Search NASA⌕ Search

SEARCH · Search NASA

Results for “IMPLOSIONS”

Search indexed NASA NTRS and DOE OSTI research on propulsion, heat transfer, battery materials and energy systems. Follow report and document links to the original sources.

Quote a phrase for an exact phrase match. Source license links do not imply unrestricted reuse.

At least 1,351 records · Page 75
All sourcesNASA NTRSDOE OSTI
DOE OSTI2017

Materials Selection for Heavy Ion Fusion Hohlraums

The hohlraum surrounds the fuel capsule in a heavy ion fusion (HIF) target. The hohlraum absorbs ion beam driver energy and emits this energy uniformly around the capsule in the form of X-rays. High-atomic-number materials are necessary in the walls of the hohlraum to contain the X-ray energy around the capsule during the implosion process. These high-atomic-number hohlraum materials affect many aspects of an HIF power plant operation. A systematic review of available information for all high-atomic-number elements was conducted to select candidate hohlraum materials. The effects of materials on target fabrication, energy cost, target gain, radioactivity, chemical toxicity, and potential for recycle were considered. Lead and tungsten are the lowest-cost acceptable materials in the primary coolant. The combination of lead and tungsten provide better target gain than either material alone. Seeding the primary coolant with submicron-sized tungsten particles can minimize tungsten growth in small openings in power plant components such as vacuum tritium disengagers. In conclusion, concerns remain for possible tungsten particle agglomeration, settling, or erosion caused by tungsten particles. Tungsten could be replaced by several lanthanide elements if tungsten proves unacceptable.

70 PLASMA PHYSICS AND FUSION TECHNOLOGY↗
DOE OSTI2016

Technique for Forming Solid D2 and D-T Layers for Shock Timing Experiments at the National Ignition Facility

Capsule implosion experiments on the National Ignition Facility (NIF) are driven with a carefully tailored laser pulse that delivers a sequence of shocks to the ablator and fuel. In order to ensure the shocks converge at the desired position, the shock strength and velocity are measured in experimental platforms referred to as keyhole targets. We made shock measurements on capsules completely filled with liquid deuterium for the solid deuterium tritide (D-T) layer campaigns. Modeling has been used to extend these results to form an estimate of the shock properties in solid D-T layers. Furthermore, to verify and improve the surrogacy of the liquid-filled keyhole measurements, we have developed a technique to form a solid layer inside the keyhole capsule. The layer is typically uniform over a 400-μm-diameter area. This is sufficient to allow direct measurement of the shock velocity. This layering technique has been successfully applied to 13 experiments on the NIF. The technique may also be applicable to fast-igniter experiments since some proposed designs resemble keyhole targets. We discuss our method in detail and give representative results.

42 ENGINEERING↗
DOE OSTI2017

Quantitative Defect Analysis of Ablator Capsule Surfaces Using a Leica Confocal Microscope and a High-Density Atomic Force Microscope

High-density carbon (HDC) is being evaluated as an alternative to the current National Ignition Facility (NIF) point-design ablator material (glow discharge plasma, or GDP, plastic) due to its high density and optimal opacity, which leads to a higher implosion velocity. Chemical-vapor-deposition-coated HDC capsules have a near perfect surface figure but a microscopically rough surface. After polishing, the surface becomes smooth at nanometer scales but has numerous micron-sized surface pits, whose volumes, morphology, and distribution must be quantified to guide NIF target selection. Traditional metrology tools for GDP surface defects, such as the atomic force microscope (AFM) based Spheremapper and a phase-shifting differential interferometer, lack the resolution to characterize these localized features. In this paper, we describe how this metrology challenge is met by developing automated surface metrology solutions based on a high-density (HD) AFM and a Leica confocal microscope. Furthermore, these tools are complementary in nature. HD-AFM has a 0.1-μm spatial resolution and determines the overall shape distortion and pit statistics by tracing great circles on a capsule with high throughput.

