Recently, significant progress has been made in using finite-difference analysis cod es to simulate the responses of complex structures due to direct lightning. Advances have been made in interfacing a finite-difference code with commercial computer aided design tools, in suppressing a weak instability associated with the thin-wire algorithm for modeling conductors much smaller than a cell size, and in visualizing the results with color movies. Preliminary comparisons between the results of the finite-difference code and the results obtained during a recent rocket-triggered lightning test are also presented.
The US Department of Energy`s Nuclear Plant Lifetime Improvement Program is investigating the use of prognostic monitoring to extend the operational lifetime of specific equipment. Benefits of these achievements will include safer and more reliable nuclear Plants, reduced maintenance costs, and increased lifetime of equipment. This report describes the development and application of a monitoring system designed to predict starting system performance of Emergency Diesel Generators. The monitor system is evaluated on two different engines, each using a different method of starting.
Portable acoustic wave sensor (PAWS) systems are being developed for real-time, on-line monitoring of volatile organic compounds (VOC`s). These systems are built around acoustic wave (SAW) devices coated with viscoelastic polymers. Two independent responses of the SAW sensor, wave velocity and wave attenuation, are measured to provide information about the chemical species sorbed by the coating. Rapid, reversible detection of gas phase volatile organics has been demonstrated for process monitoring and waste minimization in environmentally conscious manufacturing (ECM) applications and for documenting contaminant concentrations in remediation efforts.
The Hard Rock Penetration program is developing technology to reduce the costs of drilling and completing geothermal wells. Current projects include: lost circulation control, rock penetration mechanics, instrumentation, and industry/DOE cost shared projects of the Geothermal Drilling organization. Last year, a number of accomplishments were achieved in each of these areas. A new flow meter being developed to accurately measure drilling fluid outflow was tested extensively during Long Valley drilling. Results show that this meter is rugged, reliable, and can provide useful measurements of small differences in fluid inflow and outflow rates. By providing early indications of fluid gain or loss, improved control of blow-out and lost circulation problems during geothermal drilling can be expected. In the area of downhole tools for lost circulation control, the concept of a downhole injector for injecting a two-component, fast-setting cementitious mud was developed. DOE filed a patent application for this concept during FY 91. The design criteria for a high-temperature potassium, uranium, thorium logging tool featuring a downhole data storage computer were established, and a request for proposals was submitted to tool development companies. The fundamental theory of acoustic telemetry in drill strings was significantly advanced through field experimentation and analysis. A new understanding of energy loss mechanisms was developed.
Sandia National Laboratories (SNL) is in the final stages of developing a Universal Authenticated Item Monitoring System (AIMS). When completed, AIMS will provide applicable agencies in the US government, and those in the International arena, with a secure and convenient method of monitoring the physical status of selected items. The benefit derived from this development activity will be the commercial availability of an item monitoring system with the capability for ``quick set-up`` monitoring, as well as long-term unattended monitoring. The AIMS includes a variety of sensors, a robust and authenticated radio frequency (RF) communication link, a Receiver Processing Unit (RPU), and an inspector-friendly personal computer (PC) interface for collecting, sorting, viewing and archiving pertinent event histories. The system will provide the capability to monitor selected items in a real-time mode, a remotely interrogated mode, and a stand-alone, unattended data collection mode. The sensor suite under development includes advanced motion sensors, interior volumetric intrusion sensors, Re-usable, In-situ Verifiable Authenticated (RIVA) fiber-optic seal sensors, generic utility sensors (to accommodate contact closure inputs), and radiation and environmental sensors. A new generation authentication algorithm recently has been developed that provides a high degree of system security 121. The AIMS has potential safeguards applications in the areas of arms control and treaty verification military asset control, International Atomic Energy Agency (IAEA) and Euratom safeguards verification activities, as well as domestic nuclear safeguard activities. Commercial applications could include high-value inventory control and security systems. This paper describes the second-generation AIMS along with its recently expanded sensor suite and enhanced data collection capabilities.
In a joint effort conducted by Sandia National Laboratories, the International Atomic Energy Agency (IAEA), and the Japan Atomic Energy Research Institute (JAERI), an authentication system has been installed at the Fast Critical Assembly (FCA) facility in Tokai-mura, Japan. The purpose of this authentication system is to provide the IAEA with an independent means of authenticating the operator-provided Advanced Containment and Survellance (AC/S) system already in place at the facility. Authentication Controllers were installed at the AC/S Portal Monkor and Penetration Monitor to collect data and to randomly test sensor functions between IAEA inspections. During each inspection the authentication data is collected with an Inspector`s portable computer and printed for comparison to the data recorded by the AC/S system. Installation of the authentication equipment took place in November 1991 and a three-month field test began in December 1991. This paper will describe the authentication system, the operator interface, and the preliminary results of the field tests.
A public-key Treaty Data Authentication Module (TDAM) based on the National Institute of Standards and Technology (NIST) Digital Signature Standard (DSS) has been developed to support treaty verification systems. The TDAM utilizes the Motorola DSP56001 Digital Signal Processor as a coprocessor and supports both the STD Bus and PC-AT Bus platforms. The TDAM is embedded within an Authenticated Data Communication Subsystem (ADCS) which provides transparent data authentication and communications, thereby concealing the details of securely authenticating and communicating compliance data and commands. The TDAM has been designed according to the NIST security guidelines for cryptographic modules. Public-key data authentication is important for support of both bilateral and multi-lateral treaties. 8 refs.
Parametric weld size predictions, in which weld size and shape are predicted given a knowledge of material and process parameters, offer a great deal of benefit to the welding engineer. This is so because the technique promises to replace expensive and time-consuming lab or shop activity followed by destructive examination with simple numeric or nomographic calculations. The work to be presented here uses a simple two-dimensional axisymmetric spot-on-plate computer simulation in which thermal diffusivity vs temperature is varied.
The change in the world military posture and the reduction in military personnel require the flexible and rapid deployment of priority defense assets. Air Force security personnel and operators must maintain the ability to secure these deployed assets and receive advanced warning of threats. The Air Force will meet this need through the Dispersed Integrated Security System (DISS). The system will be rapidly deployable, relocatable, support mission flexibility, and be capable of intrusion detection, area and alarm display, night assessment, and wireless data communications. Wireless links, as obtained through radio, are quickly deployed and cost less than their hardwire counterpart when labor cost and equipment reuse are considered. DISS communications systems will be flexible and have broad application. By integrating commercial components and using menu-driven setup procedures, low cost, versatile, easy-to-use communication systems will be implemented to meet Air Force user requirements and provide desired capabilities.
It has long been United States Government (USG) policy to actively support nuclear nonproliferation efforts, as evinced in the 1970 US ratification of the Nuclear I Nonproliferation Treaty (NPT) and the 1978 US Voluntary Treaty with the IAEA (INFCIRC/288). Under INFCIRC 288, US facilities without direct national security involvement are eligible for International Atomic Energy Agency (IAEA) safeguards. Throughout the past decade, the IAEA has selected one or two US facilities for implementation of IAEA safeguards at a given time. The facilities selected have generally been those which allowed the IAEA to test new or advanced safeguards techniques, facilities which were prototypical or similar to other nuclear facilities which they will have to safeguard in other countries, or facilities which have been engaged in international commerce in nuclear materials. The US is now actively addressing issues of the interim and permanent disposal of nuclear waste and spent nuclear fuel -- the back end of the open US nuclear fuel cycle. The Nuclear Waste Policy Act (NWPA) of 1982 designated the US Department of Energy (DOE) to be responsible for the long term storage and isolation from the biosphere of spent nuclear fuel (SNF) and high-level waste (HLW) and created the DOE Office of Civilian Radioactive Waste Management (OCRWM) to develop, construct, and manage the Civilian Radioactive Waste Management System (CRWMS). Refinements to the NWPA occurred in 1987 in the Nuclear Waste Policy Amendments Act of 1987. CRWMS facilities will be eligible for IAEA safeguards. They are likely to be selected because they will be among the first SNF and HLW disposal operations worldwide.
As the US nuclear stockpile is reduced, large numbers of nuclear components must be placed in storage. The necessity for periodic inventories of these components as well as the act of placement of the components in storage areas could result in increased radiation exposure to operations personnel. The use of robotics can significantly reduce or even eliminate such exposure. An automated system is being designed in a project at Sandia Laboratories to allow an operator to remotely stack and retrieve component containers in storage areas using a robotic loader and a portable control console. The operator need not enter the storage area. Operator commands for the loader would be implemented through a supervisory architecture that would insure that the loader did not violate safety constraints. Individual aspects of the loader`s activities would be automated to reduce possible operator errors for many repetitive tasks. The loader will be outfitted with appropriate sensors so that the supervisory controller can enforce safe operations. The system will be configured so that monitoring of components for accountability can be accomplished.
To achieve the goal of remediating waste sites throughout its complex and of bringing its facilities into full compliance by the year 2019, the DOE has established the Office of Environmental Restoration and Waste Management (E). Within E, the Office of Technology Development (OTD) has been created to develop technologies that will support DOE`s cleanup goal. The OTD is accelerating remediation technology application by leveraging the expenditure of available funds through international technology development and demonstration projects. These projects will address EM`s environmental restoration and waste management needs. For this reason, the OTD has created the International Technology Exchange Program (ITEP) whose primary objective is to effect collaboration among governments, industries, and educational institutions to identify worldwide technologies suitable for this purpose. These technologies should also meet US commercial needs. The ITEP will also serve as a mechanism for transferring technologies developed under DOE sponsorship to US industry for ultimate application in the international arena.
The US Department of Energy (DOE) has committed to the remediation of waste sites throughout its complex, and has recognized that it can accelerate its technology development efforts and leverage the expenditure of available funds through an international cooperation among government entities, private industry, and educational institutions. To support the technology transfer of environmental information, the DOE has sponsored the development of EnviroTRADE - an international information system that will facilitate the exchange of environmental restoration and waste management technologies worldwide. During DOE`s fiscal year 1992, a beta prototype is being developed by Sandia National Laboratories (SNL). During fiscal year 1993 and beyond, the full system will be developed and networked among international users. The system will contain profiles on both environmental restoration/waste management needs and foreign/domestic technologies. Users will be able to identify matches between worldwide needs and available or emerging technologies. Where matches between needs and existing technologies are not found, the system will identify the potential for development of new and innovative technologies to address environmental problems. EnviroTRADE will also provide general information on international environmental restoration and waste management organizations, sites, activities, and contacts.
As part of the update of the Safety analysis Report (SAR) for the Annular Core Research Reactor (ACRR), operational limiting events under the category of inadvertent withdrawal of an experiment while at power or during a power pulse were determined to be the most limiting event(s) for this reactor. This report provides a summary of the assumptions, modeling, and results in evaluation of: Reactivity and thermal hydraulics analysis to determine the amount of fuel melt or fuel damage ratios; The reactor inventories following the limiting event; A literature review of post NUREG-0772 release fraction experiment results on severe fuel damages; Decontamination factors due to in-pool transport; and In-building transport modeling and building source term analysis.
As part of the Direct Optical Initiation (DOI) program, an assessment of the possibility of introducing lightning energy into an exclusion region via an Optical Barrier Feedthrough (OBF) is being carried out. One postulated penetration mechanism is the tracking of current past the OBF on the surface of the dielectric optical fiber itself. During September and October of 1991, a series of tests was conducted on a closed metallic cylindrical test object representing the electrical exclusion region of a weapon. Median-level (30-kA) and severe (200-kA) simulated lightning return strokes, singly, doubly, and in combination with a moderate continuing current, were attached directly to the exterior portion of a fiber optic cable, which penetrated through a hole of controlled size into the interior of the exclusion region. The thickness of the barrier surrounding the hole was 0.06 in. Attempts were made to measure any conducted current flowing on the fiber at distances of 1 and 4 inches from the interior surface of the stainless steel top of the cylinder. Test parameter variations included diameter of the penetration hole (475 and 500 microns), length of the exterior portion of the cable and whether or not its jacket was present, and the applied test currents. It is concluded that no signal above measurement noise was recorded on any of the data shots that made up the test series. Measurement resolution was of the order of several amperes. Based on the highest recorded response of 8.5 A, corresponding to a 200-kA input, the OBF can be characterized by a direct-strike lightning attenuation factor of approximately 5 {times} lO{sup {minus}5} or better. Based on the more typically observed noise level of a few amps, the attenuation is commensurately greater.
Detailed mineralogical studies of the matrix and fracture-fill materials of a large number of samples from the Rustler Formation have been carried out using x-ray diffraction, high-resolution transmission electron microscopy, electron microprobe analysis, x-ray fluorescence, and atomic absorption spectrophotometry. These analyses indicate the presence of four clay minerals: interstratified chlorite/saponite, illite, chlorite, and serpentine. Corrensite (regularly stratified chlorite/saponite) is the dominant clay mineral in samples from the Culebra dolomite and two shale layers of the lower unnamed member of the Rustler Formation. Within other layers of the Rustler Formation, disordered mixed chlorite/saponite is usually the most abundant clay mineral. Studies of the morphology and composition of clay crystallites suggest that the corrensite was formed by the alteration of detrital dioctahedral smectite in magnesium-rich pore fluids during early diagenesis of the Rustler Formation. This study provides initial estimates of the abundance and nature of the clay minerals in the Culebra dolomite in the vicinity of the Waste Isolation Pilot Plant.
This document describes an automated, data acquisition system designed to test the performance of remote badge readers. These readers interrogate badges by transmitting and receiving energy. The performance of such readers is statistical and can be affected by geometrical and environmental variables. Characterization of performance, therefore, requires multiple measurements while the known variables are controlled. Automation makes this a practical task.
The contribution of essential service water (ESW) system failure to core damage frequency has long been a concern of the NRC. The objective of this study is to assess the safety significance of the loss of ESW systems in LWRs relative to core damage frequency (CDF) and perform a limited value/impact analysis of potential modifications to solve ESW vulnerabilities using a prototypical (pilot) plant. Previous studies indicate that service water systems contribute from < 1% to 65% of the total internal CDF. For the pilot plant analyzed, common ESW vulnerabilities are failure of standby service water pumps to start, backflow through check valves for cross-tied pumps, and failure of normally closed isolation valves in diesel generator cooling loops to open on demand. For the potential modifications evaluated for the pilot plant, the results showed that they could reduce the CDF by as much as 33 percent. However, the dollars per person REM measures resulting from various groups of these modifications significantly exceeded the current criteria of $1000. The results, since they only apply to the prot plant, are not typical of all LWRs. Due to the importance of service water to CDF and the plant specific nature of ESW systems, there could be plants for which there would be cost-effective modifications. Additional analysis would be required to identify them.
The low field (E{congruent}2kV/cm) Metal Oxide Varistor (MOV) is a voltage regulation device. This report describes a technique for performing DC characteristic measurements on a MOV. The varistor is in the feedback loop of a high voltage operational amplifier. A current source forces a staircase current waveform through a MOV. An operational amplifier provides the required applied voltage to maintain the desired values of current through the varistor. The current values change at a maximum rate of 33.3 readings per second and a high speed voltmeter measures the varistor voltage. The maximum available current and voltage at present are 5 mA and 10 kV respectively. Examples of its use are with data from the MC3596 and XMC4317.
The performance Assessment (PA) Department of Sandia National Laboratories annually compares the Waste Isolation Pilot Plant (WIPP) with the Environmental Protection Agency`s Environmental Radiation Protection Standards for Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes, 40 CFR 191. To assist the analyst in these comparisons the PA Department developed CAMCON, the Compliance Assessment Methodology Controller, which creates an analysis system out of the diverse computer modeling codes needed for this interdisciplinary comparison. This reference manual describes the use of most of the codes in the CAMCON system that an analyst may use when performing the PA comparisons. Although some of the codes included in CAMCON have their own user`s guide, this manual summarizes these guides as well to provide the user with one comprehensive document of the codes within the CAMCON system.
Site-characterization, data interpretation, and modeling efforts have been conducted for the Waste Isolation Pilot Plant (WIPP), a US Department of Energy facility, in southeastern New Mexico as part of the evaluation of the suitability of the bedded salt of the Salado Formation for isolation of defense transuranic wastes. The Culebra Dolomite Member of the Rustler Formation is the most transmissive and laterally continuous hydrogeologic unit above the Salado Formation and is considered to be the principal offsite pathway for radionuclide transport in the subsurface, should a breach of the repository occur. The potential importance of this offsite pathway has motivated the design and implementation of tests to characterize the solute-transport properties of the Culebra dolomite. On a regional scale, long-term pumping tests have been performed and analyzed to provide information concerning the broad hydrologic flow characteristics of the Culebra dolomite. At the local (or hydropad) scale, conservative (i.e., nonreactive) tracer tests have been performed to characterize the solute-transport properties of the Culebra dolomite. The tracer-test interpretations presented in this report were performed by INTERA Inc. under contract to SNL. The tracer tests and their interpretation provide data for use in performance-assessment calculations of site suitability for waste isolation. In particular, transport parameters determined from these tests are used as input for offsite solute-transport simulations.
An essential part of the license application for a geologic repository will be the demonstration of compliance with the standards set by the Environmental Protection Agency. The performance assessments that produce the demonstration must rely on models of various levels of detail. The most detailed of these models are needed for understanding thoroughly the complex physical and chemical processes affecting the behavior of the system. For studying the behavior of major components of the system, less detailed models are often useful. For predicting the behavior of the total system, models of a third kind may be needed. These models must cover all the important processes that contribute to the behavior of the system, because they must estimate the behavior under all significant conditions for 10,000 years. In addition, however, computer codes that embody these models must calculate very rapidly because of the EPA standard`s requirement for probabilistic estimates, which will be produced by sampling thousands of times from probability distributions of parameters. For this reason, the total-system models must be less complex than the detailed-process and subsystem models. The total-system performance is evaluated through modeling of the following components: Radionuclide release from the engineered-barrier system. Fluid flow in the geologic units. Radionuclide transport to the accessible environment. Radionuclide release to the accessible environment and dose to man.
