Publications

This report documents the development and testing of the 375492, a Schottky barrier diode die, similar to the Hewlett-Packard 5082-0094. 18 figs., 4 tabs.

This document contains the technical specifications and implementation details for the Product Evaluation Management Information System (PREMIS) Version 1.1.2. This document does not include the requirements analysis or design information and is not intended as a user's guide. The INGRES Applications-by-Forms (ABF) software development tool was used to specify and define the modules and screens which comprise the PREMIS application. Several external procedures are called by the ABF procedures; these have been written in VAX/VMS DCL (Digital Command Language) and SQL (Standard Query Language). These specifications together with the PREMIS information model and corresponding database definition constitute the PREMIS Version 1.1.2 technical specification and implementation description presented herein.

The feasibility of performing, numerous spent fuel cask operations using fully integrated robotic systems is under evaluation. Using existing technology, operational and descriptive software and hardware in the form of robotic end effectors are being designed in conjunction with interfacing cask components. A robotic radiation and contamination survey system has been developed and used on mock-up cask hardware to evaluate the impact of such fully automated operations on cask design features and productivity. Based on experience gained from the survey system, numerous health physics operations can be reliably performed with little human intervention using a fully automated system. Such operations can also significantly reduce time requirements for cask-receiving operations. 7 refs., 51 figs., 6 tabs.

A new technique, called tethered rocket, has been developed for testing in the penetration and/or impact modes. The technique involves tethering a rocket-motor assembly to an earth-fixed pivot so that the resulting semicircular arc delivers a payload to a precise impact point. Discussions are presented which describe the analytical and experimental activities of the tethered rocket technique. A series of analytical models has been integral to the success of the tethered rocket development. The analytic results were verified by testing. The tests demonstrated the viability of the technique for penetration and/or impact testing. Also included is a discussion of potential applications of the method. 18 refs., 53 figs., 17 tabs.

Cracking, craters, spotty damage (discoloration), and missing chunks of material have been observed on limiters and along the midplane of tokamak inner walls. This damage is assumed to be due to runaway electron discharges. These runaway electrons have been predicted to range in energy from a few MeV to several hundred MeV. The energy density from the runaway electron discharges ranges from 10 to 500 MJ/m{sup 2} over pulse lengths of 5 to 50 msec. The PTA code package is a unique application of PATRAN, the Integrated TIGER Series, and ABAQUS for modeling high energy electron impact on tokamak first wall and limiter materials. The PTA code package provides a three-dimensional, time dependent, computational code package which predicts energy deposition, temperature rise, and damage on relevant fusion materials from runaway electrons. In this benchmark study, three experiments were modeled to validate the PTA code package. The first and third experiment simulated runaway electrons scattering through a plasma facing surface (graphite) into an internal structure (copper), and the second experiment tested the thermal and structural response from high energy electron impact on different fusion relevant materials. The PTA calculations compared favorably with the experimental results. In particular, the PTA models identified gap conductance, thermal contact, x-ray generation in materials, and the placement of high stopping power materials as key factors in the design of plasma facing components that are resistant to runaway electron damage. 13 refs., 40 figs., 3 tabs.

We have determined experimentally the Shielding Effectiveness (SE) at microwave frequencies of various types of single- and double-braided cables and connectors typical of systems that have been hardened to electromagnetic fields. This report describes a laboratory-sized reverberation chamber and the techniques used to measure the SE of several interconnecting components. Graphical results are presented in the report, along with smoothed overlay plots for each category of measurements. The overlay plots indicate the general trends in the raw data and highlight the differences between tested components. 7 refs., 22 figs.

This report describes a statistical model for field amplitudes within a mode-stirred chamber. The parameters of the probability density function for field amplitudes are estimated by means of maximum likelihood. The accuracy of these parameters is specified as a function of the amount of data used. An experimental investigation of the possibility of using an existing electromagnetic shield room as a mode-stirred chamber is described. The physical alterations of the chamber and the instrumentation are summarized. Descriptions of the tests results are reported. The tests were conducted to determine: the unloaded and loaded Q of the chamber, descriptive statistics of the electromagnetic fields, correlation distances of the fields in frequency, tuner angle, and spatial position, and the possibility of using frequency stirring as an alternative to mechanical stirring. 10 refs., 20 figs., 10 tabs.

