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  1. MOOSE

    Energy Science and Technology Software Center (OSTI)

    002565WKSTN01 Multiphysics Object Oriented Simulation Environment https://github.com/idaholab/moose

  2. MOOSE: Multiphysics Object-Oriented Simulation Environment

    ScienceCinema (OSTI)

    Gaston, Derek

    2014-05-30

    An overview of Idaho National Laboratory's MOOSE: Multiphysics Object-Oriented Simulation Environment

  3. Bull Moose Energy | Open Energy Information

    Open Energy Info (EERE)

    Energy Jump to: navigation, search Name: Bull Moose Energy Address: P.O. Box 231501 Place: Encinitas, California Zip: 92023 Region: Southern CA Area Sector: Biomass Product:...

  4. Bull Moose Energy LLC | Open Energy Information

    Open Energy Info (EERE)

    Place: San Diego, California Sector: Biomass Product: Focused on development of biomass waste energy projects. References: Bull Moose Energy LLC1 This article is a stub. You...

  5. Delcer Butte Geothermal Project | Open Energy Information

    Open Energy Info (EERE)

    Butte Geothermal Project Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Development Project: Delcer Butte Geothermal Project Project Location Information...

  6. Butte Springs Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    Butte Springs Geothermal Area Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Butte Springs Geothermal Area Contents 1 Area Overview 2 History and Infrastructure 3...

  7. Butte, Montana: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    Butte, Montana: Energy Resources (Redirected from Butte, MT) Jump to: navigation, search Equivalent URI DBpedia Coordinates 46.003917, -112.534446 Show Map Loading map......

  8. Moose Lake Water & Light Comm | Open Energy Information

    Open Energy Info (EERE)

    Website: www.mooselakepower.com Facebook: https:www.facebook.compagesMoose-Lake-Water-Light-Commission445326012175319?frefts Outage Hotline: (218) 485-4100 References:...

  9. Pervasive Restart In MOOSE-based Applications

    SciTech Connect (OSTI)

    Derek Gaston; Cody Permann; David Andrs; John Peterson; Andrew Slaughter; Jason Miller

    2014-01-01

    Multiphysics applications are inherently complicated. Solving for multiple, interacting physical phenomena involves the solution of multiple equations, and each equation has its own data dependencies. Feeding the correct data to these equations at exactly the right time requires extensive effort in software design. In an ideal world, multiphysics applications always run to completion and produce correct answers. Unfortunately, in reality, there can be many reasons why a simulation might fail: power outage, system failure, exceeding a runtime allotment on a supercomputer, failure of the solver to converge, etc. A failure after many hours spent computing can be a significant setback for a project. Therefore, the ability to continue a solve from the point of failure, rather than starting again from scratch, is an essential component of any high-quality simulation tool. This process of continuation is commonly termed restart in the computational community. While the concept of restarting an application sounds ideal, the aforementioned complexities and data dependencies present in multiphysics applications make its implementation decidedly non-trivial. A running multiphysics calculation accumulates an enormous amount of state: current time, solution history, material properties, status of mechanical contact, etc. This state data comes in many different forms, including scalar, tensor, vector, and arbitrary, application-specific data types. To be able to restart an application, you must be able to both store and retrieve this data, effectively recreating the state of the application before the failure. When utilizing the Multiphysics Object Oriented Simulation Environment (MOOSE) framework developed at Idaho National Laboratory, this state data is stored both internally within the framework itself (such as solution vectors and the current time) and within the applications that use the framework. In order to implement restart in MOOSE-based applications, the total state of the system (both within the framework and without) must be stored and retrieved. To this end, the MOOSE team has implemented a pervasive restart capability which allows any object within MOOSE (or within a MOOSE-based application) to be declared as state data, and handles the storage and retrieval of said data.

  10. Coffin Butte Biomass Facility | Open Energy Information

    Open Energy Info (EERE)

    NEEDS 2006 Database Retrieved from "http:en.openei.orgwindex.php?titleCoffinButteBiomassFacility&oldid397332" Feedback Contact needs updating Image needs updating...

  11. Butte County, Idaho: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    6 Climate Zone Subtype B. Places in Butte County, Idaho Arco, Idaho Butte City, Idaho Moore, Idaho Retrieved from "http:en.openei.orgwindex.php?titleButteCounty,Idaho&oldi...

  12. Sigurd Red Butte No2 | Open Energy Information

    Open Energy Info (EERE)

    Sigurd Red Butte No2 Jump to: navigation, search NEPA Document Collection for: Sigurd Red Butte No2 EIS for NA Sigurd to Red Butte No. 2 345kV Transmission Project General NEPA...

  13. EA-1996: Glass Buttes Radio Station, Lake County, Oregon | Department...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    6: Glass Buttes Radio Station, Lake County, Oregon EA-1996: Glass Buttes Radio Station, Lake County, Oregon SUMMARY The Bureau of Land Management (BLM), with DOE's Bonneville Power...

  14. Development Wells At Glass Buttes Area (DOE GTP) | Open Energy...

    Open Energy Info (EERE)

    Glass Buttes Area (DOE GTP) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Development Wells At Glass Buttes Area (DOE GTP) Exploration Activity...

  15. Multispectral Imaging At Glass Buttes Area (DOE GTP) | Open Energy...

    Open Energy Info (EERE)

    Glass Buttes Area (DOE GTP) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Multispectral Imaging At Glass Buttes Area (DOE GTP) Exploration...

  16. Aeromagnetic Survey At Glass Buttes Area (DOE GTP) | Open Energy...

    Open Energy Info (EERE)

    Glass Buttes Area (DOE GTP) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Aeromagnetic Survey At Glass Buttes Area (DOE GTP) Exploration...

  17. Cuttings Analysis At Glass Buttes Area (DOE GTP) | Open Energy...

    Open Energy Info (EERE)

    Glass Buttes Area (DOE GTP) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Cuttings Analysis At Glass Buttes Area (DOE GTP) Exploration Activity...

  18. Butte County, California: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    Companies in Butte County, California FAFCO Inc Sierra Nevada Brewing Company Springboard Biodiesel LLC Energy Generation Facilities in Butte County, California Oroville Biomass...

  19. Butte, Montana: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    is a stub. You can help OpenEI by expanding it. Butte is a city in Silver Bow County, Montana. It falls under Montana's At-large congressional district.12 Registered Energy...

  20. Innovative Exploration Technologies Maui Hawaii & Glass Buttes, Oregon |

    Broader source: Energy.gov (indexed) [DOE]

    Department of Energy Technologies Maui Hawii & Glass Buttes, Oregon presentation at the April 2013 peer review meeting held in Denver, Colorado. PDF icon moui_glass_buttes_ormat_peer2013.pdf More Documents & Publications Innovative Exploration Technologies Maui Hawaii & Glass Buttes, Oregon Blind Geothermal System Exploration in Active Volcanic Environments; Multi-phase Geophysical and Geochemical Surveys in Overt & Subtle Volcanic Systems, Hawaii & Maui Merging high

  1. Static Temperature Survey At Glass Buttes Area (DOE GTP) | Open...

    Open Energy Info (EERE)

    to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Static Temperature Survey At Glass Buttes Area (DOE GTP) Exploration Activity Details Location Glass...

