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.

The Software Utilities Package for the Engineering Sciences (SUPES) is a collection of subprograms which perform frequently used non- numerical services for the engineering applications programmer. The three functional categories of SUPES are: (1) input command parsing, (2) dynamic memory management, and (3) system dependent utilities. The subprograms in categories one and two are written in standard FORTRAN-77, while the subprograms in category three are written to provide a standardized FORTRAN interface to several system dependent features. 2 refs.

Magnet configurations are found that limit the 6-MeV electrons threatening satellite electronics to <1% of the incident flux. Successful configurations of permanent magnets and electromagnets require magnetic energies of {approximately}8 to 12 kJ to protect each liter of electronics volume. The fundamental strength of materials leads to a required minimum mass of {approximately}48 to 64 kg/liter to support the magnetic pressure. With the electronics requiring {approximately}5 liters, several hundred kilograms are needed for this support. Except for protecting small apertures, magnetic shielding provides little, if any, advantage over that obtained by coating with an equivalent mass using traditional methods. 7 refs., 9 figs., 1 tab.

Until recently, hydrologic characterization in closed sections of boreholes at the Waste Isolation Pilot Plant (WIPP) has relied on measurements of pressure and temperature to establish the permeability of the host geological formations. There were no provisions for monitoring tool compliance and salt creep resulting from borehole closure. The new permeability test tool used to characterize the WIPP underground facility has been equipped with a series of sensors to measure the movement of the tool with respect to the borehole and borehole wall movement. A FORTRAN program can interpret the output data from each test and calculate the change in borehole radius, test zone length, and test zone volume. These values provide a correlation of fluid compressibility and tool compliance with the permeability results derived from the test data. 4 figs., 3 tabs.

The evaluations and selected interim test results from eight different models of small (approximately 10 A) charge controllers are described. They are being subjected to a comprehensive test program including thorough electrical characterizations at selected temperatures, photovoltaic inputs, and load levels. After electrical characterizations, the charge controllers are divided into concurrent evaluation paths. One path consists of side-by-side operational system tests in which the charge controllers are installed in identical stand-alone PV systems. The other path consists of continuous environmental and electrical cycling in which the controllers are subjected to programmed electrical inputs, temperatures, and relative humidities. Recharacterizations of all controllers are performed on a periodic basis to detect changes in electrical performance. In addition, selected custom tests are performed on identical models to determine response to transients, installation issues, and system capabilities. The data presented include measured electrical characteristics of the controllers, temperature effects, operational performance, and interface measurements at the array, battery, and load.

The capabilities of a versatile Nd:YAG pulsed-laser system developed at Sandia National Laboratories for solar cell processing applications is described. The results of statistically based, multifactor experiments used to characterize the influence of laser-system process variables on patterns produced in silicon wafers and silicon-oxide layers are presented, and an initial assessment of laser-grooved solar cell processing conditions is given.

AlGaAs/GaAs solar cells are typically characterized as having relatively high interface recombination velocities at the heteroface. Some of the factors influencing the design of solar cell window layers are examined, and the effect of substituting InAlAs/GaAs superlattice alloys and InAlAs bulk alloys in place of AlGaAs is considered. Potential advantages are reduced surface recombination at the heterojunction, reduced thermionic emission into the window layer, thinner window layers, and reduced absorption in the window layer. Theoretical models predict a lower effective surface recombination velocity and a smaller acceptor activation energy for superlattice alloys. Experimental absorption data show that superlattice alloys have a lower absorption coefficient at short wavelengths near the UV roll off.

Facilities are now coming under Agency safeguards which have large amounts of nuclear material and/or nuclear material which is very difficult to access for reverification. Containment and Surveillance (C/S) technologies may be used to assist in resolution of this problem. This study examines the concept of redundant and independent C/S Systems, and discusses how these systems could be used to lower the need for remeasurement of materials which are difficult to access, or materials included in very large inventories. This paper dose not address increasing levels of C/S measures to protect different types of materials. However, the paper does discuss how redundant and independent C/S Systems will improve the reliability of safeguards information. Equipment which may be used in such systems, and examples of potential systems, are presented. Decisions on how much C/S equipment is enough for a given facility, or type of material, must be made by the inspectorate. 6 refs., 4 figs.