High-quality recording of an oscilloscope waveform is usually made on photographic film. Achieving high quality, especially in a possible radiation environment and with fast sweep speeds, requires a thorough understanding of all aspects of the imaging and recording processes. This paper represents a compilation of techniques and procedures to achieve optimum oscilloscope imagery under adverse conditions and in an environment where unwanted radiation is a possibility. 10 figs., 1 tab.

Structural system identification methods are analytical techniques for reconciling test data with analytical models. However, for system identification to become a practical tool for engineering analysis, the estimation techniques/codes must communicate with finite element software packages without intensive analyst intervention and supervision. This paper presents a technique used to integrate commercial software packages for finite element modeling (MSC/NASTRAN), mathematical programming techniques (ADS), and linear system analysis (PRO-MATLAB). The parameter estimation techniques and the software for controlling the overall system were programmed in PRO-MATLAB. Two examples of application of this software using measured data are presented. The examples consist of a truss structure in which the model form is well defined, and an electronics package whose model form is ill-defined since it is difficult to model with finite elements. A comparison of the resulting updated models with the experimental data showed significant improvement. 22 refs.

A Level II/III probabilistic risk assessment (PRA) has been performed for N Reactor, a Department of Energy (DOE) production reactor located on the Hanford reservation in Washington. The accident progression analysis documented in this report determines how core damage accidents identified in the Level I PRA progress from fuel damage to confinement response and potential releases the environment. The objectives of the study are to generate accident progression data for the Level II/III PRA source term model and to identify changes that could improve plant response under accident conditions. The scope of the analysis is comprehensive, excluding only sabotage and operator errors of commission. State-of-the-art methodology is employed based largely on the methods developed by Sandia for the US Nuclear Regulatory Commission in support of the NUREG-1150 study. The accident progression model allows complex interactions and dependencies between systems to be explicitly considered. Latin Hypecube sampling was used to assess the phenomenological and systemic uncertainties associated with the primary and confinement system responses to the core damage accident. The results of the analysis show that the N Reactor confinement concept provides significant radiological protection for most of the accident progression pathways studied.

This report documents the development and testing of the SA3263 high voltage rectifier diode manufactured by Microsemi. 15 refs., 4 tabs.

A new gridless electrostatic field solver which utilities Fourier decomposition in the azimuthal coordinate has been developed and tested. The scaling with the number of simulation particles is N log N. This algorithm has been implemented in the BUCKSHOT code, which originally used a direct summation algorithm with N{sup 2} scaling. The Fourier decomposition in the new algorithm is done about the center of mass of each species, thus nonlinear ion hose physics is included in the m = O mode. Higher order modes describe non-axisymmetric profile changes. The breakeven point between the new solver and the direct summation algorithm is about N = 64 particles per species when up to m = 2 Fourier modes are kept. For a typical ion hose simulation with 256 particles per species the new solver is faster by a factor of about 2.7. 8 refs., 11 figs.

In order to generate a lithium vapor on the anode surface within PBFA II, an electrically insulating, lithium-coated substrate is required. One approach for providing this lithium source is the ceramic-option anode. This anode consists of two halves, equatorially split, each containing an insulating ceramic insert onto which a lithium-bearing film is sputtered. A lithium vapor is generated by ohmically pulse heating this film to 1500 K. The half-anode structure required to produce this vapor consists of a ceramic insulator, steel housing, and disk conductors. This report describes the design and fabrication of these separate components and the procedures required to join them to form the half-anode assembly. In addition, appendices are included which contain detailed drawings and specifications for these operations. 5 refs., 10 figs.

This report describes standard design criteria for and intrabuilding and interbuilding telecommunications wiring system to provide voice and open data services to facilities at Sandia National Laboratories, Albuquerque.

The US Department of Energy's (DOE) Waste Isolation Pilot Plant (WIPP) must comply with EPA regulation 40 CFR Part 191, Subpart B, which sets environmental standards for radioactive waste disposal. The regulation, Environmental Radiation Protection Standards for Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes (hereafter referred to as the Standard), was vacated in 1987 by a Federal Court of Appeals and is underground revision. By agreement with the Sate of New Mexico, the WIPP project is evaluating compliance with the Standard as promulgated, in 1985 until a new regulation is available. This report summarizes the early-1990 status of Sandia National Laboratories' (SNL) understanding of the Project's ability to achieve compliance. The report reviews the qualitative and quantitative requirements for compliance, and identifies unknowns complicating performance assessment. It discusses in relatively nontechnical terms the approaches to resolving those unknowns, and concludes that SNL has reasonable confidence that compliance is achievable with the Standard as first promulgated. 46 refs., 7 figs.