36 MATERIALS SCIENCE↗
DOE OSTI2020

Optical characterization of the on-target OMEGA focal spot at high energy using the full-beam in-tank diagnostic

The full-beam in-tank (FBIT) diagnostic has been deployed to directly measure the target-plane beam fluence profile, when operated at high energy, of the OMEGA Laser System at the University of Rochester’s Laboratory for Laser Energetics. This article presents the results of early measurements taken with this diagnostic and discusses an improvement that has overcome performance limitations discovered during the initial testing. The diagnostic gives new insight into the ability of the OMEGA Laser System to provide uniform fluence profiles that are consistent across all 60 beams in the laser. Overall, the ultimate goal of the FBIT diagnostic is to allow accurate assessment of the fluence uniformity on a spherical target in 60-beam implosion experiments

47 OTHER INSTRUMENTATION↗
DOE OSTI2022

Design of proton deflectometry with in situ x-ray fiducial for magnetized high-energy-density systems

We report a design and implementation of proton deflectometry with an in situ reference x-ray image of a mesh to precisely measure non-uniform magnetic fields in expanding plasmas at the OMEGA and OMEGA EP laser facilities. The technique has been developed with proton and x-ray sources generated from both directly driven capsule implosions and short pulse laser–solid interactions. The accuracy of the measurement depends on the contrast of both the proton and x-ray images. Here we present numerical and analytic studies to optimize the image contrast using a variety of mesh materials and grid spacings. Our results show clear enhancement of the image contrast by factors of four to six using a high Z mesh with large grid spacing. This leads to further improvement in the accuracy of the magnetic field measurement using this technique in comparison with its first demonstration at the OMEGA laser facility [Rev. Sci. Instrum. 93, 023502 (2022) [CrossRef]].

47 OTHER INSTRUMENTATION↗
DOE OSTI2017

Simplified model of pinhole imaging for quantifying systematic errors in image shape

In this paper, we examine systematic errors in x-ray imaging by pinhole optics for quantifying uncertainties in the measurement of convergence and asymmetry in inertial confinement fusion implosions. We present a quantitative model for the total resolution of a pinhole optic with an imaging detector that more effectively describes the effect of diffraction than models that treat geometry and diffraction as independent. This model can be used to predict loss of shape detail due to imaging across the transition from geometric to diffractive optics. We find that fractional error in observable shapes is proportional to the total resolution element we present and inversely proportional to the length scale of the asymmetry being observed. Finally, we have experimentally validated our results by imaging a single object with differently sized pinholes and with different magnifications.

70 PLASMA PHYSICS AND FUSION TECHNOLOGY↗
DOE OSTI2026

Fabrication of freeform potassium dihydrogen phosphate crystals by belt-on-wheel polishing for spatially tailored polarization control in high-power lasers

Large-aperture (>30 cm) optical components that provide spatially tailored control of the properties of a laser beam, such as phase, polarization, and amplitude, have been the focus of much research and development in recent years. Such optics can improve energy throughput and target implosion efficiency in high-power laser systems conducting inertial confinement fusion research. Here, a method is demonstrated for fabricating freeform surface topographies into the birefringent crystalline material, potassium dihydrogen phosphate (KDP). Belt-on-wheel polishing with an oil-based fluid, developed to mitigate the deliquescent properties of KDP, is used to deterministically polish a freeform topography into KDP, enabling the fabrication of a wave plate with spatially arbitrary retardance. Testing of the laser-induced damage threshold of belt-on-wheel polished KDP was conducted at a wavelength of 351 nm and a pulse duration of 1 ns. The results revealed that the polished surfaces are highly resistant to laser-induced damage, making them suitable for large-aperture, high-power laser applications.

Urban, Nathaniel D. [Univ. of Rochester, NY (Unite↗
DOE OSTI2017

Interaction of doughnut-shaped laser pulses with glasses

Non-Gaussian laser beams can open new opportunities for microfabrication, including ultrashort laser direct writing. By using a model based on Maxwell’s equations, we investigate the dynamics of doughnut-shaped laser beams focused inside fused silica glass, in comparison with Gaussian pulses of the same energy. The laser propagation dynamics reveals intriguing features of beam splitting and sudden collapse toward the beam axis, overcoming the intensity clamping effect. The resulting structure of light absorption represents a very hot, hollow nanocylinder, which can lead to an implosion process that brings matter to extreme thermodynamic states. Furthermore, by monitoring the simulations of the laser beam scattering we see a considerable difference in both the blueshift and the angular distribution of scattered light for different laser energies, suggesting that investigations of the spectra of scattered radiation can be used as a diagnostic of laser-produced electron plasmas in transparent materials.