The effects of pressure on the energetics and kinetics of electron emission and capture processes by several important deep levels in Si are discussed. The results yield the first quantitative measures of the breathing mode lattice relaxations accompanying these processes. © 1990, Taylor & Francis Group, LLC. All rights reserved.

A Level 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 objectives of the PRA are to assess the risks to the public and the Hanford site workers posed by the operation of N Reactor, to compare those risks to proposed DOE safety goals, and to identify changes to the plant that could reduce the risk. The scope of the PRA is comprehensive, excluding only sabotage and operation 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 of five commercial nuclear power plants. The structure of the probabilistic models allowed complex interactions and dependencies between systems to be explicitly considered. Latin Hypercube sampling techniques were used to develop uncertainty distributions for the risks associated with postulated core damage events initiated by fire, seismic, and internal events as well as the overall combined risk. The combined risk results show that N Reactor meets the primary DOE safety goals and compared favorably to the plants considered in the NUREG-1150 analysis. 36 figs., 81 tabs.

This report discusses the performance of commercial amorphous silicon modules used in photovoltaic power systems from 1985 through 1989. Topics discussed include initial degradation, reliability, durability, and effects of temperature and solar irradiance on peak power and energy production. 6 refs., 18 figs.

This report is the outcome of a study of the technical and procedural requirements which would need to be met if the Agency and facility operators were to agree that under certain circumstances the operator could remove or apply on Agency seal in the absence of an inspector. In the FRG and USA Support Programmes respectively an electronic seal (VACOSS) and a CCTV system (MIVS) have been developed. Through a joint project, an interface has been demonstrated which enables the seal data to be superimposed upon the surveillance data. This interface is briefly described in the appendix. A proposed application for this integrated system is to allow facility operators to carry-out some of the seal procedures normally performed by an inspector, thereby reducing the need for inspector presence at certain crucial times.

Thermal battery functional test data are stored in an HP3000 minicomputer operated by the Power Sources Department. A program was written to read data from a battery data base, compute simple statistics (mean, minimum, maximum, standard deviation, and K-factor), print out the results, and store the data in a file for subsequent plotting. A separate program was written to plot the data. The programs were written in the Pascal programming language. 1 tab.

This document describes the Nuclear Weapons Complex (NWC) detached'' CIM file header. The file header concept is defined and its form and content are specified. Guidelines for the use of file headers by the CIM community in the NWC are also included. This document is the result of the combined efforts of the Lead Laboratory and the NWC File Header Subgroup. It has evolved through a process of cooperation and compromise and represents a consensus view of the NWC.

At Sandia National Laboratories data engineering is the application of both the art and science aspects of engineering principles to the acquisition and storage of product-related test and traceability data and to the transformation of this data into useful information through data retrieval and analysis processes. This report describes the application of data engineering to the data systems that have been developed in support of production agency built or procured product. The production agencies that are addresses in this report include Mason Hanger, Amarillo, TX; GEND, Largo, FL, Allied Signal, KCD, Kansas City, MO; and Mount, Miamisburg, OH. Also discussed is the Weapon Evaluation Test Laboratory (7264)/Amarillo. The scope of the data engineering program for each production agency (or test facility) is presented along with the interfaces and constraints. The present contractors' data system is described and system limitations and future plans are discussed. 7 refs., 38 figs.

BUCKL is an inexpensive x-ray deposition computer code which considers one-dimensional transport and accounts for two-dimensional effects in a buckling approximation. This manual contains input instructions and sample input.