  2. Pressure Temperature Log At Glass Buttes Area (DOE GTP) | Open...

    Open Energy Info (EERE)

    navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Pressure Temperature Log At Glass Buttes Area (DOE GTP) Exploration Activity Details Location Glass...

  3. Dr. Calvin O. Butts, III | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Calvin O. Butts, III About Us Dr. Calvin O. Butts, III - President, State University of New York (SUNY) College at Old Westbury Dr. Calvin O. Butts, III Dr. Calvin O. Butts, III, is President of State University of New York, College at Old Westbury and Pastor of the renowned Abyssinian Baptist Church in New York City. Regularly sought by leaders in politics, business, and the media for his insight and opinions, he has had a pervasive impact across his career on such wide-ranging issues as

  4. Butts County, Georgia: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    Number 3 Climate Zone Subtype A. Places in Butts County, Georgia Flovilla, Georgia Jackson, Georgia Jenkinsburg, Georgia Retrieved from "http:en.openei.orgw...

  5. Box Butte County, Nebraska: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    Box Butte County, Nebraska: Energy Resources Jump to: navigation, search Equivalent URI DBpedia Coordinates 42.1911471, -103.0817903 Show Map Loading map......

  6. Documentation of Hybrid Hydride Model for Incorporation into Moose-Bison

    Energy Savers [EERE]

    and Validation Strategy | Department of Energy Documentation of Hybrid Hydride Model for Incorporation into Moose-Bison and Validation Strategy Documentation of Hybrid Hydride Model for Incorporation into Moose-Bison and Validation Strategy This report documents the development, demonstration and validation of a mesoscale, microstructural evolution model for simulation of zirconium hydride d-ZrH1.5 precipitation in the cladding of used nuclear fuels that may occur during long-term dry

  7. Ground Gravity Survey At Glass Buttes Area (DOE GTP) | Open Energy...

    Open Energy Info (EERE)

    Ground Gravity Survey At Glass Buttes Area (DOE GTP) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Ground Gravity Survey At Glass Buttes Area...

  8. FMI Log At Glass Buttes Area (DOE GTP) | Open Energy Information

    Open Energy Info (EERE)

    Glass Buttes Area (DOE GTP) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: FMI Log At Glass Buttes Area (DOE GTP) Exploration Activity Details...

  9. LiDAR At Glass Buttes Area (DOE GTP) | Open Energy Information

    Open Energy Info (EERE)

    Glass Buttes Area (DOE GTP) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: LiDAR At Glass Buttes Area (DOE GTP) Exploration Activity Details...

  10. Slim Holes At Glass Buttes Area (DOE GTP) | Open Energy Information

    Open Energy Info (EERE)

    Glass Buttes Area (DOE GTP) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Slim Holes At Glass Buttes Area (DOE GTP) Exploration Activity...

  11. Field Mapping At Glass Buttes Area (DOE GTP) | Open Energy Information

    Open Energy Info (EERE)

    Glass Buttes Area (DOE GTP) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Field Mapping At Glass Buttes Area (DOE GTP) Exploration Activity...

  12. Gas Sampling At Glass Buttes Area (DOE GTP) | Open Energy Information

    Open Energy Info (EERE)

    Gas Sampling At Glass Buttes Area (DOE GTP) (Redirected from Water-Gas Samples At Glass Buttes Area (DOE GTP)) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home...

  13. Gas Sampling At Glass Buttes Area (DOE GTP) | Open Energy Information

    Open Energy Info (EERE)

    Gas Sampling At Glass Buttes Area (DOE GTP) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Gas Sampling At Glass Buttes Area (DOE GTP)...

  14. Flow Test At Glass Buttes Area (DOE GTP) | Open Energy Information

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Flow Test At Glass Buttes Area (DOE GTP) Exploration Activity Details Location Glass Buttes Area...

  15. Glass Buttes Exploration and Drilling: 2010 Geothermal Technologies Program Peer Review Presentation, Walsh, et al, Ormat

    DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

    Zemach, Ezra

    2010-01-01

    Glass Buttes Exploration and Drilling: 2010 Geothermal Technologies Program Peer Review Presentation, Walsh, et al, Ormat

  16. Glass Buttes Exploration and Drilling: 2010 Geothermal Technologies Program Peer Review Presentation, Walsh, et al, Ormat

    DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

    Zemach, Ezra

    Glass Buttes Exploration and Drilling: 2010 Geothermal Technologies Program Peer Review Presentation, Walsh, et al, Ormat

  17. Butte Falls, Oregon: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    This article is a stub. You can help OpenEI by expanding it. Butte Falls is a town in Jackson County, Oregon. It falls under Oregon's 2nd congressional district.12 References...

  18. Red Butte, Wyoming: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    Hide Map This article is a stub. You can help OpenEI by expanding it. Red Butte is a census-designated place in Natrona County, Wyoming. It falls under Wyoming's...

  19. Redwing: A MOOSE application for coupling MPACT and BISON

    SciTech Connect (OSTI)

    Frederick N. Gleicher; Michael Rose; Tom Downar

    2014-11-01

    Fuel performance and whole core neutron transport programs are often used to analyze fuel behavior as it is depleted in a reactor. For fuel performance programs, internal models provide the local intra-pin power density, fast neutron flux, burnup, and fission rate density, which are needed for a fuel performance analysis. The fuel performance internal models have a number of limitations. These include effects on the intra-pin power distribution by nearby assembly elements, such as water channels and control rods, and the further limitation of applicability to a specified fuel type such as low enriched UO2. In addition, whole core neutron transport codes need an accurate intra-pin temperature distribution in order to calculate neutron cross sections. Fuel performance simulations are able to model the intra-pin fuel displacement as the fuel expands and densifies. These displacements must be accurately modeled in order to capture the eventual mechanical contact of the fuel and the clad; the correct radial gap width is needed for an accurate calculation of the temperature distribution of the fuel rod. Redwing is a MOOSE-based application that enables coupling between MPACT and BISON for transport and fuel performance coupling. MPACT is a 3D neutron transport and reactor core simulator based on the method of characteristics (MOC). The development of MPACT began at the University of Michigan (UM) and now is under the joint development of ORNL and UM as part of the DOE CASL Simulation Hub. MPACT is able to model the effects of local assembly elements and is able calculate intra-pin quantities such as the local power density on a volumetric mesh for any fuel type. BISON is a fuel performance application of Multi-physics Object Oriented Simulation Environment (MOOSE), which is under development at Idaho National Laboratory. BISON is able to solve the nonlinearly coupled mechanical deformation and heat transfer finite element equations that model a fuel element as it is depleted in a nuclear reactor. Redwing couples BISON and MPACT in a single application. Redwing maps and transfers the individual intra-pin quantities such as fission rate density, power density, and fast neutron flux from the MPACT volumetric mesh to the individual BISON finite element meshes. For a two-way coupling Redwing maps and transfers the individual pin temperature field and axially dependent coolant densities from the BISON mesh to the MPACT volumetric mesh. Details of the mapping are given. Redwing advances the simulation with the MPACT solution for each depletion time step and then advances the multiple BISON simulations for fuel performance calculations. Sub-cycle advancement can be applied to the individual BISON simulations and allows multiple time steps to be applied to the fuel performance simulations. Currently, only loose coupling where data from a previous time step is applied to the current time step is performed.

