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Dive into the research topics where D. E. Hinkel is active.

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Featured researches published by D. E. Hinkel.


Nature | 2014

Fuel gain exceeding unity in an inertially confined fusion implosion

O. A. Hurricane; D. A. Callahan; D. T. Casey; Peter M. Celliers; C. Cerjan; E. L. Dewald; T. R. Dittrich; T. Döppner; D. E. Hinkel; L. Berzak Hopkins; J. L. Kline; S. Le Pape; T. Ma; A. G. MacPhee; J. L. Milovich; A. Pak; H.-S. Park; P. K. Patel; B. A. Remington; J. D. Salmonson; P. T. Springer; R. Tommasini

Ignition is needed to make fusion energy a viable alternative energy source, but has yet to be achieved. A key step on the way to ignition is to have the energy generated through fusion reactions in an inertially confined fusion plasma exceed the amount of energy deposited into the deuterium–tritium fusion fuel and hotspot during the implosion process, resulting in a fuel gain greater than unity. Here we report the achievement of fusion fuel gains exceeding unity on the US National Ignition Facility using a ‘high-foot’ implosion method, which is a manipulation of the laser pulse shape in a way that reduces instability in the implosion. These experiments show an order-of-magnitude improvement in yield performance over past deuterium–tritium implosion experiments. We also see a significant contribution to the yield from α-particle self-heating and evidence for the ‘bootstrapping’ required to accelerate the deuterium–tritium fusion burn to eventually ‘run away’ and ignite.


Physics of Plasmas | 2011

Point design targets, specifications, and requirements for the 2010 ignition campaign on the National Ignition Facility

S. W. Haan; J. D. Lindl; D. A. Callahan; D. S. Clark; J. D. Salmonson; B. A. Hammel; L. J. Atherton; R. Cook; M. J. Edwards; S. H. Glenzer; Alex V. Hamza; S. P. Hatchett; Mark Herrmann; D. E. Hinkel; D. Ho; H. Huang; O. S. Jones; J. L. Kline; G. A. Kyrala; O. L. Landen; B. J. MacGowan; M. M. Marinak; D. D. Meyerhofer; J. L. Milovich; K. A. Moreno; E. I. Moses; David H. Munro; A. Nikroo; R. E. Olson; Kyle Peterson

Point design targets have been specified for the initial ignition campaign on the National Ignition Facility [G. H. Miller, E. I. Moses, and C. R. Wuest, Opt. Eng. 443, 2841 (2004)]. The targets contain D-T fusion fuel in an ablator of either CH with Ge doping, or Be with Cu. These shells are imploded in a U or Au hohlraum with a peak radiation temperature set between 270 and 300 eV. Considerations determining the point design include laser-plasma interactions, hydrodynamic instabilities, laser operations, and target fabrication. Simulations were used to evaluate choices, and to define requirements and specifications. Simulation techniques and their experimental validation are summarized. Simulations were used to estimate the sensitivity of target performance to uncertainties and variations in experimental conditions. A formalism is described that evaluates margin for ignition, summarized in a parameter the Ignition Threshold Factor (ITF). Uncertainty and shot-to-shot variability in ITF are evaluated, and...


Physics of Plasmas | 1998

Hot electron production and heating by hot electrons in fast ignitor research

M.H. Key; M. D. Cable; Thomas E. Cowan; K. G. Estabrook; B. A. Hammel; S. P. Hatchett; E. A. Henry; D. E. Hinkel; J. D. Kilkenny; J. A. Koch; W. L. Kruer; A. B. Langdon; Barbara F. Lasinski; R.W. Lee; B. J. MacGowan; A. J. Mackinnon; J. D. Moody; M. J. Moran; A. A. Offenberger; Deanna M. Pennington; M. D. Perry; T. J. Phillips; Thomas C. Sangster; M. Singh; M. A. Stoyer; Max Tabak; G. L. Tietbohl; M. Tsukamoto; Kenneth Bradford Wharton; S. C. Wilks

In an experimental study of the physics of fast ignition the characteristics of the hot electron source at laser intensities up to 10(to the 20th power) Wcm{sup -2} and the heating produced at depth by hot electrons have been measured. Efficient generation of hot electrons but less than the anticipated heating have been observed.