A variety of geomechanical analyses are presented that support the WIPP project. The scale of the analyses ranged through laboratory experiments, small-scale in-situ tests, large-scale in-situ tests, underground rooms, shafts and shaft keys, and multi-room panels. The structural behavior of underground rooms, shafts, and experiments was investigated using the finite element method. Both two and three dimensional analyses simulated the time-dependent behavior of the salt host rock. Two different constitutive models were used to represent the creeping motion of the salt. The investigations aided in experimental planning, code validation, and assessing excavation responses for safety and performance assessment. This report compiles ten different structural analyses which assess the performance of excavations and experiments located at the Waste Isolation Pilot Plant (WIPP) in Carlsbad, NM. Chapter 2 discusses the constitutive models used to represent the salt behavior. Each of Chapters 3 through 12 presents an analysis. Chapter 13 concludes the report. 36 refs., 48 figs., 17 tabs.

An interactive computerized and automated system to provide environmental control for atmospheric corrosion experiments has been added to the FACT, as well as computerized data acquisition for sample weighing. The FACT allows control of corrosive gas concentrations to simulate industrial atmospheric conditions and requires constant manual adjustment to provide a stable test environment. Because constant manual adjustment is impractical, we have automated this facility to achieve the desired stability. This system incorporates an IBM PC AT using Keithley's Series 500 hardware and Quick500 software development environment to calibrate gas analyzers, and to monitor exposure time, test chamber temperature, and gas concentrations. A second PC has been connected to a Mettler M3 microbalance through an IEEE-488 interface communicating under Lotus Measure. Weighings with a sensitivity of 1 {times} 10{sup {minus}6} gram are transferred directly into a Lotus 123 spreadsheet where the data can then be easily manipulated and plotted. Under computer control, the FACT can now run unattended for more than a week and maintain much better control over gas concentrations (200 {plus minus} 5 ppb and 10 {plus minus} 0.5 ppb for NO{sub 2} and H{sub 2}O and H{sub 2}S, respectively) than was possible with manual control (100 {plus minus} 25 ppb for either gas), after initial stabilization. 9 figs.

The Linear Explosive Shaped Charge Analysis (LESCA) code is used to analytically model and optimize the design of a linear shaped charge (LSC). A variety of LSCs are initially modeled with the LESCA code, and the predicted jet penetration versus standoff data are compared to experimental data. The LSCs varied in explosive loading size form 600 to 10,500 grains per foot. The LSC liner material for this study was cooper. The variables optimized in this study included the LSC apex angle, liner thickness, explosive width, and explosive width, and explosive height. 8 ref., 24 figs.

The PCP PHEMTO-CHEM 100 ion mobility spectrometer (IMS) exhibits a number of characteristics that affect its performance for the quanititative and qualitative analysis of explosives in solution and in the gas phase. These characteristics, as well as modifications to the system that will either eliminate, or reduce, the extent of some problems associated with these characteristics, are described. Also described are other aspects of the operation and performance of this system. 9 refs., 10 figs., 1 tab.

This report discusses the purpose and requirements that were established for the data logger at the 34-m diameter, research- oriented vertical axis wind turbine, the Test Bed, which Sandia National Laboratories built at Bushland, Texas. The data logger is a minicomputer-based system that collects data from 35 channels, displays the collected data, and records them on a hard disc. Both the hardware and software that make up the data logger are also described, and the operator's instructions and the operating system commands and procedure files are appended. The data logger is used to obtain long-term data to characterize the wind at the site of the turbine, record the performance data of the control system, obtain a continuous record of events at the test sire, consolidate displays for the test engineer, and provide a display of current information for visitors to the site. 7 refs., 3 figs., 4 tabs.

Analytical equations for barrel-tamped explosively accelerated flyer plates are used to generate graphical solutions to flyer problems. Given the problem geometrical dimensions, explosive weight, detonation velocity, explosive exponent, barrel-tamping weight, and flyer weight, the graphical representation of the calculated data allows for a fast approximation of the final or maximum flyer plate velocity. Graphically obtained flyer velocities are compared to experimentally published data. The graphical solution for flyer velocity is particularly useful when a computer is not available. The graphical representation of the various barrel-tamped flyer parameters results in a parametric study which illustrates the effect on final flyer velocity in varying parameters. The graphical analysis scheme can be used with any explosive, tamper and flyer materials. 15 refs., 12 figs., 4 tabs.

