Geometric features with characteristic lengths on the order of the size of the contact patch interface may be at least partly responsible for the variability observed in experimental measurements of structural stiffness and energy dissipation per cycle in a bolted joint. Experiments on combinations of two different types of joints (statically determinate single-joint and statically indeterminate three-joint structures) of nominally identical hardware show that the structural stiffness of the tested specimens varies by up to 25% and the energy dissipation varies by up to nearly 300%. A pressure-sensitive film was assembled into the interfaces of jointed structures to gain a qualitative understanding of the distribution of interfacial pressures of nominally conformal surfaces. The resultant pressure distributions suggest that there are misfit mechanisms that may influence contact patch geometry and also structural response of the interface. These mechanisms include local plateaus and machining induced waviness. The mechanisms are not consistent across nominally machined hardware interfaces. The proposed misfit mechanisms may be partly responsible for the variability in energy dissipation per cycle of joint experiments.
Damping in a micro-cantilever beam was measured for a very broad range of air pressures from atmosphere (10 5 Pa) down to 0.2 Pa. The beam was in open space free from squeeze films. The damping ratio, due mainly to air drag, varied by a factor of 10 4 within this pressure range. The damping due to air drag was separated from other sources of energy dissipation so that air damping could be measured at 10 -6 of critical damping factor. The linearity of the damping was confirmed over a wide range of beam vibration levels. Lastly, the measured damping was compared with several existing theories for air-drag damping for both rarified and viscous flow gas theories. The measured data indicate that, in the rarefied regime the air damping is proportional to pressure, independent of viscosity, and in the viscous regime the damping is determined by viscosity.
The development of transmitter and receiver Multichip Module subassemblies implemented in LTCC for an S-band radar application followed an approach that reduces the number of discrete devices and increases reliability. The LTCC MCM incorporates custom GaAs RF integrated circuits in faraday cavities, novel methods of reducing line resistance and enhancing lumped element Q, and a thick film back plane which attaches to a heat sink. The incorporation of PIN diodes on the receiver and a 50W power amplifier on the transmitter required methods for removing heat beyond what thermal vias can accomplish. The die is a high voltage pHEMT GaAs power amplifier RFIC chip that measures 6.5 mm × 8 mm. Although thermal vias are adequate in certain cases, the thermal solution includes heat spreaders and thermally conductive backplates. Processing hierarchy, including gold-tin die attach and various use of polymeric attachment, must allow rework on these prototypical devices. LTCC cavity covers employ metallic coatings on their exterior surfaces. The processing of the LTCC and its effect on the function of the transmitter and receiver circuits is discussed in the poster session.
American Solar Energy Society - SOLAR 2008, Including Proc. of 37th ASES Annual Conf., 33rd National Passive Solar Conf., 3rd Renewable Energy Policy and Marketing Conf.: Catch the Clean Energy Wave
This paper summarizes operational histories of three Russian-designed photovoltaic (PV) lighthouses in Norway and Russia. All lighthouses were monitored to evaluate overall system and Nickel Cadmium (NiCad) battery bank performance to determine battery capacity, charging trends, temperature, and reliability. The practical use of PV in this unusual mode, months of battery charging followed by months of battery discharging, is documented and assessed. This paper presents operational data obtained from 2004 through 2007.
In order for the IAEA to draw valid safeguards conclusions, they must be assured that the data used to draw those conclusions are authentic. In order to provide that assurance, authentication measures are applied to the safeguards equipment and the data from the equipment. These authentication measures require that IAEA personnel have direct electronic and physical access to the equipment and severely limit access to the equipment by the operator. Providing the necessary access for the IAEA personnel can be intrusive and potentially disruptive to plant operations. If the equipment is to be used jointly by the operator and the IAEA, the authentication measures can cause difficulties for the operator by limiting his ability to repair and maintain the hardware. In many cases, tamper indicating conduit and enclosures are also required. The installation, sealing, and inspection of this tamper indicating hardware also add to the intrusiveness of the safeguards activities and increase the cost of safeguards. This paper discusses these impacts and proposes methods for mitigating them.