A sensor-based intelligent control system is described that utilizes a multiple degree-of-freedom robotic system for the automated remote manipulation and precision docking of large payloads such as waste canisters. Computer vision and ultrasonic proximity sensing are used to control the automated precision docking of a large object with a passive target cavity. Real-time sensor processing and model-based analysis are used to control payload position to a precision of {plus_minus} 0.5 millimeter.
Historical and projected inventories of spent fuel from commercial light-water nuclear reactors exhibit diverse decay characteristics and ages. This report summarizes a preliminary reexamination of a method for determining equivalent thermal loads for the range of spent fuel expected at a potential underground repository. The method, known at the Equivalent Energy Density (EED) concept, bases its equivalence criteria on the assumption that a given waste will produce worst-case thermomechanical effects equal to worst-case thermomechanical effects produced by a baseline waste, provided that the thermal energy deposited in the host rock over a specified deposition period is the same for both waste descriptions. To test this assumption, temperature histories at representative locations within the host rock were calculated using layouts defined by the EED concept and four deposition periods (20, 50, 100, and 300 years). It was found that the peak temperatures at near-field locations were best matched by the shorter deposition periods of 20 and 50 years. However, due to the sensitivity of the near-field environment to short-term canister-to-canister interactions, caution,should be used when choosing a near-field deposition period. At the location chosen to represent the far-field, a 300-year deposition period provided reasonable correspondence of peak temperature responses for all waste descriptions examined.
LLUVIA-II is a program designed for the efficient solution of two- dimensional transient flow of liquid water through partially saturated, porous media. The code solves Richards equation using the method-of-lines procedure. This document describes the solution procedure employed, input data structure, output, and code verification.
A complete edge-weighted directed graph on vertices 1,2,...,n that assigns cost c(i,j) to the edge (i,j) is called Monge if its edge costs form a Monge array, i.e., for all i < k and j < l, c[i, j]+c[k,l]{le} < c[i,l]+c[k,j]. One reason Monge graphs are interesting is that shortest paths can be computed quite quickly in such graphs. In particular, Wilber showed that the shortest path from vertex 1 to vertex n of a Monge graph can be computed in O(n) time, and Aggarwal, Klawe, Moran, Shor, and Wilber showed that the shortest d-edge 1-to-n path (i.e., the shortest path among all 1-to-n paths with exactly d edges) can be computed in O(dn) time. This paper`s contribution is a new algorithm for the latter problem. Assuming 0 {le} c[i,j] {le} U and c[i,j + 1] + c[i + 1,j] {minus} c[i,j] {minus} c[i + 1, j + 1] {ge} L > 0 for all i and j, our algorithm runs in O(n(1 + 1g(U/L))) time. Thus, when d {much_gt} 1 + 1g(U/L), our algorithm represents a significant improvement over Aggarwal et al.`s O(dn)-time algorithm. We also present several applications of our algorithm; they include length-limited Huffman coding, finding the maximum-perimeter d-gon inscribed in a given convex n-gon, and a digital-signal-compression problem.
This report documents the lightning threat warning system at the Tonopah Test Range and the technology it uses. The report outlines each of the system's individual components and the information each contributes.
Three seals constructed of compressed crushed salt blocks have been successfully emplaced vertically down in three 97-cm (38.2-in.) diameter boreholes drilled from the repository horizon of the Waste Isolation Pilot Plant. All three seals are designed to allow fluid flow measurements and two of the seals are heavily instrumented with pressure and hole closure gages. The seals are providing structural and fluid flow data useful for evaluating predictive models and long-term crushed salt seal performance. Results to date, 1100 to 1450 days after seal emplacement, indicate the current average densities of the seals to be about 85% of intact rock salt. Relative densities have increased about 2% since emplacement. The results to date are consistent with previous laboratory and modeling studies of crushed salt behavior. This report provides information necessary for evaluating these data including as-built test configurations, construction histories, and instrumentation descriptions. Seal and instrumentation installation techniques are also described.
The ECM Newsletter is published at Sandia National Laboratories to disseminate information obtained from research and development programs and demonstration, testing, and evaluation projects at research facilities on environmentally conscious manufacturing processes. This issue covers the topics of Life Cycle Assessment, etching processes for Kovar, cleaning of plutonium surfaces, non- chromate conversion coatings for aluminum,, and circuit board manufacturing.
The Mixed-Waste Landfill Integrated Demonstration (MWLID) has been assigned to Sandia National Laboratories (SNL) by the US Department of Energy (DOE) Office of Technology Development. The mission of the MWLID is to assess, implement and transfer technologies and systems that lead to quicker, safer, and more efficient remediation of buried chemical and mixed-waste sites. The MWLID focus is on two landfills at SNL in Albuquerque, New Mexico: The Chemical Waste Landfill (CWL) and the Mixed-Waste Landfill (MWL). These landfills received chemical, radioactive and mixed wastes from various SNL nuclear research programs. A characterization system has been designed for the definition of the extent and concentration of contamination. This system includes historical records, directional drilling, and emplacement membrane, sensors, geophysics, sampling strategy, and on site sample analysis. In the remediation task, in-situ remediation systems are being designed to remove volatile organic compounds (VOC`s) and heavy metals from soils. The VOC remediation includes vacuum extraction with electrical and radio-frequency heating. For heavy metal contamination, electrokinetic processes are being considered. The MWLID utilizes a phased, parallel approach. Initial testing is performed at an uncontaminated site adjacent to the CWL. Once characterization is underway at the CWL, lessons learned can be directly transferred to the more challenging problem of radioactive waste in the MWL. The MWL characterization can proceed in parallel with the remediation work at CWL. The technologies and systems demonstrated in the MWLID are to be evaluated based on their performance and cost in the real remediation environment of the landfills.
The structural, electrical and magnetic properties are compared for three superconducting Tl-Ca-Ba-Cu-O thin films prepared by different deposition and sintering protocols. One film containing a mixture of Tl{sub 2}Ca{sub 2}Ba{sub 2}Cu{sub 3}O{sub x} and Tl{sub 2}Cu{sub 1}Ba{sub 2}Cu{sub 2}O{sub y} structural phases has the best superconducting properties. Deposition of a Tl-free Ca-Ba-Cu-O precursor film followed by sintering in Tl-O vapor may be the preferred protocol to obtain a single structural phase.
Sandia National Laboratories (SNL) designs, tests and operates a variety of accelerators that generate large amounts of high energy Bremsstrahlung radiation over an extended time. Typically groups of similar accelerators are housed in a large building that is inaccessible to the general public. To facilitate independent operation of each accelerator, test cells are constructed around each accelerator to shield it from the radiation workers occupying surrounding test cells and work-areas. These test cells, about 9 ft. high, are constructed of high density concrete block walls that provide direct radiation shielding. Above the target areas (radiation sources), lead or steel plates are used to minimize skyshine radiation. Space, accessibility and cost considerations impose certain restrictions on the design of these test cells. SNL Health Physics division is tasked to evaluate the adequacy of each test cell design and compare resultant dose rates with the design criteria stated in DOE Order 5480.11. In response SNL-Health Physics has undertaken an intensive effort to asses existing radiation shielding codes and compare their predictions against measured dose rates. This paper provides a summary of the effort underway and its results.
Here at Sandia, I design new weapon components using PRO-ENGINEER and find that not only am I responsible for the initial design, but that I must be able to justify that design and show that I have analyzed the design for stress, considering thermal, static, and dynamic conditions. I must be able to create models at a reasonable cost using stereolithography. I must be able to create vivid graphic arts presentations for managements approval, if I want the design to be accepted. I must be able to communicate my design to the production people for comment. These problems, plus others must be done in a timely manner with a minimum of paper involved, and less money than ever before. Therefore, Rapid Prototyping takes on an more important stature than originally proposed, and I would like to show you a rapid prototyping process using PRO-ENGINEER as the fundamental base from which to operate.
A previous paper showed that for condensed phase explosives, the C-J density of the detonation product gases correlates to the initial density of the unreacted explosive by a simple power function. This paper extends that correlation to the very low density region which includes detonation of suspended particles of explosives in air as well as gas phase detonations. Extending this correlation of experimental data by an additional three orders of magnitude caused a slight change in the empirical constants of the correlation.
We have used a combination of methods to probe the structure and kinetics of electron beam induced damage in a monolayer of PF{sub 3} on Ru(001). This is a particularly rich system, in which molecularly adsorbed PF{sub 3} is reduced to PF{sub 2}, PF and P by electron bombardment. The concentrations and kinetics of damage by 550 eV electrons are measured as a function of surface temperature (100 to 300 K) and PF{sub 3} coverage using soft x-ray photoemission spectroscopy (SXPS) excited by synchrotron radiation. Structures of fragments and ion desorption kinetics are measured using electron stimulated desorption ion angular distribution (ESDIAD). Evidence is seen for quenching of Desorption induced by electronic transitions (DIET) processes via intermolecular interactions at high coverages. Damage rates and product distributions vary with temperature, due to a competition between DIET and thermal kinetic processes.
This bulletin presents fabrication methods helpful to industry. This issue contains articles on the use of computers in fast casting, techniques for optimizing encapsulation, high quality electroformed parts, improved welding with detection of contaminants, and special machine guards for enhanced safety. (GHH)
Probabilistic risk assessment studies are being extended to include a wider spectrum of reactor plants than was considered in NUREG-1150. There is a need for computationally simple models of direct containment heating (DCH) that could be used for screening studies aimed at identifying potentially significant contributors to overall risk. The two-cell kinetic model developed here is an extension of the two-cell equilibrium model developed previously, which captured a major mitigating feature due to containment compartmentalization. This extension of the equilibrium model represents additional mitigating features resulting from two kinetic competitions: time-of-flight limitations to debris/gas heat transfer and debris oxidation, and the noncoherence or reactor coolant system blowdown with debris residence in the atmosphere. Predictions of containment pressurization and hydrogen production are compared to experiment data taken in the Surtsey facility located at Sandia National Laboratories.
Epitaxial films of Ba{sub 2}YCu{sub 3}O{sub 7-{delta}} (BYCO) as thin as 250 {Angstrom} and with J{sub c}`s approaching those of the best in situ grown films can be formed by co-evaporating BaF{sub 2}, Y, and Cu followed by a two-stage anneal. High quality films of these thicknesses become possible if low oxygen partial pressure [p(O{sub 2}) = 4.3 Torr] is used during the high temperature portion of the anneal (T{sub a}). The BYCO melt line is the upper limit for T{sub a}. The use of low p(O{sub 2}) shifts the window for stable BYCO film growth to lower temperature, which allows the formation of smooth films with greater microstructural disorder than is found in films grown in p(O{sub 2}) = 740 Torr at higher T{sub a}. The best films annealed in p(O{sub 2}) = 4.3 Torr have J{sub c} values a factor of four higher than do comparable films annealed in p(O{sub 2}) = 740 Torr. The relationship between the T{sub a} required to grow films with the strongest pinning force and p(O{sub 2}) is log [p(O{sub 2})] {proportional_to} T{sub a}{minus}{sup 1a} independent of growth method (in situ or ex situ) over a range of five orders of magnitude of p(O{sub 2}).
We have used 2.0-{mu}sec microwave pulses at a frequency of 2.856 GHz to rapidly heat thin amorphous yttrium-barium-copper-oxide (YBCO) films deposited onto silicon substrates. The samples were irradiated inside a WR-284 waveguide by single-pass TE{sub 10} pulses in a traveling wave geometry. X-ray diffractometry studies show that an amorphous-to-crystalline phase transition occurs for incident pulse powers exceeding about 6 MW, in which case the amorphous YBCO layer is converted to Y{sub 2}BaCuO{sub 5}. Microscopy of the irradiated film reveals that the phase transition is brought about by melting of the YBCO precursor film and crystallization of the molten layer upon solidification. Time-resolved in situ experiments of the microwave reflectivity (R) and transmissivity (T) show that there is an abrupt change in R for microwave pulse powers exceeding the melt threshold, so that measurements of R and T can be used to monitor the onset of surface melting.
This paper reports the phase-one results of a planned longitudinal study of the incidence of entrepreneurship among inventors who were employees of national laboratories. A survey of 192 inventors employed by national laboratories and 24 ex-employee inventors who became entrepreneurs provided data for comparison of situational and attitudinal variables. Significant differences in attitudes (as measured by the Entrepreneurial Attitude Orientation Scale) were found between inventors who have not become entrepreneurs and those who have. The differences in perceptions of situational variables between the two groups was significant for only two of the seven dimensions tested.
In order to resolve questions regarding the source of the extended linear viscosity-concentration regime in rod-like systems the distribution of orientations in confined systems has to be determined and related to changes in viscosity. In this work we describe our experimental and computer simulation studies on systems of neutrally buoyant suspensions of rod-like particles confined by the walls of a cylindrical container.
Recent results from light ion fusion experiments on the Particle Beam Fusion Accelerator (PBFA II) are reported. Intense proton beams have been used to drive two different types of targets. In the thermal source targets, the proton beam heated a low-density foam. The specific power deposition of the proton beam in the foam exceeded 100 TW/gm. In the spherical hydrodynamic targets, the proton beam heated a thin-walled deuterium gas-filled target directly, producing a radial convergence of the deuterium of about 6. In order to increase the specific power deposition in the target, we are developing focused lithium beams. A preformed lithium ion source has been produced using a two-step laser evaporation and ionization approach. This preformed source provides the basis for experiments being planned to reduce the divergence of the lithium beam, a critical step in demonstrating the feasibility of light ion fusion.
The first major round of target experiments driven by intense light ion beams was conducted during August and September 1991. In these experiments, intense proton beams were used to drive two different types of targets. We attempted to obtain information on the two separable issues of ion deposition and implosion hydrodynamics. Ion deposition was studied using a low density hydrocarbon foam contained within a cylindrical gold shell. Implosion hydrodynamics was studied using an ion driven exploding pusher configuration in which the ion beam heated the shell directly, exploding it both outward and inward. One of the main objectives of the experiments was to determine the extent to which we could diagnose the ion deposition and the subsequent behavior of the targets. The diagnostics included time-integrated and time-resolved x-ray pinhole cameras, time-integrated and time-resolved grazing incidence x-ray spectrometers, an 11-channel filtered x-ray diode (XRD) array, an 11-channel PIN diode array, an energy-resolved 1-dimensional imaging x-ray streak camera, a transmission grating spectrometer, an elliptical crystal x-ray spectrograph, and a bolometer. Intense beam diagnostics included an ion movie camera and an off-axis 1D slit imaging magnetic spectrograph for obtaining Rutherford-scattered ion images, momenta, and ion power densities.
The last decade has offered many challenges to the welding metallurgist: new types of materials requiring welded construction, describing the microstructural evolution of traditional materials, and explaining non-equilibrium microstructures arising from rapid thermal cycle weld processing. In this paper, the author will briefly review several advancements made in these areas, often citing specific examples of where new insights were required to describe new observations, and to show how traditional physical metallurgy methods can be used to describe transformation phenomena in advanced, non-traditional materials. The paper will close with comments and suggestions as to the needs required for continued advancement in the field.
An improved technology to extract VOCs from the unsaturated zone has developed into a cooperative Environmental Restoration and Technology Development effort. This cooperation is important because the timing of an innovative technology demonstration is critical to the transfer of that technology into an ER remedial action decision. The Mixed-Waste Landfill Integrated Demonstration (MWLID) Program will be demonstrating a Thermal Enhanced Vapor Extraction System that will improve existing vacuum vapor extraction technology by applying in-situ soil heating. Combined demonstrations of vacuum vapor extraction and both powerline frequency and radiofrequency soil heating technologies began in FY92.
SAFSIM (System Analysis Flow SIMulator) is a FORTRAN computer program that provides engineering simulations of user-specified flow networks at the system level. It includes fluid mechanics, heat transfer, and reactor dynamics capabilities. SAFSIM provides sufficient versatility to allow the simulation of almost any flow system, from a backyard sprinkler system to a clustered nuclear reactor propulsion system. In addition to versatility, speed and robustness are primary goals of SAFSIM. The current capabilities of SAFSIM are summarized, and some illustrative example results are presented.
Lost circulation is the loss of drilling fluid from the wellbore to fractures or pores in the rock formation. In geothermal drilling, lost circulation is often a serious problem that contributes greatly to the cost of the average geothermal well. The Lost Circulation Technology Development Program is sponsored at Sandia National Laboratories by the US Department of Energy. The goal of the program is to reduce lost circulation costs by 30--50% through the development of mitigation and characterization technology. This paper describes the technical progress made in this program during the period April 1991--March 1992. 8 refs.
The US Department of Energy`s Office of Technology Development (OTD) has sponsored the development of the Generic Intelligent System Controller (GISC) for application to remote system control. Of primary interest to the OTD is the development of technologies which result in faster, safer, and cheaper cleanup of hazardous waste sites than possible using conventional approaches. The objective of the GISC development project is to support these goals by developing a modular robotics control approach which reduces the time and cost of development by allowing reuse of control system software and uses computer models to improve the safety of remote site cleanup while reducing the time and life cycle costs.