This report presents the results of numerical modeling of the electron beam generation, transport, and conditioning in the Sandia accelerators RADLAC, IBEX, and RLA for the year 1989. The codes used were the particle code MAGIC, the trajectory code TRAJ, and some preliminary work with the 3-D code Quicksilver. The results are mostly in the areas of injector design, beam propagation in IFR channels and B{sub {Theta}} cells, and emittance measurements. The energy range of these electron beams is from 1 MeV to 20 MeV. 16 refs., 42 figs.

Finite-difference time-domain (FDTD) codes can, in principle, be used to determine the electromagnetic response of complex scatterers. However, the extent to which structural details can be accommodated is limited by computer resources and one's ability to specify necessary parameters. By embedding into the FDTD code alternative numerical methods that solve the aspects of the problem which are not practical, or possible, for the FDTD code to handle, power and flexibility can be added. This report investigates three such hybrid schemes. Topics include: (1) embedding a transient multiconductor/circuit-analysis code so that coupling down to the component level can be directly computed; (2) the effectiveness of using a multiconductor transmission-line code to analyze shielded multiwire cables in FDTD calculations; and (3) the effectiveness of using two-- and three-- dimensional aperture transfer functions to model narrow apertures in FDTD formulations. These topics were selected because of their immediate need in system assessments. Experimental measurements and/or alternative solution methods are used to verify the hybrid approaches. 56 figs.

In past five years, Department 1510 has developed a state-of-the-art Aerosol Dynamics Laboratory (ADL). This report documents the current instrumentation and capabilities that exist in this laboratory. The ADL was developed from a variety of sources, with a primary contribution from Department 1510's Independent Research and Development program in aerosol dynamics. Current capabilities of the ADL include: (1) generation of calibration-quality monodisperse particles with diameters between 0.005 to 100 {mu}m, (2) real-time measurement of particle size distributions for particle diameters between 0.01 and 100 {mu}m, (3) in situ, real-time measurement of particle size distributions for particle diameters between 0.3 and 100 {mu}m, and (4) real-time measurement of particle charge distributions for particle diameters between 0.01 and 1.0 {mu}m. 14 refs., 5 figs.

Analyses related to the Supplemental Environmental Impact Statement and preliminary performance assessment studies have suggested that alteration of the method of waste emplacement in the Waste Isolation Pilot Plant (WIPP) may be necessary in order to satisfy waste storage regulations. Good engineering practice also dictates consideration of changes which are useful for better containment of waste. This report presents a preliminary evaluation of various engineered modifications that might be considered. The report is based on work that has been ongoing at Sandia National Laboratories since FY88, before formation of the present Engineering Alternative Task Force by the Department of Energy WIPP Project Office. The engineered modifications under consideration are described and characterized in the first part of the report according to: the objective that would be addressed by their application; their level of complexity; and some of the presently understood limitations and uncertainties of their use. Results of studies conducted to date to examine the feasibility of some of the modification concepts are presented, with emphasis on the effects of waste supercompaction.'' 21 refs., 14 figs., 5 tabs.

When the Morton Salt Mine in Weeks Island, Louisiana was converted into a strategic Petroleum Reserve oil reservoir, massive concrete bulkheads were installed to seal the access shafts against oil or water leakage. Recent inspection of these bulkheads has raised questions about their ability to perform satisfactorily in the event of a catastrophic water leak into the mine. Calculations are reported here which examine the response of the five bulkheads to a worst-case scenario of flooding by brine from the surface into the oil reservoir below the bulkheads. These calculations show that, under conservative analysis assumptions, factors of safety under such a load for the bulkheads sealing the service shaft and the two raisebores are close to 1. The Markel incline and production shaft bulkheads exhibit safety factors in excess of 2 and 3, respectively. 10 refs., 24 figs., 3 tabs.

