometry and the associated diagnostics are described in detail. The initial data are presented and compared with numerical simulations. As the primary goal of these experiments is to assess and minimize the adiabat in related DT implosions, a methodology is described for quantifying the adiabat from the shock velocity measurements. Results ...


Physics of Plasmas | 2015

Radiation hydrodynamics modeling of the highest compression inertial confinement fusion ignition experiment from the National Ignition Campaign

D. S. Clark; M. M. Marinak; C. R. Weber; David C. Eder; S. W. Haan; B. A. Hammel; D. E. Hinkel; O. S. Jones; J. L. Milovich; P. K. Patel; H. F. Robey; J. D. Salmonson; S. M. Sepke; C. A. Thomas

The recently completed National Ignition Campaign (NIC) on the National Ignition Facility (NIF) showed significant discrepancies between post-shot simulations of implosion performance and experimentally measured performance, particularly in thermonuclear yield. This discrepancy between simulation and observation persisted despite concerted efforts to include all of the known sources of performance degradation within a reasonable two-dimensional (2-D), and even three-dimensional (3-D), simulation model, e.g., using measured surface imperfections and radiation drives adjusted to reproduce observed implosion trajectories [Clark et al., Phys. Plasmas 20, 056318 (2013)]. Since the completion of the NIC, several effects have been identified that could explain these discrepancies and that were omitted in previous simulations. In particular, there is now clear evidence for larger than anticipated long-wavelength radiation drive asymmetries and a larger than expected perturbation seeded by the capsule support tent. This paper describes an updated suite of one-dimensional (1-D), 2-D, and 3-D simulations that include the current best understanding of these effects identified since the NIC, as applied to a specific NIC shot. The relative importance of each effect on the experimental observables is compared. In combination, these effects reduce the simulated-to-measured yield ratio from 125:1 in 1-D to 1.5:1 in 3-D, as compared to 15:1 in the best 2-D simulations published previously. While the agreement with the experimental data remains imperfect, the comparison to the data is significantly improved and suggests that the largest sources for the previous discrepancies between simulation and experiment are now being included.


Review of Scientific Instruments | 2006

Development of nuclear diagnostics for the National Ignition Facility (invited)

V. Yu. Glebov; D. D. Meyerhofer; T. C. Sangster; C. Stoeckl; S. Roberts; C. A. Barrera; J. Celeste; Charles Cerjan; Lucile S. Dauffy; David C. Eder; R. L. Griffith; S. W. Haan; B. A. Hammel; S. P. Hatchett; N. Izumi; J. R. Kimbrough; J. A. Koch; O. L. Landen; R. A. Lerche; B. J. MacGowan; M. J. Moran; E. W. Ng; Thomas W. Phillips; P. Song; R. Tommasini; B. K. Young; S. E. Caldwell; Gary P. Grim; S. C. Evans; J. M. Mack

The National Ignition Facility (NIF) will provide up to 1.8MJ of laser energy for imploding inertial confinement fusion (ICF) targets. Ignited NIF targets are expected to produce up to 1019 DT neutrons. This will provide unprecedented opportunities and challenges for the use of nuclear diagnostics in ICF experiments. In 2005, the suite of nuclear-ignition diagnostics for the NIF was defined and they are under development through collaborative efforts at several institutions. This suite includes PROTEX and copper activation for primary yield measurements, a magnetic recoil spectrometer and carbon activation for fuel areal density, neutron time-of-flight detectors for yield and ion temperature, a gamma bang time detector, and neutron imaging systems for primary and downscattered neutrons. An overview of the conceptual design, the developmental status, and recent results of prototype tests on the OMEGA laser will be presented.