42 ENGINEERING↗
DOE OSTI2025

Impact of increased smoothing by spectral dispersion bandwidth on stimulated Brillouin scattering in laser driven Hohlraums

Experiments were conducted at the National Ignition Facility (NIF) to investigate the impact of increased smoothing by spectral dispersion (SSD) bandwidth on the production of stimulated Brillouin scattering (SBS) within an indirect-drive inertial confinement fusion (ICF) Hohlraum. This was done in a subscale gold Hohlraum driven by 192 laser beams depositing 1.1 MJ of energy. The laser bandwidth was increased from 45 to 118 GHz (before frequency tripling) on the 30° and 50° cones, where backscatter could be measured using the Full Aperture Backscatter Station (FABS). It was expected that this 2.6-fold increase in bandwidth would suppress SBS generated within the Hohlraum plasma and lower the backscattered SBS energy on the 50° cones by over a factor of four. Experimental results, however, show that this SSD change only reduced the 50° cone SBS during the main capsule drive by -18±31% and -4.5±7.8% over the entire pulse. This is small compared to expected shot-to-shot SBS reproducibility (∼30%), such that the result can be considered within normal performance fluctuations. New 3D parallel paraxial code (pF3D) simulations, accounting for beam refractive intensification reproduce this result, suggesting that closer to 300 GHz of bandwidth would have been required to mitigate SBS to the expected level. Delivering such a high bandwidth is not feasible at NIF when operating at high peak power and would potentially prevent NIF’s ability to use cross-beam energy transfer (CBET) for implosion symmetry tuning.

Physics↗
DOE OSTI2018

Moment Tensor Source-Type Analysis for the Democratic People's Republic of Korea-Declared Nuclear Explosions (2006-2017) and 3 September 2017 Collapse Event

The Democratic People's Republic of Korea (DPRK) conducted its sixth announced nuclear test on 3 September 2017 03:30 UTC (mb 6.1). There was an aftershock 8.5 min later (mb 4.1). Such aftershocks were noteworthy and often associated with post–nuclear explosion collapses. We performed moment tensor (MT) and network sensitivity solution (NSS) analysis using regional long-period surface-wave and first-motion (FM) polarities. We also extended this analysis to the previous five DPRK nuclear tests. The NSS results, which include MT solution uncertainties, show large isotropic components for the events and are within the population of other U.S. nuclear and collapse events on the fundamental lune. The FM data improved the NNS source-type resolution. The agreement between MT seismic moments and independent coda-envelope amplitudes indicated no biases with the Earth model error or poorly constrained seismic moment for shallow seismic sources. The MT for the collapse is not a pure implosion and consistent with an equivalent tensional closing crack mechanism and two-sided vertical point force.

58 GEOSCIENCES↗
DOE OSTI2013

A study of fluid-structure interaction on overlapping grids with a focus on flexible beams

Fluid-structure interaction problems appear in many areas of science and engineering. Adequately understanding these problems is crucial to the study of such disciplines as aeroelastic flutter, wind turbine performance, implosions and explosions, and hemodynamics, to name a few. One technique to explore these problems is the use of numerical simulations. Although methods for the accurate and efficient numerical simulation of many problems involving only flexible structures or those involving only fluids have existed for a long time, the simulation of coupled problems, in which a flexible structure (or structures) interact with fluids remains challenging. The source of the difficulty with these problems is the construction of schemes for the coupling between the fluid and the solid that are both accurate and stable. There are two general approaches to designing a coupling procedure. In the first, the so-called monolithic approach, a single solver is implemented that handles both the fluid equations and the solid equations in a single framework. In this scheme, the solver handles the fluid and solid equations simultaneously, resulting in a strong coupling between the two. The second approach, named the partitioned approach, handles the fluid and structure domains separately. Whereas in the monolithic scheme there is a single solver for both the fluid and the structure, in the partitioned scheme there are separate solvers for the fluid and the structure. This separation heavily restricts the communication and coordination that can occur between the two solvers. Typically the only communication done in these schemes is through the application of boundary conditions (where the fluid applies a boundary condition on the fluid, and the solid one (or more) on the fluid). This makes the implementation of partitioned schemes easy, especially because they can take advantage of existing algorithms and software developed for the simulation of fluid flow or computational mechanics. However, they have a weakness – accuracy and stability are much harder to achieve. Stability is a particular problem for these schemes, as they are prone to the so-called added-mass effect.