  20. EIS-0077-S: Bonneville Power Administration Crow Butte Slough Crossing

    Broader source: Energy.gov [DOE]

    The Bonneville Power Administration developed this SEIS to evaluate potential impacts resulting from construction of a 4,700-foot segment of the Ashe-Slatt transmission line at Crow Butte Slough, overhead on towers on the existing right-of-way. This SEIS is a supplement to DOE/EIS-0077, Ashe-Slatt (Pebble Springs) 500-kilovolt Transmission Line, originally filed as FES 75-79.

  1. The Western Environmental Technology Office (WETO), Butte, Montana. Technology summary

    SciTech Connect (OSTI)

    1996-03-01

    The Western Environmental Technology Office (WETO) is a multi-purpose engineering test facility located in Butte, Montana, and is managed by MSE, Inc. WETO seeks to contribute to environmental research by emphasizing projects to develop heavy metals removal and recovery processes, thermal vitrification systems, and waste minimization/pollution prevention technologies. WETO`s environmental technology research and testing activities focus on the recovery of usable resources from waste. In one of WETO`s areas of focus, groundwater contamination, water from the Berkeley Pit, located near the WETO site, is being used in demonstrations directed toward the recovery of potable water and metal from the heavy metal-bearing water. The Berkeley Pit is part of an inactive copper mine near Butte that was once part of the nation`s largest open-pit mining operation. The Pit contains approximately 25 billion gallons of Berkeley Pit groundwater and surface water containing many dissolved minerals. As part of DOE/OST`s Resource Recovery Project (RRP), technologies are being demonstrated to not only clean the contaminated water but to recover metal values such as copper, zinc, and iron with an estimated gross value of more than $100 million. When recovered, the Berkeley Pit waters could benefit the entire Butte valley with new water resources for fisheries, irrigation, municipal, and industrial use. At WETO, the emphasis is on environmental technology development and commercialization activities, which will focus on mine cleanup, waste treatment, resource recovery, and water resource management.

  2. Preliminary geologic map of the Sleeping Butte volcanic centers

    SciTech Connect (OSTI)

    Crowe, B.M.; Perry, F.V.

    1991-07-01

    The Sleeping Butte volcanic centers comprise two, spatially separate, small-volume (<0.1 km{sup 3}) basaltic centers. The centers were formed by mildly explosive Strombolian eruptions. The Little Black Peak cone consists of a main scoria cone, two small satellitic scoria mounds, and associated lobate lava flows that vented from sites at the base of the scoria cone. The Hidden Cone center consists of a main scoria cone that developed on the north-facing slope of Sleeping Butte. The center formed during two episodes. The first included the formation of the main scoria cone, and venting of aa lava flows from radial dikes at the northeast base of the cone. The second included eruption of scoria-fall deposits from the summit crater. The ages of the Little Black Peak and the Hidden Cone are estimated to be between 200 to 400 ka based on the whole-rock K-Ar age determinations with large analytical undertainty. This age assignment is consistent with qualitative observations of the degree of soil development and geomorphic degradation of volcanic landforms. The younger episode of the Hidden Cone is inferred to be significantly younger and probably of Late Pleistocene or Holocene age. This is based on the absence of cone slope rilling, the absence of cone-slope apron deposits, and erosional unconformity between the two episodes, the poor horizon- development of soils, and the presence of fall deposits on modern alluvial surfaces. Paleomagnetic data show that the centers record similar but not identical directions of remanent magnetization. Paleomagnetic data have not been obtained for the youngest deposits of the Hidden Cone center. Further geochronology, soils, geomorphic, and petrology studies are planned of the Sleeping Butte volcanic centers 20 refs., 3 figs.

  3. Ultrasonic inspection of polyethylene butt-fussion joints

    SciTech Connect (OSTI)

    House, L.J.; Day, R.A.

    1982-01-01

    Researchers investigated nondestructive pulse-echo, pitch-catch, and spectroscopic ultrasonic methods for determining voids and inclusions, lack of bond, and inadequate fusion in heat-fused polyethylene butt joints in 4-in. gas distribution pipe. The pulse-echo method, using a 2.25-MHz, cylindrically focused transducer, provided the best sensitivity to the joint defects, detecting flaws as small as 0.014 in. in diameter. No correlation was established between the ultrasonic spectroscopy results and the cohesive strength of incompletely fused joints in the 1.2-3.2 MHz frequency range.

  4. Continuous integration for concurrent MOOSE framework and application development on GitHub

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Slaughter, Andrew E.; Peterson, John W.; Gaston, Derek R.; Permann, Cody J.; Andrs, David; Miller, Jason M.

    2015-11-20

    For the past several years, Idaho National Laboratory’s MOOSE framework team has employed modern software engineering techniques (continuous integration, joint application/framework source code repos- itories, automated regression testing, etc.) in developing closed-source multiphysics simulation software (Gaston et al., Journal of Open Research Software vol. 2, article e10, 2014). In March 2014, the MOOSE framework was released under an open source license on GitHub, significantly expanding and diversifying the pool of current active and potential future contributors on the project. Despite this recent growth, the same philosophy of concurrent framework and application development continues to guide the project’s development roadmap. Severalmore » specific practices, including techniques for managing multiple repositories, conducting automated regression testing, and implementing a cascading build process are discussed in this short paper. Furthermore, special attention is given to describing the manner in which these practices naturally synergize with the GitHub API and GitHub-specific features such as issue tracking, Pull Requests, and project forks.« less

  5. The Western Environmental Technology Office (WETO), Butte, Montana, technology summary

    SciTech Connect (OSTI)

    Not Available

    1994-09-01

    This document has been prepared by the DOE Environmental Management (EM) Office of Technology Development (OTD) to highlight its research, development, demonstration, testing, and evaluation activities funded through the Western Environmental Technology Office (WETO) in Butte, Montana. Technologies and processes described have the potential to enhance DOE`s cleanup and waste management efforts, as well as improve US industry`s competitiveness in global environmental markets. WETO`s environmental technology research and testing activities focus on the recovery of useable resources from waste. Environmental technology development and commercialization activities will focus on mine cleanup, waste treatment, resource recovery, and water resource management. Since the site has no record of radioactive material use and no history of environmental contamination/remediation activities, DOE-EM can concentrate on performing developmental and demonstration activities without the demands of regulatory requirements and schedules. Thus, WETO will serve as a national resource for the development of new and innovative environmental technologies.

  6. Dormaier and Chester Butte 2007 Follow-up Habitat Evaluation Procedures Report.

    SciTech Connect (OSTI)

    Ashley, Paul R.

    2008-01-01

    Follow-up habitat evaluation procedures (HEP) analyses were conducted on the Dormaier and Chester Butte wildlife mitigation sites in April 2007 to determine the number of additional habitat units to credit Bonneville Power Administration (BPA) for providing funds to enhance, and maintain the project sites as partial mitigation for habitat losses associated with construction of Grand Coulee Dam. The Dormaier follow-up HEP survey generated 482.92 habitat units (HU) or 1.51 HUs per acre for an increase of 34.92 HUs over baseline credits. Likewise, 2,949.06 HUs (1.45 HUs/acre) were generated from the Chester Butte follow-up HEP analysis for an increase of 1,511.29 habitat units above baseline survey results. Combined, BPA will be credited with an additional 1,546.21 follow-up habitat units from the Dormaier and Chester Butte parcels.