The authors describe the progress that has led to the triggering of high-power photoconductive semiconductor switches (PCSSs) with laser diodes. An 850 W optical pulse from a laser diode array has been used to trigger a 1.5 cm long switch that delivered 8.5 MW to a 38.3 Ω load. Using 166 W arrays, a 2.5 mm long switch has been triggered, delivering 1.2 MW with 600 ps risetimes at pulse repetition frequencies of 1 kHz. These 2.5 mm long switches were tested for pulse lifetime and survived 105 pulses at 1.0 MW levels. In single pulse operation up to 600 A has been switched with laser diode arrays. The goal is to switch up to 5 kA in a single shot mode and up to 100 MW repetitively at up to 10 kHz. It is pointed out that these goals are feasible since the switches can be used in parallel or in series.

This report provides system designers with basic human factors information and guidelines to help in the selection of manual data input devices. The selection of such devices is important with respect to the environment in which the device with be used, speed of data entry required, error potential, and the user friendliness of the candidate devices. The report reviews several of the most commonly used data input devices and provides a description of each, experimental evaluations, and observations and recommendations based on review of the data. In addition, the appendix presents an input device matrix that gives general guidance concerning input devices and the physical and mission environment in which they might be used. Additional assistance should be requested from Sandia National Laboratories (SNL) Human Factors Personnel. 23 refs., 13 figs.

Concerns about energy spreads due to degradation of 1.1-MV, 34-ns duration accelerating cavity repeating pulse shapes have resulted in improving the 24-switch trigger system for the ET-2 cavity, and identifying critical factors in the cavity design that affect the pulse shape. The authors summarize the improvements (completed and proposed) for the existing ET-2 cavity and the status of the design analysis and modeling of accelerating cavities. A relativistic electron beam (REB) injector for the RLA is being installed which will provide a higher amplitude

As a crosslinking polymer cures, dramatic changes in molecular architecture occur. These structural changes in turn affect the viscoelastic behavior of the material. At a critical extent of reaction (the gel point), the polymer undergoes a transition from a viscous liquid to an elastic solid. We have monitored the evolution of structure and viscoelasticity in the most common epoxy encapsulant used at Sandia, diethanolamine-cured Epon 828. The structure evolves according to percolation theory, and the viscoelasticity evolves according to our dynamic scaling theory for branched polymers. 9 refs., 12 figs.

Calculations are performed to predict the distribution of the (5p){sup 5}(5d)--(5p){sup 5}(6p)emission cross section in Xe in a strong magnetic field. For isotopes with no nuclear magnetic moment, the question is the calculation of Lande g factors. This is done with wavefunctions obtained by diagonalizing the electrostatic interaction in jj coupling, leading to reasonable accurate Lande g factors. For levels described by quantum numbers J and M, the Zeeman interaction is always diagonal in M, and with a 6 kG magnetic field the Zeeman interaction is effectively diagonal in J (the non-diagonal matrix elements are negligible), so the resulting cross section calculations are simple. For the isotopes with non-zero magnetic moments, one must determine the dipole and quadrupole hyperfine splitting coefficients. To do this and to improve the overall fit of the calculated and measured energy levels, it was necessary to include configuration interaction between terms of the (5p){sup 5}(5d) and (5p){sup 5}(6s) configurations. Comparisons are made between these calculated hyperfine parameters and experiment. Hyperfine splittings are tabulated as are the cross sections and energy shifts due to hyperfine interaction in each transition. When hyperfine interaction is included and levels are characterized by the quantum numbers F and M{sub F}, the Zeeman interaction is diagonal in M{sub F} but different F. All these effects were included in the calculations leading to a particularly rich spectrum for Xe(131) with I = 3/2. For example, the (5p){sup 5}(5d){sub J} = 4{minus}(5p){sup 5}(6p){sub J} = 3 transition is split into approximately 336 components. 21 refs., 3 figs., 12 tabs.

This annual report summarizes progress which has been made in Fiscal Year 1989 on this program of geotechnology for tight gas reservoirs. Most of the studies are an outgrowth of the results and experience from the Multiwell Experiment -- an unprecedented investigation of western gas reservoirs typical of the Mesaverde Formation. Results are presented in the following study areas: (1) tectonism, subsidence and fracturing of these reservoirs, (2) mechanism for the formation of regional fractures in flat-lying basins, (3) the case against natural hydraulic fracturing, (4) characterization and implications of dickite-mineralized fractures, (5) significance of coring-induced fractures, (6) determination of an effective stress law for permeability in tight sandstones, and (7) stress azimuths for two well sites in the Piceance Basin. In addition, technology transfer aspects and impact of the Multiwell Experiment are summarized. 27 refs., 28 figs., 1 tab.