97 MATHEMATICS AND COMPUTING↗
DOE OSTI2013

Studies of Dynamic, Radiative Macroscopic Magnetized HED Plasmas with Closed B-Field Lines

The purpose of this research has been to study the physics of macroscopic magnetized high-energy-density laboratory plasmas (HEDLPs) created through the compression of a high-beta compact toroid (CT) plasma having closed magnetic field lines. The high-beta CT chosen for this work is a field-reversed configuration (FRC). The basic approach is to investigate CT plasmas as they are compressed to a HED state by the electromagnetic implosion of a surrounding metallic shell or solid liner (Figure 1). The shell provides an axisymmetric, electrically-conducting boundary around the plasma and its supporting magnetic field and is imploded by means of the magnetic pressure force arising from axial current flow in the liner interacting with its associated azimuthal magnetic field. Compression of the CT will bring the plasma to fusion temperatures at higher densities and magnetic fields (multi-MegaGauss [MG]) than have previously been present in conventional magnetic fusion approaches. The resulting energy densities will be ~1 Mbar or greater and thus will place the plasma in a parameter space intermediate to MFE and IFE. This work has been a collaboration between the Air Force Research Laboratory, Los Alamos National Laboratory, and NumerEx, LLC.

70 PLASMA PHYSICS AND FUSION TECHNOLOGY↗
DOE OSTI2014

Development of Eulerian Code Modeling for ICF Experiments

One of the most pressing unexplained phenomena standing in the way of ICF ignition is understanding mix and how it interacts with burn. Experiments were being designed and fielded as part of the Defect-Induced Mix Experiment (DIME) project to obtain data about the extent of material mix and how this mix influenced burn. Experiments on the Omega laser and National Ignition Facility (NIF) provided detailed data for comparison to the Eulerian code RAGE1. The Omega experiments were able to resolve the mix and provide “proof of principle” support for subsequent NIF experiments, which were fielded from July 2012 through June 2013. The Omega shots were fired at least once per year between 2009 and 2012. RAGE was not originally designed to model inertial confinement fusion (ICF) implosions. It still lacks lasers, so the code has been validated using an energy source. To test RAGE, the simulation output is compared to data and by means of postprocessing tools that were developed. Here, the various postprocessing tools are described with illustrative examples.

70 PLASMA PHYSICS AND FUSION TECHNOLOGY↗
DOE OSTI2014

Solid Radiochemistry Nuclear Diagnostic Results from Exploding Pusher Shot (N130503-002) at the National Ignition Facility

The Solid Radiochemistry (SRC) nuclear diagnostic platform has been developed for the assessment of various performance parameters, such as areal fuel density and ablator-fuel mixing, associated with the capsule implosion of DT-fuel, hohlraum based shots at the National Ignition Facility (NIF). This diagnostic is based on the collection and characterization of debris from the capsule and surrounding materials (primarily gold from the hohlraum). SRC utilizes two diagnostic instrument manipulators (DIMs), 90-78 and 0-0, to field debris collectors (maximum of four metallic and/or graphite foils per DIM) inside the NIF chamber during shots. The debris collectors are removed after a shot and transferred to the Nuclear Counting Facility (NCF) for the measurement of gold activation (Au-196m and Au-196) and capture (Au-198) products via gamma spectroscopy. The results from SRC which show a strong dependency on an independently measured neutron down scatter ratio (DSR) are utilized as part of a 1-D capsule model to determine the areal densities (ρR(DT) and ρR(CH)) during burn. This report summarizes the SRC results from the Indirect Drive Exploding Pusher shot (N130503-002) designed to produce low ρR at burn time (~40 mg/cm 2 ) leading to a significant decrease in DSR (0.23±0.07 %). As a result, this shot is considered a calibration shot for SRC nuclear diagnostic.