  7. The coupling of the neutron transport application RATTLESNAKE to the nuclear fuels performance application BISON under the MOOSE framework

    SciTech Connect (OSTI)

    Gleicher, Frederick N.; Williamson, Richard L.; Ortensi, Javier; Wang, Yaqi; Spencer, Benjamin W.; Novascone, Stephen R.; Hales, Jason D.; Martineau, Richard C.

    2014-10-01

    The MOOSE neutron transport application RATTLESNAKE was coupled to the fuels performance application BISON to provide a higher fidelity tool for fuel performance simulation. This project is motivated by the desire to couple a high fidelity core analysis program (based on the self-adjoint angular flux equations) to a high fidelity fuel performance program, both of which can simulate on unstructured meshes. RATTLESNAKE solves self-adjoint angular flux transport equation and provides a sub-pin level resolution of the multigroup neutron flux with resonance treatment during burnup or a fast transient. BISON solves the coupled thermomechanical equations for the fuel on a sub-millimeter scale. Both applications are able to solve their respective systems on aligned and unaligned unstructured finite element meshes. The power density and local burnup was transferred from RATTLESNAKE to BISON with the MOOSE Multiapp transfer system. Multiple depletion cases were run with one-way data transfer from RATTLESNAKE to BISON. The eigenvalues are shown to agree well with values obtained from the lattice physics code DRAGON. The one-way data transfer of power density is shown to agree with the power density obtained from an internal Lassman-style model in BISON.

  8. Evaluation of INL Supplied MOOSE/OSPREY Model: Modeling Water Adsorption on Type 3A Molecular Sieve

    SciTech Connect (OSTI)

    Pompilio, L. M.; DePaoli, D. W.; Spencer, B. B.

    2014-08-29

    The purpose of this study was to evaluate Idaho National Labs Multiphysics Object-Oriented Simulation Environment (MOOSE) software in modeling the adsorption of water onto type 3A molecular sieve (3AMS). MOOSE can be thought-of as a computing framework within which applications modeling specific coupled-phenomena can be developed and run. The application titled Off-gas SeParation and REcoverY (OSPREY) has been developed to model gas sorption in packed columns. The sorbate breakthrough curve calculated by MOOSE/OSPREY was compared to results previously obtained in the deep bed hydration tests conducted at Oak Ridge National Laboratory. The coding framework permits selection of various options, when they exist, for modeling a process. For example, the OSPREY module includes options to model the adsorption equilibrium with a Langmuir model or a generalized statistical thermodynamic adsorption (GSTA) model. The vapor solid equilibria and the operating conditions of the process (e.g., gas phase concentration) are required to calculate the concentration gradient driving the mass transfer between phases. Both the Langmuir and GSTA models were tested in this evaluation. Input variables were either known from experimental conditions, or were available (e.g., density) or were estimated (e.g., thermal conductivity of sorbent) from the literature. Variables were considered independent of time, i.e., rather than having a mass transfer coefficient that varied with time or position in the bed, the parameter was set to remain constant. The calculated results did not coincide with data from laboratory tests. The model accurately estimated the number of bed volumes processed for the given operating parameters, but breakthrough times were not accurately predicted, varying 50% or more from the data. The shape of the breakthrough curves also differed from the experimental data, indicating a much wider sorption band. Model modifications are needed to improve its utility and predictive capability. Recommended improvements include: greater flexibility for input of mass transfer parameters, time-variable gas inlet concentration, direct output of loading and temperature profiles along the bed, and capability to conduct simulations of beds in series.

  9. Quasi-Rayleigh waves in butt-welded thick steel plate

    SciTech Connect (OSTI)

    Kamas, Tuncay E-mail: victorg@sc.edu Giurgiutiu, Victor E-mail: victorg@sc.edu Lin, Bin E-mail: victorg@sc.edu

    2015-03-31

    This paper discusses theoretical and experimental analyses of weld guided surface acoustic waves (SAW) through the guided wave propagation (GWP) analyses. The GWP analyses have been carried out by utilizing piezoelectric wafer active sensors (PWAS) for in situ structural inspection of a thick steel plate with butt weld as the weld bead is ground flush. Ultrasonic techniques are commonly used for validation of welded structures in many in-situ monitoring applications, e.g. in off-shore structures, in nuclear and pressure vessel industries and in a range of naval applications. PWAS is recently employed in such ultrasonic applications as a resonator as well as a transducer. Quasi-Rayleigh waves a.k.a. SAW can be generated in relatively thick isotropic elastic plate having the same phase velocity as Rayleigh waves whereas Rayleigh waves are a high frequency approximation of the first symmetric (S0) and anti-symmetric (A0) Lamb wave modes. As the frequency becomes very high the S0 and the A0 wave speeds coalesce, and both have the same value. This value is exactly the Rayleigh wave speed and becomes constant along the frequency i.e. Rayleigh waves are non-dispersive guided surface acoustic waves. The study is followed with weld-GWP tests through the pitch-catch method along the butt weld line. The tuning curves of quasi-Rayleigh wave are determined to show the tuning and trapping effect of the weld bead that has higher thickness than the adjacent plates on producing a dominant quasi-Rayleigh wave mode. The significant usage of the weld tuned and guided quasi-Rayleigh wave mode is essentially discussed for the applications in the in-situ inspection of relatively thick structures with butt weld such as naval offshore structures. The paper ends with summary, conclusions and suggestions for future work.

  10. The Western Environmental Technology Office (WETO), Butte, Montana. Technology summary (Revised)

    SciTech Connect (OSTI)

    1996-03-01

    This document has been prepared by the US Department of Energy`s (DOE`s) Office of Environmental Management (EM) Office of Science and Technology (OST) to highlight its research, development, demonstration, testing, and evaluation (RDDT&E) activities funded through the Western environmental Technology Office (WETO) in Butte, Montana. Technologies and processes described in this document have the potential to enhance DOE`s cleanup and waste management efforts, as well as improve US industry`s competitiveness in global environmental markets. The information presented in this document has been assembled from recently produced OST documents that highlight technology development activities within each of the OST program elements and Focus Areas. This document presents one in a series for each of DOE`s Operations Office and Energy Technology Centers.

  11. EA-1925: Midnight Point and Mahogany Geothermal Exploration Projects, Glass Buttes, Oregon

    Broader source: Energy.gov [DOE]

    This EA evaluates Ormat Nevada, Inc.’s (Ormat’s) proposed geothermal project consists of drilling up to 16 wells for geothermal exploration approximately 70 miles southeast of Bend, Oregon and 50 miles northwest of Burns, Oregon just south of U.S. Highway 20. The proposed project includes three distinct drilling areas. Up to three wells would be drilled on lands managed by the Bureau of Land Management (BLM) Prineville District (Mahogany), up to ten wells would be drilled on lands managed by the BLM Burns District (Midnight Point), and up to three wells would be drilled on private land located adjacent to the federal geothermal leases west of Glass Butte (Private Lands). DOE funding would be associated with three of the sixteen proposed wells. BLM is the lead agency and DOE is participating as a cooperating agency.