Stimulated reactions on Pt(111) surfaces containing coadsorbates have been probed using laser resonance-enhanced multiphoton ionization (REMPI) spectroscopy of the neutral products. In particular, the electron stimulated dissociation products of NO{sub 2}(a) coadsorbed with up to 0.75 ML of atomic O on Pt(111) has been studied. The coadsorbed O causes a large enhancement of the specific dissociation yield, a narrowing of the NO translational energy, a reduction of the NO internal energy, and the release of the O dissociation fragment into the gas phase. Reactive scattering between coadsorbates has also been studied. Specifically, NO{sub 2}(d) production has been observed during electron-beam irradiation of NO coadsorbed with O{sub 2} on Pt(1211). The NO{sub 2}(d) was indirectly observed as NO({upsilon}=5) and O({sup 3}P{sub J}) gas phase photodissociation fragments. We assign NO{sub 2} production to an electron-stimulated surface reaction involving a collision between energetic O atoms and adsorbed NO.
Heat-Pipe reflux receivers have been identified as a desirable interface to couple a Stirling engine with a parabolic dish solar concentrator. The reflux receiver provides power uniformly and nearly isothermally to the engine heater heads while de-coupling the heater head design from the solar absorber surface design. Therefore, the heat pipe reflux receiver allows the receiver and heater head to be independently thermally optimized, leading to high receiver thermal transport efficiency. Dynatherm Corporation designed and fabricated a screen-wick heat-pipe receiver for possible application to the Cummins Power Generation, Inc. first-generation 4 kW{sub e} free-piston dish-Stirling system, which required up to 30 kW{sub t}. The receiver features a composite absorber wick and a homogeneous sponge-wick on the aft dome to provide sodium to the absorber during hot restarts. The screen wick is attached to the absorber dome by spot welds. Refluxing troughs collect the condensate in a cylindrical condenser and return it directly to the absorber surface. The receiver was fabricated and lamp tested to 16 kW{sub t} throughput by Dynatherm. The receiver has been tested on Sandia`s 60 kW{sub t} solar furnace to a throughput power of 27.5 kW{sub t} and vapor space temperature up to 780{degrees}C. Infrared thermography was used to monitor the entire absorber dome for impending dryout while the receiver was tested. The receiver was started using solar input, without the assistance of electrical pre-heaters. The power was extracted with a gas-gap cold-water calorimeter to simulate the operation of a Stirling engine. The receiver design, thermal performance analysis, flux distribution analysis, test results, and post-test analysis are presented. 11 refs.
Nuclear thermal propulsion systems are envisioned as a fast and efficient form of transportation for the exploration of space. Several nuclear reactor concepts have been proposed. This document discusses SAFSIM (System Analysis Flow SIMulator) which is an engineering computer program that allows the fluid mechanic, heat transfer, and reactor dynamic simulation of the entire propulsion system. SAFSIM currently contains three basic physics modules: (1) fluid mechanics, (2) heat transfer, and (3) reactor dynamics. All three modules are coupled to allow the prediction of system performance. The analyst can employ any or all of the physics modules as the problem dictates.
A summary of the plans to test a prestressed concrete containment vessel (PCCV) model to failure is provided in this paper. The test will be conducted as a part of a joint research program between the Nuclear Power Engineering Corporation (NUPEC), the United States Nuclear Regulatory Commission (NRC), and Sandia National Laboratories (SNL). The containment model will be a scaled representation of a PCCV for a pressurized water reactor (PWR). During the test, the model will be slowly pressurized internally until failure of the containment pressure boundary occurs. The objectives of the test are to measure the failure pressure, to observe the mode of failure, and to record the containment structural response up to failure. Pre- and posttest analyses will be conducted to forecast and evaluate the test results. Based on these results, a validated method for evaluating the structural behavior of an actual PWR PCCV will be developed. The concepts to design the PCCV model are also described in the paper.
The transient transmission of laser activity cavity materials has been measured when they are subjected to 20 ms, fat, and nominal $3 nuclear radiation pulses from Sandia National Laboratories ACRR reactor. Infrasil and 7940 fused silica, and AR and high reflectance coatings have been transient tested at 1.06, 1.73, and 2.03 microns for gamma doses ranging from 0.3 to 0.65 Mrad and neutron fluences ranging from 4.0 to 1.5 10{sup 14} n/cm{sup 2}. pulse widths range from 12 to 250 ms. Transient absorption in 7940 silica and the AR coatings is less than the noise for the conditions of this experiment. At the wavelengths listed above the upper bound for the absorption coefficient of 17940 is 0.00158 cm{sup {minus}1} for single pulse operation. The reflectivity of the HR coating does not change when it is irradiated. Infrasil has both a transient and a permanent induced absorption when it is subjected to radiation. For single pulse operation the absorption coefficients at 1.06, 1.73, and 2.03 microns are 0.0115, 0.0026, and 0.0039 cm{sup {minus}1}, respectively.
The Naval Surface Weapons Laboratory has constructed a small electrical subsystem for the purpose of evaluating electrical upset from various electromagnetic sources. The subsystem consists of three boxes, two of which are intended to be illuminated by electromagnetic waves. The two illuminated boxes are connected by two unshielded cable bundles. The goal of the Navy test series is to expose the subsystem to electromagnetic illumination from several different types of excitation, document upset levels, and compare the results. Before its arrival at Sandia National Laboratories (SNL) the system was illuminated in a mode stirred chamber and in an anechoic chamber. This effort was a continuation of that test program. The Sandia tests involved the test methodology referred to as bulk current injection (BCI). Because this is a poorly-shielded, multiple-aperture system, the method was not expected to compare closely to the other test methods. The test results show that. The BCI test methodology is a useful test technique for a subset of limited aperture systems; the methodology will produce incorrect answers when used improperly on complex systems; the methodology can produce accurate answers on simple systems with a well-controlled electromagnetic topology. This is a preliminary study and the results should be interpreted carefully.
This report describes how small threaded fasteners should be used in threaded connections. Considerable test experience gives many insights into how small threaded fasteners should be used. The test evidence is summarized in this report. The test methods and procedures are described for tension tests to determine strength and ductility. Small threaded fasteners have been used successfully for many years in Sandia applications. Problems have been encountered in manufacturing parts using three fasteners. This report addresses these manufacturing problems and offers recommendations in five areas: (1) design and layout of threaded connections, (2) required depths for tapped holes, (3) characteristics of mating (clamped) surfaces, (4) tensile strength testing procedures and lengths of engagement needed to achieve the full tensile strength of these small fasteners, and (5) installation procedures. 15 refs.
This document serves as the proceedings for the annual project review meeting held by Sandia National Laboratories` Photovoltaic Technology and Photovoltaic Evaluation Departments. It contains information supplied by organizations making presentations at the meeting, which was held July 14--15, 1992 at the Sheraton Old Town Hotel in Albuquerque, New Mexico. Overview sessions covered the Department of Energy (DOE) program, including those at Sandia and the National Renewable Energy Laboratory (NREL), and non-DOE programs, including the EPRI concentrator collector program, The Japanese crystalline silicon program, and some concentrating photovoltaic activities in Europe. Additional sessions included papers on Sandia`s Photovoltaic Device Fabrication Laboratory`s collaborative research, cell processing research, the activities of the participants in the Concentrator Initiative Program, and photovoltaic technology evaluation at Sandia and NREL.
Laser ablation studies of copper oxide using fiber optics to deliver the radiation have been made. A tapered fiber with a 600 micron input and a 200 micron output is used. For continuous operation the damage threshold at the input end is observed to be 2.5 mJ. The Dektak traces indicate the output beem is spatially uniform.
The purification of pyrite (FeS{sub 2}) used in Li-alloy/FeS{sub 2} thermal batteries by the physical process of flotation was evaluated for reduction of the quartz impurity. The process was compared to the standard process of leaching with concentrated hydrofluoric acid. Flotation was an attractive alternative because it avoided many of the safety and environmental concerns posed by the use of concentrated HF. The effects of particle size and initial purity of the pyrite feed material upon the final purity and yield of the product concentrate were examined for batch sizes from 3.5 kg to 921 kg. Feed materials as coarse as 8 mm and as fine as -325 mesh were treated; the coarse pyrite was ground wet in a rod mill or dry in a vibratory mill to -230 mesh prior to flotation. Both the HF-leached and the flotation-treated pyrite were leached with HCI (1:1 v/v) to remove acid-soluble impurities. The flotation-purified pyrite concentrates were formulated into catholytes; their electrochemical performance was evaluated in both single cells and 5-cell batteries for comparison to data generated under the same discharge conditions for catholytes formulated with HF/HCI-purified pyrite.
Diethyltoluenediamine (DETDA) (Ethyl Corp.`s Ethacure 100) was evaluated as a curing agent to replace methylenedianiline (MDA) (Shell`s Agent Z), which is a suspected carcinogen. Shell Z and Ethacure 100 are used to cure Epon 828 epoxy resin for encapsulation of headers for thermal batteries at Sandia. The physical properties of the alumina-filled epoxies cured with Shell Z and Ethacure 100 were characterized to determine if the material strengths were comparable. The study also included epoxies that were aged at 130{degrees}C for one month, to simulate storage at 40{degrees}C for 25 years. Properties that were measured included tensile strength, elastic modulus, shear strength, butt tensile strength, and elongation. The. specific heats of the alumina-filled epoxies were measured for use in thermal-modeling programs for thermal batteries. Batteries built with the Ethacure 100-cured epoxy encapsulation were aged for up to one year at 74{degrees}C and were subjected to severe (1,800 g/50 ms) lateral shock to test the adhesion to the stainless steel header.
Preliminary experiments on the transmission properties of optical fibers exposed to nuclear radiations has been performed. Three wavelengths, 400, 1730 and 2030 nm, were observed for silica fibers. The long term goal of this effort is to develop a method using fiber optics to determine transmission and reflection properties of laser cavity components while being exposed to nuclear radiations. 5 refs.
The aqueous concentration of a radionuclide is one factor that determines the rate at which the radionuclide might be transported away from a nuclear waste repository should a repository breach occur. This study documents research examining the solubility of plutonium in a brine composition of interest for performance assessment for the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico. Solutions starting with five different forms of plutonium, Pu(III), Pu(IV), Pu(IV)-polymer, Pu(V), and Pu(VI), were allowed to equilibrate in a brine with composition similar to that measured from the Culebra Member of the Rustler Formation in the Air Intake Shaft to the WIPP. Nearsteady-state conditions were reached within a year of reaction time. The resulting concentrations represent an upper bound on the amount of plutonium that can remain dissolved in solution under the experimental conditions (e.g., exclusive of colloids) and can thus be transported with the aqueous phase.
The Integral Effects Test (IET) series was designed to investigate the effects of subcompartment structures on direct containment heating (DCH). Scale models of the Zion reactor pressure vessel (RPV), cavity, instrument tunnel, and subcompartment structures were constructed in the Surtsey Test Facility at Sandia National Laboratories. The RPV was modelled with a melt generator that consisted of a steel pressure barrier, a cast MgO crucible, and a thin steel inner liner. The melt generator/crucible had a hemispherical bottom head containing a graphite limiter plate with a 4 cm exit hole to simulate the ablated hole in the RPV bottom head that would be formed by tube ejection in a high pressure melt ejection (HPME) accident. The reactor cavity model contained an amount of water (3.48 kg) that was scaled to condensate levels in the Zion plant. Iron oxide, aluminum, chromium thermite (43 kg) was used to simulate molten corium. The driving gas was 440 g{center_dot}moles of steam at an initial absolute pressure of 7.1 MPa in IET-1 and 477 g{center_dot}moles of steam at an initial pressure of 6.3 MPa in IET-1R. Steam blowdown entrained debris into the Sorts vessel resulting in a peak pressure increase in Sorts of 98 kPa in IET-1 and 110 kPa in IET-1R. The total debris mass ejected into the Sorts vessel was 43.0 kg in IET-1, compared to 36.2 kg in IET-1R. The Sorts vessel had been previously inerted with N{sub 2}. The total quantity of hydrogen produced by steam/metal reactions was 223 g{center_dot}moles in IET-1 and 252 g{center_dot}moles in IET-1R.
The purpose of this study is to investigate transient pressure loads form hydrogen combustion. Specifically, this study relates pressure loads to variations in mixture and initial conditions, mixture heterogeneities, ignition location, and variations in geometry. This study has shown that initial conditions and variations in mixture have a large effect upon the adiabatic isochoric complete combustion, detonation, and reflected detonation pressures. An inert gas layer between a detonable gas mixture and surface can give rise to reflected pressures higher than in the homogeneous case. A deflagration-to-detonation transition (DDT) event near a surface gives rise to higher reflected pressures, and lower impulses, than if the DDT occurred far from the surface. Edges and corners focus detonation waves, which increases both pressures and impulses over those seen from a normally reflected detonation. The loads at points behind an obstacle is less than the load that would be seen if the obstacle were not there.
The Transportation Systems Center at Sandia Laboratory performs research, development, and implementation of technologies that enhance the safe movement of people, goods, and information. Our focus is on systems engineering. However, we realize that to understand the puzzle, you must also understand the pieces. This brochure describes some of the activities currently underway at the Center and presents the breadth and depth of our capabilities. Please contact the noted, individuals for more, information.
The mission of our Center is to enhance the security, prosperity and well-being of our citizens by the application of a security systems approach incorporating the concepts of protection-in-depth, balance, and cost-effective protection. We will build upon the expertise gained through decades of providing security for the DOE nuclear weapons complex and DoD nuclear weapons storage facilities and solve security problems of national importance. Our mission will be accomplished while: Enhancing our ability to fulfill our role as the lead DOE Laboratory in physical security R&D; enhancing our ability to fulfill our role in nuclear weapons surety; enhancing our ability to respond to security requests from other federal, state,, and local agencies; and providing taxpayers a substantial return on investment, both directly in cost savings and indirectly in leveraged benefits. A brief description of research on security systems is described.
The 34-meter Test Bed is a research-oriented, variable-speed vertical-axis wind turbine located at the USDA Agricultural Research Station in Bushland, Texas. Sandia National Laboratories designed and built this machine to perform research in structural dynamics, aerodynamics, and fatigue. Testing to determine its performance in various wind conditions and rotation rates has been ongoing for over three years. This report documents a broad range of test data and includes comparisons to analytical results.
Mechanical properties of the tuffaceous rocks within Yucca Mountain are needed for near and far-field modeling of the potential nuclear waste repository. If the mechanical properties are significantly anisotropic (i.e., direction-dependent), a more complex model is required. Relevant data from tuffs tested in earlier studies indicate that elastic and strength properties are anisotropic. This scoping study confirms the elastic anisotropy and concludes some tuffs are transversely isotropic. An approach for sampling and testing the rock to determine the magnitude of the anisotropy is proposed.
This report describes an assessment of the long-term performance of a repository system that contains deeply buried highly radioactive waste; the system is assumed to be located at the potential site at Yucca Mountain, Nevada. The study includes an identification of features, events, and processes that might affect the potential repository, a construction of scenarios based on this identification, a selection of models describing these scenarios (including abstraction of appropriate models from detailed models), a selection of probability distributions for the parameters in the models, a stochastic calculation of radionuclide releases for the scenarios, and a derivation of complementary cumulative distribution functions (CCDFs) for the releases. Releases and CCDFs are calculated for four categories of scenarios: aqueous flow (modeling primarily the existing conditions at the site, with allowances for climate change), gaseous flow, basaltic igneous activity, and human intrusion. The study shows that models of complex processes can be abstracted into more simplified representations that preserve the understanding of the processes and produce results consistent with those of more complex models.
Accurate alignment and focus of mirror facets are critical for the integration of concentrators and receivers in many of the low-cost stretched-membrane concentrators currently under development. In this report, the theoretical development of computer software that traces light rays from a source to a facet of a point-focusing solar concentrator and then to a target is given. Examples of approaches for the alignment of faceted point-focusing solar concentrators, which make use of targets generated by this computer program, are also presented.
This review of ongoing research at Sandia National Laboratory in the areas of nuclear weapons development and testing, arms control. As a multiprogram laboratory, their core competencies make special contributions in other areas of national importance. Work on US DOE programs is presented on the following subjects: robots; computers: arms control; nuclear weapons reliability; fusion research; solar energy; semiconductor detectors; radioactive waste management; nuclear explosion detection; and others. The laboratories strategic plan and other management methods are outlined. (GHH)
The efficient operation of a Stirling engine requires the application of a high heat flux to the relatively small area occupied by the heater head tubes. Previous attempts to couple solar energy to Stirling engines generally involved directly illuminating the heater head tubes with concentrated sunlight. In this study, operation of a 75-kW{sub t} sodium reflux pool-boiler solar receiver has been demonstrated and its performance characterized on Sandia's nominal 75-kW{sub t} parabolic-dish concentrator, using a cold-water gas-gap calorimeter to simulate Stirling engine operation. The pool boiler (and more generally liquid-metal reflux receivers) supplies heat to the engine in the form of latent heat released from condensation of the metal vapor on the heater head tubes. The advantages of the pool boiler include uniform tube temperature, leading to longer life and higher temperature available to the engine, and decoupling of the design of the solar absorber from the engine heater head. The two-phase system allows high input thermal flux, reducing the receiver size and losses, therefore improving system efficiency. The receiver thermal efficiency was about 90% when operated at full power and 800{degree}C. Stable sodium boiling was promoted by the addition of 35 equally spaced artificial cavities in the wetted absorber surface. High incipient boiling superheats following cloud transients were suppressed passively by the addition of small amounts of xenon gas to the receiver volume. Stable boiling without excessive incipient boiling superheats was observed under all operating conditions. The receiver developed a leak during performance evaluation, terminating the testing after accumulating about 50 hours on sun. The receiver design is reported here along with test results including transient operations, steady-state performance evaluation, operation at various temperatures, infrared thermography, x-ray studies of the boiling behavior, and a postmortem analysis.