Science | 2010

Symmetric Inertial Confinement Fusion Implosions at Ultra-High Laser Energies

S. H. Glenzer; B. J. MacGowan; P. Michel; N. B. Meezan; L. J. Suter; S. Dixit; J. L. Kline; G. A. Kyrala; D. K. Bradley; D. A. Callahan; E. L. Dewald; L. Divol; E. G. Dzenitis; M. J. Edwards; Alex V. Hamza; C. A. Haynam; D. E. Hinkel; D. H. Kalantar; J. D. Kilkenny; O. L. Landen; J. D. Lindl; S. LePape; J. D. Moody; A. Nikroo; T. Parham; M. B. Schneider; R. P. J. Town; Paul J. Wegner; K. Widmann; Pamela K. Whitman

Ignition Set to Go One aim of the National Ignition Facility is to implode a capsule containing a deuterium-tritium fuel mix and initiate a fusion reaction. With 192 intense laser beams focused into a centimeter-scale cavity, a major challenge has been to create a symmetric implosion and the necessary temperatures within the cavity for ignition to be realized (see the Perspective by Norreys). Glenzer et al. (p. 1228, published online 28 January) now show that these conditions can be met, paving the way for the next step of igniting a fuel-filled capsule. Furthermore, Li et al. (p. 1231, published online 28 January) show how charged particles can be used to characterize and measure the conditions within the imploding capsule. The high energies and temperature realized can also be used to model astrophysical and other extreme energy processes in a laboratory settings. Laser-driven temperatures and implosion symmetry are close to the requirements for inertial-fusion ignition. Indirect-drive hohlraum experiments at the National Ignition Facility have demonstrated symmetric capsule implosions at unprecedented laser drive energies of 0.7 megajoule. One hundred and ninety-two simultaneously fired laser beams heat ignition-emulate hohlraums to radiation temperatures of 3.3 million kelvin, compressing 1.8-millimeter-diameter capsules by the soft x-rays produced by the hohlraum. Self-generated plasma optics gratings on either end of the hohlraum tune the laser power distribution in the hohlraum, which produces a symmetric x-ray drive as inferred from the shape of the capsule self-emission. These experiments indicate that the conditions are suitable for compressing deuterium-tritium–filled capsules, with the goal of achieving burning fusion plasmas and energy gain in the laboratory.


Physics of Plasmas | 2010

Symmetry tuning via controlled crossed-beam energy transfer on the National Ignition Facilitya)

P. Michel; S. H. Glenzer; L. Divol; David K. Bradley; D. A. Callahan; S. Dixit; S. Glenn; D. E. Hinkel; R. K. Kirkwood; J. L. Kline; W. L. Kruer; G. A. Kyrala; S. Le Pape; N. B. Meezan; R. P. J. Town; K. Widmann; E. A. Williams; B. J. MacGowan; J. D. Lindl; L. Suter

The Hohlraum energetics experimental campaign started in the summer of 2009 on the National Ignition Facility (NIF) [E. I. Moses et al., Phys. Plasmas 16, 041006 (2009)]. These experiments showed good coupling of the laser energy into the targets [N. Meezan et al., Phys. Plasmas 17, 056304 (2010)]. They have also demonstrated controlled crossed-beam energy transfer between laser beams as an efficient and robust tool to tune the implosion symmetry of ignition capsules, as predicted by earlier calculations [P. Michel et al., Phys. Rev. Lett. 102, 025004 (2009)]. A new linear model calculating crossed-beam energy transfer between cones of beams on the NIF has been developed. The model has been applied to the subscale Hohlraum targets shot during the National Ignition Campaign in 2009. A good agreement can be found between the calculations and the experiments when the impaired propagation of the laser beams due to backscatter is accounted for.