This study was performed under FUTURE LOOK, a joint Defense Nuclear Agency/Department of Energy (DNA/DOE) sponsored study. The intent of FUTURE LOOK is to identify and develop means of providing requisite security and survivability to the Non-Strategic Nuclear Forces (NSNF) in the Twenty-First Century. Our current thinking about the future world in Europe is summarized. In this report we develop four scenarios/stockpile cases to cover the spectrum of potential happenings in Europe; we also develop general security and survivability implications and recommendations for each case. The four cases are: (1) a substantially reduced (factor of 2--10) European stockpile; (2) a near-zero stockpile, with no Army weapons remaining in Europe; (3) current stockpile in Europe remains; and (4) current stockpile numbers remain, but aggressive modernization is allowed. We plan to use the information in this report to assist in developing detailed security and survivability options as part of our follow-on to FUTURE LOOK studies. 8 refs., 6 tabs.

The purpose of this computer program is to serve as a tool in the daily operation of the R D storage function. This menu-driven, interactive program was written in DBase III+ for use on an IBM PC-XT computer to efficiently store items in a minimum space, inventory, locate, report, withdraw and record the activities in a history file. A drive path is utilized in numbering each storage location to minimize the distance and time required to store and retrieve an item. An empty-space listing is available for a limited inventory.

The United States Department of energy, after considering a number of alternative disposal methods for radioactive wastes in the United States, Proposed that these wastes should be disposed of in deep geologic repositories. This alternative is currently being developed at the Waste Isolation Pilot Plant (WIPP), for transuranic waste, and investigated at Yucca Mountain, for spent power-reactor fuel and vitrified high-level waste, the latter resulting principally from defense activities. In addition, a research program on subseabed disposal was active from 1973 until 1987 but is currently suspended. The two deep-geologic disposal projects are discussed in detail and the subseabed-disposal research project is briefly summarized. 28 refs., 39 figs., 4 tabs.

Thermal and mechanical models for intact and jointed rock mass behavior are being developed, verified, and validated at Sandia National Laboratories for the Yucca Mountain Project. Benchmarking is an essential part of this effort and is the primary tool for verifying engineering software used to solve thermomechanical problems. This report presents the results of the second phase of the first thermomechanical benchmark exercise. In the first phase of this exercise, three finite element codes for nonlinear heat conduction and one coupled thermoelastic boundary element code (HEFF) were used to solve the thermal portion of the benchmark problem. The boundary element code HEFF was used in this exercise because it calculates a solution to the coupled thermal/elastic problem using an approximate analytical method and, thus, provides a means of comparing the finite element solutions with a solution obtained by an independent method. The results from the thermal analysis were then used as input to the second phase of the analysis, which consisted of solving the structural portion of the benchmark problem using a linear elastic rock mass model. Five different structural codes, JAC, SPECTROM-31, VISCOT, and HEFF, were used by the participants in this portion of the study. The problem solved by each code was a two-dimensional idealization of a series of drifts with the approximate dimensions of the proposed design for vertical emplacement of nuclear waste at Yucca Mountain. 6 refs., 74 figs., 4 tabs.

This report documents the development and testing of the SA3262, a high voltage rectifier diode, manufactured by Microsemi. 13 figs., 4 tabs.

Dual focus laser velocimetry (L2F), photographic techniques, and pressure measurements were used to investigate particle and flame characteristics of a high velocity oxygen/fuel (HVOF) flame spray gun known as CDS''. Velocities of alumina, tungsten carbide, and Triballoy particles within the HVOF effluent stream have been measured using L2F techniques. Photographs of the exiting gases were used to determine the local Mach numbers within the gas stream. Measurements of Mach angles in the photographs were used to determine the actual gas velocity in the free jet of the device. Pressure measurements were made on the HVOF device which enabled calculations of the gas content, R, and the specific heat ratio, {kappa}. These calculations combined with estimates of gas temperature are used to calculate gas velocities at Mach 1 (nozzle exit). The HVOF device was used to produce dense WC/12 wt. % Co and Triballoy T-400 coatings. For the two gas flow conditions examined, higher hardness values and densities were observed for coatings deposited at the higher gas flow rates.

