Publications

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.