This document specifies the natural phenomena design loads for the Cold Vacuum Drying System.

Gamma-Ray imaging is a potentially powerful tool for the areas of arms-control, counter proliferation, safeguards and forensics. Combining spectral and spatial information increases the amount of information available for the detection and characterization of Special Nuclear Material (SNM). Two advanced gamma ray imaging technologies have been completed and are nearing completion at LLNL. These include the Gamma Ray Imaging System (GRIS), used to detect sub-600 keV gamma rays, and the Gamma Ray Bar Imaging Telescope (GRABIT), which extends the work of GRIS to larger areas and higher energies ({approximately}1000 keV). We proposed to continue work on a third, complementary type of detector, a Gamma Ray Color Camera (GRCC), which will incorporate spatial and spectral information from a gamma emitter.

The problem addressed by our invention is that of municipal solid waste utilization. The dimensions of the problem can be visualized by the common comparison that the average individual in America creates in five years time an amount of solid waste equivalent in weight to the Statue of Liberty. The combustible portion of the more than 11 billion tons of solid waste (including municipal solid waste) produced in the United States each year, if converted into useful energy, could provide 32 quads per year of badly needed domestic energy, or more than one-third of our annual energy consumption. Conversion efficiency and many other factors make such a production level unrealistic, but it is clear that we are dealing with a very significant potential resource. This report describes research pertaining to the co-combustion of oil shale with solid municipal wastes in a circulating fluidized bed. The oil shale adds significant fuel content and also constituents that can possible produce a useful cementitious ash.

This is the second annual report of the Committee on Interagency Radiation Research and Policy Coordination (CIRRPC). CIRRPC was established on April 9, 1984, to replace the Committee on Interagency Radiation Policy and was assigned responsibilities of the former Interagency Radiation Research Committee and former Radiation Policy Council. CIRRPC is chartered under the Federal Coordinating Council for Science, Engineering and Technology (FCCSET) and reports to the Office of Science and Technology Policy (OSTP), Executive Office of the President. Its overall charge is to coordinate radiation matters between agencies, evaluate radiation research, and provide advice on the formulation of radiation policy. During CIRRPC`s second year, the member agencies have called upon this interagency resource to assist in coordinating science and policy issues and to provide a vehicle to accomplish multiagency tasks.

Our two year project concluded with mixed results. The basic idea of using ozone and hydroxyl radical in a two stage plasma chemical reactor to remove NO{sub x} from automotive exhaust proved to be correct. However we found the energy needed to operate the plasma chemical reactor is 30% of the engine`s output, which is three times larger than that of the conventional catalytic converter. Our project is a partial success. If compactness is dropped as a requirement for our plasma-chemical reactor so that it is applicable to stationary rather than mobile power generators, then the reactor needs only 5% of the engine`s power. The energy inefficient component of the reactor, the part which makes our reactor compact, would be unnecessary. Thus our reactor has the potential for being a practical device to remove the NO{sub x} from the emissions of power plants.

The definitions of the magnetic field in MAD and in the standard multipole expansion (SME) used internally by Teapot are different. This note, perhaps for the umpTeenth time, defines the relationship between the two field definitions, assuming that they are in fact referring to the same physical quantity. After this discussion we define the relationship between RHIC's measured multipole coefficients and those of Teapot.

The purpose of this report is to examine and compare the approaches and practices of selected countries for disposal of low-level radioactive waste (LLW) with those of the US Department of Energy (DOE). The report addresses the programs for disposing of wastes into engineered LLW disposal facilities and is not intended to address in-situ options and practices associated with environmental restoration activities or the management of mill tailings and mixed LLW. The countries chosen for comparison are France, Sweden, Canada, and the United Kingdom. The countries were selected as typical examples of the LLW programs which have evolved under differing technical constraints, regulatory requirements, and political/social systems. France was the first country to demonstrate use of engineered structure-type disposal facilities. The UK has been actively disposing of LLW since 1959. Sweden has been disposing of LLW since 1983 in an intermediate-depth disposal facility rather than a near-surface disposal facility. To date, Canada has been storing its LLW but will soon begin operation of Canada`s first demonstration LLW disposal facility.