This report documents the characterization and development of the 381558 (2N6193JTXV), a medium power PNP silicon transistor designed for switching and wide band amplifier applications. The 2N6193JTXV is manufactured by Motorola. 50 figs., 6 tabs.

This report documents the characterization and development of the 381568 (2N5339JTXV), a medium power NPN silicon transistor designed for switching and wide band amplifier applications. The 2N5339JTXV is manufactured by Motorola. 50 figs., 6 tabs.

This report describes the major hardware and software components of the HERMES III Control and Monitor System at the Simulation Technology Laboratory (STL) at Sandia National Laboratories. The HERMES III Control and Monitor System is a computer controlled system that controls and monitors the charging, arming, and firing of the HERMES III accelerator. This documentation is intended to be a general introduction to the system for engineers and technicians involved in the maintenance and modification of the system. It may also be useful to persons interested in designing and constructing a similar control system. This report collects many of the documents produced throughout the project and directs the reader toward other documents written for this project.

This report describes the components and installation of the Oxygen Deficiency Monitor System (ODMS) at the Simulation Technology Laboratory (STL) at Sandia National Laboratories. The ODMS presently monitors the oxygen concentration of the ambient air in the lower levels of the laboratory where air circulation may be insufficient to disperse gases that may settle and accumulate creating an oxygen-deficient environment. The intent of this report is to provide a general introduction to the system for personnel involved in the maintenance and modifications of the system and may be useful to people interested in installing a similar system. This will report describe the hardware components, installation considerations, operation, and maintenance of the system. 6 refs., 5 figs.

The literature is reviewed on the amount and the characteristics of particulate material (crud), that is deposited on Light Water Reactor (LWR) fuel rods and assemblies. Currently available data on crud composition, specific activity, spallation mechanisms, potential environmental release, and particle size distributions is considered. In addition, literature that pertains to the possible impact of crud on repository operations is surveyed. This report consists of rather extensive excerpts from the published literature on crud that may have a bearing on repository risk assessment. Commentary on the possible effects of crud on repository operations and the applicability of available crud information to repository risk analyses is included. In addition, estimates are made of the quantity of crud that might be available for release during the different phases of repository operations. Using these estimates, the total effective dose equivalent is determined at several distances from a release point.

This 1989 report contains monitoring data from routine radiological and nonradiological environmental surveillance activities. Summaries of significant environmental compliance programs in progress such as National Environmental Policy Act documentation, environmental permits, environmental restoration, and various waste management programs for Sandia National Laboratories in Albuquerque (SNL, Albuquerque) are included. The maximum offsite dose impact was calculated to be 8.8 {times} 10{sup {minus}4} mrem. The total Albuquerque population received a collective dose of 0.097 person-rem during 1989 from SNL, Albuquerque, operations. As in the previous year, SNL, Albuquerque, operations in 1989 had no adverse impact on the general public or on the environment. 46 refs., 20 figs., 31 tabs.

This report summarizes the environmental surveillance activities conducted by Environmental Protection Agency (EPA) and Reynolds Electrical and Engineering Company (REECo) for the Tonopah Test Range (TTR) operated by Sandia National Laboratories (SNL). Other environmental compliance programs such as National Environmental Policy Act of 1969 (NEPA), environmental permits, environmental restoration, and waste management programs are also included. The maximum offsite dose impact from 1989 operations was 8.7 {times} 10{sup {minus}4} mrem as a result of an unusual occurrence. The population received a collective dose of 1.2 {times} 10{sup {minus}5} person-rem from this incidence, while the same populations received 4.94 person-rem from natural background radiation. The 1989 SNL, TTR operations had no adverse impact on the general public or the environment. 18 refs., 2 figs., 14 tabs.

Drillholes H-11b1, H-11b2, and H-11b3 were drilled from August to December 1983 for site characterization and hydrologic studies of the Culebra Dolomite Member of the Upper Permian Rustler Formation at the Waste Isolation Pilot Plant (WIPP) site in southeastern New Mexico. In October 1984, the three wells were subjected to a series of pumping tests designed to develop the wells, provide information on hydraulic communication between the wells, provide hydraulic properties information, and to obtain water samples for quality of water measurements. Based on these tests, it was determined that this location would provide an excellent pad to conduct a convergent-flow non-sorbing tracer test in the Culebra dolomite. In 1988, a fourth hole (H-11b4) was drilled at this complex to provide a tracer-injection hole for the H-11 convergent-flow tracer test and to provide an additional point at which the hydraulic response of the Culebra H-11 multipad pumping test could be monitored. A suite of geophysical logs was run on the drillholes and was used to identify different lithologies and aided in interpretation of the hydraulic tests. 4 refs., 6 figs., 6 tabs.