GREPOS is a mesh utility program that repositions or modifies the configuration of a two-dimensional or three-dimensional mesh. GREPOS can be used to change the orientation and size of a two-dimensional or three-dimensional mesh; change the material block, nodeset, and sideset IDs; or explode'' the mesh to facilitate viewing of the various parts of the model. GREPOS also updates the EXODUS Quality Assurance (QA) and information records to help track the codes and files used to generate the mesh. GREPOS reads and writes two-dimensional and three-dimensional mesh databases in the GENESIS database format; therefore, it is compatible with the preprocessing, postprocessing, and analysis codes used by the Engineering Analysis Department at Department at Sandia National Laboratories (SNL).

A seismic signal processing procedure is designed so that its performance is optimized for a specific seismic array looking for explosions at a specific teleseismic location. In this report we first describe the processing procedure, which essentially estimates beamformer signal power as a function of time in a specified frequency band. Then we calibrate the procedure for the Norwegian Regional Seismic array (NRSA) in terms of equivalent body magnitude'' (emb) level versus signal power using US Department of Interior/Geological Survey (USGS) epicenter data from documented explosions at the USSR Semipalatinsk test area in Eastern Kazakh. Finally, we test the performance of the procedure on actual NRSA data and estimate that explosions above approximately mb 4.0 at Semipalatinsk correspond with an event rate in the emb signal on the order of one to ten events per hour. We conclude that, to detect and analyze events around the clock at levels below mb 4.0, an automatic event locator must be used to process the output of the procedure described here. 8 refs., 19 figs., 1 tab.

This interim report provides results of the molten salt pump and valve loop testing, lessons learned, and recommendations based on the test results to date. The molten salt pump and valve test loop is intended to demonstrate the effectiveness of full-scale hot and cold salt pumps and valves. The pump and valve testing consists of two pumped loops, one to simulate the hot side of the receiver (565{degree}C, referred to as the hot loop) and one for the cold side (285{degree}C, referred to as the cold loop). Each loop contains a pump and six representative valves scaled for a 60-MW{sub e} commercial solar power plant using molten salt heat transport fluid. The test loop is part of the Molten Salt Subsystem/Component Test Experiment (MSS/CTE), which is being conducted to reduce the technical risk of building and operating commercial solar central receiver plants. The project, managed by Sandia National Laboratories (SNL) with Babcock and Wilcox (B W) as the prime contractor, is cost shared by DOE and six contractors. The hot loop has operated over 2400 hours in the fully automatic sequence mode. The last 500 hours have been through continuous 24-hour, 7-day operation. The hot pump operation hours simulate over 2 years of pump cycles. The cold loop has operated 12 hours in the manual mode; this is because of problems caused in the manufacturing of the pump and motor. 9 refs., 6 figs., 1 tab.

Sandia National Laboratories operates the Primary Standards Laboratory (PSL) for the Department of Energy, Albuquerque Operations Office (DOE/AL). This report summarizes metrology activities that received emphasis in the second half of 1989 and provides information pertinent to the operation of the DOE/AL system-wide Standards and Calibration Program. 7 refs.

The technology that led to very large-scale integrated circuits on silicon chips also provides a basis for new microsensors that are small, inexpensive, low power, rugged, and reliable. Two examples of microsensors Sandia is developing that take advantage of this technology are the microelectronic chemical-sensor array and the radiation-sensing field-effect transistor (RADFET). Increasingly, the technology of chemical sensing needs new microsensor concepts. Applications in this area include environmental monitoring, criminal investigations, and state-of-health monitoring, both for equipment and living things. Chemical microsensors can satisfy sensing needs in the industrial, consumer, aerospace, and defense sectors. The microelectronic chemical-sensor array (Figure 1) may address some of these applications. We have fabricated six separate chemical gas-sensing areas on the microelectronic chemical-sensor array. By using different catalytic metals on the gate areas of the diodes, we can selectively sense several gases. 14 refs., 12 figs.