This report describes a hardware implementation of a fast fourier transform (FFT) based real time data compression system. The system is currently configured to compress and analyze airborne vehicle vibration data but it can be utilized for compressing any one- dimensional data stream. The algorithm uses a two-stage process to compress successive stationary time periods of input data. The first stage compresses data by transforming continuous blocks of 2048 points to the frequency domain using Welch's method. The second stage provides further compression by logarithmically averaging adjacent frequency bins of the transformed signal. These compression techniques result in a bandwidth savings from 8:1 to 64:1 per channel compared to strictly analog or digital transmission techniques. The complete technique as well as the hardware used to implement it is described in detail in this report.
We have developed a controlled environment system in which to perform wetting experiments to analyze the effects of various atmospheres, both inert and reducing, on solder processing. This system consists of a custom designed vacuum chamber, an apparatus for heating specimens and a video system for data acquisition. The system design allows for rapid changes to various processing atmospheres. Specimens can be heated to soldering temperature from room temperature rapidly. The temperature is regulated by a controller which gives a maximum heating rate of 23{degrees}C/second while minimizing the amount of overshoot, thereby quickly a stabilized temperature. A video system is used to acquire the data in the form of both numerical data and real-time video images. The video system allows multiple views of the wetting process to be captured and simultaneously records time and temperature information. The recorded information is suitable for digital analysis. The controlled atmosphere soldering system has been used to perform experiments that examine the effect of inert and acid vapor atmospheres on solder wetting behavior.
Measurements have recently been conducted and computer models constructed to determine the coupling of lightning energy into munition storage bunkers as detailed in companion conference papers. In this paper transfer functions from the incident current to the measured parameters are used to construct simple circuit models that explain much of the important observed quantitative and qualitative information and differences in transfer functions are used to identify nonlinearities in the response data. In particular, V{sub oc} -- the open-circuit voltage generated between metal objects in the structure, I{sub sc} -- the short-circuit current generated in a wire connecting metal objects in the structure, and a typical current measurement in the buried counterpoise system behave in a relatively simple manner explainable by one or several circuit elements. The circuit elements inferred from measured data are comparable in magnitude with those developed from simple analytical models for inductance and resistance. These analytical models are more useful in predicting bounding electromagnetic environment values rather than providing exact time domain waveforms. 2 refs.
As a multiprogram engineering laboratory, Sandia National Laboratories (SNL) has major research and development responsibilities for nuclear weapons, arms control, energy, environment, and other areas of strategic importance to national security. To accomplish this diversified mission, analysts within the Engineering Sciences Directorate support the entire laboratory using finite element and finite difference solution schemes to solve problems in fluid dynamics (steady state and transient, compressible and incompressible), thermodynamics (heat transfer), hydrodynamics (impact physics, penetration mechanics), solid mechanics (structural/thermal analysis, fracture mechanics, ground subsidence, impact modeling) and structural dynamics. To assist these analysts in performing these analyses most efficiently, the Applied Visualization Group was formed and tasked to develop a ``production scientific visualization environment.`` In this paper, we characterize a visualization environment that has been designed and prototyped for a large community of scientists and engineers. The proposed environment makes use of a visualization server concept to provide effective, interactive visualization to the user`s desktop. Benefits of using the visualization server approach are discussed. Some thoughts regarding desirable features for visualization server hardware architectures are also addressed. A brief discussion of the software environment is included. The paper concludes by summarizing certain observations which we have made regarding the implementation of such visualization environments.
Aryl-, ethynyl- and alkyl-bridged polysilsesquioxanes were prepared by the hydrolysis and condensation of the respective bridged triethoxysilanes under both acidic and basic conditions. Gelation of the resulting sols can take place at concentrations as low as 0.02 M in tetrahydrofuran. The gels can be air dried to afford xerogels or extracted with supercritical carbon dioxide to give high surface area aerogels. The materials were characterized by solid state {sup 13}C and {sup 29}Si CP MAS NMR spectroscopies, gas sorption porosimetry, and thermal gravimetric analysis. The bridged polysilsesquioxanes offer the opportunity to prepare hybrid organic-inorganic materials with properties unique from other siloxane network materials and silica gels.
This paper describes current research and development on miniaturized sensing systems for use during in situ characterization of nuclear waste storage tanks, buried waste sites, and decommissioned production facilities. Each miniaturized sensor system will consist of a suite of chemical, radiological, and physical properties sensors integrated into a compact package which will be mounted on the end of a robotic arm and/or vehicle. While the specific size of this remote sensor head and the types of sensors included will depend on site needs, the supporting generic computing system may be used for other waste characterization applications. This computing system will contain all necessary hardware and software to acquire, combine, interpret, display, and archive a wide range of sensor data. This paper describes the present status of the project, the lessons learned from the first prototype, and planned future designs of the next generation system. 7 refs.
One of the principal objectives of the International Technology Exchange Program (ITEP) is the exchange of waste management and environmental restoration (WM/ER) technologies between the US and other nations. The current emphasis of ITEP is the transfer of technologies to the US that could provide better, faster, cheaper, or safer solutions to the needs of the DOE complex. The 10 candidate technologies that have been identified thus far by ITEP are discussed. The highlights of preliminary evaluations of these technologies through a systems approach are also described. The technologies have been evaluated by a screening process to determine their applicability to the leading WM/ER needs of the DOE complex. The technologies have been qualitatively compared with the known or anticipated capabilities of domestic, base case technologies.
During inspections of the Waste Isolation Pilot Plant Waste Shaft in May 1990, patchy areas of apparently degraded concrete were observed on the inner surface of the shaft liner between approximately 810 feet and 900 feet below the surface. The apparent cause of this degradation is chemical reaction of the concrete with magnesium-bearing brine in the annulus between the concrete liner and the host rock. The greater thickness of the degraded layer below the joint may be related to the different chemical compositions that were determined by analyses of the paste portions of concrete samples from above and below the joint. The analytical results support a complex mechanistic explanation of concrete degradation observed behind the liner and in the joint: chemical weakening of the concrete paste; cracking by precipitation of solids in pores; and increased permeability due to calcium chloroaluminate formation. Additional sampling, analyses, and regular monitoring are worth considering to bound the vertical extent of Waste Shaft liner degradation, detect concrete liner degradation in other shafts, and measure any ongoing degradation that may be occurring.
This paper presents recent progress in using finite-difference analysis codes to simulate the responses of complex structures due to direct lightning. Significant advances have been made in interfacing a finite-difference code with commercial computer aided design tools, in suppressing a pervasive instability associated with the thin-wire algorithm for modeling conductors much smaller than a cell size, and in visualizing the results with color movies. Preliminary comparisons between the results of the finite-difference code and the results obtained during a recent rocket-triggered lightning test are also presented. 3 refs.
Computer modeling of the blasting process can aid in gaining an understanding of the physics controlling the process. The sequence of events in a blast occur so rapidly and in such a violent environment that measurements are still difficult to obtain. Computer modeling using a program such as DMC [Taylor and Preece, 1989a, 1989b] can provide insights into the physics of the rapid and violent events associated with a blast. DMC has been used to simulate crater blasting [Preece, 1990c] and the blasting of Oil Shale for modified in-situ retorting [Preece, 1990a, 1990b]. This paper will address the influence that damping has on the velocity distribution in the rock mass during the rock motion phase of a blast. Since velocity distribution is a controlling factor of muck pile shape, damping also contributes to muck pile shape.
The most recent RADLAC experiments studied propagation and hose stability of a high current beam propagating in the atmosphere, and confirmed the convective nature of the hose instability. The unique combination of high beam current and extremely small initial perturbation, allowed saturation of the hose instability to be observed for the first time. Data on high current propagation was needed because the current scaling is more complex than energy scaling. It was important to collect data at atmospheric pressure to insure that subtle air chemistry effects such as avalanche did not distort the experiment. With this philosophy, the results should be directly scaleable to applications at higher energy.
The possibility of long-term smoke emissions (from 1 to 3 years) from burning Kuwaiti oil wells has increased concerns regarding personnel exposure and acute and chronic health effects. This document, which is the result of work done in the spring of 1991, addresses those concerns. Part 1 of this document describes follow-on efforts to the pre-war modeling studies of the toxicological hazards to exposed Kuwaiti populations. Part 2 describes a pollutant monitoring program that could be carried out in the summer of 1991 to measure real-time exposure levels and to obtain more detailed information about the pollutant source terms and meteorological conditions that are necessary inputs to model computations.
This project was a collaboration between Sandia National Laboratories and the Harvey E. Yates Company (Heyco), Roswell, NM, conducted under the auspices of Department of Energy`s Oil Recovery Technology Partnership. The project applied Sandia perspectives on the effects of natural fractures, stress, and sedimentology for the stimulation and production of low permeability gas reservoirs to low permeability oil reservoirs, such as those typified by the Bone Spring sandstones of the Delaware Basin, southeast New Mexico. This report details the results and analyses obtained in 1990 from core, logs, stress, and other data taken from three additional development wells. An overall summary gives results from all five wells studied in this project in 1989--1990. Most of the results presented are believed to be new information for the Bone Spring sandstones.
Waveguide-to-microstrip transitions are extremely important components of mm-wave communication systems because it is the interface between the signal processing circuitry and the transmitted/received signal. This report describes the design procedure, construction detail, and measurement of both 3 and 4 step stepped ridge waveguide (RWG) transitions. Both transitions had > 10 dB return loss over the frequency band of interest (57--63 GHz) while insertion loss was less than 1 dB. Also, the transition lengths were at least half as long as traditional finline transitions while having superior performance. These shorter lengths were achieved by violating the ``small-step`` assumption usually used in RWG transition design. 7 refs.
The most costly problem routinely encountered in geothermal drilling is lost circulation, which occurs when drilling fluid is lost to the formation rather than circulating back to the surface. The successful and economical treatment of lost circulation requires the accurate measurement of drilling fluid flow rate both into and out of the well. This report documents the development of a meter for measuring drilling fluid outflow rates in the return line of a drilling rig. The meter employs a rolling counterbalanced float that rides on the surface of the fluid in the return line. The angle of the float pivot arm is sensed with a pendulum potentiometer, and the height of the float is calculated from this measurement. The float height is closely related to the fluid height and, therefore, the flow rate in the line. The prototype rolling float meter was extensively tested under laboratory conditions in the Wellbore Hydraulics Flow Facility; results from these tests were used in the design of the field prototype rolling float meter. The field prototype meter was tested under actual drilling conditions in August and September 1991 at the Long Valley Exploratory Well near Mammoth Lakes, Ca. In addition, the performance of several other commercially available inflow and outflow meters was evaluated in the field. The tested inflow meters included conventional pump stroke counters, rotary pump speed counters, magnetic flowmeters, and an ultrasonic Doppler flowmeter. On the return flow line, a standard paddlemeter, an acoustic level meter, and the prototype rolling float meter were evaluated for measuring drilling fluid outflow rates.
This paper discusses the imaging radar technology requirements for the Open Skies regime including the unresolved issues to be discussed at future Open Skies Consultative Commission (OSCC) meetings. Compliance with international rules on shared technology is addressed and some of the practical considerations for operational deployment of the radar imaging equipment in an Open Skies aircraft are presented. The Open Skies Treaty requirements and validation methodologies for imaging radars that have been agreed on and those that will require future OSCC review are discussed.
Supercritical fluid technology has been used in industry for the extraction and separation of materials in a number of applications such as food preparation and petroleum processing. Gel-derived microcellular polymer foam technology, developed at Sandia, requires the extraction of organic solvents from thermally-induced phase separated gels to yield microcellular foams. We have applied supercritical fluid extraction technology to these specialized materials by using supercritical carbon dioxide to extract a variety of organic solvents from gels to produce foams. Our supercritical extraction process will be described, as well as high pressure equipment that is used to perform the extractions. The results of gel extraction trails and qualitative supercritical carbon dioxide/solvent miscibility experiments will also be presented. We plan to pursue other related areas in this field, including supercritical fluid cleaning, quantitative solubility studies, and supercritical fluid chromatography.
This document contains five appendices documenting how Sandia implemented the DOE Conduct of Operations (5480.19) and DOE Quality Assurance (5700.6C) orders. It provides a mapping of the Sandia integrated requirements to the specific requirements of each Order and a mapping to Sandia`s approved program for implementing the Conduct of Operations Order.
Many problems in computer applications can in theory be solved by searching through a directed-acyclic graph (DAG). In practice, however, this approach has been hampered by our analytical inability to predict the search cost accurately without actually implementing and executing the program. To overcome this inability, a simple and quick heuristic procedure based on a stratified sampling approach is presented. In generalizes a tree sampling technique already shown to be useful in predicting the performance of tree-searching programs. With the addition of this DAG sampling procedure, we should be able to forecast the complexity and feasibility of alternative tree or DAG searching algorithms so that we may utilize our computational resources more effectively.
The purpose of this document is to present and detail the deliverables for the Tiger Team Action Plan, Finding MF-11, and milestones in the FY92 Performance Appraisal for Conduct of Operations from Sandia National Laboratories to DOE. The ``Proposal for Reporting Conduct of Operations & Quality Assurance Compliance to DOE`` describes what the deliverables shall be. Five major steps that result in the development of line practices are covered in this document. These line practices specify what Sandia will do to comply with the above DOE management orders. The five steps include: hazard classification; programmatic risk classification; management grouping; compliance plan; and corporate reporting.
An automatic attenuation/phase calibration system which simultaneously certifies attenuation and transmission angle through up to 100 dB of loss has been developed at Sandia National Laboratories. System hardware is commercially available while the software and the certification techniques constitute the development effort. The system is computer controlled and intended primarily for standards type measurements. 14 refs.
Sandia has developed a third-generation set of specifications for performance and reliability testing of photovoltaic concentrator modules. Several new requirements have been defined. The primary purpose of the tests is to screen new concentrator designs and new production runs for susceptibility to known failure mechanisms. Ultraviolet radiation testing of materials precedes receiver section and module performance and environmental tests. The specifications include the purpose, procedure, and requirements for each test. Recommendations for future improvements are presented.
A number of correlations describing the advent of gas blowthrough and the subsequent exit quality were collected and examined. A simple scaling analysis was applied to these correlations to identify important nondimensional groups, and the range of values for these dimensionless groups at nuclear power plant (NPP) and experimental scales were used to examine the applicability of the correlations at different scales. The performance of each of the correlations was also assessed over a typical parameter range for NPP and experimental conditions. The Gluck correlations for the onset of gas blowthrough is recommended for high pressure melt ejection analyses. AL new model is developed for predicting the two-phase flow quality following the onset of gas blowthrough. Uncertainty estimates for the blowthrough correlation and the flow quality correlation are quantified.
Kennedy, R.P.; Von Riesemann, W.A.; Wyllie Jr., L.A.; Schiff, A.J.; Ibanez, P.
In December 1980, the US Nuclear Regulatory Commission (NRC) designated ``Seismic Qualification of Equipment in Operating Plants`` as an Unresolved Safety Issue (USI), A-46. The objective of USI A-46 is to develop alternative seismic qualification methods and acceptance criteria that can be used to assess the capability of mechanical and electrical equipment in operating nuclear power plants to perform the intended safety functions. A group of affected utilities formed the Seismic Qualification Utility Group (SQUG) to work with the NRC in developing a program methodology to enable resolution of the A-46 issue. To assist in developing a program methodology, SQUG and the NRC jointly selected and supported a five-member Senior Seismic Review and Advisory Panel (SSRAP) in June 1983 to make an independent assessment of whether certain classes of equipment in operating nuclear power plants in the United States have demonstrated sufficient ruggedness in past earthquakes so as to render an explicit seismic qualification unnecessary. SSRAP operated as an independent review body with all of its findings submitted concurrently to both SQUG and the NRC. During their period of involvement, SSRAP issued several draft reports on their conclusions. This document contains the final versions of these reports; namely, ``Use of Seismic Experience and Test Data to Show Ruggedness of Equipment in Nuclear Power Plants,`` dated February 1991 and ``Review Procedure to Assess Seismic Ruggedness of Cantilever Bracket Cable Tray Supports,`` dated March 1, 1991.
JNMM, Journal of the Institute of Nuclear Materials Management
Ewing, Ronald I.
Measurements of the nuclear radiation from spent reactor fuel are being considered to qualify assemblies for loading into casks that will be used to transport spent fuel from utility sites to a federal storage facility. To ensure nuclear criticality safety, the casks are being designed to accept assemblies that meet restrictions as to burnup, initial enrichment and cooling time. Measurements could be used to ensure that only fuel assemblies that meet the restrictions are selected for loading. The 'Fork' measurement system, designed at Los Alamos National Laboratory and used by the International Atomic Energy Agency to verify burnup and age in international safeguards applications, is being investigated for this application.
This paper presents a theoretical model to predict the curvature of a rectangular gel which is subjected to a pH gradient. The curvature is formulated as a function of volumetric strains. Experimental observations indicate a direct coupling between the electric field and the gel that induces an immediate volume collapse independent of pH gradients. Additional deformations occur later due to a pH gradient evolving through hydrolysis.