A computer model for simulating the explosive dispersal of a fuel agent in the far-field regime is described and is applied to a wide variety of initial conditions to judge their effect upon the resulting fuel/air cloud. This work was directed toward modeling the dispersal process associated with Fuel-Air-Explosives devices. The far-field dispersal regime is taken to be that time after the initial burster charge detonation in which the shock forces no longer dominate the flow field and initial canister and fuel mass breakup has occurred. The model was applied to a low vapor pressure fuel, a high vapor pressure fuel and a solid fuel. A strong dependence of the final cloud characteristics upon the initial droplet size distribution was demonstrated. The predicted fuel-air clouds were highly non-uniform in concentration. 18 refs., 86 figs., 4 tabs.

The Vindicator ETW-250 taut wire system combines a physical taut wire barrier with an intrusion detection sensor network. The sensor wires deter and/or slow physical entry into protected areas. The sensors themselves generate an alarm if the sensor wires are pulled, spread, cut, or climbed on. This physical motion is converted into an electrical waveform that is analyzed by the processor. The processor then determines if this motion is within the pre-programmed parameters. If it is not, an alarm is generated through a relay back to the monitoring station. Small changes, such as those caused by temperature, are rejected. Installation and testing are described.

Containment and Surveillance (C/S) equipment, which is used in international safeguards applications, is normally expected to operate unattended within a facility in a host country for extended periods of time. To ensure that this equipment consistently provides high-quality data, the equipment used to ensure the data's integrity must be highly reliable and tamper-resistant. Although designed specifically for use by the International Atomic Energy Agency to comply with the Non-Proliferation Treaty, the equipment has potential applications for both bilateral and multilateral verification schemes for other treaties. This report describes C/S equipment that has been developed by Sandia National Laboratories, and discusses its potential applications. This equipment includes surveillance equipment, seals, monitoring equipment, and authentication equipment. 16 refs., 20 figs.

Waste Isolation Pilot Plant (WIPP) sealing program results are embodied in the initial seal system strategy and reference design. The design provides a common basis for calculations and analyses so that results can be compared directly. The sealing strategy combines both long- and short-term seal components. Crushed salt is the principal long-term barrier to fluid flow. Short-term seal components are used until creep consolidation is sufficient. Concretes developed specifically for WIPP seals and a swelling clay material that exhibits low permeability to WIPP groundwater and brine have been chosen for the short-term components. A body of evidence exists showing the stability of these materials for the length of time they are required to function. Reference designs are described and drawings are shown for each of the principal multi-component seals. Confidence in the sealing strategy and the reference designs resulted from a combination of laboratory tests, numerical modeling, and in situ demonstrations. The sealing strategy, materials, and designs for the WIPP repository are consistent with the concepts and designs proposed previously for other national and international waste management programs. Past accomplishments and planned activities in the sealing program will produce a detailed conceptual design for the seal system and a seal system performance model. 48 refs., 11 figs., 6 tabs.

In the course of communication circuit design at Sandia National Laboratories, a set of communication symbols was created to aid, and hopefully standardize, the design process. These symbols, which allow the designer to build a circuit using black boxes, simplify circuit design and documentation. They also provide a standard set to help minimize interpretation problems among circuit designers. The symbols can be used to represent various devices in a circuit, such as modems, computers, terminals, encryption devices, converters, etc. When using these symbols to design communication circuits, the contours of each symbol show which devices interface together. Mismatch device contours indicate the need for another element (such as a null modem) between the two devices. In addition, the propagation of clock, data, and control signals through the circuit can be represented. Clocking modes on synchronous components (modems, multiplexers, etc.) and signal line crossovers can also be determined from the drawings during the design process. 30 figs.