The characteristics of transportation cask surface contamination and the weeping'' phenomenon are reviewed. In addition, literature that pertains to the possible impact of surface contamination on repository operations is reviewed. This report consists of commentary on and rather extensive excerpts from the published literature on cask surface contamination that may have a bearing on repository risk assessment. In addition, estimates are made of the quantity of contamination that might be present on a cask. These estimates are used to calculate the direct exposure rates to personnel located at several distances from the cask. 15 refs., 15 tabs.

Sandia National Laboratories has conducted research and development in the area of enhanced or unconventional natural gas recovery since the mid-1970's. This report is a compilation, in chronological order, of the formal documentation that has resulted from that work. Since its inception, this R D has covered five general areas, which evolved in roughly the following order: instrumentation, mineback experimentation, propellant fracturing, multiwell experiment, and geoscience. The Department of Energy's U:nconvetnional Gas Program has been the predominant sponsor ofthe work represented in this bibliography. All entries of this bibliography are reports, papers, and abstracts which are available publicly -- either in published journals or as reports available through the National Technical Information Service, US Department of Commerce, 5285 Port Royal Road, Springfield, VA 22161. The Journal of Petroleum Technology and other Society of Petroleum Engineers publications contain many of the journal papers. Sandia National Laboratories reports are the majority of the published reports. Abstracts are included only if they were published.

Preliminary results for the parametric dependences of the 2.63 and 2.65 {mu}m lines of a high-pressure xenon laser are given. The power deposition is varied from 200 to 800 W/cm{sup 3} for gas mixtures of Ar(830 Torr)/Xe(4 Torr), Ar(750 Torr)/Xe(83 Torr) and Ar(621 Torr)/He(210 Torr)/Xe(4 Torr). The 2.65 {mu}m line dominates the 2.63 {mu}m line for all gas mixtures and the ratio of the 2.63 {mu}m line intensity to that for the 2.65 {mu}m line is suppressed by the higher concentration of xenon. 13 refs., 4 figs.

This manual describes the procedures for implementing IMPACT-BRC Version 2.0. IMPACTS-BRC is a generic, radiological assessment code intended to be used by the US Nuclear Regulatory Commission (NRC) to evaluate petitions to classify specific waste streams as below regulatory concern (BRC). The code is designed to demonstrate compliance to BRC standards by modeling and calculating annual radiological impacts to the maximal individual, critical groups, and the general population as the result of transportation treatment, disposal, and post-disposal activities involving low-level radioactive waste. Impacts are calculated for multiple nuclides and pathways depending on data input and treatment and disposal options specified by the code user. The treatment and disposal options include onsite incineration, offsite incineration at municipal and hazardous waste landfills. Included within the disposal options is the ability to calculate impacts from the sorting and/or recycling of metal containers and metal and glass materials. Nuclide-specific accounting is provided to facilitate identification of the critical nuclides and pathways contributing to the impacts. Default environmental and facility parameters are developed from reference treatment/disposal sites. The user has the option to replace default parameters with site-specific parameters to provide more realistic estimation of impacts. 8 refs., 10 figs., 44 tabs.

The split cavity oscillator is a resonant cavity device which can be used to highly modulate the current of a relativistic electron beam for the purpose of generating high power microwaves. It consists of a cylindrical cavity resonator which has been divided into two identical cavities by a conducting foil whose radius is less than the inner radius of the cylinder. The gap between the foil endpoint and cylinder walls forms an annular slot which couples the cavities electromagnetically. Using a particle-in-cell code, we have performed a numerical investigation of SCO structures driven by high current, magnetized, annular, relativistic electron beams. Results are presented which illustrate the dependence of current modulation efficiency and oscillation frequency on injected beam current density. In addition, simulation results are presented for a new, double-foil SCO which indicate significantly enhanced performance in comparison to the single-foil device. 10 refs., 10 figs., 2 tabs.