The utilization of microwave energy for reaching high temperatures necessary to densify B{sub 4}C powder is compared with conventional means of sintering by evaluating the mechanical properties after densification. Microwave energy has been shown to be an effective means for achieving high sintered densities, even though temperatures of {approximately} 2,250 C are required. In this study, green preforms of B{sub 4}C specimens were sintered by both conventional and microwave heating. This study also utilized an advanced forming method called ``Gelcasting`` developed at ORNL. Gelcasting is a fluid forming process whereby high solids suspensions of powders containing dissolved monomers are cast into a mold, then polymerized or ``gelled`` in situ. This investigation compares microstructures and mechanical properties of both Gelcast B{sub 4}C and ``conventionally`` die-pressed B{sub 4}C. The microstructures and final mechanical properties of B{sub 4}C specimens are discussed.

The purpose of this document is to provide hydrogeologic, geochemical, and vapor monitoring data required for comprehensive monitoring of underground storage tanks (UST) 0439-U, 0440-U, 2073-U, 2074-U, and 2075-U at the East End Fuel Station. Comprehensive monitoring was conducted at the site in May 1996 at the direction of the Tennessee Department of Environment and Conservation (TDEC) based on review and notice of deficiencies in the Site-specific Standard Request. This document is organized into three sections. Section 1 presents introductory information relative to the site including regulatory initiative and a description of the site. Section 2 includes the results of water level measurement and sampling of monitoring wells at the site. Section 3 presents data from vapor monitoring conducted in subsurface utilities present at the site. Appendix A contains the original analytical laboratory results for environmental and quality control samples collected during comprehensive monitoring.

Numerical studies of the nonlinear evolution of MHD-type tearing modes in three-dimensional toroidal geometry with neoclassical effects are presented. The inclusion of neoclassical physics introduces an additional free-energy source for the nonlinear formation of magnetic islands through the effects of a bootstrap current in Ohm`s law. The neoclassical tearing mode is demonstrated to be destabilized in plasmas which are otherwise {Delta}` stable, albeit once an island width threshold is exceeded. The plasma pressure dynamics and neoclassical tearing growth is shown to be sensitive to the choice of the ratio of the parallel to perpendicular diffusivity ({Chi}{parallel}/{Chi}{perpendicular}). The study is completed with a demonstration and theoretical comparison of the threshold for single helicity neoclassical MHD tearing modes, which is described based on parameter scans of the local pressure gradient, the ratio of perpendicular to parallel pressure diffusivities {Chi}{perpendicular}/{Chi}{parallel}, and the magnitude of an initial seed magnetic perturbation.

This report describes the Computer Codes for Evaluation of Control Room Habitability (HABIT). HABIT is a package of computer codes designed to be used for the evaluation of control room habitability in the event of an accidental release of toxic chemicals or radioactive materials. Given information about the design of a nuclear power plant, a scenario for the release of toxic chemicals or radionuclides, and information about the air flows and protection systems of the control room, HABIT can be used to estimate the chemical exposure or radiological dose to control room personnel. HABIT is an integrated package of several programs that previously needed to be run separately and required considerable user intervention. This report discusses the theoretical basis and physical assumptions made by each of the modules in HABIT and gives detailed information about the data entry windows. Sample runs are given for each of the modules. A brief section of programming notes is included. A set of computer disks will accompany this report if the report is ordered from the Energy Science and Technology Software Center. The disks contain the files needed to run HABIT on a personal computer running DOS. Source codes for the various HABIT routines …

This report compares the performance of several computers. Some of the machines are discontinued, and some are anticipated, but most are currently installed at Sandia Laboratories. All the computers are personal workstations or departmental servers, except for comparison, one is a Cray C90 mainframe supercomputer (not owned by the Laboratories). A few of the computers have multiple processors, but parallelism is not tested. The time to run three programs is reported for every computer. Unlike many benchmarks, these are complete application programs. They were written and are used at Sandia Laboratories. Also SPECmarks are reported for many computers. These are industry standard performance ratings. They are in general agreement with the speeds of running the Sandia programs. This report concludes with some background material and notes about specific manufacturers.