  12. Merging high resolution geophysical and geochemical surveys to reduce exploration risk at glass buttes, Oregon

    SciTech Connect (OSTI)

    Walsh, Patrick; Fercho, Steven; Perkin, Doug; Martini, Brigette; Boshmann, Darrick

    2015-06-01

    The engineering and studies phase of the Glass Buttes project was aimed at reducing risk during the early stages of geothermal project development. The project’s inclusion of high resolution geophysical and geochemical surveys allowed Ormat to evaluate the value of these surveys both independently and in combination to quantify the most valuable course of action for exploration in an area where structure, permeability, and temperature are the most pressing questions. The sizes of the thermal anomalies at Glass Buttes are unusually large. Over the course of Phase I Ormat acquired high resolution LIDAR data to accurately map fault manifestations at the surface and collected detailed gravity and aeromagnetic surveys to map subsurface structural features. In addition, Ormat collected airborne hyperspectral data to assist with mapping the rock petrology and mineral alteration assemblages along Glass Buttes faults and magnetotelluric (MT) survey to try to better constrain the structures at depth. Direct and indirect identification of alteration assemblages reveal not only the geochemical character and temperature of the causative hydrothermal fluids but can also constrain areas of upflow along specific fault segments. All five datasets were merged along with subsurface lithologies and temperatures to predict the most likely locations for high permeability and hot fluids. The Glass Buttes temperature anomalies include 2 areas, totaling 60 km2 (23 mi2) of measured temperature gradients over 165° C/km (10° F/100ft). The Midnight Point temperature anomaly includes the Strat-1 well with 90°C (194 °F) at 603 m (1981 ft) with a 164 °C/km (10°F/100ft) temperature gradient at bottom hole and the GB-18 well with 71°C (160 °F) at 396 m (1300 ft) with a 182°C/km (11°F/100ft) gradient. The primary area of alteration and elevated temperature occurs near major fault intersections associated with Brothers Fault Zone and Basin and Range systems. Evidence for faulting is observed in each data set as follows. Field observations include fault plane orientations, complicated fault intersections, and hydrothermal alteration apparently pre-dating basalt flows. Geophysical anomalies include large, linear gradients in gravity and aeromagnetic data with magnetic lows possibly associated with alteration. Resistivity low anomalies also appear to have offsets associated with faulting. Hyperspectral and XRF identified alteration and individual volcanic flow units, respectively. When incorporated into a 3D geologic model, the fault intersections near the highest proven temperature and geophysical anomalies provide the first priority targets at Midnight Point. Ormat geologists selected the Midnight Point 52-33 drilling target based on a combination of pre-existing drilling data, geologic field work, geophysical interpretation, and geochemical analysis. Deep temperatures of well 52-33 was lower than anticipated. Temperature gradients in the well mirrored those found in historical drilling, but they decreased below 1500 ft and were isothermal below 2000 ft.

  13. The direct collapse of a massive black hole seed under the influence of an anisotropic Lyman-Werner source

    SciTech Connect (OSTI)

    Regan, John A.; Johansson, Peter H.; Wise, John H.

    2014-11-10

    The direct collapse model of supermassive black hole seed formation requires that the gas cools predominantly via atomic hydrogen. To this end we simulate the effect of an anisotropic radiation source on the collapse of a halo at high redshift. The radiation source is placed at a distance of 3 kpc (physical) from the collapsing object and is set to emit monochromatically in the center of the Lyman-Werner (LW) band. The LW radiation emitted from the high redshift source is followed self-consistently using ray tracing techniques. Due to self-shielding, a small amount of H{sub 2} is able to form at the very center of the collapsing halo even under very strong LW radiation. Furthermore, we find that a radiation source, emitting >10{sup 54} (∼ 10{sup 3} J{sub 21}) photons s{sup –1}, is required to cause the collapse of a clump of M ∼ 10{sup 5} M {sub ☉}. The resulting accretion rate onto the collapsing object is ∼0.25 M {sub ☉} yr{sup –1}. Our results display significant differences, compared to the isotropic radiation field case, in terms of the H{sub 2} fraction at an equivalent radius. These differences will significantly affect the dynamics of the collapse. With the inclusion of a strong anisotropic radiation source, the final mass of the collapsing object is found to be M ∼ 10{sup 5} M {sub ☉}. This is consistent with predictions for the formation of a supermassive star or quasi-star leading to a supermassive black hole.

  14. The DNA repair endonuclease XPG interacts directly and functionally with the WRN helicase defective in Werner syndrome

    SciTech Connect (OSTI)

    Trego, Kelly S.; Chernikova, Sophia B.; Davalos, Albert R.; Perry, J. Jefferson P.; Finger, L. David; Ng, Cliff; Tsai, Miaw-Sheue; Yannone, Steven M.; Tainer, John A.; Campisi, Judith; Cooper, Priscilla K.

    2011-04-20

    XPG is a structure-specific endonuclease required for nucleotide excision repair (NER). XPG incision defects result in the cancer-prone syndrome xeroderma pigmentosum, whereas truncating mutations of XPG cause the severe postnatal progeroid developmental disorder Cockayne syndrome. We show that XPG interacts directly with WRN protein, which is defective in the premature aging disorder Werner syndrome, and that the two proteins undergo similar sub-nuclear redistribution in S-phase and co-localize in nuclear foci. The co-localization was observed in mid- to late-S-phase, when WRN moves from nucleoli to nuclear foci that have been shown to contain protein markers of both stalled replication forks and telomeric proteins. We mapped the interaction between XPG and WRN to the C-terminal domains of each and show that interaction with the C-terminal domain of XPG strongly stimulates WRN helicase activity. WRN also possesses a competing DNA single-strand annealing activity that, combined with unwinding, has been shown to coordinate regression of model replication forks to form Holliday junction/chicken foot intermediate structures. We tested whether XPG stimulated WRN annealing activity and found that XPG itself has intrinsic strand annealing activity that requires the unstructured R- and C-terminal domains, but not the conserved catalytic core or endonuclease activity. Annealing by XPG is cooperative, rather than additive, with WRN annealing. Taken together, our results suggest a novel function for XPG in S-phase that is at least in part carried out coordinately with WRN, and which may contribute to the severity of the phenotypes that occur upon loss of XPG.

  15. Cohesive zone finite element analysis of crack initiation from a butt joint’s interface corner

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Reedy, E. D.

    2014-09-06

    The Cohesive zone (CZ) fracture analysis techniques are used to predict the initiation of crack growth from the interface corner of an adhesively bonded butt joint. In this plane strain analysis, a thin linear elastic adhesive layer is sandwiched between rigid adherends. There is no preexisting crack in the problem analyzed, and the focus is on how the shape of the traction–separation (T–U) relationship affects the predicted joint strength. Unlike the case of a preexisting interfacial crack, the calculated results clearly indicate that the predicted joint strength depends on the shape of the T–U relationship. Most of the calculations usedmore » a rectangular T–U relationship whose shape (aspect ratio) is defined by two parameters: the interfacial strength σ* and the work of separation/unit area Γ. The principal finding of this study is that for a specified adhesive layer thickness, there is any number of σ*, Γ combinations that generate the same predicted joint strength. For each combination there is a corresponding CZ length. We developed an approximate CZ-like elasticity solution to show how such combinations arise and their connection with the CZ length.« less

  16. Current Activities Assessing Butt Fusion Joint Integrity in High Density Polyethylene Piping

    SciTech Connect (OSTI)

    Crawford, Susan L.; Cinson, Anthony D.; Doctor, Steven R.; Denslow, Kayte M.