The purposes of this one day meeting were to identify and to consolidate the issues associated with the performance of dimensional measurement systems as indicated by the results of the DOD Quality Assurance Council, the National Science Foundation, the Rich Walker GIDEP Alert, the B89 Standards Committee's work, IMOG Measurement Technology Subgroup discussions, NIST, and the CAM-I DITS (Dimensional Inspection Technologies Standards) Project. The expected results were a clearer definition and understanding of the problems, establishment of objectives for problem resolution, an approach to resolve the problems, and the identification of potential funding requirements and sources. 10 figs.

The Hypersonic Arbitrary-Body Aerodynamics (HABA) computer program predicts static and dynamic aerodynamic derivatives at hypersonic speeds for any vehicle geometry. It is intended to be used during conceptual design studies where fast computational speed is required. It uses the same geometry and hypersonic aerodynamic methods as the Mark IV Supersonic/Hypersonic Arbitrary-Body Program (SHABP) developed under sponsorship of the Air Force Flight Dynamics Laboratory; however, the input and output formats have been improved to make it easier to use. This program is available as part of the Department 9140 CAE software.

To assist in the repair of the Modular Integrated Video System (MIVS) printed circuit boards, a maintenance or service manual is essential. This manual provides a simplified overview of each PC board and explains the functions of each component. Setup procedures and parts lists for each board are included to minimize the task of aligning the boards and identifying replacement parts.

The Plasma Opening Switch (POS) designed for use on PBFA-2 was operated on the Blackjack 5 generator at Maxwell Laboratories in early 1988. Various switch configurations were tested, with the overall goal of understanding the point at which the switch begins to open, and improving uniformity of opening. Improved load current rate-or-rise and current transfer into high impedance loads were also goals. A baseline-design POS appears to have produced results similar to those seen in an earlier test series of this hardware on Blackjack 5 in 1986. Addition of a second-stage opening switch yielded improvements in the areas mentioned above. Analysis of current signals indicates that switch opening in all geometries was characterized by significant power flow asymmetry downstream of the POS. This report is an analysis of data from this test series.

Part 1 of this review deals with the effects of ionizing radiation on glass in the absence of hydrogen and should be consulted for background information not repeated in Part 2. This part includes information on the behavior of hydrogen in glass and how it is affected by experimental variables such as temperature, pressure, and glass composition. The reaction of hydrogen with irradiated glass is treated next, and finally the effects of ionizing radiation on hydrogen-impregnated glass are summarized. 51 refs., 1 tab.

This MIVS instruction manual provides a detailed description of all the capabilities that this system can perform. It provides step by step instruction for setting up the system parameters and the procedure for initiating surveillance. This information complements the training received prior to field operation of this system. 6 figs., 13 tabs.

The effects of ionizing radiation (e.g., beams of electrons of {gamma}-radiation) on silica and borosilicate glasses are summarized in this review article. In Part 1, irradiation in the absence of hydrogen is considered. The combined effects of hydrogen and irradiation are treated in Part 2. Descriptions and, if available, mechanisms of changes in the glass properties are discussed. Several experimental variables which may affect the outcome of an irradiation procedure are also outlined. 47 refs.

An elastic/plastic material model has been developed for use with the suite of Sandia Engineering Analysis Department finite element codes. This model describes post-yield strain hardening by a power law equation involving the equivalent plastic strain and includes a yield plateau or Lueders strain region. This combination of power law hardening and Lueders strain accurately represents the mechanical behavior of a large number of commonly used engineering materials. The material model is vectorized to take advantage of current super-computer architecture. The model shows only a modest increase in CPU time over the linear hardening material model currently in the codes. Several example problems are presented to show the accuracy and flexibility of the elastic/plastic power law hardening model. 12 refs., 10 figs., 3 tabs.