This paper describes several different types of constraints that can be placed on multilayered feedforward neural networks which are used for automatic target recognition (ATR). We show how unconstrained networks are likely to give poor generalization on the ATR problem. We also show how the ATR problem requires a special type of classifier called a one-class classifier. The network constraints come in two forms: architectural constraints and learning constraints. Some of the constraints are used to improve generalization, while others are incorporated so that the network will be forced to perform one-class classification. 14 refs
Foams, like most highly structured fluids, exhibiting rheological behavior that is both fascinating and complex. We have developed microrheological models for uniaxial extension and simple shearing flow of a `dry`, perfectly ordered, three-dimensional foam composed of thin films with uniform surface tension T and negligible liquid content. We neglect viscous flow in the thin films and examine large elastic-plastic deformations of the foam. The primitive undeformed foam structure is composed of regular space-filling tetrakaidecahedra, which have six square and eight hexagonal surfaces. This structure possesses the film-network topology that is necessary to satisfy equilibrium: three films meet at each edge, which corresponds to a Plateau border, and four edges meet at vertex. However, to minimize surface energy, the films must meet at equal angles of 120{degrees} and the edges must join at equal tetrahedral angles of cos{sup {minus}1}({minus}1/3) {approx} 10.947{degree}. No film in an equilibrium foam structure can be a planar polygon because no planar polygon has all angles equal to the tetrahedral edge. In the equilibrium foam structure known as Kelvin`s minimal tetrakaidecahedron, the `squares` are planar quadrilateral surfaces with curved edges and the `hexagons` are non-planar saddle surfaces with zero mean curvature. As the foam structure evolves with the macroscopic flow, each film maintains zero mean curvature because the pressure is the same in every bubble. In general, the shape of each thin film, defined by z = h(x,y), satisfies R{sub 1}/1 + R{sub 2}/1 = {del}{center_dot} (1 + {vert_bar}{del}h{vert_bar}){sup {1/2}} = O where R{sub 1}{sup {minus}1} and A{sub 2}{sup {minus}1} are the principal curvatures. The appropriate boundary conditions correspond to three films meeting at equal angles. For the homogeneous deformations under consideration, the center of each film moves affinely with the flow. 5 refs
We have grown Zn{sub 1-x}Mn{sub x}Te alloys by molecular beam epitaxy and characterized them using x-ray diffraction and low temperature magnetoluminescence. Zn{sub 1-x}Mn{sub x}Te is a dilute magnetic semiconductor (DMS) whose bandgap ranges from the green through the blue part of the spectrum and is therefore of interest for blue LEDs.
Renewable energy technologies convert naturally occurring phenomena into useful energy forms. These technologies use resources that generally are not depleted, such as the direct energy (heat and light) from the sun and the indirect results of its impact on the earth (wind, falling water, heating effects, plant growth), gravitational forces (the tides), and the heat of the Earth`s core (geothermal), as the sources from which they produce useful energy. These very large stores of natural energy represent a resource potential that is incredibly massive -- dwarfing that of equivalent fossil energy resources. The magnitude of these resources is, therefore, not a key constraint on energy production. However, they are generally diffuse and not fully accessible, some are intermittent, and all have distinct regional and local variability. It is these aspects of their character that give rise to difficult, but generally solvable, technical, institutional, and economic challenges inherent in development and use of renewable energy resources. This report discusses the technologies and their associated energy source.
Theoretical models have been formulated describing the dynamic behavior of the swelling and contracting of polyelectrolyte gels. This paper presents a method of weighted residuals approach to solving the governing system of equations by finite element analysis. The modulation of the imbibition of solvent by a spherical gel is studied.
There is considerable interest in the use of chemically vapor deposited (CVD) polycrystalline diamond films in advanced materials technology. However, most of the potential applications of CVD diamond films require well-controlled properties which depend on the film structure, and in turn, on the conditions under which the films are synthesized. The structure of the vapor-deposited diamond films is frequently characterized by Raman spectroscopy. Despite extensive research, much work still needs to be completed to understand the various features of the Raman spectra and to understand how the processing variables affect the spectral features. This paper examines the Raman spectra of diamond films prepared by a hot-filament-assisted CVD process as a function of substrate processing and deposition parameters.
Many applications of national importance require the design, analysis, and simulation of complex electromagnetic phenomena. These applications range from the simulation of synthetic aperture radar to the design and analysis of low-observable platforms, antenna design, and automatic target recognition. In general, the modeling of complex electromagnetic phenomena requires significant amounts of computer time and capacity on conventional vector supercomputers but takes far less on massively parallel computers. Sandia National Laboratories is currently developing massively parallel methods and algorithms for the characterization of complex electromagnetic phenomena. The goal of on going research at Sandia is to understand the characteristics, limitations, and trade-offs associated with complex electromagnetic systems including: modeling the seeker response to complex targets in clutter, calculating the radiation and scattering from conformal communication and radar system antennas, and the analysis and design of high speed circuitry. By understanding the theoretical underpinnings of complex electromagnetic systems it is possible to achieve realistic models of system performance. The first objective is the development of computationally practical, high fidelity, systems models targeted for massively parallel computers. Research to achieve this objective is conducted in such areas as mathematical algorithms, problem decomposition, inter-processor communication schemes, and load balancing. The work in mathematical algorithms includes both the development of new methods and the parallel implementation of existing techniques. The second objective is the application of these high fidelity models to facilitate a better understanding of systems level performance for many C{sup 3}I platforms. This presentation describes applications of much current interest and novel solution techniques for these applications utilizing massively parallel processing techniques.
A neighboring external control problem is formulated for a hypersonic glider to execute a maximum-terminal-velocity descent to a stationary target. The resulting two-part, feedback control scheme initially solves a nonlinear algebraic problem to generate a nominal trajectory to the target altitude. Secondly, a neighboring optimal path computation about the nominal provides a lift and side-force perturbations necessary to achieve the target downrange and crossrange. On-line feedback simulations of the proposed scheme and a form of proportional navigation are compared with an off-line parameter optimization method. The neighboring optimal terminal velocity compares very well with the parameter optimization solution and is far superior to proportional navigation. 8 refs.
A camera with 3-ns time resolution -- and a continuous (> 100-ns) record length -- has been developed to image a 10{sup 12}-10{sup 13} W/cm{sup 2} ion beam for inertial-confinement-fusion experiments. A thin gold Rutherford-scattering foil placed in the path of the beam scatters ions into the camera. The foil is in a near-optimized scattering geometry and reduces the beam intensity seven orders of magnitude. The scattered ions are pinhole imaged onto a 2-D array of 39 p-i-n diode detectors. The output of each detector is recorded on a LeCroy 6880 transient-waveform digitizer. The waveforms are analyzed and combined to produce a 39-pixel movie which can be displayed on an image processor to provide, for example, time-resolved horizontal- and vertical-focusing information.
A survivable debris shield is necessary if very high levels of cleanliness are to be achieved on samples exposed to soft x rays from laboratory simulation sources. These samples, often of optical quality, require a low or zero debris environment in order to distinguish low levels of soft x-ray damage from debris-induced effects. We will describe the development of survivable debris shield technology on the Sandia National Laboratories` Saturn x-ray simulation facility, which permits ultraclean exposure over sample areas of 58 cm{sup 2} {at} {approximately}0.35 cal/cm{sup 2}, 5 cm{sup 2}{at} {approximately}0.8 cal/cm{sup 2}, cm{sup 2}, 2.8 cm{sup 2} {at} {approximately}1.2 cal/cm{sup 2}, and 0.8 cm{sup 2} {at} {approximately}1.5 cal/cm{sup 2} with 3-keV argon K-shell photons. These new fluence-area produce test capabilities represent an order-of-magnitude improvement in the state of the art (previously 0.25 cm{sup 2} {at} {approximately} 1 cal/cm{sup 2} or 1.0 cm{sup 2} {at} {approximately}0.35 cal/cm{sup 2}) for soft x-ray simulators.
Methods which report an ability to determine interstitial oxygen (O{sub i}) in heavily doped silicon include the short baseline (SBL) and the curved baseline (CBL) techniques. Both the SBL and CBL methods are similar with the exception of the calibration. We developed a FORTRAN software package to provide separate methods for calculating O{sub i}. The strength of the software is its ability to rapidly compare methods. We report on a comparison of calculation methods including the ASTM standard test F1188-88 which is used in a calibration, and the SBL and the CBL methods, which are used for the heavily doped silicon to provide reliable results. The O{sub i} values calculated for both virgin and thermally processed silicon are reported.
This paper describes the design of an inverse adaptive filter, using the Least-Mean-Square (LMS) algorithm, the correct data taken with an analog filter. The gradient estimate used in the LMS algorithm is based upon the instantaneous error, e{sup 2}(n). Minimizing the mean-squared-error does not provide an optimal solution in this specific case. Therefore, another performance criterion, error power, was developed to calculate the optimal inverse model. Despite using a different performance criterion, the inverse filter converges rapidly and gives a small mean-squared-error. Computer simulations of this filter are also shown in this paper.
Intense light ion beams are being developed to drive inertial confinement fusion (ICF) targets. Recently, intense proton beams have been used to drive two different types of targets in experiments on the Particle Beam Fusion Accelerator. The experiments focused separately on ion deposition physics and on implosion hydrodynamics. In the ion deposition physics experiments, a 3--4 TW/cm{sup 2} proton beam heated a low-density foam contained within a gold cylinder with a specific power deposition exceeding 100 TW/gm for investigating ion deposition, foam heating, and generation of x-rays. The significant results from these experiments included the following: the foam provided an optically thin radiating region, the uniformity of radiation across the foam was good, and the foam tamped the gold case, holding it in its original position for the 15 ns beam pulse width.
This paper identifies some of the sources of resistance to change that face Sandia National Laboratories` management, and examines the mechanisms that are being used to minimize the effects of that resistance. The rapid and radical nature of many of the changes now being demanded of Sandia make them all the more likely to meet stiff resistance from within the organization. Sandia`s management has attempted to anticipate some of the sources of resistance to the changes planned for its operating procedures and has taken action to minimize their effects. Within this paper, particular attention is given to those individuals who will not only be most effected by, by may also be required to implement the changes. The change process at Sandia is currently ongoing. It is not complete. No claim is made that all of the changes that will be necessary at Sandia National Laboratories have been recognized, nor that all sources of resistance have been anticipated.
A production vacuum arc remelt (VAR) furnace was modified to enable direct viewing of the metal vapor arc and molten electrode tip during melting of 432 mm dia. alloy 718 electrodes into 508 mm dia. ingots. Diffuse and constricted arcing conditions were characterized using high speed cinematography, standard video format, and monochromatic imaging. Constricted arcing was observed while melting electrodes contaminated with oxide slag of the type used for refractory linings in vacuum induction furnaces. Monochromatic imaging was used in visualize the ion distribution in the arc plasma; these images clearly showed whether the arc operated in a diffuse or constricted model. Diffuse arc melting conditions were very similar to those previously reported in the literature for smaller laboratory sized melts.
In November of 1989, technology transfer became a mission for Sandia National Laboratories, (SNL), with the passage of the National Competitiveness Technology Transfer Act. In order to address the specialized technology transfer needs of small businesses, SNL created and implemented the Technology-Based Regional Economic Development (TRED) program. The TRED model has two major components -- technology assistance (or teaming), and `` widget transfer.`` In the technology assistance component, SNL`s technology resources (expertise, services, and equipment) are made available to companies developing commercial products. In the ``widget transfer`` component, SNL`s intellectual property (patents, copyrights) is placed with private sector firms through various partnership intermediaries
This manual is intended to aid operators of the pressure controller in the Transducer Calibration Laboratory. We include discussions of automated control, data acquisition, and data analysis techniques that improve the quality and thoroughness of transducer pressure calibration procedures.
This memorandum is a synopsis of the description and operation of the equipment used and the events occurring during the calibration of an accelerometer on the 5000 g centrifuge.
Many MoS{sub 2} lubricant film formulations exhibit tribological performance degradation after extended storage in high humidity ambient environments. As a part of an extensive study of the effects of high humidity storage on a wide variety of MoS{sub 2} lubricant film formulations, the effects of high humidity storage on sputtered MoS{sub 2} films have been examined. The surface chemistries of a series of ten different commercially deposited MoS{sub 2} lubricant film formulations on 440C stainless steel have been examined before and after 1 month of storage at 98% relative humidity. While the films varied greatly in film chemistry prior to high humidity storage, many smaller differences were observed after high humidity storage. Addition of Ni to the films affects the film chemistry far more dramatically than the addition of AuPd or SbO{sub x}, facilitating oxidation of the MoS{sub 2} and enhancing formation of sulfate species. All of the films are adequately characterized by considering only MoS{sub 2} and MoO{sub 3} species, with the exception of the films co-sputtered with Ni and ion implanted with N{sup +}, where some MoO{sub 2} or MoS{sub 2-x}O{sub x} must also be present.
This bibliography contains 64 references concerning the management of business and industry. Books and articles are both cited. Methods for gathering and utilizing information are emphasized. (GHH)
A power MOSFET macro-model for use with the circuit simulator SPICE has been developed suitable for use over the temperature range of {minus}55 to 125{degrees}C. The model is comprised of a single parameter set with the temperature dependence accessed through the SPICE TEMP card. This report describes in detail the development of the model and the extraction algorithms used to obtain model parameters. The extraction algorithms are described in sufficient detail to allow for automated measurements which in turn allows for rapid and cost effective development of an accurate SPICE model for any power MOSFET. 22 refs.
The analytical procedures for establishing the fragment hazard zone for explosive test facilities are presented. Environment, safety and health regulations require that a hazard zone analysis be conducted for every explosive test facility. Analyses are presented for explosively driven missile fragment trajectories resultant from cased explosive configurations. Fragment trajectory parameter data are presented in graphical form for three different fragment materials (aluminum, steel and tantalum), initial velocities between 0.6mm/{mu}s (2000 ft/sec) to 4.3mm/{mu}s (14,000 ft/sec), and for various geometries. This trajectory information is used, as an example, to determine the safe distance or hazard zone for the Area 2 explosive test facility at Sandia National Laboratories.
The equations of motion of beam and channel particles are analyzed in the ion focused regime. Using the paraxial approximation and assuming only transverse electro-magnetostatic interactions between beam and channel particles for the equations of motion (the same equations solved in the BUCKSHOT code) are written in non-dimensional form and scaling relations are derived for propagation parameters, magnetic erosion, and evaporation. These relations are very useful in doing parameter studies with a limited number of computer simulations.
Methods of mechanical and thermal testing specifically directed toward evaluation of impact-limiting materials for radioactive material transportation containers are presented. Associated figures of merit and procedures for rank-ordering the materials are also developed. Based on testing and evaluation procedures developed herein, thermal and mechanical results are presented for high- and low-density aluminum honeycombs, polyurethane foams, and aluminum foams. On a minimum mass basis, the high-density aluminum honeycomb is found to be a superior impact energy absorber up to the point of lock up. On a minimum volume basis, the high-density polyurethane foam is far superior, however. Based on the thermal figures of merit, the high-density polyurethane foam was found to be the most favorable material.
The energy-absorbing capability of impact limiters is an important part of radioactive waste transportation system. This document presents the results of the Basic Impact Limiter Study (BILS). The objective of this design development program was to increase the energy-absorbing capabilities of an external impact limiter for both axial and off-axis response. The impact limiter that was evaluated was made of stainless steel and was a right circular cylinder. The evaluation included computer analysis complemented by static and dynamic testing of quater-scale and half-scale models. The design development, analysis, and testing were conducted at Sandia National Laboratories.
Analyses have shown that early rupture of the Mark-I boiling water reactor containment-by the direct action of core debris depends strongly on the time that core debris is superheated above its liquidus. The analyses of the duration of superheat in the core debris are compared to predictions obtained with the CORCON-MOD 3 computer code. The predicitons of this computer code as functions of the core debris mass, composition, and initial superheat are used to create a polynomial response surface. This response surface is used in a Monte Carlo analysis to produce probability distributions for the duration of superheat in core debris in the drywell of a Mark-I containment. It is concluded that to a high level of confidence (>90%) the duration of superheating predicted with the CORCON-MOD 3 code is less than what has been used in the analyses of the threats to the Mark-I containment liner. Based on these results, to the extent superheat duration dictates the threat to the liner, analyses in NUREG/CR-5423 would appear to overestimate the threat to the liner in comparison to threats estimated using the predictions of the duration of superheating obtained with CORCON-MOD 3.
A postnotification record is required for all Highway Route Controlled Quantities of radioactive materials that are shipped in the United States. These reports, which are required by 49 CFR 172.203(d), are compiled in the Radioactive Materials Routing Report (RAMRT) database at the US Department of Transportation (DOT). Sandia National Laboratories` has developed an expanded version of the RAMRT which is entitled the Radioactive Materials Postnotification (RAMPOST) database. This paper provides the summary detail on the following topics: major carriers of highway route controlled quantities, major US Department of Energy (DOE) shippers, major US Nuclear Regulatory Commission (NRC) shippers and a breakdown of the types of Highway Route Controlled Quantities that have been shipped for the time period 1985--1990.
We describe the design and operation of an optical fiber accelerometer intended for environments inhospitable to electronic components. An overview of the device is presented along with descriptions of the optical, electronic, and mechanical components. The performance of the current prototype is equivalent to state of the art piezoelectric accelerometers. Improvements to the current design are discussed.
The possibility of formulating and validating a multi-site, multi- solute model for prediction of contaminant transport in groundwaters is being evaluated through experiments with simple analog systems. These systems consist of mixtures of well-characterized synthetic and natural materials in which the effects of sorption by ion exchange and amphoteric sites are isolated. Initial results are reported for studies of lead sorption by mixtures of goethite and montmorillonite, and Ni-Sr and Pb-Sr ion exchange by montmorillonite. The results of studies of simple clay-oxide mixtures indicate that the pH-dependent sorption behavior of Ni by mixtures of minerals containing amphoteric sites can be predicted from the properties of the component minerals.
