Bayesian inference of inaccuracies in radiation transport physics from inertial confinement fusion experiments
Abstract not provided
70 PLASMA PHYSICS AND FUSION TECHNOLOGY↗
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Spectral characterization by CVD diamond detectors of energetic protons from high-repetition rate laser for aneutronic nuclear fusion experiments
This work describes the results of experiments performed at the femtosecond ECLIPSE laser facility at CELIA in Bordeaux. Targets constituted by aluminium foils of various thicknesses were irradiated with accelerated protons with energies in the range of interest for p+ 11 B nuclear fusion. Plasma formed in the laser-target interaction were detected using high temperature high radiation resistant diamonds. Time-of-flight measurements were performed by using Chemical Vapor Deposition (CVD) monocrystalline diamonds detectors, which are specifically designed to operate in harsh environments where large ElectroMagnetic Pulses (EMPs) are generated during laser-target interaction. The 1 Hz high repetition rate used for the ECLIPSE laser allowed the collection of a large number of similar shots, giving therefore a large statistics to accurately characterize the energy spectrum of the laser-plasma accelerated protons. As a result, the laser repetitivity at a relatively small intensity permits to improve the signal-to-noise ratio of the detection of the products of low cross-section reactions, such as the p+ 11 B one, by their collection over a large number of similar shots.
46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗
Origins and Scaling of Hot-Electron Preheat in Ignition-Scale Direct-Drive Inertial Confinement Fusion Experiments
Planar laser-plasma interaction (LPI) experiments at the National Ignition Facility (NIF) have allowed access for the rst time to regimes of electron density scale length (~500 to 700 μm), electron temperature (~3 to 5 keV), and laser intensity (6 to 16 x 10 14 W/cm 2 ) that are relevant to direct-drive inertial confinement fusion ignition. Unlike in shorter-scale-length plasmas on OMEGA, scattered-light data on the NIF show that the near-quarter-critical LPI physics is dominated by stimulated Raman scattering (SRS) rather than by two-plasmon decay (TPD). This difference in regime is explained based on absolute SRS and TPD threshold considerations. SRS sidescatter tangential to density contours and other SRS mechanisms are observed. The fraction of laser energy converted to hot electrons is ~0.7% to 2.9%, consistent with observed levels of SRS. The intensity threshold for hot-electron production is assessed, and the use of a Si ablator slightly increases this threshold from ~4 x 10 14 to ~6 x 10 14 W/cm 2 . These results have significant implications for mitigation of LPI hot-electron preheat in direct-drive ignition designs.
70 PLASMA PHYSICS AND FUSION TECHNOLOGY↗
First spectral measurement of deuterium-tritium fusion γ rays in inertial fusion experiments
Here, the R-matrix analysis of A = 5 nuclear systems has been partially validated by applying the technique to the 5 Li system and comparing the predicted γ-ray spectrum with historical data. R-matrix analysis of the similar 5 He system was then used to predict the γ-ray spectral shape for the deuterium-tritium (DT) reaction. The resulting spectra have been used in the analysis of DT implosions on the Omega laser where the γ-ray interaction rate was measured by a gas Cherenkov detector. Comparison of predictions to experiment confirmed the presence of both 16.75 and ≈ 13 MeV γ-ray contributions; analysis, using R-matrix spectra, yielded a ratio of γ-ray emission from a transition to the intermediate excited state to that from a transition to the ground state of (2.1 ± 0.4):1, substantiating the first spectral measurement of the DT fusion γ ray in an inertial fusion environment.
73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗
Measurements of the temperature and velocity of the dense fuel layer in inertial confinement fusion experiments
Abstract not provided.