This Conceptual Design Letter Report provides details on the activities required to be performed for this project and also provides cost estimates and schedules for those activities.

Several structural dynamics codes have been developed at, and under contract to, the National Wind Technology Center (NWTC). These design codes capture knowledge and expertise that has accumulated over the years through federally funded research and wind industry operational experience. The codes can generate vital information required to successfully implement wind turbine active control. However, system information derived from the design codes does not necessarily produce a system description that is consistent with the one assumed by standard control design and analysis tools (e.g., MATLAB{reg_sign} and Matrix-X{reg_sign}). This paper presents a system identification-based method for extracting and utilizing high-fidelity dynamics information, derived from an existing wind turbine structural dynamics code (FAST), for use in active control design. A simple proportional-integral (PI) aileron control case study is then used to successfully demonstrate the method, and to investigate controller performance for gust and turbulence wind input conditions. Aileron control results show success in both power regulation and load mitigation.

This document consists of a list of projects supporting work on oil recovery programs. A publications list and index of companies and institutions is provided. The remaining portion of the document provides brief descriptions on projects in chemical flooding, gas displacement, thermal recovery, geoscience, resource assessment, and reservoir class field demonstrations.

The Controlled, Clean, and Stable (CCS) Design Requirements Document (DRD) contains the technically defensible and traceable functions and requirements for maintaining the Single-Shell Tank Farms in a cost effective and safe interim end state. The CCSDRD functions and requirements constitute the project characteristics that are minimally sufficient to meet the CCS mission goals.

A few conventions for thinking about and writing quantum pseudocode are proposed. The conventions can be used for presenting any quantum algorithm down to the lowest level and are consistent with a quantum random access machine (QRAM) model for quantum computing. In principle a formal version of quantum pseudocode could be used in a future extension of a conventional language.

Measurements of {sup 14}C/{sup 13}C ratios were made on samples of Oxalic Acid and {sup 14}C dead materials spanning the mass range from 10 {micro}g to {approximately} 1 mg. These measurements have allowed the determination of both the amount, and the {sup 14}C content, of the contaminant carbon introduced during sample processing in the laboratory. These data were used to correct measured {sup 14}C/{sup 13}C ratios obtained from ANU Sucrose and {approximately} one-half-life old test samples for the influence of the contaminant. The test samples spanned the 10 {micro}g to {approximately} 1 mg mass range and the corrections were made using three different formulae. The results obtained from these calculations allow the accuracy of these background correction formulae to be evaluated.

1.1 Purpose The purpose of this investigation is to collect data to confirm the presence or absence of contamination, evaluate the potential for contaminant migration, and select appropriate closure methods for these sites. The potential closure methods for these sites involve either clean closure, closure in place, or no further action. 1.2 Scope The scope of this investigation includes collecting surface and subsurface soil samples at the Roller Coaster Lagoons; and collecting surface soil samples at the North Disposal Trench and the small spill area associated with the Voluntary Cotiective Action (VCA) that was conducted in 1995.