    2012-09-01

    The Pacific Northwest National Laboratory (PNNL) in Richland, Washington, conducted initial studies to evaluate the effectiveness of nondestructive examinations (NDE) coupled with mechanical testing for assessing butt fusion joint integrity in high density polyethylene (HDPE) pipe. The work provided insightful information to the United States Nuclear Regulatory Commission (NRC) on the effectiveness of volumetric inspection techniques for detecting lack of fusion (LOF) conditions in the fusion joints. HDPE has been installed on a limited basis in American Society of Mechanical Engineers (ASME) Class 3, buried piping systems at several operating U.S. nuclear power plants and has been proposed for use in new construction. A comparison was made between the results from ultrasonic and microwave nondestructive examinations and the results from mechanical destructive evaluations, specifically the high-speed tensile test and the side-bend test, for determining joint integrity. The data comparison revealed that none of the NDE techniques detected all of the lack-of-fusion conditions that were revealed by the destructive tests. Follow-on work has recently been initiated at PNNL to accurately characterize the NDE responses from machined flaws of varying size and location in PE 4710 materials as well as the LOF condition. This effort is directed at quantifying the ability of volumetric NDE techniques to detect flaws in relation to the critical flaw size associated with joint integrity. A status of these latest investigations is presented.

  17. A Methodology for the Assessment of Unconventional (Continuous) Resources with an Application to the Greater Natural Buttes Gas Field, Utah

    SciTech Connect (OSTI)

    Olea, Ricardo A.; Cook, Troy A.; Coleman, James L.

    2010-12-15

    The Greater Natural Buttes tight natural gas field is an unconventional (continuous) accumulation in the Uinta Basin, Utah, that began production in the early 1950s from the Upper Cretaceous Mesaverde Group. Three years later, production was extended to the Eocene Wasatch Formation. With the exclusion of 1100 non-productive ('dry') wells, we estimate that the final recovery from the 2500 producing wells existing in 2007 will be about 1.7 trillion standard cubic feet (TSCF) (48.2 billion cubic meters (BCM)). The use of estimated ultimate recovery (EUR) per well is common in assessments of unconventional resources, and it is one of the main sources of information to forecast undiscovered resources. Each calculated recovery value has an associated drainage area that generally varies from well to well and that can be mathematically subdivided into elemental subareas of constant size and shape called cells. Recovery per 5-acre cells at Greater Natural Buttes shows spatial correlation; hence, statistical approaches that ignore this correlation when inferring EUR values for untested cells do not take full advantage of all the information contained in the data. More critically, resulting models do not match the style of spatial EUR fluctuations observed in nature. This study takes a new approach by applying spatial statistics to model geographical variation of cell EUR taking into account spatial correlation and the influence of fractures. We applied sequential indicator simulation to model non-productive cells, while spatial mapping of cell EUR was obtained by applying sequential Gaussian simulation to provide multiple versions of reality (realizations) having equal chances of being the correct model. For each realization, summation of EUR in cells not drained by the existing wells allowed preparation of a stochastic prediction of undiscovered resources, which range between 2.6 and 3.4 TSCF (73.6 and 96.3 BCM) with a mean of 2.9 TSCF (82.1 BCM) for Greater Natural Buttes. A second approach illustrates the application of multiple-point simulation to assess a hypothetical frontier area for which there is no production information but which is regarded as being similar to Greater Natural Buttes.

  18. Parametric source of two-photon states with a tunable degree of entanglement and mixing: Experimental preparation of Werner states and maximally entangled mixed states

    SciTech Connect (OSTI)

    Cinelli, C.; Di Nepi, G.; De Martini, F.; Barbieri, M.; Mataloni, P.

    2004-08-01

    A parametric source of polarization-entangled photon pairs with striking spatial characteristics is reported. The distribution of the output electromagnetic k modes excited by spontaneous parametric down-conversion and coupled to the output detectors can be very broad. Using these states realized over a full entanglement ring output distribution, the nonlocal properties of the generated entanglement have been tested by standard Bell measurements and by Ou-Mandel interferometry. A 'mode-patchwork' technique based on the quantum superposition principle is adopted to synthesize in a straightforward and reliable way any kind of mixed state, of large conceptual and technological interest in modern quantum information. Tunable Werner states and maximally entangled mixed states have indeed been created by this technique and investigated by quantum tomography. A study of the entropic and nonlocal properties of these states has been undertaken experimentally and theoretically, by a unifying variational approach.

  19. Implementation of ASME Code, Section XI, Code Case N-770, on Alternative Examination Requirements for Class 1 Butt Welds Fabricated with Alloy 82/182

    SciTech Connect (OSTI)

    Sullivan, Edmund J.; Anderson, Michael T.

    2012-09-17

    In May 2010, the NRC issued a proposed notice of rulemaking that includes a provision to add a new section to its rules to require licensees to implement ASME Code Case N-770, Alternative Examination Requirements and Acceptance Standards for Class 1 PWR Piping and Vessel Nozzle Butt Welds Fabricated with UNS N06082 or UNS W86182 Weld Filler Material With or Without the Application of Listed Mitigation Activities, Section XI, Division 1, with 15 conditions. Code Case N-770 contains baseline and inservice inspection (ISI) requirements for unmitigated butt welds fabricated with Alloy 82/182 material and preservice and ISI requirements for mitigated butt welds. The NRC stated that application of ASME Code Case N-770 is necessary because the inspections currently required by the ASME Code, Section XI, were not written to address stress corrosion cracking Alloy 82/182 butt welds, and the safety consequences of inadequate inspections can be significant. The NRC expects to issue the final rule incorporating this code case into its regulations in the spring 2011 time frame. This paper discusses the new examination requirements, the conditions that NRC is imposing , and the major concerns with implementation of the new Code Case.

  20. Gravity and magnetic anomalies associated with Tertiary volcanism and a Proterozoic crustal boundary, Hopi Buttes volcanic field, Navajo Nation (Arizona)

    SciTech Connect (OSTI)

    Donovan-Ealy, P.F. . Geology Dept.); Hendricks, J.D. )

    1992-01-01

    The Hopi Buttes volcanic field is located in the Navajo Nation of northeastern Arizona, near the southern margin of the Colorado Plateau. Explosive phreatomagmatic eruptions from late Miocene to mid-Pliocene time produced more than 300 maar-diatremes and deposited limburgite tuffs and tuff breccia and monchiquite dikes, necks and flows within a roughly circular 2,500 km[sup 2] area. The volcanic and volcaniclastic rocks make up the middle member of the Bidahochi Formation, whose lower and upper members are lacustrine and fluvial, respectively. The Bidahochi Formation overlies gently dipping Mesozoic sedimentary rocks exposed in the southwestern portion of the volcanic field. Two significant gravity and magnetic anomalies appear within the Hopi Buttes volcanic field that are unlike the signatures of other Tertiary volcanic fields on the Colorado Plateau. A circular 20 mGal negative gravity anomaly is centered over exposed sedimentary rocks in the southwestern portion of the field. The anomaly may be due to the large volume of low density pyroclastic rocks in the volcanic field and/or extensive brecciation of the underlying strata from the violent maar eruptions. The second significant anomaly is the northeast-trending Holbrook lineament, a 5 km-wide gravity and magnetic lineament that crosses the southeastern part of the volcanic field. The lineament reflects substantial gravity and magnetic decreases of 1.67 mGals/km and 100 gammas/km respectively, to the southeast. Preliminary two-dimensional gravity and magnetic modeling suggests the lineament represents a major Proterozoic crustal boundary and may correlate with one of several Proterozoic faults exposed in the transition zone of central Arizona. Gravity modeling shows a 3--5 km step'' in the Moho near the crustal boundary. The decrease in depth of the Moho to the northwest indicates either movement along the fault or magmatic upwelling beneath the volcanic field.