70 PLASMA PHYSICS AND FUSION TECHNOLOGY↗
Radiation induced noise in x-ray imagers for high-yield inertial confinement fusion experiments
Abstract not provided
46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗
Plasma-Surface Interaction Studies on DIII-D and Their Implications for Next-Step Fusion Experiments
Unique diagnostic and access features of the DIII-D tokamak, including a sample exposure system, have been used to carry out controlled and well-diagnosed plasma-surface interactions (PSI) experiments. An important contribution of the experiments has been the ability to link a given plasma exposure condition to a measured response of the plasma-facing surface and to thus understand the interaction. This has allowed for benchmarking certain aspects of erosion models, particularly near-surface particle transport. DIII-D has empirically quantified some of the PSI effects that will limit the operation availability and lifetime of future fusion devices, namely, net erosion limiting divertor plate lifetime and hydrogenic fuel retention in deposit layers. Cold divertor plasmas obtained with detachment can suppress net carbon divertor erosion, but many low-temperature divertor PSI phenomena remain poorly understood: nondivertor erosion sources, long-range particle transport, global erosion/deposition patterns, the enhancement of carbon erosion with neon impurity seeding, the sputtered carbon velocity distribution, and the apparent suppression of carbon chemical erosion in detachment. Long-term particle and energy fluences have reduced the chemical erosion yield of lower-divertor tiles. Finally, plasma-caused modification of a material’s erosion properties, including material mixing, will occur quickly and be important in long-pulse fusion devices, making prediction of PSI difficult in future devices.
70 PLASMA PHYSICS AND FUSION TECHNOLOGY↗
Hotspot mix diagnostics in Inertial Confinement Fusion experiments with the Nuclear Imaging System
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70 PLASMA PHYSICS AND FUSION TECHNOLOGY↗
Theory and measurements of convective Raman side scatter in inertial confinement fusion experiments
Raman side-scatter, whereby scattered light is resonant while propagating perpendicular to a density gradient in a plasma, was identi ed experimentally in planar-target experiments at the National Ignition Facility (NIF) at intensities orders of magnitudes below the threshold for absolute instability. We have derived a new theoretical description of convective Raman side-scatter below the absolute threshold, validated by numerical simulations. We show that ICF experiments at full ignition-scale, i.e. with mm-scale spot sizes and density scale lengths, are prone to increased coupling losses from Raman side-scatter as the instability can extend from the absolute regime near the quarter-critical density to the convective regime at lower electron densities.
70 PLASMA PHYSICS AND FUSION TECHNOLOGY↗
Performance Scaling in Magnetized Liner Inertial Fusion Experiments
Not Available
70 PLASMA PHYSICS AND FUSION TECHNOLOGY↗
Persistent Hot-Spot Mix in Cryogenic Direct-Drive Fusion Experiments
We show that an x-ray emission signature associated with acceleration phase mass injection correlates with poor experimental hot-spot convergence and a reduced neutron production relative to expectations. It is shown that with increased target mass as well as with higher-design adiabats, this signature is reduced, whereas with increased debris on the target the signature is increased. Here, we estimate that the vapor region in typical best designs may have up to 2x the assumed hydrogen mass at the start of deceleration.
70 PLASMA PHYSICS AND FUSION TECHNOLOGY↗
Foam-lined hohlraum, inertial confinement fusion experiments on the National Ignition Facility
Experiments on the National Ignition Facility (NIF) to study hohlraums lined with a 20-mg/cc 400-μm-thick Ta 2 O 5 aerogel at full scale (hohlraum diameter = 6.72 mm) are reported. Driven with a 1.6-MJ, 450-TW laser pulse, the performance of the foam liner is diagnosed using implosion hot-spot symmetry measurements of the high-density carbon (HDC) capsule and measurement of inner beam propagation through a thin-wall 8-μm Au window in the hohlraum. Results show an improved capsule performance due to laser energy deposition further inside the hohlraum, leading to a modest increase in x-ray drive and reduced preheat due to changes in the x-ray spectrum when the foam liner is included. In addition, the outer cone bubble uniformity is improved, but the predicted improvement in inner beam propagation to improve symmetry control is not realized for this foam thickness and density.
