Geothermal energy represents the largest U.S. energy resource base and already provides an important contribution to our nation's energy needs. This overview looks at the basic science behind the various geothermal technologies and provides information on DOE Geothermal Energy Program activities and accomplishments.

Tensile stresses in the Toshiba cold mass support links generated by the loadings the coil is subject to, and the deflections the coil experiences as a result of these loadings, are estimated. The axial links are conservatively designed and it should be reasonably easy to ensure that the three links at each end of the coil carry approximately equal loads. Small deviations from this ideal should not have great consequence as a system-of-three is somewhat forgiving in this regard. The use of preload makes the north operating deflection equal to the smaller south operating deflection, possibly a convenience when the nozzle design is contemplated. Toshiba has indicated they will establish the desired preload using strain gauges near the warm ends of the links.

This engineering note documents calculations done to determine the margin of safety for the lower clean room roof. The analysis was done to give me a feeling of what the loads, stresses and capacity of the roof is prior to installation and installation work to be done for the helium refrigerator upgrade. The result of this quick look showed that the calculated loads produce stress values and loads at about half the allowables. Based on this result, I do not think that special precautions above personal judgement are required for the installation work.

None

Report updating the original and 1989 Transit plans for DART mobility projects. It provides a summary of services including bus, HOV, rail, and general mobility. It also breaks down the corridor recommendations, including the North Central Corridor, South Oak Cliff Corridor, and others. This plan supersedes the Transit Plan adopted in 1989.

This analysis is prepared by the Mined Geologic Disposal System (MGDS) Waste Package Development Department (WPDD) as specified in the Waste Package Implementation Plan (pp. 4-8,4-11,4-24,5-1, and 5-13; Ref. 5.10) and Waste Package Plan (pp. 3-15,3-17, and 3-24; Ref. 5.9). The design data request addressed herein is: Characterize the conceptual Defense High Level Waste (DHLW) Disposal Container design to show that the design is feasible for use in the MGDS environment when loaded with a plutonium/cesium greenfield glass waste form. The purpose of this analysis is to respond to a concern that the long-term disposal thermal issues for the conceptual DHLW disposal container design do not preclude compatibility with the MGDS if it is loaded with alternate waste forms. The objective of this analysis is to provide thermal parameter information for the conceptual DHLW disposal container design loaded with an alternative waste form containing a plutonium/cesium mixture under nominal MGDS repository conditions. The results are intended to show that the design loaded with this alternative waste form has a reasonable chance to meet the MGDS design requirements for normal MGDS operation and to provide the required guidance to determining the major design issues for future design efforts. Future design efforts …

This analysis is prepared by the Mined Geologic Disposal System (MGDS) Waste Package Development Department (WPDD) as specified in the Waste Package Implementation Plan (pp. 4-8,4-11,4-24,5-1, and 5-13; Ref. 5.10) and Waste Package Plan (pp. 3-15,3-17, and 3-24; Ref. 5.9). The design data request addressed herein is: (1) Characterize the conceptual 40 BWR Multi-Purpose Canister (MPC) Waste Package (WP) design to show that the design is feasible for use in the MGDS environment when loaded with BWR MOX SNF. (2) Characterize the conceptual 24 BWR Multi-Purpose Canister (MPC) Waste Package (WP) design to show that the design is feasible for use in the MGDS environment when loaded with BWR MOX SNF. The purpose of this analysis is to respond a concern that the long-term disposal thermal issues for the Multi-Purpose Canister (MPC) Subsystem Design, if used with SNF designed for a MOX fuel cycle, do not preclude MPC compatibility with the MGDS. The objective of this analysis is to provide thermal parameter information for the conceptual MPC design with disposal container which is loaded with BWR MOX SNF under nominal MGDS repository conditions. The results are intended to show that the design has a reasonable chance to meet the MGDS …

The purpose of this analysis is to produce coordinate geometry calculations sufficient to establish the position of the conceptual Geologic Repository Operations Area (GROA) as it relates to the position of the Exploratory Studies Facility (ESF) planned exploratory drifting and the physical site. The focus of this analysis is to show the mathematical validity of the arrangement. The documentation which supports the development of the configuration can be found in References 5.3 and 5.4. This analysis supports the production of the ESF/GROA Interface drawings which are used by the Project to demonstrate and control the physical interfaces between the ESF and Repository.