Site characterization is an integral component of any environmental assessment or restoration project. However, it is often difficult to know how to prioritize site characterization activities. In the absence of a preliminary analysis, site characterization decisions are sometimes guided by little more than intuition. The objective of this paper is to show that a Performance Assessment Methodology, used very early in a project, can be a useful tool for guiding site characterization activities. As an example, a ``preliminary`` performance assessment for the Greater Confinement Disposal project is used to demonstrate implementation of the methodology.
We present results that correlate microstructure and mechanical evolution to variations of deformation rate, hold time and environmental effects on the thermomechanical fatigue (TMF) behavior of 60Sn-40Pb solder. The results are used to define valid conditions for performing accelerated TMF tests. TMF tests at deformation rates of 5.6{times}10{sup {minus}4}s{sup {minus}1}, 2.8{times}10{sup {minus}4}s{sup {minus}1} and 2.1{times}10{sup {minus}4}s{sup {minus}1} were performed. Deformation rates greater than 2.8{times}10{sup {minus}4}s{sup {minus}1} result in fewer cycles to failure. At low deformation rates, the microstructure heterogeneously coarsens at cell boundaries. At higher rates, the deformation mechanism changes, and heterogeneous coarsening occurs at a strain concentration in the joint, independent of the microstructure. TMF tests with hold times of 0, 3 and 6 min. at the temperature extremes were performed. At hold times 3 min. or longer the damage at cell boundaries is annealed, resulting in heterogeneous coarsening. With no hold times the TMF life was greatly enhanced as a result of limited coarsening. The effect of the oxygen environment was explored. The TMF life in the presence of oxygen was found to be extended. Valid acceleration conditions for a TMF test of solder are: a deformation rate of 2.8{times}10{sup {minus}4}s{sup {minus}1} or lower, with hold times of 3 mn. or longer.
The discrete Fourier transform and power spectral density are often used in analyzing data from analog-to-digital converters. These analyses normally apply a window to the data to alleviate the effects of leakage. This paper describes how windows modify the magnitude of a discrete Fourier transform and the level of a power spectral density computed by Welch`s method. For white noise, the magnitude of the discrete Fourier transform at a fixed frequency has a Rayleigh probability distribution. For sine waves with an integer number of cycles and quantization noise, the theoretical values of the amplitude of the discrete Fourier transform and power spectral density are calculated. We show how the signal-to-noise ratio in a single discrete Fourier transform or power spectral density frequency bin is related to the normal time-domain definition of the signal-to-noise ratio. The answer depends on the discrete Fourier transform length, the window type and the function averaged.
A new, laser-based system has been developed for rapid evaluation of monolithic thermoluminescence dosimetry (TLD) arrays. A precision controlled CO{sub 2} laser is used to sequentially heat 1.5 mm diameter, {approx} 0.04 mm thick TLDs deposited on a .125 mm thick polymer substrate in a 3 mm {times} 3 mm grid. Array areas up to 30 cm {times} 30 cm are used (> 10,000 TLD elements), with evaluation times of 45--90 minutes. Isodose contours and various analysis functions are available on the system-operating PC. This system allows for greatly expanded dosimetry compared to standard TLDs, simultaneously decreasing effort and record keeping. We compared the dosimetric characteristics of this system with standard techniques, using near Si-equivalent CaF{sub 2}:Mn TLD elements, in a test with 19 MeV end-point X radiation. The results show the laser system performs as well as the standard system. 4 refs.
The Chemical Waste Landfill (CWL) was used by Sandia National Laboratories (SNL), Albuquerque for disposal of hazardous chemicals from the years 1962 to 1985. Prompted by the detection of low levels of trichlorethylene (TCE) in groundwater samples from a water table aquifer approximately 146 meters below ground surface, a RCRA Site Investigation (RSI) and remediation of organic contaminants will be performed at the CWL prior to closure of this landfill. The RSI is focused on optimal characterization of the VOC and dense non-aqueous phase liquid (DNAPL) contamination at this site which will be possible through application of innovative strategies for characterization and promising new technologies. This paper provides a discussion of conceptual models of contaminant transport at the CWL, and an overview of our investigative strategy which is focused on characterizing transport of VOC and DNAPLS. Each stage of the RSI has been developed to gather information which will reduce the uncertainty in the design of each subsequent phase of the investigation. Three stages are described; a source characterization stage, unsaturated zone characterization stage, and a saturated zone characterization stage. The unsaturated zone characterization must provide all data necessary to make decisions concerning the necessity of a saturated zone characterization phase.
This paper summarizes the results of aging, condition monitoring, and accident testing of Class 1E cables used in nuclear power generating stations. Three sets of cables were aged for up to 9 months under simultaneous thermal ({approximately}100{degrees}C) and radiation ({approximately}0.10 kGy/hr) conditions. After the aging, the cables were exposed to a simulated accident consisting of high dose rate irradiation ({approximately}6 kGy/hr) followed by a high temperature steam (up to 400{degrees}C) exposure. A fourth set of cables, which were unaged, was also exposed to the accident conditions. The cables that were aged for 3 months and then accident tested were subsequently exposed to a high temperature steam fragility test (up to 400{degrees}C), while the cables that were aged for 6 months and then accident tested were subsequently exposed to a 1000-hour submergence test in a chemical solution. The results of these tests do not indicate any reason to believe that many popular nuclear power plant cable products cannot inherently be qualified for 60 years of operation for conditions simulated by this testing. Mechanical measurements (primarily elongation, modulus, and density) are more effective than electrical measurements for monitoring age-related degradation. In the high temperature steam test, ethylene propylene rubber (EPR) cable materials generally survived to higher temperatures than crosslinked polyolefin (XLPO) cable materials. In dielectric testing after the submergence testing, the XLPO materials performed better than the EPR materials.
Numerous investigations have studied the potential for chaotic vibrations of nonlinear systems. It has been shown for many simple nonlinear systems, that when they are excited severely enough, or with the appropriate parametric combinations, that they will execute chaotic vibrations. The present investigation considers the potential for the occurrence of chaos in a practical nonlinear system -- the isolated accelerometer. A simple, first order model is proposed for the isolated accelerometer, and it is shown that chaos can occur in the isolated accelerometer. A preliminary investigation into the bearing that this chaos potential has on the measurement of shock response is summarized. 7 refs.
Carrier-driven photochemical reactions require direct participation of free carriers for the chemical reaction to proceed. Therefore, they can be selectively suppressed by increasing the carrier recombination rate through creation of defects using ion implantation. The residual defect concentration following ion implantation should correlate with etching suppression. Changes in the Raman LO-phonon lineshape correlate well with the degree of etching suppression and predict etching behavior better than defect concentrations calculated with the Monte Carlo code, TRIM. Raman spectroscopy may be a useful pre-etch diagnostic to predict the degree of etching suppression resulting from a given implantation treatment. 11 refs.
Direct containment heating (DCH) has recently been studied at Sandia National Laboratory`s Surtsey facility in a number of experiments in which high-temperature thermite melts are ejected by pressurized steam from a melt generator into scaled reactor cavities. Steam blowdown from the melt generator disperses at least part of the melt into the Surtsey vessel. Efficient team-metal chemical reaction was observed in many of the experiments. Analysis of the results suggests that hydrogen generation occurs primarily in the cavity can actually reduce hydrogen generation by separating the debris from the blowdown steam. Debris-gas heat transfer appears to include both a component that takes place in the cavity in proportion to the hydrogen generation, and a second component that takes place in the Surtsey vessel itself. The magnitude of the latter depends upon the amount of debris dispersed and the length of the unobstructed flight path in the Surtsey vessel. Some possible implications of these results are discussed.
A Senate Committee requested assistance from Sandia in determining the adequacy of the investigation of the incident aboard the USS IOWA. This currently unexplained explosion occurred in Turret 2 of the battleship on April 19, 1989, killing 47 crewmen. The investigation included material characterization of debris found after the explosion, ignition experiments to characterize the propellant, and analytic modeling of the mechanics, interior ballistics and ignition. The analytic modeling is described in this paper. The modeling of the incident was concerned with the mechanics of the ramming equipment used to load the 16 inch guns, and the interior ballistic and ignition of the propellant. Many separate analyses were performed to explain the crushing of the propellant grains, the dynamics and location of ignition of the propellant train, and the presence of damage after the incident. The goal of this modeling was to assess the feasibility of the various events in the turret, and to identify the cause of the incident. An item of particular interest was damage to the rammer control handle quadrant. The US Navy conjectured that the blast propelled the rammermans seat into the quadrant in such a way as to suggest low speed ram during the incident. The speed of the ram was discovered to be very important in determining the probability of ignition during an overram, and an analysis of the rammermans seat motion was completed. In order to understand how the seat impacts the quadrant, a three-dimensional finite element analysis was completed using ABAQUS/Explicit. The loading of the seat was due to two-phase gas and propellant flow through the bag train and into the turret volume. The results showed that impact onto the quadrant probably first occurred at the rear, dislodging it from its mount. This analysis was pivotal in the examination of the incident, and was the final evidence that the cause of the explosion could not be conclusively determined.
High spatial resolution x-ray microanalysis in the analytical electron microscope (AEM) describes a technique by which chemical composition can be determined on spatial scales of less than 50 nm. Dependent upon the size of the incident probe, the energy (voltage) of the beam, the average atomic number of the material being analyzed, and the thickness of the specimens at the point of analysis it is possible to measure uniquely the composition of a region 2--20 nm in diameter. Conventional thermionic (tungsten or LaB{sub 6}) AEMs can attain direct spatial resolutions as small as 20 nm, while field emission (FEG) AEM`s can attain direct spatial resolutions approaching 2 nm. Recently, efforts have been underway to extract compositional information on a finer spatial scale by using massively parallel Monte Carlo electron trajectory simulations coupled with AEM measurements. By deconvolving the measured concentration profile with the calculated x-ray generation profile it is possible to extract compositional information at near atomic resolution.
Chemical and physical transformations involved in ion implantation processes in glasses determine changes in mechanical. and tribological properties, in network dilatation, in induced optical absorption and luminescence and in the composition and chemical behavior as a function of different experimental conditions (ion, energy, dose, target temperature). Variations of chemical etch rate in HF are related to radiation damages and formation of compounds. A systematic study of the etch rate changes in silica due to Ar, N, Si plus N implants has been performed. Structure modifications at depths greater than the corresponding implanted ion ranges are evidenced for nuclear deposited energy greater than 10{sup 22} keV cm{sup {minus}3}. Formation of silicon oxynitrides reduces the etch rate values.
Archimedes is a prototype mechanical assembly system which generates and executes robot assembly programs from a CAD model input. The system seeks to increase flexibility in robotic mechanical assembly applications by automating the programming task. Input is a solid model of the finished assembly, augmented by additional design information such as weld specifications. Parts relationships and geometric constraints are deduced from the solid model. A rule-based planner generates a ``generic`` assembly plan that satisfies the geometric constraints, as well as other constraints embodied in the rules. A plan compiler then converts the generic plan into code specific to an application environment. Other outputs include fixture designs, workcell layout information, object-recognition (vision) routines, grasp plans, and executable code for controlling the robot and workcell accessories. Lessons from operating and demonstrating the system are presented, with a particular emphasis on the implications for future systems. 12 refs.
Isolated accelerometer measurement systems are used to measure environments composed of a wide spectrum of frequencies including the natural frequency of the isolated accelerometer. Because the isolated accelerometer measurement system is a nonlinear system, it is subject to the potential for chaotic vibrations. it is clear that this potential if realized, affects the response of the measurement system to vibration input and perhaps to shock input also. This paper explores the effects that the potential for chaotic vibrations and nonlinear response, in general, has on the random vibration response of the isolated accelerometer measurement system. Specifically, the system response to white noise is investigated and assessed in terms of response histogram and response spectral density. 6 refs.
In the Federal Register, Volume 51, Number 168, NRC has intended the use of IMPACTS-BRC to evaluate petitions for evaluating radioactive waste streams as below regulatory concern. IMPACTS-BRC is a generic radiological assessment code that allows calculation of potential impacts to maximum individuals, waste disposal workers, and the general population resulting from exemption of very low-level radioactive waste from regulatory control. The code allows calculations to be made of human exposure to the waste by many pathways and exposure scenarios. This document describes the code history and the quality assurance work that has been carried out on IMPACTS-BRC. The report includes a summary of all the literature reviews pertaining to IMPACTS-BRC up to Version 2.0. The new code and data verification work necessary to produce IMPACTS-BRC, Version 2.1 is presented. General comments about the models and treatment of uncertainty in IMPACTS-BRC are also given.
This work describes the collection, handling, transportation, thermal desorption, and analysis of explosive vapors using quartz collection tubes. A description of the sampling system is presented, along with the collection efficiency of the quartz tubes and some of the precautions necessary to maintain the sample integrity. The design and performance characteristics of the thermal desorption system are also discussed. Collection of explosive vapor using empty, 0.25 inch O.D. by 5.25 inch long quartz tubes at a flow rate of 200 mL min-1 is quite different. Thermal desorption of the explosive vapor molecules using a furnace that allows control of the gas phase chemistry in the IMS has been shown to provide a reliable, reproducible means of analysis. Empty quartz tubes provide a sharper desorption profile than packed collection tubes, resulting in a better signal-to-noise ratio, and perhaps, a lower detection limit than packed quartz tubes. Both the ion drift time of the explosive and its desorption characteristics can provide a means of identification. Sample handling, packaging, and transportation methods which minimize sample loss and contamination have been developed and evaluated.
This report contains the purchasing and materials management operating highlights for Fiscal Year 1991. Included in the report are compiled data on: personnel; type of procurement; small business procurements; disadvantaged business procurements; woman-owned business procurements; New Mexico commercial business procurements; Bay Area commercial business procurements; commitments by states and foreign countries to commercial suppliers; and, transportation activities. Other statistical data tables enumerate the following: the twenty-five commercial contractors receiving the largest dollar commitments; commercial contractors receiving commitments of $1000 or over; integrated contractor and federal agency commitments of $1000 or over from Sandia National Laboratories-Albuquerque and Livermore; and, transportation commitments of $1000 or over from Sandia National Laboratories-Albuquerque and Livermore.
This white paper addresses the issue of banning lead from solders used in electronics manufacturing. The current efforts by legislative bodies and regulatory agencies to curtail the use of lead in manufactured goods, including solders, are described. In response to a ban on lead or the imposition of a tax which makes lead uneconomical for use in solder alloys, alternative technologies including lead-free solders and conductive epoxies are presented. The recommendation is made that both users and producers of solder materials join together as partners in a consortium to address this issue in a timely and cost-effective manner.
The MELCOR code has been used to simulate the ST-1 and ST-2 in-pile product source term experiments performed in the ACRR facility. As expected, there were no major differences observed in the results calculated for the different test conditions. The CORSOR, CORSOR-M and CORSOR-Booth release models all were tested, and the effect of including the surface-volume correction term was evaluated. MELCOR results were compared to test data and to VICTORIA results, and also directly to the correlations and to ST-1/ST-2 results predicted by Battelle using their stand-alone CORSOR code to verify that the models have been implemented correctly in MELCOR. The release rates and total release fractions calculated by MELCOR generally agreed well with the test data, for both volatile and refractory species, with none of the release model options available yielding consistently better agreement with data for species. Sensitivity studies checking for time step and noding effects and machine dependencies were done, and some machine dependencies associated with very small numbers were identified and corrected in the code. Additional sensitivity studies were run on parameters affecting core heatup and core damage, including both variations in code models such as convective heat transfer coefficients, radiation view factors, candling assumptions, and in experimental conditions such as pressures, flow rates, power levels, and insulation thermal conductivity. Code and user input modeling errors encountered in these analyses are described.
This paper presents a method to solve partial differential equations governing two-phase fluid flow by using a genetic algorithm on the NCUBE/2 multiprocessor computer. Genetic algorithms represent a significant departure from traditional approaches of solving fluid flow problems. The inherent parallelism of genetic algorithms offers the prospect of obtaining solutions faster than ever possible. The paper discusses the two-phase flow equations, the genetic representation of the unknowns, the fitness function, the genetic operators, and the implementation of the genetic algorithm on the NCUBE/2 computer. The paper investigates the implementation efficiency using a pipe blowdown test and presents the effects of varying both the genetic parameters and the number of processors. The results show that genetic algorithms provide a major advancement in methods for solving two-phase flow problems. A desired goal of solving these equations for a specific simulation problem in real time or faster requires computers with an order of magnitude more processors or faster than the NCUBE/2`s 1024.
Although plasma cleaning is a recognized substitute for solvent cleaning in removing organic contaminants, current cleaning rates are impractically low for many applications. A set of experiments is described which demonstrate that the rate of plasma removal of organic contaminants can be greatly increased by modification of the plasma chemistry. A comparison of plasma cleaning rates of argon, oxygen and oxygen/sulfur hexafluoride gases shows that the fluorine containing plasma is at least an order of magnitude faster at etching organics. Rates are reported for the removal of polymer films and of A-9 Aluminum cutting fluid. 7 refs.
Measuring the yield of an underground nuclear detonation using sensor cables has been proposed for verification purposes. These cables not only sense the signals associated with the yield they also capture the sensitive primary and secondary electromagnetic pulses associated with the detonation but have nothing to do with the yield. An anti-intrusiveness device is to be connected to the sensor cable to prevent the electromagnetic pulses from passing through to the verifier. The anti-intrusiveness device both attenuates the electromagnetic pulses and adds noise to the cable over the interval of time that the electromagnetic pulses may be present. This report addresses the problem of determining the optimum noise spectral density for masking the electromagnetic pulses. To this end it derives an expression for the lower bound on the error in the estimation of the time separation between two pulses when the time of arrival of neither is known and they are imbedded in Gaussian noise. The noise spectral shapes considered are white, and lowpass, and bandpass.