Physics of Plasmas | 1999

Review of indirect-drive ignition design options for the National Ignition Facility

T. R. Dittrich; S. W. Haan; M. M. Marinak; Stephen M. Pollaine; D. E. Hinkel; D. H. Munro; C. P. Verdon; George L. Strobel; R. McEachern; R. Cook; C.C. Roberts; D. C. Wilson; P. A. Bradley; Larry R. Foreman; William S. Varnum

Several inertial confinement fusion (ICF) capsule designs have been proposed as possible candidates for achieving ignition by indirect drive on the National Ignition Facility (NIF) laser [Paisner et al., Laser Focus World 30, 75 (1994)]. This article reviews these designs, their predicted performance using one-, two-, and three-dimensional numerical simulations, and their fabricability. Recent design work at a peak x-ray drive temperature of 250 eV with either 900 or 1300 kJ total laser energy confirms earlier capsule performance estimates [Lindl, Phys. Plasmas 2, 3933 (1995)] that were based on hydrodynamic stability arguments. These simulations at 250 eV and others at the nominal 300 eV drive show that capsules having either copper doped beryllium (Be+Cu) or polyimide (C22H10N2O4) ablators have favorable implosion stability and material fabrication properties. Prototypes of capsules using these ablator materials are being constructed using several techniques: brazing together machined hemishells (Be+Cu)...


Physics of Plasmas | 1996

Laser–plasma interactions in ignition‐scale hohlraum plasmas

B. J. MacGowan; Bedros Afeyan; C. A. Back; R. L. Berger; G. Bonnaud; M. Casanova; Bruce I. Cohen; D. E. Desenne; D. F. DuBois; A. G. Dulieu; K. G. Estabrook; J. C. Fernandez; S. H. Glenzer; D. E. Hinkel; T. B. Kaiser; D. H. Kalantar; R. L. Kauffman; R. K. Kirkwood; W. L. Kruer; A. B. Langdon; Barbara F. Lasinski; D. S. Montgomery; John Moody; David H. Munro; L. V. Powers; H. A. Rose; C. Rousseaux; R. E. Turner; B. H. Wilde; S. C. Wilks

Scattering of laser light by stimulated Brillouin scattering (SBS) and stimulated Raman scattering (SRS) is a concern for indirect drive inertial confinement fusion (ICF). The hohlraum designs for the National Ignition Facility (NIF) raise particular concerns due to the large scale and homogeneity of the plasmas within them. Experiments at Nova have studied laser–plasma interactions within large scale length plasmas that mimic many of the characteristics of the NIF hohlraum plasmas. Filamentation and scattering of laser light by SBS and SRS have been investigated as a function of beam smoothing and plasma conditions. Narrowly collimated SRS backscatter has been observed from low density, low‐Z, plasmas, which are representative of the plasma filling most of the NIF hohlraum. SBS backscatter is found to occur in the high‐Z plasma of gold ablated from the wall. Both SBS and SRS are observed to be at acceptable levels in experiments using smoothing by spectral dispersion (SSD).


Physics of Plasmas | 2014

The high-foot implosion campaign on the National Ignition Facilitya)

O. A. Hurricane; D. A. Callahan; D. T. Casey; E. L. Dewald; T. R. Dittrich; T. Döppner; M. A. Barrios Garcia; D. E. Hinkel; L. Berzak Hopkins; P. Kervin; J. L. Kline; S. Le Pape; T. Ma; A. G. MacPhee; J. L. Milovich; J. D. Moody; A. Pak; P. K. Patel; H.-S. Park; B. A. Remington; H. F. Robey; J. D. Salmonson; P. T. Springer; R. Tommasini; L. R. Benedetti; J. A. Caggiano; Peter M. Celliers; C. Cerjan; Rebecca Dylla-Spears; D. H. Edgell

The “High-Foot” platform manipulates the laser pulse-shape coming from the National Ignition Facility laser to create an indirect drive 3-shock implosion that is significantly more robust against instability growth involving the ablator and also modestly reduces implosion convergence ratio. This strategy gives up on theoretical high-gain in an inertial confinement fusion implosion in order to obtain better control of the implosion and bring experimental performance in-line with calculated performance, yet keeps the absolute capsule performance relatively high. In this paper, we will cover the various experimental and theoretical motivations for the high-foot drive as well as cover the experimental results that have come out of the high-foot experimental campaign. At the time of this writing, the high-foot implosion has demonstrated record total deuterium-tritium yields (9.3×1015) with low levels of inferred mix, excellent agreement with implosion simulations, fuel energy gains exceeding unity, and evidenc...