A literature review on extractants for strontium removal was initially performed at Northern Illinois University to assess their potential in magnetically assisted chemical separation. A series of potential strontium extractants was systematically evaluated there using radioanalytical methods. Initial experiments were designed to test the uptake of strontium from nitric acid using several samples of magnetic extractant particles that were coated with various crown ether ligands. High partition coefficient (K(sub d)) values for stimulant tank waste were obtained. Further studies demonstrated that the large partitioning was due to uncoated particles.

The dynamic response of magnetically levitated (maglev) ground transportation systems has important consequences for safety and ride quality, guideway design, and system costs. Ride quality is determined by vehicle response and by environmental factors such as humidity and noise. The dynamic response of the vehicles is the key element in determining ride quality, while vehicle stability is an important safety-related element. To design a guideway that provides acceptable ride quality in the stable region, vehicle dynamics must be understood. Furthermore, the trade-off between guideway smoothness and levitation and control systems must be considered if maglev systems are to be economically feasible. The link between the guideway and the other maglev components is vehicle dynamics. For a commercial maglev system, vehicle dynamics must be analyzed and tested in detail. This report, which reviews various aspects of the dynamic characteristics, experiments and analysis, and design guidelines for maglev systems, discusses vehicle stability, motion dependent magnetic force components, guideway characteristics, vehicle/ guideway interaction, ride quality, suspension control laws, aerodynamic loads and other excitations, and research needs.

A number of physics problems may be cast in terms of Hilbert-Schmidt integral equations. In many cases, the integrals tend to be zero over a large portion of the domain of interest. All of the information is contained in compact regions of the domain which renders their use very attractive from the standpoint of efficient numerical computation. Discrete representation of these integrals leads to a system of N elements which have pair-wise interactions with one another. A direct solution technique requires computational effort which is O(N{sup 2}). Fast multipole methods (FMM) have been widely used in recent years to obtain solutions to these problems requiring a computational effort of only O(Nln N) or O(N). In this paper we present an overview of several variations of the fast multipole method along with examples of its use in solving a variety of physical problems.

This report describes inorganic and organic analyses results from samples obtained from the headspace of the Hanford waste storage Tank 241-TY-101 (referred to as Tank TY-101). The results described here were obtained to support safety and toxicological evaluations. A summary of the results for inorganic and organic analytes is listed in Table 1. Detailed descriptions of the results appear in the text. Quantitative results were obtained for the inorganic compounds ammonia (NH{sub 3}), nitrogen dioxide (NO{sub 2}), nitric oxide (NO), and water vapor (H{sub 2}O). Sampling for hydrogen cyanide (HCN) and sulfur oxides (SO{sub x}) was not requested. In addition, quantitative results were obtained for the 39 TO-14 compounds plus an additional 14 analytes. Off these, 5 were observed above the 5-ppbv reporting cutoff. One tentatively identified compound (TIC) was observed above the reporting cutoff of (ca.) 10 ppbv and are reported with concentrations that are semiquantitative estimates based on internal-standard response factors. The six organic analyses identified are listed in Table 1 and account for approximately 100% of the total organic components in Tank TY-101. Two permanent gases, carbon dioxide (CO{sub 2}) and nitrous oxide (N{sub 2}O), were also detected. Tank TY-101 is on the Ferrocyanide Watch List.

Colloidal particles are known to enhance the transport of radioactive metals through soil and rock systems. This study was performed to determine if a soil microorganism, isolated from the surface samples collected at Yucca Mountain, NV, could affect the colloidal properties of day particles. The agglomeration of a Wyoming bentonite clay in a sterile uninoculated microbial growth medium was compared to the agglomeration in the medium inoculated with a Pseudomonas sp. In a second experiment, microorganisms were cultured in the succinate medium for 50 h and removed by centrifugation. The agglomeration of the clay in this spent was compared to sterile uninoculated medium. In both experiments, the agglomeration of the clay was greater than that of the sterile, uninoculated control. Based on these results, which indicate that this microorganism enhanced the agglomeration of the bentonite clay, it is possible to say that in the presence of microorganisms colloidal movement through a rock matrix could be reduced because of an overall increase in the size of colloidal particle agglomerates. 32 refs.