38 RADIATION CHEMISTRY, RADIOCHEMISTRY, AND NUCLEA↗
DOE OSTI2015

Damaged Surface Hydrodynamics (DSH) Flash Report

In an effort to understand the complex hydrodynamic flow present when a non-ideal (or damaged) surface between a dense, solid-state metal impinges on a light, gas in converging geometry, two DSH experiments have been conducted at the LANL LANSCE pRad facility utilizing magnetic drive from the Precision High Energy-density Liner Implosion eXperiment (PHELIX) pulsed power capacitor bank. Here a tungsten power coated target aluminum cylinder was filled with inert gas (Ar/Xe). An outer aluminum cylinder is magnetically accelerated and impacts the target shock launching the powder into the gas and compressing the cylinder until such time as the increase in gas pressure causes stagnation. Each experiment is imaged with a 21-frame proton radiography movie where gas shocks, powder distribution, and target cylinder are clearly visible. These two experiments complement the DSH-0 experiment from FY14 where the target cylinder was evacuated as a control case.

70 PLASMA PHYSICS AND FUSION TECHNOLOGY↗
DOE OSTI2014

Generalized Uncertainty Quantification for Linear Inverse Problems in X-ray Imaging

In industrial and engineering applications, X-ray radiography has attained wide use as a data collection protocol for the assessment of material properties in cases where direct observation is not possible. The direct measurement of nuclear materials, particularly when they are under explosive or implosive loading, is not feasible, and radiography can serve as a useful tool for obtaining indirect measurements. In such experiments, high energy X-rays are pulsed through a scene containing material of interest, and a detector records a radiograph by measuring the radiation that is not attenuated in the scene. One approach to the analysis of these radiographs is to model the imaging system as an operator that acts upon the object being imaged to produce a radiograph. In this model, the goal is to solve an inverse problem to reconstruct the values of interest in the object, which are typically material properties such as density or areal density. The primary objective in this work is to provide quantitative solutions with uncertainty estimates for three separate applications in X-ray radiography: deconvolution, Abel inversion, and radiation spot shape reconstruction. For each problem, we introduce a new hierarchical Bayesian model for determining a posterior distribution on the unknowns and develop efficient Markov chain Monte Carlo (MCMC) methods for sampling from the posterior. A Poisson likelihood, based on a noise model for photon counts at the detector, is combined with a prior tailored to each application: an edge-localizing prior for deconvolution; a smoothing prior with non-negativity constraints for spot reconstruction; and a full covariance sampling prior based on a Wishart hyperprior for Abel inversion. After developing our methods in a general setting, we demonstrate each model on both synthetically generated datasets, including those from a well known radiation transport code, and real high energy radiographs taken at two U. S. Department of Energy laboratories.

46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗
DOE OSTI2015

Research Challenges in Magneto-Inertial Fusion

Inertial Confinement Fusion (ICF) is a grand challenge for high-energy-density science. In traditional ICF, alpha heating is achieved by producing T ~ 4 keV hot spot surrounded by a high areal density (ρR ~1 g/cm 2 ) of cold fuel, requiring hot-spot pressures above 400 Gbar. In Magneto-Inertial Fusion (MIF), the pressure and areal density requirements are relaxed by the presence of a magnetic field strong enough to magnetically confine charged particles within a radius smaller than the fuel radius. The key parameter for MIF is thus BR rather than ρR, and for BR >0.5 MG-cm, the magnetic field effectively traps electrons, 1 MeV tritons, and fusion-produced alpha particles for almost arbitrarily small ρR. Consequently, thermal conduction losses are reduced and trapped alpha particles return much of their energy to the burning plasma. Operating at intermediate plasma density and pressure regimes between traditional magnetic confinement fusion and ICF systems, MIF concepts achieve self-heating at pressures of only ~5 Gbar, with GJ-scale yields appearing possible. Ongoing experiments demonstrate good inertial and magnetic confinement, stable implosions, and promising yields, but challenges remain in optimizing preheat, mitigating mix, and understanding fundamental plasma physics and magneto-hydrodynamic behavior in these extreme conditions.

70 PLASMA PHYSICS AND FUSION TECHNOLOGY↗