Physics of Plasmas | 2010

National Ignition Campaign Hohlraum energetics

N. B. Meezan; L. J. Atherton; D. A. Callahan; E. L. Dewald; S. Dixit; E. G. Dzenitis; M. J. Edwards; C. A. Haynam; D. E. Hinkel; O. S. Jones; O. L. Landen; Richard A. London; P. Michel; J. D. Moody; J. L. Milovich; M. B. Schneider; C. A. Thomas; R. P. J. Town; A. Warrick; S. V. Weber; K. Widmann; S. H. Glenzer; L. J. Suter; B. J. MacGowan; J. L. Kline; George A. Kyrala; A. Nikroo

The first series of experiments of the National Ignition Facility (NIF) [E. I. Moses et al., Phys. Plasmas 16, 041006 (2009)] tested ignition Hohlraum “energetics,” a term described by four broad goals: (1) measurement of laser absorption by the Hohlraum; (2) measurement of the x-ray radiation flux (TRAD4) on the surrogate ignition capsule; (3) quantitative understanding of the laser absorption and resultant x-ray flux; and (4) determining whether initial Hohlraum performance is consistent with requirements for ignition. This paper summarizes the status of NIF Hohlraum energetics experiments. The Hohlraum targets and experimental design are described, as well as the results of the initial experiments. The data demonstrate low backscattered energy (<10%) for Hohlraums filled with helium gas. A discussion of our current understanding of NIF Hohlraum x-ray drive follows, including an overview of the computational tools, i.e., radiation-hydrodynamics codes that have been used to design the Hohlraums. The perf...


Physics of Plasmas | 2002

Indirect-Drive Noncryogenic Double-Shell Ignition Targets for the National Ignition Facility: Design and Analysis

Peter A. Amendt; Jeffrey D. Colvin; Robert Tipton; D. E. Hinkel; M. J. Edwards; O. L. Landen; John D. Ramshaw; L. J. Suter; W. S. Varnum; R. G. Watt

The central goal of the National Ignition Facility (NIF) is demonstration of controlled thermonuclear ignition. The mainline ignition target is a low-Z, single-shell cryogenic capsule designed to have weakly nonlinear Rayleigh-Taylor growth of surface perturbations. Double-shell targets are an alternative design concept that avoids the complexity of cryogenic preparation but has greater physics uncertainties associated with performance-degrading mix. A typical double-shell design involves a high-Z inner capsule filled with DT gas and supported within a low-Z ablator shell. The largest source of uncertainty for this target is the degree of highly evolved nonlinear mix on the inner surface of the high-Z shell. High Atwood numbers and feed-through of strong outer surface perturbation growth to the inner surface promote high levels of instability. The main challenge of the double-shell target designs is controlling the resulting nonlinear mix to levels that allow ignition to occur. Design and analysis of a suite of indirect-drive NIF double-shell targets with hohlraum temperatures of 200 eV and 250 eV are presented. Analysis of these targets includes assessment of two-dimensional radiation asymmetry as well as nonlinear mix. Two-dimensional integrated hohlraum simulations indicate that the x-ray illumination can be adjusted to provide adequate symmetry control in hohlraums specially designed to have high laser-coupling efficiency [Suter et al., Phys. Plasmas 5, 2092 (2000)]. These simulations also reveal the need to diagnose and control localized 10-15 keV x-ray emission from the high-Z hohlraum wall because of strong absorption by the high-Z inner shell. Preliminary estimates of the degree of laser backscatter from an assortment of laser-plasma interactions suggest comparatively benign hohlraum conditions. Application of a variety of nonlinear mix models and phenomenological tools, including buoyancy-drag models, multimode simulations and fall-line optimization, indicates a possibility of achieving ignition, i.e., fusion yields greater than 1 MJ. Planned experiments on the Omega laser to test current understanding of high-energy radiation flux asymmetry and mix-induced yield degradation in double-shell targets are described.

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D. A. Callahan

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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O. L. Landen

Lawrence Livermore National Laboratory

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J. D. Moody

Lawrence Livermore National Laboratory

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L. Divol

Lawrence Livermore National Laboratory

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N. B. Meezan

Lawrence Livermore National Laboratory

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P. Michel

Lawrence Livermore National Laboratory

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O. S. Jones

Lawrence Livermore National Laboratory

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J. L. Milovich

Lawrence Livermore National Laboratory

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