The Home Energy Rating System (HERS) Building Energy Simulation Test (BESTEST) is a method for evaluating the credibility of software used by HERS to model energy use in buildings. The method provides the technical foundation for ''certification of the technical accuracy of building energy analysis tools used to determine energy efficiency ratings,'' as called for in the Energy Policy Act of 1992 (Title I, Subtitle A, Section 102, Title II, Part 6, Section 271). Certification is accomplished with a uniform set of test cases that Facilitate the comparison of a software tool with several of the best public-domain, state-of-the-art building energy simulation programs available in the United States. The HERS BESTEST work is divided into two volumes. Volume 1 contains the test case specifications and is a user's manual for anyone wishing to test a computer program. Volume 2 contains the reference results and suggestions for accrediting agencies on how to use and interpret the results.

In the proposal for this work, submitted in November 1990, the author described the application of silicon micro-vertex tracking to hadron collider physics, and outlined a plan of involvement in the first such application, at the CDF Detector, studying p{anti p} collisions at {radical}s = 1.8 TeV at the Fermilab Tevatron. The proposal included discussion on the use of silicon tracking in B physics measurements, and also some speculation on the ability of silicon tracking to aid in identification of the top quark. In the five years since this proposal, the author has played a significant role in the installation and commissioning of the first such silicon tracking device at a hadron collider, and the utilization of this device in the discovery of the top quark and the study of B production mechanisms. This paper is a summary of this work.

This study identifies four categories of GTCC LLW: nuclear utility; sealed sources; DOE-held; and other generators. Within each category, inventory and projection data are modeled in three scenarios: (1) Unpackaged volume--this is the unpackaged volume of waste that would exceed Class C limits if the waste calculation methods in 10 CFR 61.55 were applied to the discrete items before concentration averaging methods were applied to the volume; (2) Not-concentration-averaged (NCA) packaged volume--this is the packaged volume of GTCC LLW assuming that no concentration averaging is allowed; and (3) After-concentration-averaging (ACA) packaged volume--this is the packaged volume of GTCC LLW, which, for regulatory or practical reasons, cannot be disposed of in a LLW disposal facility using allowable concentration averaging practices. Three cases are calculated for each of the volumes described above. These values are defined as the low, base, and high cases. The following tables explain the assumptions used to determine low, base, and high case estimates for each scenario, within each generator category. The appendices referred to in these tables are appendices to Greater-Than-Class C Low-Level Radioactive Waste Characterization: Estimated Volumes, Radionuclide Activities, and Other Characteristics (DOE/LLW-114, Revision 1).

This report presents the justification and technical documentation for all changes and updates made (since 1993) to the Energy Code for Commercial and High-Rise Residential Buildings, the codified version of ASHRAE/IES Standard 90.1-1989, ``Energy Efficient Design of New Buildings Except Low-Rise Residential Buildings.`` These changes and updates, which were subject to the ASHRAE addenda approval process, include Addenda b, c, d, e, g, and i. A seventh addenda, Addenda f, which has not been officially approved by ASHRAE, has been included into the proposed rule. Also included in the changes was technical work conducted to justify revisions to the 1993 DOE lighting power densities. The updated text will be reviewed by the U.S. Department of Energy (DOE) and issued as the new Federal Commercial Building Energy Code (10 CFR 434); Mandatory for New Federal Commercial and Multi-Family High Rise Residential Buildings.

Since 1982, there has been a major effort expended to evaluate the susceptibility of nuclear Power plant equipment to failure and significant damage during seismic events. This was done by making use of data on the performance of electrical and mechanical equipment in conventional power plants and other similar industrial facilities during strong motion earthquakes. This report is intended as an extension of the seismic experience data collection effort and a compilation of experience data specific to power plant piping and supports designed and constructed US power piping code requirements which have experienced strong motion earthquakes. Eight damaging (Richter Magnitude 7.7 to 5.5) California earthquakes and their effects on 8 power generating facilities in use natural gas and California were reviewed. All of these facilities were visited and evaluated. Seven fossel-fueled (dual use natural gas and oil) and one nuclear fueled plants consisting of a total of 36 individual boiler or reactor units were investigated. Peak horizontal ground accelerations that either had been recorded on site at these facilities or were considered applicable to these power plants on the basis of nearby recordings ranged between 0.20g and 0.5lg with strong motion durations which varied from 3.5 to 15 seconds. Most …

The purpose of this study is to extend the knowledge base for wetland treatment to include processes and substances of particular importance to small, on-site systems receiving oil and gas well waste water. Collection of data on the sorption of heavy metals and the degradation of toxic organics is one of the key tasks. The toxic organics phenolics and anthracene, and chromium and copper have been selected as target adsorbates. An information search was performed on oil refinery waste treatment wetland systems.

