In this paper we discuss multiple input/multiple output (MIMO) constrained subspace identification techniques that will be evaluated when applied to the fundamental problem of identification of a dynamic structural model from noisy vibrational response measurements. The structure is a cylindrical copper pipe consisting of three (3) accelerometers positioned along its length as well as a single transducer measuring the excitation function (chirp or white noise) totaling ten (10) sensor channels (9 outputs and a single input). Here we discuss a suite of "constrained" subspace identification techniques and evaluate their performance on experimental data.

Monitoring mechanical systems operating in uncertain environments contaminated with both environmental disturbances and noise lead directly to low signal-to-noise-ratios, creating an extremely challenging processing problem, especially in real-time. In order to estimate the performance of a particular system from uncertain vibrational data, it is necessary to identify its unique resonant (modal) frequency signature. The monitoring of structural modes to determine the condition of a device under investigation is essential, especially if it is a critical entity of an operational system. The development of a model-based scheme capable of the on-line tracking of the inherent structural modal frequencies by applying both constrained subspace identification techniques to extract the modal frequencies and state estimation methods to track the evolution is discussed. An application of this approach to a cylindrical structural device (pipe-in-air) is analyzed based on theoretical simulations along with controlled validation experiments, including injected anomalies illustrate the approach and performance. Statistics are gathered to bound potential processors for real-time performance employing these constrained techniques.

In this paper we discuss the signal processing of a cylindrical object, a pipe (in air), subjected to random excitations by a hammer-like surface from a cam-driven motor. The overall objective of this effort is to develop real-time hardware capable of monitoring mechanical systems (structures) for potential anomalies. We briefly discuss the development process: (1) theoretical modeling; (2) sophisticated simulations; (3) analysis; (4) controlled experiments; (5) signal processing; (6) modal frequency estimation; and (7) modal tracking. The primary emphasis is on the signal processing, modal extraction and tracking for single and multi-channel data.

One of the scientific goals of the National Ignition Facility (NIF) at Lawrence Livermore National Laboratory, Livermore CA, is to obtain thermonuclear ignition by compressing 2.2 mm diameter capsules filed with deuterium and tritium to densities approaching 1000 g/cm(3) and temperatures in excess of 4 keV. The fusion reaction d + t -> n + alpha results in a 14.03 MeV neutron providing a source of diagnostic particles to characterize the implosion. The spectrum of neutrons emanating from the assembly may be used to infer the fusion yield, plasma ion temperature, and fuel areal density, all key diagnostic quantities of implosion quality. The neutron time-of-flight (nToF) system co-located along the Neutron Imaging System line-of-site, (NIToF), is a set of 4 scintillation detectors located approximately 27.3 m from the implosion source. Neutron spectral information is inferred using arrival time at the detector. The NIToF system is described below, including the hardware elements, calibration data, analysis methods, and an example of its basic performance characteristics.

Inertial Confinement Fusion experiments at the National Ignition Facility (NIF) are designed to understand and test the basic principles of self-sustaining fusion reactions by laser driven compression of deuterium-tritium (DT) filled cryogenic plastic (CH) capsules. The experimental campaign is ongoing to tune the implosions and characterize the burning plasma conditions. Nuclear diagnostics play an important role in measuring the characteristics of these burning plasmas, providing feedback to improve the implosion dynamics. The Neutron Imaging (NI) diagnostic provides information on the distribution of the central fusion reaction region and the surrounding DT fuel by collecting images at two different energy bands for primary (13-15 MeV) and downscattered (10-12 MeV) neutrons. From these distributions, the final shape and size of the compressed capsule can be estimated and the symmetry of the compression can be inferred. The first downscattered neutron images from imploding ICF capsules are shown in this paper.

Directly laser driven and X-radiation driven DT filled capsules differ in the relationship between neutron and X-ray images. Shot N110217, a directly driven DT-filled glass micro-balloon provided the first neutron images at the National Ignition Facility. As seen in implosions on the Omega laser, the neutron image can be enclosed inside time integrated X-ray images. HYDRA simulations show the X-ray image is dominated by emission from the hot glass shell while the neutron image arises from the DT fuel it encloses. In the absence of mix or jetting, X-ray images of a cryogenically layered THD fuel capsule should be dominated by emission from the hydrogen rather than the cooler plastic shell that is separated from the hot core by cold DT fuel. This cool, dense DT, invisible in X-ray emission, shows itself by scattering hot core neutrons. Germanium X-ray emission spectra and Ross pair filtered X-ray energy resolved images suggest that germanium doped plastic emits in the torus shaped hot spot, probably reducing the neutron yield.