70 PLASMA PHYSICS AND FUSION TECHNOLOGY↗
Properties of vapor-deposited and solution-processed targets for laser-driven inertial confinement fusion experiments
Targets for low-adiabat direct-drive-implosion experiments on OMEGA must meet rigorous specifications and tight tolerances on the diameter, wall thickness, wall-thickness uniformity, and presence of surface features. Of these, restrictions on the size and number of defects (bumps and depressions) on the surface are the most challenging. The properties of targets that are made using vapor-deposition and solution-based microencapsulation techniques are reviewed. Targets were characterized using confocal microscopy, bright- and dark-field microscopy, atomic force microscopy, electron microscopy, and interferometry. Each technique has merits and limitations, and a combination of these techniques is necessary to adequately characterize a target. The main limitation with the glow-discharge polymerization (GDP) method for making targets is that it produces hundreds of domes with a lateral dimension of 0.7–2 μm. Polishing these targets reduces the size of some but not all domes, but it adds scratches and grooves to the surface. Solution-made polystyrene shells lack the dome features of GDP targets but have hundreds of submicrometer-size voids throughout the wall of the target; a few of these voids can be as large as ∼12 μm at the surface.
70 PLASMA PHYSICS AND FUSION TECHNOLOGY↗
The influence of hohlraum dynamics on implosion symmetry in indirect drive inertial confinement fusion experiments
High laser energy (>1.2 MJ) implosion experiments on the National Ignition Facility show that low mode implosion symmetry is highly dependent on an expanding high-Z wall “bubble” plasma feature. The bubble is caused by the early time deposition of laser beams incident on the interior near the entrance of the cylindrical hohlraum (outer cone beams). It absorbs beams designated for the waist of the hohlraum (inner cone beams) causing a redistribution of x-ray flux on the capsule. From measurements, we are able to quantify the absorption and expansion of this bubble. Measurements show that the resulting hot spot is more oblate when there is more inner beam absorption in the bubble. We also find absorption in the bubble to be between 51 ± 3% and 62 ± 2%. This bubble absorption is found to evolve predictably as a function of the early time outer cone laser pulse fluence and the pulse length. From this, a phenomenological model of the effective drive symmetry and subsequent implosion shape is found indicating a very strong dependence of implosion shape on early time laser fluence and laser pulse duration.
70 PLASMA PHYSICS AND FUSION TECHNOLOGY↗
A new aperture for neutron and x-ray imaging of inertial confinement fusion experiments
Recent neutron imaging of experiments at the National Ignition Facility has provided useful information about the hotspot shape and cold-fuel distribution and has also given insight into avenues for improvement. Neutron image reconstruction depends on accurate pointing information because the point-spread function of the neutron aperture is not shift invariant. Current pointing techniques are limited in their accuracy and rely upon detailed information about the as-built structure of the array, which is difficult to determine. We present a technique for extracting high-precision pointing information from both neutron and x-ray images, and a new aperture design with features to facilitate this technique, and allow future co-registration of neutron and x-ray images.
46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗
Design of magnetized liner inertial fusion experiments using the Z facility.
Abstract not provided.
Sefkow, Adam B↗
Spectral sensor error analysis for measuring x-ray radiation drive using the DANTE diagnostic toward inertial confinement fusion experiments
DANTE is a diagnostic used to measure the x-radiation drive produced by heating a high-Z cavity (“hohlraum”) with high-powered laser beams. It records the spectrally and temporally resolved radiation flux at x-ray energies between 50 eV and 20 keV. Each sensor configuration on DANTE is composed of filters, mirrors, and x-ray diodes to define 18 different x-ray channels whose output is voltage as a function of time. The absolute flux is then determined from the photometric calibration of the sensor configuration and a spectral reconstructing algorithm. The reconstruction of the spectra vs time from the measured voltages and known response of each channel has presented challenges. Here we demonstrate a novel approach here for quantifying the error on the determined flux based on the channel sensor configuration and most commonly used reconstruction algorithm. In general, we find that the integrated spectral flux from a hohlraum can robustly be reconstructed (within ~14%) using a traditional unfold approach with as few as ten channels due to the underlying assumption of a largely Planckian spectral intensity distribution.
47 OTHER INSTRUMENTATION↗