Consistent direction for identification, long-term reporting and trending, and correction of conditions adverse to the environment, safety and health will facilitate a successful transition and follow- on for the Project Hanford Management Contractor (PHMC). Continuity of the corrective action management process is vital. It provides consistency via reporting and trending on corrective action management activities at the Site during the transition process. To ensure success,consideration of the business rules and the Hanford Action Tracking System (HATS), the automated tool that supports them, is essential. This document provides a consolidated synopsis of corrective action management business rules, the process, and the HATS to support the transition process at Hanford. It applies to the baseline of corrective action work the PHMC and its subcontractors will inherit. HATS satisfies the requirement for collection of data that enables long-term reporting and trending. The information contains all originating document, condition,and action data. HATS facilitates consistent tracking,reporting, closure, and trending of the corrective action work in progress across the Site. HATS follows the glossary standard definitions for commitment tracking listed in Appendix A and Site data value standards that are applicable. For long term access and use, HATS data are fed to a full text search …

The development of a silicon carbide (SiC) heat exchanger is a critical step in the development of the Externally-Fired Combined Cycle (EFCC) power system. SiC is the only material that provides the necessary combination of resistance to creep, thermal shock, and oxidation. While the SiC structure materials provide the thermomechanical and thermophysical properties needed for an efficient system, the mechanical properties of the SiC tubes are severely degraded through corrosion by the coal combustion products. To obtain the necessary service life of thousands of hours at temperature, a protective coating is needed that is stable with both the SiC tube and the coal combustion products, resists erosion from the particle laden gas stream, is thermal shock resistant, adheres to SiC during repeated thermal shocks (start-up, process upsets, shut-down), and allows the EFCC system to be cost competitive. This demanding set of technical performance and cost drivers was used in reviewing and selecting candidate protective materials. After a review of open literature, discussion with leading researchers in materials for coal combustion environments, and preliminary thermodynamic studies, a total of ten materials were identified for future study that were grouped into three categories: alumina-based materials, materials stable with SiO{sub 2}, and low …

Alloys under consideration as candidates for the high level nuclear waste containers at Yucca Mountain were exposed to a range of corrosion conditions and their performance measured. The alloys tested were Incoloy 825, 70/30 Copper-Nickel, Monel 400, Hastelloy C- 22, and low carbon steel. The test conditions varied were: temperature, concentration, agitation, and crevice simulation. Only in the case of carbon steel was significant attack noted. This attack appeared to be transport limited.

The 1990 announcement of the Huffman-Kratschmer fullerene-production technique set off a world-wide explosion of research into the properties and potential applications of C{sub 60} and C{sub 70}. In the last five years, 4,000+ fullerene articles have appeared in the scientific literature dealing with these fascinating molecules and their condensed phases. They possess a complex chemistry reminiscent of the alkenes, and this has led to the syntheses of numerous new compounds and fullerene-based materials, with suggested applications ranging from medicine to photo-conducting polymers to rocket fuel. The work summarized in this report focused on the creation and destruction of fullerene-based materials, for the purpose of producing new materials of interest. This three year project was supported by a grant from the Advanced Energy Projects Division, Office of Basic Energy Sciences, U.S. Department of Energy (DE-FG03-93ER12133). Following are outlines of the work completed in each of the three years, a section devoted to the professional and educational development of those involved, a brief section on the outlook for fullerene-based materials, and an appendix listing the publications resulting from this project.

The design of the D0 single sided 3 chip ladder is shown in figures 1-3. The SVX II chips are mounted directly opposite the cooling channel so that they are most efficiently cooled. Outboard of the cooling channel on the ladder top side is mounted a flex hybrid of copper/kapton. which is adhered to a beryllium substrate using a two part epoxy. The beryllium substrate. aside from providing a solid mounting structure for the flex circuit. provides a thermal conduction path between the components on the hybrid which dissipate heat and the cooling channel. The thickness of the top and bottom beryllium substrates is selected based on the [expected] channel temperature. the power dissipation of the SVX II chips, the power dissipation of the hybrid passive components, and the maximum acceptable silicon temperature within the ladder. The thermal conductivity of the various materials within the ladder must be known to a fair degree of confidence in order to accurately simulate the ladder steady state cooling performance. The thermal conductivity of a number of ladder epoxy candidates was measured using a device at Lab D at Fermilab. Preliminary measurements at Lab D, using a similar setup. have been performed in order …