  1. Characterization of Mg/Al butt joints welded by gas tungsten arc filling with Zn29.5Al0.5Ti filler metal

    SciTech Connect (OSTI)

    Liu, Fei; Wang, Hongyang; Liu, Liming, E-mail: liulm@dlut.edu.cn

    2014-04-01

    The multivariate alloying design of a welding joint is used in the Mg to Al welding process. A Zn29.5Al0.5Ti alloy is added as filler metal in gas tungsten arc welding of Mg and Al alloy joint based on the analysis of Al and Mg alloy characteristics. The tensile strength, microstructure, and phase constitution of the weld seam are analyzed. The formation of brittle and hard MgAl intermetallic compounds is avoided because of the effects of Zn, Al, and Ti. The average tensile strength of the joint is 148 MPa. Al{sub 3}Ti is first precipitated and functions as the nucleus of heterogeneous nucleation during solidification. Moreover, the precipitated AlMgZn{sub 2} hypoeutectic phase exhibited a feather-like structure, which enhances the property of the MgAl dissimilar joint. - Highlights: Mg alloy AZ31B and Al alloy 6061 are butt welded by fusion welding. The effect of Ti in filler metal is investigated. The formation of MgAl intermetallic compounds is avoided.

  2. Multiphysics Object-Oriented Simulation Environment (MOOSE)

    ScienceCinema (OSTI)

    None

    2013-05-28

    Nuclear reactor operators can expand safety margins with more precise information about how materials behave inside operating reactors. INL's new simulation platform makes such studies easier & more informative by letting researchers "plug-n-play" their mathematical models, skipping years of computer code development.

  3. MOOSE simulating nuclear reactor CRUD buildup

    ScienceCinema (OSTI)

    None

    2014-07-21

    This simulation uses multiple physical models to show how the buildup of boron deposits on reactor fuel can affect performance and the reactor's power profile.

  4. MOOSE simulating nuclear reactor CRUD buildup

    SciTech Connect (OSTI)

    2014-02-06

    This simulation uses multiple physical models to show how the buildup of boron deposits on reactor fuel can affect performance and the reactor's power profile.

  5. Gordon Butte | Open Energy Information

    Open Energy Info (EERE)

    W 9,000,000,000 mW 0.009 GW Number of Units 6 Commercial Online Date 2012 Wind Turbine Manufacturer GE Energy References AWEA 2012 Market Report1 Loading map......

  6. The Hydrogeologic Character of the Lower Tuff Confining Unit and the Oak Springs Butte Confining Unit in the Tuff Pile Area of Central Yucca Flat

    SciTech Connect (OSTI)

    Drellack, Jr., Sigmund L.; Prothro, Lance B.; Gonzales, Jose L.; Mercadante, Jennifer M.

    2010-07-30

    The lower tuff confining unit (LTCU) in the Yucca Flat Corrective Action Unit (CAU) consists of a monotonous sequence of pervasively zeolitized volcanic tuff (i.e., mostly bedded with lesser nonwelded to poorly welded tuff; not fractured) (Bechtel Nevada, 2006). The LTCU is an important confining unit beneath Yucca Flat because it separates the alluvial and volcanic aquifers, where many underground nuclear tests were conducted, from the regional lower carbonate aquifer. Recent sub-CAU-scale modeling by Los Alamos National Laboratory in the Tuff Pile area of Yucca Flat (Boryta, et al., in review) includes postulated low-porosity, high-permeability zones (i.e., fractured welded-tuff aquifers) within the LTCU. This scenario indicates that such postulated low-porosity, high-permeability zones could provide fast-path lateral conduits to faults, and eventually to the lower carbonate aquifer. A fractured and faulted lower carbonate aquifer is postulated to provide a flow path(s) for underground test-derived contaminants to potential offsite receptors. The ramifications of such a scenario are obvious for groundwater flow and contaminant migration beneath Yucca Flat. This paper describes the reasoning for not including postulated low-porosity, high-permeability zones within the LTCU in the Tuff Pile area or within the LTCU in the Yucca Flat CAU-scale model. Both observational and analytical data clearly indicate that the LTCU in the Tuff Pile area consists of pervasively zeolitic, nonwelded to poorly welded tuffs that are classified as tuff confining units (i.e., high-porosity, low-permeability). The position regarding the LTCU in the Tuff Pile area is summarized as follows: The LTCU in the Tuff Pile area consists of a monotonous sequence of predominantly zeolitic nonwelded to poorly welded tuffs, and thus is accurately characterized hydrogeologically as a tuff confining unit (aquitard) in the Yucca Flat-Climax Mine hydrostratigraphic framework model (Bechtel Nevada, 2006). No welded-tuff (or lava-flow aquifers), referred to as low-porosity, high-permeability zones in Boryta et al. (in review), are present within the LTCU in the Tuff Pile area. Fractures within the LTCU are poorly developed, a characteristic of zeolitic tuffs; and fracture distributions are independent of stratigraphic and lithologic units (Prothro, 2008). Groundwater flow and radionuclide transport will not be affected by laterally extensive zones of significantly higher permeability within the LTCU in the Tuff Pile area. Although not the primary focus of this report, the hydrogeologic character of the Oak Spring Butte confining unit (OSBCU), located directly below the LTCU, is also discussed. The OSBCU is lithologically more diverse, and does include nonwelded to partially welded ash-flow tuffs. However, these older ash-flow tuffs are poorly welded and altered (zeolitic to quartzofeldspathic), and consequently, would tend to have properties similar to a tuff confining unit rather than a welded-tuff aquifer.

  7. Innovative Exploration Technologies Maui Hawaii & Glass Buttes...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    * Delays have also resulted from preparation of Cultural Inventory Assessment (CIA) for inclusion into EIS. Maui- Project 2011-2013 activity: Permitting Process 6 | US DOE ...

  8. Glass Buttes Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    Oregon Exploration Region: Cascades GEA Development Phase: Resource Estimate Mean Reservoir Temp: Estimated Reservoir Volume: Mean Capacity: USGS Mean Reservoir Temp: USGS...

  9. Glass Buttes Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    GEA Development Phase: Resource Estimate Mean Reservoir Temp: Estimated Reservoir Volume: Mean Capacity: USGS Mean Reservoir Temp: USGS Estimated Reservoir Volume: USGS Mean...

  10. Mitchell Butte Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    120C393.15 K 248 F 707.67 R 1 USGS Estimated Reservoir Volume: 2 km 1 USGS Mean Capacity: 10 MW 1 Click "Edit With Form" above to add content History and...