A series of test has evaluated the current-carrying characteristics of several proposed detonator strong safety link (DSSL) drive cables to conduct current into an electrically simulated radiation case enclosure. The drive cables tested included a dielectric cable made up of either one or two braided Kevlar threads in a polysulfone sleeve, an existing DSSL conductive drive cable similar to a bicycle shift cable, with and without an external ground-strap diversion feature, and the flex circuit hook assembly used for DSSL instrumentation purposes. Each of the test samples was connected to a 200-kV, 30-kA Marx generator and terminated inside an electrically simulated radiation case enclosure. Two lengths of drive cables (4 and 13 in.) within the simulated radiation case were tested for each type. The results indicate that the conductive drive cables without an external short-circuit diversion feature conducted about 5 to 9 times as much current into the simulated radiation case as either the dielectric drive cables or the conductive drive cables with an external short-circuit feature. Surprisingly, the flex circuit hook assemblies, both the short and long cables, conducted nearly 100% of the available current into the simulated radiation case enclosure. The next series of experiments will repeat the tests at the SNL Lightning Facility in order to scale the results up to the maximum lightning threat levels of 200 kA. 18 figs., 1 tab.

Little work has been performed to characterize the exposure sensitivity, contrast, and tone of candidate resists for photon energies between 100-300 eV, the range in which projection soft x-ray lithography will be developed. We report here the characterization of near-edge x-ray absorption fine structure (NEXAFS) spectra, exposure sensitivity, contrast, and post-exposure processing of selected polysilane resists at photon energies close to the Si L2,3 absorption edge (100 eV). We find absorption resonance features in the NEXAFS spectra which we assign to excitation into Si-Si and Si-C σ∗ orbitals. Using monochromatized XUV exposures on the Si-Si σ∗ resonance at 105 eV, followed by solvent dissolution development, we have measured the exposure sensitivity curves of these resists. We find sensitivities in the range of 600-3000 mJ/cm2 and contrasts in the range from 0.5-1.4, depending on the polysilane side chain. We have also performed exposure sensitivity measurements at 92 eV, below the edge. Sensitivity decreases slightly compared to 105 eV exposures and the saturation depth and contrast both increase, as expected. We find also that exposing resist films to oxygen after XUV exposure, but before development, increases the sensitivity markedly.

The solderability of 60Sn40Pb solder on Kovar was examined as a function of surface-cleaning procedure, flux, and solder-bath temperature. Organic-acid fluxes were more effective at lowering the contact angle than was a mildly activated, rosin-based (RMA) flux on chemically etched Kovar. The contact angles were as low as 29{degree} {plus minus} 5{degree} as compared to 61{degree} {plus minus} 11{degree}, respectively. Varying the solder temperature through the range of 215{degree}C to 288{degree}C caused an insignificant change in the contact angle for the RMA flux and a decrease of the contact angle for a candidate water-based, organic-acid flux. The dilution strength of the flux and the elapsed cleaning time significantly influenced the solder-flux interfacial tension, {sub {gamma}LF}. T-peel strengths of Kovar-60Sn40Pb-OFHC copper joints had a low correlation with the contact angle derived from the solderability experiments. The results of the solderability tests and the T-peel mechanical tests, and subsequence microanalysis of the as-soldered and T-peel samples revealed that the best results for the RMA flux were achieved by using an electropolishing procedure and a solder temperature of 240{degree}C to 260{degree}C. A relatively low contact angle of 31{degree} {plus minus} 2{degree} was observed, with no evidence of cracking or thick-film intermetallic formation at the Kovar-solder interface. T-peel strengths were nominally 9.4{degree} {plus minus} 0.5 {times} 10{sup 6} dyn/cm. 21 refs., 36 figs., 11 tabs.

Parachute system performance issues such a turnover and wake recontact may be strongly influenced by velocities induced by the wake of the delivering aircraft, especially if the aircraft is maneuvering at the time of parachute deployment. The effect of the aircraft on the parachute system is a function of the aircraft size, weight, and flight path. In order to provide experimental data for validation of a computer code to predict aircraft wake velocities, a test was conducted in the NASA 14 {times} 22 ft wind tunnel using a 5.78% model of the B-1B strategic bomber. The model was strut mounted through the top of its fuselage by a mechanism which was capable of pitching the model at moderate rates. In this series of tests, the aircraft was pitched at 10{degree}/sec from a cruise angle of attack of 5.3{degree} to an angle of attack of 11{degree} in order to simulate a 2.2g pullup. Data were also taken for the subsequent pitch down sequence back to the cruise angle of attack. Instantaneous streamwise and vertical velocities were measured in the wake at a number of points using a hot wire anemometer. These data have been reduced to the form of downwash coefficients which are a function of the aircraft angle of attack time-history. Unsteady effects are accounted for by use of a wake convection lag-time correlation. 12 refs., 59 figs., 4 tabs.