Physics of Plasmas | 2014

Dynamic symmetry of indirectly driven inertial confinement fusion capsules on the National Ignition Facilitya)

R. P. J. Town; D. K. Bradley; A. L. Kritcher; O. S. Jones; J. R. Rygg; R. Tommasini; M. A. Barrios; L. R. Benedetti; L. Berzak Hopkins; Peter M. Celliers; T. Döppner; E. L. Dewald; David C. Eder; J. E. Field; S. M. Glenn; N. Izumi; S. W. Haan; S. F. Khan; J. L. Kline; G. A. Kyrala; T. Ma; J. L. Milovich; J. D. Moody; S. R. Nagel; A. Pak; J. L. Peterson; H. F. Robey; J. S. Ross; R. H. H. Scott; B. K. Spears

In order to achieve ignition using inertial confinement fusion it is important to control the growth of low-mode asymmetries as the capsule is compressed. Understanding the time-dependent evolution of the shape of the hot spot and surrounding fuel layer is crucial to optimizing implosion performance. A design and experimental campaign to examine sources of asymmetry and to quantify symmetry throughout the implosion has been developed and executed on the National Ignition Facility (NIF) [E. I. Moses et al., Phys. Plasmas 16, 041006 (2009)]. We have constructed a large simulation database of asymmetries applied during different time intervals. Analysis of the database has shown the need to measure and control the hot-spot shape, areal density distribution, and symmetry swings during the implosion. The shape of the hot spot during final stagnation is measured using time-resolved imaging of the self-emission, and information on the shape of the fuel at stagnation can be obtained from Compton radiography [R. Tommasini et al., Phys. Plasmas 18, 056309 (2011)]. For the first time on NIF, two-dimensional inflight radiographs of gas-filled and cryogenic fuel layered capsules have been measured to infer the symmetry of the radiation drive on the capsule. These results have been used to modify the hohlraum geometry and the wavelength tuning to improve the inflight implosion symmetry. We have also expanded our shock timing capabilities by the addition of extra mirrors inside the re-entrant cone to allow the simultaneous measurement of shock symmetry in three locations on a single shot, providing asymmetry information up to Legendre mode 4. By diagnosing the shape at nearly every step of the implosion, we estimate that shape has typically reduced fusion yield by about 50% in ignition experiments.


Journal of The Optical Society of America B-optical Physics | 1987

X-ray laser research at the Lawrence Livermore National Laboratory Nova laser facility

Dennis L. Matthews; Mordecai D. Rosen; S. Brown; Natale M. Ceglio; David C. Eder; A. M. Hawryluk; C. J. Keane; Richard A. London; B. J. MacGowan; S. Maxon; D. Nilson; James H. Scofield; J. E. Trebes

We describe our optical-laser-pumped x-ray laser program. Our long-term goal is to develop and utilize a fully coherent, gigowatt-power-level sub-44-A laser. To this end we have been studying the characteristics of the exploding-foil amplifier coupled with various inversion schemes: Ne-like and Ni-like collisional excitation as well as H-like three-body recombination. Most of our experimental results to date are for the Ne-like schemes; we have observed ~15 laser transitions in Se, Y, and Mo having wavelengths from 26.3 to 10.6 nm. Output power to at least 1 MW has been observed for the Se J = 2 to 1 lines at 20.6 and 20.9 A along with geometrical divergence patterns for the beam. We have also observed time-dependent beam refraction from these amplifiers and have been able to demonstrate double-pass amplification by using a multilayer mirror operated at normal incidence. Future plans for improving beam coherence and producing lasing at wavelengths shorter than 44 A are discussed.