In this document, masses of the STAR-C power system and an optimized out-of-core thermionic reactor (OTR) power system versus power level are investigated. The impacts of key system parameters on system performance are also addressed. The STAR-C is mass competitive below about 15 kWe, but at higher power levels the scalability is relatively poor. An optimized OR is the least massive space nuclear power system below 25 kWe, and scales well to 50 kWe. The system parameters that have a significant impact on the scalability of the STAR-C are core thermal flux, thermionic converter efficiency, and core length to diameter ratio. The emissivity of the core surface is shown to be a relatively unimportant parameter. For an optimized OR power system, the most significant system parameter is the maximum allowable fuel temperature. It is also shown that if advanced radiation-hardened electronics are used in the satellite payload, a very large mass savings is realized. 10 refs., 23 figs., 7 tabs.

ANEOS is an in-line software package which provides thermodynamic information for shock physics codes. Solids, liquids, vapors, plasmas and phase mixtures are considered in a thermodynamically consistent and complete manner. The package is flexible and easy to use. This users manual contains input instructions, examples, and descriptions of user output. 14 refs.

Techniques for propagating data and parameter uncertainties in high-level waste (HLW) repository performance assessment models are discussed. Uncertainty analysis techniques techniques ascribe quantitative measures of reliability to model predictions. Both 10 CFR 60 and 40 CFR 191 require consideration of uncertainties, including uncertainties in data and parameters, in the performance assessment of an HLW repository system. Four categories of uncertainty analysis methods are discussed: Monte Carlo simulation, replacement models (response surface techniques), differential techniques (direct, adjoint, and Green's function technique), and geostatistical techniques (stochastic modeling using Monte Carlo simulation and spectral analysis). Advantages, disadvantages and applications of each technique are presented. Propagation of uncertainties through multiple, linked models is also discussed. Application of these techniques to sensitivity analysis is also presented. Sensitivity analyses can be useful to uncertainty studies because the number of parameters included in the uncertainty analysis can be reduced by eliminating those parameters for which the uncertainty has a minimal effect on the performance variable(s).

For improved reliability and safety, nuclear power plants are designed with redundant safety systems, many of which also have redundant trains of equipment within the system. However, the very high reliability theoretically achievable through the use of redundancy is often compromised by single events that can individually render redundant components unavailable (common cause failure (CCF) events). As evidenced by the results of probabilistic risk assessments (PRAs) and by historical experience with nuclear power plant operations, CCF events are usually major contributors to the risk posed by nuclear power plant operation. Thus, it is important that PRAs recognize the potential for CCF events and realistically account for CCF contributions to system unavailability and plant risk. Much progress has been made over the years in the area of CCF analysis, including the development of both qualitative analysis methods. Until now, however, CCF methodologies have not explicitly and systematically accounted for the impact of plant-specific defenses, such as design features and operational and maintenance policies, in place to reduce the likelihood of failure occurrences at nuclear power plants. Recognizing the importance of this issue, the NRC has funded a research effort that has focused on developing the cause-defense methodology for CCF analysis and prevention. This report presents the results of this research. Specifically, this report discusses the development of (1) procedures for identifying the potential for CCF events at individual nuclear power plants and (2) cause-defense matrices for analysis of CCF events. Also, new concepts and more precise definitions are introduced to enhance CCF terminology and interpretation of historical event data. Contains 35 refs., 8 figs., 32 tabs.

The performance and availability of the five basic identity verifiers can now meet the requirements of most physical and information security needs. However, with the lack of any evaluation standards, the independent testing of verifiers requires care with due consideration for both parts of the verifier systems; the verifier hardware and software and the user with his biometric features which is the least consistent part of the system. The method of testing and data processing must be done with care and should be reported along with reduced results.

Integrated access control portals (booths) are fast becoming a familiar part of medium-to-high security systems. Facilities wishing to expand their operations or to tighten their security, while at the same time limit or reduce their security operating expenses, find the application of portals to be a cost-effective alternative to manned entry points. With the advent of microprocessors and commuter control, portals may now be designed to operate in an automated (and in some cases, stand-alone) mode, requiring human intervention only in the event of an alarm condition. Because human intervention is minimized, a single guard can monitor the operation of several portals and thereby control multiple entry points. This report presents a description of a typical portal and its functioning and provides the information necessary to formulate a set of portal requirements. 8 figs.