The Resource Conservation and Recovery Act (RCRA), as amended, requires that tanks used for the storage or treatment of hazardous waste (HazW) be permitted, and comply with the requirements contained within the Code of Federal Regulations (CFR) TItle 40 in Subpart J of Part 264/265, unless those tanks have been exempted. Subpart J specifies requirements for the design, construction, installation, operation, inspection, maintenance, repair, release, response, and closure of HazW tanks. Also, the regulations make a distinction between new and existing tanks. Effective December 6, 1995, standards for controlling volatile organic air emissions will apply to non-exempt HazW tanks. HazW tanks will have to be equipped with a cover or floating roof, or be designed to operate as a closed system, to be in compliance with the air emission control requirements. This information brief describes those tanks that are subject to the Subpart J requirements, and will also discuss secondary containment, inspection, restrictions on waste storage, release response, and closure requirements associated with regulated HazW tanks.

The original SIMION was an electrostatic lens analysis and design program developed by D.C. McGilvery at Latrobe University, Bundoora Victoria, Australia, 1977. SIMION for the PC, developed at the Idaho National Engineering Laboratory, shares little more than its name with the original McGilvery version. INEL`s fifth major SIMION release, version 6.0, represents a quantum improvement over previous versions. This C based program can model complex problems using an ion optics workbench that can hold up to 200 2D and/or 3D electrostatic/magnetic potential arrays. Arrays can have up to 10,000,000 points. SIMION 3D`s 32 bit virtual Graphics User Interface provides a highly interactive advanced user environment. All potential arrays are visualized as 3D objects that the user can cut away to inspect ion trajectories and potential energy surfaces. User programs have been greatly extended in versatility and power. A new geometry file option supports the definition of highly complex array geometry. Extensive algorithm modifications have dramatically improved this version`s computational speed and accuracy.

The Web Interface Template System (WITS) is a tool for software developers. WITS is a three-tiered, object-oriented system operating in a Client/Server environment. This tool can be used to create software applications that have a Web browser as the user interface and access a Sybase database. Development, modification, and implementation are greatly simplified because the developer can change and test definitions immediately, without writing or compiling any code. This document explains WITS functionality, the system structure and components of WITS, and how to obtain, install, and use the software system.

This report documents calculations performed to establish a technical basis for the nuclear criticality safety of favorable geometry containers, sometimes referred to as 5-inch containers, in use at the Portsmouth Gaseous Diffusion Plant. A list of containers currently used in the plant is shown in Table 1.0-1. These containers are currently used throughout the plant with no mass limits. The use of containers with geometries or material types other than those addressed in this evaluation must be bounded by this analysis or have an additional analysis performed. The following five basic container geometries were modeled and bound all container geometries in Table 1.0-1: (1) 4.32-inch-diameter by 50-inch-high polyethylene bottle; (2) 5.0-inch-diameter by 24-inch-high polyethylene bottle; (3) 5.25-inch-diameter by 24-inch-high steel can ({open_quotes}F-can{close_quotes}); (4) 5.25-inch-diameter by 15-inch-high steel can ({open_quotes}Z-can{close_quotes}); and (5) 5.0-inch-diameter by 9-inch-high polybottle ({open_quotes}CO-4{close_quotes}). Each container type is evaluated using five basic reflection and interaction models that include single containers and multiple containers in normal and in credible abnormal conditions. The uranium materials evaluated are UO{sub 2}F{sub 2}+H{sub 2}O and UF{sub 4}+oil materials at 100% and 10% enrichments and U{sub 3}O{sub 8}, and H{sub 2}O at 100% enrichment. The design basis safe criticality limit for the Portsmouth facility …

Ceramic candle filtration is an attractive technology for particulate removal at high temperatures. The primary objective of this SBIR research program is to increase the performance, durability, and corrosion resistance of lightweight filter candles and filter tubesheet components (Fibrosic{trademark}), fabricated from vacuum formed chopped ceramic fiber (VFCCF), for use in advanced coal utilization applications. Phase 1 results proved that significant gains in material strength and particle retentivity are possible by treatment of VFCCF materials with colloidal ceramic oxides. Phase 2 effort will show how these treated materials tolerate high temperature and vapor-phase alkali species, on a long-term basis. With good durability and corrosion resistance, high temperature capability, and a low installed and replacement cost, these novel materials will help promote commercial acceptance of ceramic candle filter technology, as well as increase the efficiency and reliability of coal utilization processes in general.