The Cognitive Foundry is a unified collection of tools for Cognitive Science and Technology applications, supporting the development of intelligent agent models. The Foundry has two primary components designed to facilitate agent construction: the Cognitive Framework and Machine Learning packages. The Cognitive Framework provides design patterns and default implementations of an architecture for evaluating theories of cognition, as well as a suite of tools to assist in the building and analysis of theories of cognition. The Machine Learning package provides tools for populating components of the Cognitive Framework from domain-relevant data using automated knowledge-capture techniques. This paper describes the Cognitive Foundry with a focus on its application within the context of agent behavior modeling.
Simulation of potential radionuclide transport in the saturated zone from beneath the proposed repository at Yucca Mountain to the accessible environment is an important aspect of the total system performance assessment (TSPA) for disposal of high-level radioactive waste at the site. Analyses of uncertainty and sensitivity are integral components of the TSPA and have been conducted at both the sub-system and system levels to identify parameters and processes that contribute to the overall uncertainty in predictions of repository performance. Results of the sensitivity analyses indicate that uncertainty in groundwater specific discharge along the flow path in the saturated zone from beneath the repository is an important contributor to uncertainty in TSPA results and is the dominant source of uncertainty in transport times in the saturated zone for most radionuclides. Uncertainties in parameters related to matrix diffusion in the volcanic units, colloid-facilitated transport, and sorption are also important contributors to uncertainty in transport times to differing degrees for various radionuclides.
The drift-shadow effect describes capillary diversion of water flow around a drift or cavity in porous or fractured rock, resulting in lower water flux directly beneath the cavity. This paper presents computational simulations of drift-shadow experiments using dual-permeability models, similar to the models used for performance assessment analyses of flow and seepage in unsaturated fractured tuff at Yucca Mountain. Results show that the dual-penneability models capture the salient trends and behavior observed in the experiments, but constitutive relations (e.g., fracture capillary-pressure curves) can significantly affect the simulated results. An evaluation of different meshes showed that at the grid refinement used, a comparison between orthogonal and unstructured meshes did not result in large differences.
Uncertainty and sensitivity analyses of the expected dose to the reasonably maximally exposed individual in the Yucca Mountain 2008 total system performance assessment (TSPA) are presented. Uncertainty results are obtained with Latin hypercube sampling of epistemic uncertain inputs, and partial rank correlation coefficients are used to illustrate sensitivity analysis results.
The Total System Performance Assessment (TSPA) for the proposed high level radioactive waste repository at Yucca Mountain, Nevada, uses a sampling-based approach to uncertainty and sensitivity analysis. Specifically, Latin hypercube sampling is used to generate a mapping between epistemically uncertain analysis inputs and analysis outcomes of interest. This results in distributions that characterize the uncertainty in analysis outcomes. Further, the resultant mapping can be explored with sensitivity analysis procedures based on (i) examination of scatterplots, (ii) partial rank correlation coefficients, (iii) R2 values and standardized rank regression coefficients obtained in stepwise rank regression analyses, and (iv) other analysis techniques. The TSPA considers over 300 epistemically uncertain inputs (e.g., corrosion properties, solubilities, retardations, defining parameters for Poisson processes, ⋯) and over 70 time-dependent analysis outcomes (e.g., physical properties in waste packages and the engineered barrier system, releases from the engineered barrier system, the unsaturated zone and the saturated zone for individual radionuclides, and annual dose to the reasonably maximally exposed individual (RMEI) from both individual radionuclides and all radionuclides. The obtained uncertainty and sensitivity analysis results play an important role in facilitating understanding of analysis results, supporting analysis verification, establishing risk importance, and enhancing overall analysis credibility. The uncertainty and sensitivity analysis procedures are illustrated and explained with selected results for releases from the engineered barrier system, the unsaturated zone and the saturated zone and also for annual dose to the RMEI.
This report evaluates transportation risk for nuclear material in the proposed Global Nuclear Energy Partnership (GNEP) fuel cycle. Since many details of the GNEP program are yet to be determined, this document is intended only to identify general issues. The existing regulatory environment is determined to be largely prepared to incorporate the changes that the GNEP program will introduce. Nuclear material vulnerability and attractiveness are considered with respect to the various transport stages within the GNEP fuel cycle. It is determined that increased transportation security will be required for the GNEP fuel cycle, particularly for international transport. Finally, transportation considerations for several fuel cycle scenarios are discussed. These scenarios compare the current "once-through" fuel cycle with various aspects of the proposed GNEP fuel cycle.