Physics of Plasmas | 2014

Progress in hohlraum physics for the National Ignition Facilitya)

J. D. Moody; D. A. Callahan; D. E. Hinkel; Peter A. Amendt; K. L. Baker; D. K. Bradley; Peter M. Celliers; E. L. Dewald; L. Divol; T. Döppner; David C. Eder; M. J. Edwards; O. S. Jones; S. W. Haan; D. Ho; L. B. Hopkins; N. Izumi; D. H. Kalantar; R. L. Kauffman; J. D. Kilkenny; O. L. Landen; Barbara F. Lasinski; S. LePape; T. Ma; B. J. MacGowan; S. A. MacLaren; A. J. Mackinnon; D. Meeker; N. B. Meezan; P. Michel

Advances in hohlraums for inertial confinement fusion at the National Ignition Facility (NIF) were made this past year in hohlraum efficiency, dynamic shape control, and hot electron and x-ray preheat control. Recent experiments are exploring hohlraum behavior over a large landscape of parameters by changing the hohlraum shape, gas-fill, and laser pulse. Radiation hydrodynamic modeling, which uses measured backscatter, shows that gas-filled hohlraums utilize between 60% and 75% of the laser power to match the measured bang-time, whereas near-vacuum hohlraums utilize 98%. Experiments seem to be pointing to deficiencies in the hohlraum (instead of capsule) modeling to explain most of the inefficiency in gas-filled targets. Experiments have begun quantifying the Cross Beam Energy Transfer (CBET) rate at several points in time for hohlraum experiments that utilize CBET for implosion symmetry. These measurements will allow better control of the dynamic implosion symmetry for these targets. New techniques are b...


Review of Scientific Instruments | 2008

Absolute calibration of image plates for electrons at energy between 100 keV and 4 MeV

H. Chen; Norman L. Back; T. Bartal; F. N. Beg; David C. Eder; Anthony Link; A. G. MacPhee; Yuan Ping; Peter Song; A. L. Throop; Linn D. van Woerkom

We measured the absolute response of image plate (Fuji BAS SR2040) for electrons at energies between 100 keV and 4 MeV using an electron spectrometer. The electron source was produced from a short pulse laser irradiated on solid density targets. This paper presents the calibration results of image plate photon stimulated luminescence per electron at this energy range. The Monte Carlo radiation transport code MCNPX results are also presented for three representative incident angles onto the image plates and corresponding electron energy depositions at these angles. These provide a complete set of tools that allows extraction of our absolute calibration to other spectrometer setting at this electron energy range.


Physics of Plasmas | 2014

A survey of pulse shape options for a revised plastic ablator ignition design

D. S. Clark; J. L. Milovich; D. E. Hinkel; J. D. Salmonson; J. L. Peterson; L. Berzak Hopkins; David C. Eder; S. W. Haan; O. S. Jones; M. M. Marinak; H. F. Robey; V. A. Smalyuk; C. R. Weber

Recent experimental results using the “high foot” pulse shape for inertial confinement fusion ignition experiments on the National Ignition Facility (NIF) [Moses et al., Phys. Plasmas 16, 041006 (2009)] have shown encouraging progress compared to earlier “low foot” experiments. These results strongly suggest that controlling ablation front instability growth can significantly improve implosion performance even in the presence of persistent, large, low-mode distortions. Simultaneously, hydrodynamic growth radiography experiments have confirmed that ablation front instability growth is being modeled fairly well in NIF experiments. It is timely then to combine these two results and ask how current ignition pulse shapes could be modified to improve one-dimensional implosion performance while maintaining the stability properties demonstrated with the high foot. This paper presents such a survey of pulse shapes intermediate between the low and high foot extremes in search of an intermediate foot optimum. Of the design space surveyed, it is found that a higher picket version of the low foot pulse shape shows the most promise for improved compression without loss of stability.

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B. J. MacGowan

Lawrence Livermore National Laboratory

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Richard A. London

Lawrence Livermore National Laboratory

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Alice Koniges

Lawrence Berkeley National Laboratory

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Dennis L. Matthews

Lawrence Livermore National Laboratory

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D. E. Hinkel

Lawrence Livermore National Laboratory

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O. L. Landen

Lawrence Livermore National Laboratory

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O. S. Jones

Lawrence Livermore National Laboratory

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M. B. Schneider

Lawrence Livermore National Laboratory

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E. L. Dewald

Lawrence Livermore National Laboratory

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Peter A. Amendt

Lawrence Livermore National Laboratory

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