UPEML is a machine-portable program that emulates a subset of the functions of the standard CDC Update. Machine-portability has been achieved by conforming to ANSI standards for Fortran-77. UPEML is compact and fairly efficient; however, it only allows a restricted syntax as compared with the CDC Update. This program was written primarily to facilitate the use of CDC-based scientific packages on alternate computer systems such as the VAX/VMS mainframes and UNIX workstations. UPEML has also been successfully used on the multiprocessor ELXSI, on CRAYs under both UNICOS and CTSS operating systems, and on Sun, HP, Stardent and IBM workstations. UPEML was originally released with the ITS electron/photon Monte Carlo transport package, which was developed on a CDC-7600 and makes extensive use of conditional file structure to combine several problem geometry and machine options into a single program file. UPEML 3.0 is an enhanced version of the original code and is being independently released for use at any installation or with any code package. Version 3.0 includes enhanced error checking, full ASCII character support, a program library audit capability, and a partial update option in which only selected or modified decks are written to the complete file. Version 3.0 also checks for overlapping corrections, allows processing of pested calls to common decks, and allows the use of alternate files in READ and ADDFILE commands. Finally, UPEML Version 3.0 allows the assignment of input and output files at runtime on the control line.
The Planning and Staff Support of the Sandia National Laboratories publishes a monthly bulletin titled, Energy and Environment. The bulletin facilitates technology exchange with industries, universities, and with other government agencies. This bulletin is for the month of April 1992 and covers such things as new methods of soldering which reduces environmental threats by avoiding chlorofluorocarbon solvents. Some technologies developed are soldering in controlled atmospheres, acid-vapor soldering, and laser soldering. Another topic in this bulletin is the designing of catalysts of chemical reactions by computers. Biomimetic catalysts are being created by Computer-Aided Molecular Design. These biomimetic catalysts can aid in fuel conversion. In-situ remediation of soils contaminated by heavy metals was another topic in this bulletin. This in-situ process is called, electrokinetic remediation. It uses electrodes to induce a metal-attracting electric field in the ground. The last topic in this bulletin is the design of a semiconductor bridge (SCB) which is used to improve the timing and effectiveness of blasting. Timing and accuracy is important; and the blasting industry is no exception. This SCB gives a low-energy pulse which causes a doped region on a polysilicon substrate into a bright plasma. This plasma discharge causes the ignition and produces an accurate explosion in microseconds. (MB)
Seventeen small-scale brine inflow experiment boreholes have been and are currently being monitored for brine accumulation. All of the boreholes were drilled from underground excavations at the Waste Isolation Pilot Plant (WIPP) near Carlsbad, NM. Experiments are ongoing in Room D, Room L4, and the Q access drift in the WIPP underground. The boreholes range from approximately 5 to 90 cm in diameter and from 3 to 6 m in length. The objective of these experiments is to provide data for use in the development and validation of a predictive, mechanistic model for brine inflow to the repository. There is considerable variability in the observed responses of the different boreholes, and there are also significant similarities. Two of the boreholes in Room D have yielded no brine in more than 3.5 years, while all 15 of the other boreholes have produced anywhere from 2 to 90 kg of brine. Inflow rates vary by as much as 2 orders of magnitude for boreholes of the same dimensions in the same general location; however, inflow rates measured in most of the boreholes are of the same order of magnitude. Decreasing, increasing, and steady inflow rates have been measured. Nevertheless, 9 of the 15 brine-producing boreholes behaved similarly early in their history. These 9 boreholes all exhibited a relatively high initial inflow rate followed by a fairly smooth decline with time. Variabilities in borehole response can be explained by assuming there are heterogeneities in the formation tested. In most cases these heterogeneities are believed to be excavation-induced. Data from these experiments suggest that flow near excavations has been altered by rock deformation, including fracturing. Additional experiments are required to differentiate between a far-field, near-field, or combination brine source and to characterize the significant flow mechanism or mechanisms.
A high-velocity impact testing technique, utilizing a tethered rocket, is being developed at Sandia National Laboratories. The technique involves tethering a rocket assembly to a pivot location and flying it in a semicircular trajectory to deliver the rocket and payload to an impact target location. Integral to developing this testing technique is the parallel development of accurate simulation models. An operational computer code, called ROAR (Rocket-on-a-Rope), has been developed to simulate the three-dimensional transient dynamic behavior of the tether and motor/payload assembly. This report presents a discussion of the parameters modeled, the governing set of equations, the through-time integration scheme, and the input required to set up a model. Also included is a sample problem and a comparison with experimental results.
The Plasma/Wall Interaction and High Heat Flux Materials and Components Task Groups typically hold a joint meeting each year to provide a forum for discussion of technical issues of current interest as well as an opportunity for program reviews by the Department of Energy (DOE). At the meeting in September 1990, reported here, research programs in support of the International Thermonuclear Experimental Reactor (ITER) were highlighted. The first part of the meeting was devoted to research and development (R&D) for ITER on plasma facing components plus introductory presentations on some current projects and design studies. The balance of the meeting was devoted to program reviews, which included presentations by most of the participants in the Small Business Innovative Research (SBIR) Programs with activities related to plasma wall interactions. The Task Groups on Plasma/Wall Interaction and on High Heat Flux Materials and Components were chartered as continuing working groups by the Division of Development and Technology in DOE`s Magnetic Fusion Program. This report is an addition to the series of ``blue cover`` reports on the Joint Meetings of the Plasma/Wall Interaction and High Heat Flux Materials and Components Task Groups. Among several preceding meetings were those in October 1989 and January 1988.
The switch delay time of the MC3858 sprytron was measured using a test matrix consisting of 36 different trigger circuit configurations. The test matrix allowed the measurement of switch delay times for peak trigger voltages ranging from 47 V to 1340 V and for stored trigger energies ranging from 0.023 mJ to 2.7 mJ. The average switch delay time was independent of peak trigger voltage above approximately 800 V. Similarly, the average switch delay was independent of trigger stored energy above approximately 0.5 mJ. Below these saturation values, the average switch delay increases rapidly with decreasing trigger voltage or esergy. In contrast to the average switch delay time, the shot-to-shot variability in switch delay time does not appear to be strongly affected by peak trigger voltage as long as the trigger voltage is groater than 100 V. Below 100 V, the variability in switch delay time rises rapidly due to failure of the trigger to undergo immediate high voltage breakdown when trigger voltage is applied. The effect of an abnormally-high-resistance trigger probe on switch delay time was also investigated. It was found that a high-resistance probe behaved as a second overvoltage gap in the trigger circuit. Operation with a peak trigger voltage greater than the breakdown voltage of this second gap yielded delay times comparable to operation with a normal trigger. Operation with a peak trigger voltage less than the breakdown voltage of this second gap increased the switch delay time by an amount comparable to the time required to ramp the trigger circuit output up to the breakdown voltage of the second gap. Finally, the effect that varying the bias voltage applied to the sprytron has on switch delay time was measured. The switch delay time did not appear to depend on bias voltage for bias voltages between 725 V and 2420 V.
Performance assessment modeling for High Level Waste (HLW) disposal incorporates three different types of uncertainty. These include data and parameter uncertainty, modeling uncertainty (which includes conceptual, mathematical, and numerical), and uncertainty associated with predicting the future state of the system. In this study, the potential impact of conceptual model uncertainty on the estimated performance of a hypothetical high-level radioactive waste disposal site in unsaturated, fractured tuff has been assessed for a given group of conceptual models. This was accomplished by taking a series of six, one-dimensional conceptual models, which differed only by the fundamental assumptions used to develop them, and conducting ground-water flow and radionuclide transport simulations. Complementary cumulative distribution functions (CCDFs) representing integrated radionuclide release to the water table indicate that differences in the basic assumptions used to develop conceptual models can have a significant impact on the estimated performance of the site. Because each of the conceptual models employed the same mathematical and numerical models, contained the same data and parameter values and ranges, and did not consider the possible future states of the system, changes in the CCDF could be attributed primarily to differences in conceptual modeling assumptions. Studies such as this one could help prioritize site characterization activities by identifying critical and uncertain assumptions used in model development, thereby providing guidance as to where reduction of uncertainty is most important.
The tectonics program for the proposed high-level nuclear waste repository at Yucca Mountain in southwestern Nevada must evaluate the potential for surface faulting beneath the prospective surface facilities. To help meet this goal, Quaternary surficial mapping studies and photolineament analyses were conducted to provide data for evaluating the location, recency, and style of faulting with Midway Valley at the eastern base of Yucca Mountain, the preferred location of these surface facilities. This interim report presents the preliminary results of this work.
Sandia is a government-owned, contractor-operated national laboratory that AT&T has operated on a no-profit, no-fee basis since 1949. We have been an integral part of the nuclear weapons program, providing total concept-to-retirement engineering for every warhead and bomb in the nuclear weapon stockpile. We are proud of our contributions to national security. Our scientific and engineering skills, our facilities, and our experience have benefited not only the nuclear weapons program but have also contributed significantly to their areas of national security, including conventional defense, energy, and industrial competitiveness. Likewise, these capabilities position us well to continue a tradition of exceptional service in the national service in the national interest. Sandia is a multiprogram national laboratory with mission responsibilities in nuclear weapons, arms control and verification, energy and environment, and technology transfer. Our work for the DOE Assistant Secretary for Defense Programs constitutes 50% of the laboratory`s effort. Sandia`s arms control, verification, and related intelligence and security programs, funded by DOE and by other agencies constitute the largest aggregation of such work at any facility in the world. We also support DOE with technology development -- in particular, specialized robotics and waste characterization and treatment processes to assist in the cleanup of contaminated sites. Research and development to support the National Energy Strategy is another substantial laboratory activity. Sandia`s successful developments in renewable, nuclear, and fossil energy technologies have saved the country billions of dollars in energy supply and utilization. Technology transfer is conducted across all Sandia programs.
A series of cyclic, direct-shear tests was conducted on several replicas of a tensile fracture of welded tuff to verify the graphical method proposed by Saeb (1989) and by Amedei and Saeb (1990). Tests were performed under different levels of constant normal load and constant normal stiffness. Each test consisted of five cycles of forward and reverse shear. The effect of cyclic loading on the fracture shear behavior was investigated. Fracture surface asperity degradation was quantified by comparing fracture fractal dimensions before and after shear.
The purpose of this talk is to set the scene with a definition of records management, records and federal records. It is also to introduce some techniques to ensure that office files are properly organized and maintained, rapidly retrievable, complete, and ready for appropriate disposition the NARA (National Archives and Records Administration) way.
A designed and assembled method for a non-adjustable Interferometer cavity has been developed at Sandia National Laboratories which has enabled the development of a Fixed-Cavity Velocity Interferometer System for Any Reflector (VISAR). In this system, the critical interference adjustments are performed during assembly of the interferometer cavity, freeing the user from an otherwise repetitive task. The Fixed-Cavity VISAR System is constructed in modular form. Compared to previous VISAR systems, it is easy to use, and gives high quality results. 6 refs.
This report contains a summary of large-scale experiments conducted at Sandia National Laboratories under the Solar Detoxification of Water project. The objectives of the work performed were to determine the potential of using solar radiation to destroy organic contaminants in water by photocatalysis and to develop the process and improve its performance. For these experiments, we used parabolic troughs to focus sunlight onto glass pipes mounted at the trough's focus. Water spiked with a contaminant and containing suspended titanium dioxide catalyst was pumped through the illuminated glass pipe, activating the catalyst with the ultraviolet portion of the solar spectrum. The activated catalyst creates oxidizers that attack and destroy the organics. Included in this report are a summary and discussion of the implications of experiments conducted to determine: the effect of process kinetics on the destruction of chlorinated solvents (such trichloroethylene, perchloroethylene, trichloroethane, methylene chloride, chloroform and carbon tetrachloride), the enhancement due to added hydrogen peroxide, the optimal catalyst loading, the effect of light intensity, the inhibition due to bicarbonates, and catalyst issues.
The high-temperature stability of current and proposed aviation fuels is a major factor in the design of advanced technology aircraft engines. Efforts to develop highly stable formulations and thereby mitigate fouling problems in aircraft fuel system components would clearly benefit from a predictive model that describes the important parameters in thermally induced degradation of the liquid fuel as well as the deposition of solid species. To generate such a model, diagnostic tools are needed to characterize adequately fluid dynamics, heat transfer, mass transfer and complex chemical processes that occur in thermally stressed fuels. In this paper, the authors describe preliminary results in the use of a dynamic light scattering technique, photon correlation spectroscopy (PCS), to address one aspect of the fuel stability problem; i.e., incipient particle formation and subsequent growth in mean particle size as a function of tempreture, exposure time, degree of oxidation, etc.
Accident severity categories are used in many risk analyses for the classification and treatment of accidents involving vehicles transporting radioactive materials. Any number or definition of severity categories may be used in an analysis. A methodology which allow accident probabilities associated with one severity category scheme to be transferred to another severity category scheme is described. The supporting data and information necessary to apply the methodology are also discussed. The ability to transfer accident probabilities between severity category schemes will allow some comparisons of different studies at the category level. The methodology can be employed to transfer any quantity between category schemes if the appropriate supporting information is available.
This paper will describe two data bases which provide supporting information on radioactive material transport experience in the United States. The Radioactive Material Incident Report (RMIR) documents accident/incident experience from 1971 to the present from data acquired from the US Department of Transportation (DOT) and the Nuclear Regulatory Commission (NRC). The Radioactive Material Postnotification (RAMPOST) data base documents the shipments that have taken place for Highway Route Controlled Quantities (HRCQ) of radioactive material. HRCQ shipments are post notified (that is, after the shipment) to the DOT.
A large buildup in interface traps has been observed in commercial and radiation-hardened MOS transistors at very long times after irradiation (> 10{sup 6} s). This latent buildup may have important implications for CMOS response in space. 13 refs.
The highest {Tc}`s achieved in organic electron-donor-based systems occur in two isostructural ET salts, viz., {kappa}-[(ET){sub 2}Cu][N(CN){sub 2}]X, X = Br ({Tc} = 11.6 K, ambient pressure), X = Cl ({Tc} = 12.8 K, 0.3 kbar) whereas for the electron-acceptor-based systems derived from C{sub 60} they occur in K{sub 3}C{sub 60} ({Tc} = 19 K), Rb{sub 3}C{sub 60} ({Tc} = 29 K), Rb{sub x}Cs{sub y}C{sub 60} ({Tc} 33 K) and Rb{sub x}Tl{sub y}C{sub 60} ({Tc} {approx} 45 K). Research performed at Argonne National Laboratory, and based on the ET and C{sub 60} systems, is reviewed.
A new approach for solving two-dimensional clustering problems is presented. The method is based on an inhibitory template which is applied to each pair of dots in a data set. Direct clustering of the pair is inhibited (allowed) if another dot is present (absent), respectively, within the area of the template. The performance of the method is thus entirely determined by the shape of the template. Psychophysical experiments have been used to define the template shape for this work, so that the resulting method requires no pattern-dependent adjustment of any parameters. The novel concept of a psychophysically-defined template and the absence of adjustable parameters set this approach apart from previous work. The useful grouping performance of this approach is demonstrated with the successful grouping of a variety of dot patterns selected from the clustering literature.
Sandia National Laboratories (SNL) Environmental Restoration (ER) Program has recently implemented a highly structured CS{sup 2} required by DOE. It is a complex system which has evolved over a period of a year and a half. During the implementation of this system, problem areas were discovered in cost estimating, allocation of management costs, and integration of the CS{sup 2} system with the Sandia Financial Information System. In addition to problem areas, benefits of the system were fund in the areas of schedule adjustment, projecting personnel requirements, budgeting, and responding to audits. Finally, a number of lessons were learned regarding how to successfully implement the system.
Ferroelectric PZT 53:47 thin films were prepared by two different solution deposition methodologies. Both routes utilized carboxylate and alkoxide precursors and acetic acid, which served as both a solvent and a chemical modifier. We have studied the effects of solution preparation conditions on film microstructure and ferroelectric properties, and have used NMR spectroscopy to characterize chemical differences between the two precursor solutions. Films prepared by a sequential precursor addition (SPA) process were characterized by slightly lossy hysteresis loops, with a P{sub r} of 18.7 {mu}C/cm{sup 2} and an E{sub c} of 55.2 kV/cm. Films prepared by an inverted mixing order (IMO) process were characterized by well saturated hysteresis loops, a P{sub r} of 26.2 {mu}C/cm{sup 2} and an E{sub c} of 43.3 kV/cm. While NMR investigations indicated that the chemical environments of both the proton and carbon species were similar for the two processes, differences in the amounts of by-products (esters, and therefore, water) formed were noted. These differences apparently impacted ceramic microstructure. Although both films were characterized by a columnar growth morphology, the SPA derived film displayed a residual pyrochlore layer at the film surface, which did not transform into the stable perovskite phase. The presence of this layer resulted in poor dielectric properties and lossy ferroelectric behavior.
CEPXS/ONELD is a discrete ordinates transport code package that can model the electron-photon cascade from 100 MeV to 1 keV. The CEPXS code generates fully-coupled multigroup-Legendre cross section data. This data is used by the general-purpose discrete ordinates code, ONELD, which is derived from the Los Alamos ONEDANT and ONETRAN codes. Version 1.0 of CEPXS/ONELD was released in 1989 and has been primarily used to analyze the effect of radiation environments on electronics. Version 2.0 is under development and will include user-friendly features such as the automatic selection of group structure, spatial mesh structure, and S{sub N} order.