This report presents the concept of formalizing the elicitation and use of expert judgment in the performance assessment of high-level radioactive waste (HLW) repositories in deep geologic formations. The report begins with a discussion of characteristics (advantages and disadvantages) of formalizing expert judgment examples of previous uses of expert judgment in radioactive waste programs, criteria that can assist in deciding when to formalize expert judgment, and the relationship of formal use of expert judgment to data collection and modeling. The current state of the art with respect to the elicitation, use, and communication of formal expert judgment is presented. The report concludes with a discussion on potential applications of formal expert judgment in performance assessment of HLW repositories. 93 refs.

As part of a Department of Energy/Commission of European Communities (DOE/CEC) cooperative program, Sandia National Laboratories was asked to develop a portable ultrasonic seal pattern reading system. The system consists of a data acquisition box (DAB), a mechanical reading head, and a portable IBM-compatible PC linked to the DAB by a serial RS-232C communication link. This manual focuses on the DAB subsystem. 8 refs., 13 figs., 8 tabs.

MCPRAM (Monte Carlo PReprocessor for AMEER), a computer program that uses Monte Carlo techniques to create an input file for the AMEER trajectory code, has been developed for the Sandia National Laboratories VAX and Cray computers. Users can select the number of trajectories to compute, which AMEER variables to investigate, and the type of probability distribution for each variable. Any legal AMEER input variable can be investigated anywhere in the input run stream with either a normal, uniform, or Rayleigh distribution. Users also have the option to use covariance matrices for the investigation of certain correlated variables such as booster pre-reentry errors and wind, axial force, and atmospheric models. In conjunction with MCPRAM, AMEER was modified to include the variables introduced by the covariance matrices and to include provisions for six types of fuze models. The new fuze models and the new AMEER variables are described in this report.

The purpose of this report is to summarize for the record the objectives, planning, progress, and documentation of excavating Brine Inflow Room Q and implementing an initial set of Room Q tests. The Room Q tests were designed primarily to test the scale-up accuracy of the current brine inflow model by providing data on brine flow from the host rock salt to a large-scale excavation in the Waste Isolation Pilot Plant (WIPP). Data from these tests will also be used to reduce uncertainties in flow parameters and evaluate proposed mechanistic models. Room Q was excavated with a tunnel boring machine. The initial tests were implemented to measure brine flow parameters and room closure. Pore pressure, permeability, and brine inflow were measured with 15 tools emplaced in boreholes above, below, and on the north side of the room at a station 75 feet into the host rock from the entrance to the room. These measurements were made before, during, and after Room Q was bored to obtain data on the responses in the host rock to the boring process. Closure measurements were started almost immediately after excavation progressed past each measurement station. The designs, timing, sequence, procedures, and as-built records for these tests were documented in Sandia National Laboratories WIPP Quality Assurance files and Westinghouse WIPP Engineering records. 21 refs., 5 figs., 5 tabs.

CTH is a software system under development at Sandia National Laboratories (SNL) to model multidimensional, multi-material, large deformation, strong shock wave physics. One-dimensional rectilinear, cylindrical, and spherical meshes; two-dimensional rectangular, and cylindrical meshes; and three-dimensional rectangular meshes are currently available. A two-step Eulerian solution scheme is used with these meshes. The first step is a Lagrangian step in which the cells distort to follow the material motion. The second step is a remesh step where the distorted cells are mapped back to the original Eulerian mesh. CTH has several thermodynamic models that are used for simulating strong shock, large deformation events. Both tabular and analytic equations of state are available. CTH can model material strength, high explosive detonation, fracture, and motion of fragments smaller than a computational cell. The material strength model is elastic perfectly plastic with thermal softening. A programmed burn model is available for computing the thermodynamic properties of explosive detonation. The Jones-Wilkins-Lee equation of state is available for modelling high explosive reaction products. Fracture can be initiated based on pressure or principle stress. A special model is available for moving fragments smaller than a computational cell with the correct statistical velocity. 7 refs.

A description is given of Sandia's CONCEPT-90 module, which represents a novel type of point-focus photovoltaic concentrator module designed for improved safety, reliability, and performance, and for ease of component fabrication and module assembly. These improvements will combine to decrease the cost of electricity produced by this type of concentrator module. Unique features of the CONCEPT-90 module include encapsulated cell assemblies, simple flat components, and integral use of plastics. The first prototype of this module has been made using back-contact silicon concentrator cells and refractive secondary optical elements. The first prototype module is described, and results from outdoor tests are presented.