Summary form only given. We have installed the National Ignition Facility Neutron Imaging System. The imaging system provides information about the areal density of fuel in the various regions of the capsule implosion. A long line of sight enables imaging both the primary 14 MeV neutrons as well as the down-scattered neutrons with energies in the range of 9-12 MeV. The imager is a pinhole camera where the pinhole is located 325 mm from the target and the imaging plane is located 28 m from the target. The long absorption length of neutrons requires precise alignment of these extended imager components in order to have high detection efficiency and strong background rejection. The imaging plane is a 150 mm square scintillating fiber bundle 50 mm thick. The bundle consists of 250 μm square fibers. The fiber bundle is aligned such that the fibers point at the target. The pointing is accomplished using a retro reflection of a laser alignment device aligned to the imager line of sight. The 200 mm long pinhole is aligned to the imager line of sight using the Opposed Port Alignment System. The imager line of sight was registered to the alignment system to calculate the precise position of the pinhole. The ability of the positioning manipulator to both place and maintain the precise location of the pinhole, were monitored using the positioning imaging system as well as laser alignment device. Here we describe the various aspects of the imaging system alignment to enable the acquisition of neutron images as well as the estimated pointing errors of the first shot imaged.

Numerical modeling of the neutron imaging system for the National Ignition Facility (NIF), forward from calculated target neutron emission to a camera image, will guide both the reduction of data and the future development of the system. Located 28 m from target chamber center, the system can produce two images at different neutron energies by gating on neutron arrival time. The brighter image, using neutrons near 14 MeV, reflects the size and symmetry of the implosion "hot spot." A second image in scattered neutrons, 10-12 MeV, reflects the size and symmetry of colder, denser fuel, but with only ∼1%-7% of the neutrons. A misalignment of the pinhole assembly up to ±175 μm is covered by a set of 37 subapertures with different pointings. The model includes the variability of the pinhole point spread function across the field of view. Omega experiments provided absolute calibration, scintillator spatial broadening, and the level of residual light in the down-scattered image from the primary neutrons. Application of the model to light decay measurements of EJ399, BC422, BCF99-55, Xylene, DPAC-30, and Liquid A suggests that DPAC-30 and Liquid A would be preferred over the BCF99-55 scintillator chosen for the first NIF system, if they could be fabricated into detectors with sufficient resolution.

The ZR facility, a major refurbishment of Sandia National Laboratories' Z facility, is in the final stages of becoming operational. A number of neutron experiments are planned for this facility including deuterium gas puff z-pinch loads as well as indirect drive capsule experiments. As part of this effort, a new suite of neutron diagnostics is being developed. This suite will include improved neutron activation and neutron time-of-flight diagnostics for initial experiments. Future diagnostics being planned for ZR include neutron imaging, neutron bang time, neutron reaction history, and a neutron-proton recoil magnetic analyzer.

An experimental campaign to maximize radiation drive in small-scale hohlraums has been carried out at the National Ignition Facility (NIF) at the Lawerence Livermore National Laboratory (Livermore, CA, USA) and at the OMEGA laser at the Laboratory for Laser Energetics (Rochester, NY, USA). The small-scale hohlraums, laser energy, laser pulse, and diagnostics were similar at both facilities but the geometries were very different. The NIF experiments used on-axis laser beams whereas the OMEGA experiments used 19 beams in three beam cones. In the cases when the lasers coupled well and produced similar radiation drive, images of x-ray bumthrough and laser deposition indicate the pattern of plasma filling is very different.

Summary form only given. An experimental campaign to study radiation drive in small-scale halfraums has been carried out using the first four beams of the National Ignition Facility (NIF) at the Lawerence Livermore National Laboratory (Livermore, CA). The targets fill with plasma so quickly that, late in time, most of the laser energy is deposited at the laser entrance hole. Experiments have shown the effect of laser beam conditioning, laser power, and target size on hohlraum performance. The experimental results on X-radiation drive, laser backscatter, hard X-rays, hard X-ray imaging, and X-ray burnthrough are discussed

The National Ignition Facility's full-aperture backscatter station (FABS) is described. The FABS uses five independent diagnostics on each of the four laser beams in the initial National Ignition Facility quad to measure the energy, power, spectrum, and near-field amplitude modulations of the stimulated Brillouin and stimulated Raman backscattered light. In initial tests CO2 and C5H12 gas-filled targets were used to create various laser-plasma interaction conditions which have shown the capability of producing ignition size laser plasmas with reflectivites on the order of 10%. Results are presented for tests in which 16 kJ on target produced between 0.3 and 2.5 kJ of backscattered light. (C) 2004 American Institute of Physics.