Changing the focus of a corporate compensation and performance review system from process orientation to data base orientation results in a more integrated and flexible design. Data modeling of the business system provides both systems and human resource professionals insight into the underlying constants of the review process. Descriptions of the business and data modeling processes are followed by a detailed presentation of the data base model. Benefits derived from designing a system based on the model include elimination of hard-coding, better audit capabilities, a consistent approach to exception processing, and flexibility of integrating changes in compensation policy and philosophy.
This paper will address the purpose, scope, and approach of the Department of Energy Tiger Team Assessments. It will use the Tiger Team Assessment experience of Sandia National Laboratories at Albuquerque, New Mexico, as illustration.
The photocurrent response, photo-induced changes in hysteresis behavior, and electrooptic (birefringence) effects of sol-gel derived PZT film have been characterized as part of an effort to evaluate ferroelectric films for image storage and processing applications.
One of the common waste streams generated throughout the nuclear weapon complex is ``hardware`` originating from the nuclear weapons program. The activities associated with this hardware at Sandia National Laboratories (SNL) include design and development, environmental testing, reliability and stockpile surveillance testing, and military liaison training. SNL-designed electronic assemblies include radars, arming/fusing/firing systems, power sources, and use-control and safety systems. Waste stream characterization using process knowledge is difficult due to the age of some components and lack of design information oriented towards hazardous constituent identification. Chemical analysis methods such as the Toxicity Characteristic Leaching Procedure (TCLP) are complicated by the inhomogeneous character of these components and the fact that many assemblies have aluminum or stainless steel cases, with the electronics encapsulated in a foam or epoxy matrix. In addition, some components may contain explosives, radioactive materials, toxic substances (PCBs, asbestos), and other regulated or personnel hazards which must be identified prior to handling and disposal. In spite of the above difficulties, we have succeeded in characterizing a limited number of weapon components using a combination of process knowledge and chemical analysis. For these components, we have shown that if the material is regulated as RCRA hazardous waste, it is because the waste exhibits one or more hazardous characteristics; primarily reactivity and/or toxicity (Pb, Cd).
A brief discussion of the following topics is given in this report: Liquid Metal Divertors; Lithium Droplet Beam Divertor; Preferential Pumping of Helium; Reduced Erosion with Cu-Li, W-Li, etc.; Reduction of Erosion by Thermionic Emission; Reduced Erosion in Boronized Graphites; Proposal for Materials Experiments in TRIAM; Carbon-SiC for Plasma Facing Components; Helium Pumping with Palladium; Large Area Pump Limiter; Techniques for Enhanced Heat Removal; New Outlook on Gaseous Divertors; Gaseous Divertor Simulations; Impurity Seeding to Control ITER Particle and Heat Loads; Gaseous Divertor Experiments; Electrical Biasing to Control SOL Particle Fluxes; Biased Limiter in TEXTOR and Biased Divertor in PBX-M; Particle and Heat Flux Control Using Ponderomotive Forces; Helium Exhaust Using ICRF; Ergodic Magnetic Limiter Experiments in JFT-2M; and Helium Exhaust Using Fishbones.
The effects of argon addition to the vacuum arc remelting (VAR) process were studied in both laboratory and industrial experiments while remelting Alloy 718. The results demonstrate that argon can be added to an industrial VAR furnace to relatively high partial pressures without decreasing the melt rate, drip-short frequency, or constricting the arc plasma to a local region of the electrode surface. Laboratory experiments illustrate that this result is dependent on electrode chemistry, possibly related to magnesium content.
Melt pool shape in VAR is controlled by fluid flow, which is governed by the balance between two opposing flow fields. At low melt currents, flow is dominated by thermal buoyancy. In these instances, metal is swept radially outward on the pool surface, resulting in relatively shallow melt pools but increased heat transfer to the crucible at the melt pool surface. At high melt currents, flow is primarily driven by magento-hydrodynamic forces. In these cases, the surface flow is radially inward and downward, resulting in a constricted arc, the pool depth and relative heat transfer to the crucible are intermediate, even though the melt rate is significantly lower than either diffuse arc condition. Constricted arc conditions also result in erratic heat transfer behavior and non-uniformities in pool shape.
This report describes the Training and Qualification Program at the Simulation Technology Laboratory (STL). The main facility at STL is Hermes III, a twenty megavolt accelerator which is used to test military hardware for vulnerability to gamma-rays. The facility is operated and maintained by a staff of twenty engineers and technicians. This program is designed to ensure that these personnel are adequately trained and qualified to perform their jobs in a safe and efficient manner. Copies of actual documents used in the program are included in appendices. This program meets all the requirements for training and qualification in the DOE Orders on Conduct of Operations and Quality Assurance, and may be useful to other organizations desiring to come into compliance with these orders.
Division 2473 has characterized the performance of three types of focusing lenses used for CO{sub 2} laser beam welding. Specifically, we evaluated the plano-convex, positive meniscus, and aspheric lenses with focal lengths ranging from 1.25 to 5.0 inches. The measured responses were the resultant weld depth and width of bead-on-plate welds made using a range of focus positions. The welding parameters were 185 to 700 watts continuous wave beam power and 30 inches per minute travel speed. The results of this study quantified the weld profile dimensions as a function of lens type and focal length, beam power, depth of focus, and verified the coincidence of maximum weld depth and width.
The WC-1 and WC-3 experiments were conducted using a dry, 1:10 linear scale model of the Zion reactor cavity to obtain baseline data for comparison to future experiments that will have water in the cavity. WC-1 and WC-3 were performed with similar initial conditions except for the exit hole between the melt generator and the scaled model of the reactor cavity. For both experiments the molten core debris was simulated by a thermitically generated melt formed from 50 kg of iron oxide/aluminum/chromium powders. After the thermite was ignited in WC-1, the melt was forcibly ejected by 374 moles of slightly superheated steam at an initial driving pressure of 4.6 MPa through an exit hole with an actual diameter of 4.14 cm into the scaled model of the reactor cavity. In WC-3, the molten thermite was ejected by 300 moles of slightly superheated steam at an initial driving pressure of 3.8 MPa through an exit hole with an actual diameter of 10.1 cm into the scaled model of the reactor cavity. Because of the larger exit hole diameter, WC-3 had a shorter blowdown time than WC-1, 0.8`s compared to 3.0`s. WC-3 also had a higher debris velocity than WC-1, 54 m/s compared to 17.5 m/s. Posttest sieve analysis of debris recovered from the Surtsey vessel gave identical results in WC-1 and WC-3 for the sieve mass median particle diameter, i.e. 1.45 mm. The total mass ejected into the Surtsey vessel in WC-3 was 45.0 kg compared to 47.9 kg in WC-1. The peak pressure increase in Surtsey due to the high-pressure melt ejection (HPME) was 0.275 MPa in WC-3 and 0.272 in WC-1. Steam/metal reactions produced 181 moles of of hydrogen in WC-3 and 145 moles of hydrogen in WC-1.
Transport models used for performance assessment of the Waste Isolation Pilot Plant (WIPP) in the event of human intrusion into the repository currently rely on the K{sub d} linear sorption isotherm model to predict rates of radionuclide migration. The vast majority of K{sub d} data was measured in static (batch) experiment on powdered substrate; most data specific to the Culebra dolomite were gathered in this way for five radioelements of concern using up to four different water compositions. This report summarizes the available data, examines inconsistencies between these data and the assumptions of the K{sub d} model, and discusses potential difficulties in using existing sorption data for predictive modeling of radionuclide retardation through adsorption modeling are presented as an alternative to the K{sub d} model.
ITS is a powerful and user-friendly software package permitting state-of-the-art Monte Carlo solution of linear time-independent coupled electron/photon radiation transport problems, with or without the presence of macroscopic electric and magnetic fields of arbitrary spatial dependence. Our goal has been to simultaneously maximize operational simplicity and physical accuracy. Through a machine-portable utility that emulates the basic features of the CDC UPDATE processor, the user selects on of eight codes for running on a machine of one of at least four major vendors. The ease with which this utility is applied combines with an input scheme based on order-independent descriptive keywords that makes maximum use of defaults and internal error checking to provide experimentalists and theorists alike with a method for the routine but rigorous solution of sophisticated radiation transport problems. Physical rigor is maximized by employing the best available cross sections and sampling distributions, and the most complete physical model for describing the production and transport of the electron/photon cascade from 1.0 GeV down to 1.0 keV. Feasibility of construction permits the more sophisticated user to tailor the codes to specific applications and to extend the capabilities of the codes to more complex applications through simple update procedures. Version 3.0, the latest version of ITS, contains major improvements to the physical model, additional variance reduction via both internal restructuring and new user options, and expanded input/output capabilities.
A new algorithm for the treatment of sliding interfaces between solids with or without friction in an Eulerian wavecode is described. The algorithm has been implemented in the two-dimensional version of the CTH code. The code was used to simulate penetration and perforation of aluminum plates by rigid, conical-nosed tungsten projectiles. Comparison with experimental data is provided.
The first phase of a program to study the resistance of exclusion region barriers to ductile failure when subjected to accident-type, quasi-static extreme mechanical loads has been completed. This first phase consisted to qualification of the analytical tools used to study these types of structural deformations and the development of appropriate criteria to predict ductile failure. A series of tests were performed on hydroformed half-cylinder barrier mock-ups. The qualification activity was considered a success based upon the comparison of the deformations and loads measured during the testing to the response of these structures computed by the finite element modeling. This successful completion of the first phase allows the second phase program to proceed. 12 refs.
We have measured, by {sup 1}H and {sup 13}C nuclear magnetic resonance (NMR), the percent deuteration, the tacticity and the purity of several polymers and one solvent used in the preparation of microcellular foams. The percent deuteration was measured for polystyrene, polyacrylonitrile and polyethylene. The tacticities of polystyrene and polyacrylonitrile were determined. The purity and degradation products of polyacrylonitrile and maleic anhydride were examined. This report documents the experimental procedures and results of these measurements.
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 1991 and provides information pertinent to the operation of the DOE/AL system-wide Standards and Calibration Program.
The effects of cavern spacing and operating pressure on surface subsidence and cavern storage losses were evaluated using the finite- element method. The base case for the two sensitivity studies was a typical SPR cavern. The predicted responses of the base case and those from the pressurization study compared quite closely to measured surface subsidence and oil pressurization rates. This provided credibility for the analyses and constitutive models used. Subsidence and cavern storage losses were found to be strongly influenced by cavern spacing and pressurization. The relationship between subsidence volume and losses in storage volume varied as cavern spacing and operating pressure deviated from the base case. However, for a typical SPR cavern subsidence volume is proportional to storage loss and when expressed in ft., subsidence is equal to the percentage of storage loss.
The goal of the wet cavity (WC) test series was to investigate the effect of water in a reactor cavity on direct containment heating (DCH). The WC-1 experiment was performed with a dry cavity to obtain baseline data for comparison to the WC-2 experiment. WC-2 was conducted with water 3 cm deep (11.76 kg) in a 1:10 linear scale model of the Zion reactor cavity. The initial conditions for the experiments were similar. For both experiments the molten core debris was simulated by a thermitically generated melt formed from 50 kg of iron oxide/aluminum/chromium powders. After the charge was ignited, the debris was melted by the chemical reaction and was forcibly ejected through a nominal 3.5 cm hole into the scaled reactor cavity by superheated steam at an initial driving pressure of 4.58 MPa. The peak pressure increase in the containment due to the high-pressure melt ejection (HPME) was 0.272 MPa in WC-1 and 0.286 MPa in WC-2. The total amount of hydrogen generated in the experiments was 145 moles of H{sub 2} in WC-1 and 179 moles of H{sub 2} in WC-2. The total mass of debris ejected into the containment was identical for both experiments. These results suggest that water in the cavity slightly enhanced DCH.
Laboratory simulation of the approach of a radar fuze towards a target is an important factor in our ability to accurately measure the radar`s performance. This simulation is achieved, in part, by dynamically delaying and attenuating the radar`s transmitted pulse and sending the result back to the radar`s receiver. Historically, the device used to perform the dynamic delay has been a limiting factor in the evaluation of a radar`s performance and characteristics. A new device has been proposed that appears to have more capability than previous dynamic delay devices. This device is the digital RF memory. This report presents the results of an analysis of a digital RF memory used in a signal-delay application. 2 refs.
This report describes research and development related to Mo-based catalysts supported on hydrous metal oxide in exchangers for use in direct coal liquefaction processes. A group of NiMo catalysts were prepared on different hydrous titanium oxide (HTO) supports to serve as baseline materials for use in determining the effects of altering process parameters on the physical and catalytic properties of NiMoHTO catalysts. The baseline group included catalysts which had hydrogenation activities up to 40% higher than the best commercial NiMo/Al{sub 2}O{sub 3} catalysts used in coal liquefaction pilot plant studies on a weight of catalyst basis while containing 25% less active metal. The results of high resolution electron microscopy (HREM) studies addressing the effects of processing parameters on microstructure are also presented. NiMoHTO catalysts were included in a group of some 30 commercial and experimental catalysts tested at Amoco Oil Co. to determine applicability for upgrading coal resids. The performance of NiMoHTO catalysts in these tests was better than or comparable to the best commercial catalysts available for this application. The initial work with thin-film NiMoHTO catalysts supported on commercial silica gel spheres is presented. Second generation thin-film catalysts containing about 1% Mo have hydrogenation activities of about 75% of those of extruded commercial NiMo/Al{sub 2}O{sub 3} catalysts containing 10--13% Mo and up to 50% of the hydrodesulfurization activity of the commercial catalysts. The use of thin-film HTO technology, which allows for preparation of NiMoHTO catalysts on virtually any substrate lowers catalyst cost by reducing the amount of Ti required and provides engineering forms of HMO materials without development work needed to convert bulk HTO materials into usable engineering forms. Work done with NiMo catalysts supported on hydrous zirconium oxide (HZO) is also presented.
The third experiment of the Integral Effects Test (IET-3) series was conducted to investigate the effects of high pressure melt ejection (HPME) on direct containment heating (DCH). A 1:10 linear scale model of the Zion reactor pressure vessel (RPV), cavity, instrument tunnel, and subcompartment structures were constructed in the Surtsey Test Facility at Sandia National Laboratories (SNL). The RPV was modeled with a melt generator that consisted of a steel pressure barrier, a cast MgO crucible, and a thin steel inner liner. The melt generator/crucible had a semi-hemispherical bottom head containing a graphite limitor plate with a 3.5 cm exit hole to simulate the ablated hole in the RPV bottom head that would be formed by tube ejection in a severe nuclear power plant (NPP) accident. The reactor cavity model contained 3.48 kg of water with a depth of 0.9 cm that correspond to condensate levels in the Zion plant. A steam driven iron oxide/aluminum/chromium thermite was used to simulate HPME. IET-3 replicated the first experiment in the IET series (IET-1) except the Surtsey vessel contained 0.09 MPa air and 0.1 MPa nitrogen. No steam explosions occurred in the cavity in IET-3 experiment. The cavity pressure measurements showed that rapid vaporization of water occurred in the cavity at about the same time as the steam explosion in IET-1. However, the oxygen in the Surtsey vessel in IET-3 resulted in a vigorous hydrogen burn, which caused a significant increase in the peak pressure, 246 kPa compared to 98 kPa in the IET-1 test. The total debris mass ejected into the Surtsey vessel in IET-3 was 34.3 kg, and gas grab sample analysis indicated that 223 moles of hydrogen were produced by steam/metal reactions. About 186 moles of hydrogen burned and 37 moles remained unreacted.
This document presents planned actions, and their associated costs, for addressing the findings in the Environmental, Safety and Health Tiger Team Assessment of the Sandia National Laboratories, Albuquerque, May 1991, hereafter called the Assessment. This Final Action Plan should be read in conjunction with the Assessment to ensure full understanding of the findings addressed herein. The Assessment presented 353 findings in four general categories: (1)Environmental (82 findings); (2) Safety and Health (243 findings); (3) Management and Organization (18 findings); and (4) Self-Assessment (10 findings). Additionally, 436 noncompliance items with Occupational Safety and Health Administration (OSHA) standards were addressed during and immediately after the Tiger Team visit.
This paper addresses problems of synchronization and coordination in the context of faulty shared memory. We present algorithms for the consensus problem, and for reliable shared memory objects, from collections of read/write registers, 2-processor binary test-and-set objects, and read-modify-write registers, some of which may be faulty.
A computer program has been developed to reduce and analyze data from a standardized piezoelectric polymer (PVDF) shock-wave stress rate gauge. The program is menu driven with versatile graphic capabilities, input/output file options, hard copy options, and unique data processing capabilities. This program was designed to analyze digital current-mode'' data recorded from a Bauer PVDF stress-rate gauge and reduce it to a stress-versus-time record. The program was also designed to combine two simulanteously recorded data channels.
The purpose of the molten-salt pump and valve loop test is to demonstrate the performance, reliability, and service life of full-scale hot- and cold-salt pumps and valves for use in commercial central receiver solar power plants. This test was in operation at Sandia National Laboratories National Solar Thermal Test Facility from January 1988 to September 1990. The test hardware consists of two pumped loops; the hot-salt loop'' to simulate the piping and components on the hot (565{degrees}C) side of the receiver and the cold-salt loop'' to simulate piping and components on the receiver's cold (285{degrees}C) side. Each loop contains a pump and five valves sized to be representative of a conceptual 60-MW{sub e} commercial solar power plant design. The hot-salt loop accumulated over 6700 hours of operation and the cold-salt loop over 2500 hours during the test period. This project has demonstrated the performance and reliability required for commercial-scale molten-salt pumps and valves.