  11. EA-1996: Glass Buttes Radio Station, Lake County, Oregon

    Broader source: Energy.gov [DOE]

    The Bureau of Land Management (BLM), with DOE’s Bonneville Power Administration (BPA) as a cooperating agency, is preparing an EA that will evaluate the potential environmental impacts of a proposal to construct two telecommunications facilities, one of which would provide BPA telecommunications services, on BLM land. Additional information is available at http://www.blm.gov/or/districts/prineville/plans/glassbuttes/.

  12. Geology And A Working Conceptual Model Of The Obsidian Butte...

    Open Energy Info (EERE)

    with a wealth of subsurface information made available for the first time from the databases of present and prior field operators. The Unit 6 sector of the system is hosted by...

  13. Documentation of Hybrid Hydride Model for Incorporation into Moose-Bison and Validation Strategy.

    SciTech Connect (OSTI)

    Weck, Philippe F; Tikare, Veena; Schultz, Peter Andrew; Clark, B; Mitchell, J; Glazoff, Michael V.; Homer, Eric R.

    2014-10-01

    This report documents the development, demonstration and validation of a mesoscale, microstructural evolution model for simulation of zirconium hydride δ-ZrH{sub 1.5} precipitation in the cladding of used nuclear fuels that may occur during long-term dry storage. While the Zr-based claddings are manufactured free of any hydrogen, they absorb hydrogen during service, in the reactor by a process commonly termed ‘hydrogen pick-up’. The precipitation and growth of zirconium hydrides during dry storage is one of the most likely fuel rod integrity failure mechanisms either by embrittlement or delayed hydride cracking of the cladding (Hanson et al., 2011). While the phenomenon is well documented and identified as a potential key failure mechanism during long-term dry storage (Birk et al., 2012 and NUREG/CR-7116), the ability to actually predict the formation of hydrides is poor. The model being documented in this work is a computational capability for the prediction of hydride formation in different claddings of used nuclear fuels. This work supports the Used Fuel Disposition Research and Development Campaign in assessing the structural engineering performance of the cladding during and after long-term dry storage. In this work, a model to numerically simulate hydride precipitation at the microstructural scale, in a wide variety of Zr-based claddings, under dry-storage conditions is being developed. It will be used to aid in the evaluation of the mechanical integrity of used fuel rods during dry storage and transportation by providing the structural conditions from the microstructural scale to the continuum scale to engineering component scale models to predict if the used fuel rods will perform without failure under normal and off-normal conditions. The microstructure, especially, the hydride structure is thought to be a primary determinant of cladding failure, thus this component of UFD’s storage and transportation analysis program is critical. The model development, application and validation of the model are documented and the limitations of the current model are discussed. The model has been shown to simulate hydride precipitation in Zircaloy-4 cladding with correct morphology, thermodynamics and kinetics. An unexpected insight obtained from simulations hydride formation in Zircaloy-4 is that small (sub-micron) precipitates need to order themselves to form the larger hydrides typically described as radially-reoriented precipitates. A limitation of this model is that it does not currently solve the stress state that forms dynamically in the precipitate or matrix surrounding the precipitate. A method to overcome the limitations is suggested and described in detail. The necessary experiments to provide key materials physics and to validate the model are also recommended.

  14. Merging high resolution geophysical and geochemical surveys to reduce exploration risk at Glass Buttes, Oregon

    Broader source: Energy.gov [DOE]

    DOE Geothermal Technologies Peer Review - 2010. The primary objective of this project is to combine a suite of high resolution geophysical and geochemical techniques to reduce exploration risk by characterizing hydrothermal alteration, fault geometries and relationships.

  15. A Demonstration Project for Capturing Geothermal Energy from Mine Waters beneath Butte, MT

    Broader source: Energy.gov [DOE]

    Project objectives. Demonstrate performance of heat pumps in a large HVAC system in a heating-dominated climate.

  16. Documentation of Hybrid Hydride Model for Incorporation into...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    into Moose-Bison and Validation Strategy Documentation of Hybrid Hydride Model for Incorporation into Moose-Bison and Validation Strategy This report documents the ...

  17. Ward Co. Dunn Co. McLean Co. McHenry Co. Mountrail Co. McKenzie...

    U.S. Energy Information Administration (EIA) Indexed Site

    RATTLESNAKE POINT ELLSWORTH CHURCH BORDER HANSON GROVER HULSE COULEE SAKAKAWEA AURELIA ROUND TOP BUTTE GORHAM BUTTE W MARMON MANITOU SHEALEY CLAYTON SERGIS N SADDLE BUTTE HAYLAND ...

  18. Browse by Discipline -- E-print Network Subject Pathways: Power...

    Office of Scientific and Technical Information (OSTI)

    Werner (Werner Aeschbach-Hertig) - Institut fr Umweltphysik, Universitt Heidelberg Afton, Alan D. (Alan D. Afton) - Louisiana Cooperative Fish and Wildlife Research Unit. ...

  19. Browse by Discipline -- E-print Network Subject Pathways: Environmenta...

    Office of Scientific and Technical Information (OSTI)

    Werner (Werner Aeschbach-Hertig) - Institut fr Umweltphysik, Universitt Heidelberg Afton, Alan D. (Alan D. Afton) - Louisiana Cooperative Fish and Wildlife Research Unit. ...

  20. Volcanic episodes near Yucca Mountain as determined by paleomagnetic studies as Lathrop Wells, Crater Flat, and Sleeping Butte, Nevada

    SciTech Connect (OSTI)

    Champion, D.E.

    1991-12-31

    It has been suggested that mafic volcanism in the vicinity of Yucca Mountain, Nevada, is both recent (20 ka) and a product of complex {open_quotes}polycyclic{close_quotes} eruptions. This pattern of volcanism, as interpreted by some workers at the Lathrop Wells volcanic complex, comprises a sequence of numerous small-volume eruptions that become more tephra-producing over time. Such sequences are thought to occur over timespans as long as 100,000 years. However, paleomagnetic studies of the tephra and lava flows from mafic volcanoes near Yucca Mountain fail to find evidence of repeated eruptive activity over timespans of 10{sup 3} to 10{sup 5} years, even though samples have been taken that represent approximately 95% of the products of these volcanoes. Instead, the eruptions seem to have occurred as discrete episodes at each center and thus can be considered to be {open_quotes}monogenetic.{close_quotes} Dates of these episodes have been obtained by the proven radiometric-geochronometer methods of K-Ar or {sup 40}Ar/{sup 39}Ar dating.

  1. Microstructure evolution of Al/Mg butt joints welded by gas tungsten arc with Zn filler metal

    SciTech Connect (OSTI)

    Liu Fei; Zhang Zhaodong; Liu Liming, E-mail: liulm@dlut.edu.cn

    2012-07-15

    Based on the idea of alloying welding seam, Gas tungsten arc welding method with pure Zn filler metal was chosen to join Mg alloy and Al alloy. The microstructures, phases, element distribution and fracture morphology of welding seams were examined. The results indicate that there was a transitional zone in the width of 80-100 {mu}m between the Mg alloy substrate and fusion zone. The fusion zone was mainly composed of MgZn{sub 2}, Zn-based solid solution and Al-based solid solution. The welding seam presented distinct morphology in different location owning to the quite high cooling rate of the molten pool. The addition of Zn metal could prevent the formation of Mg-Al intermetallics and form the alloyed welding seam during welding. Therefore, the tensile strengths of joints have been significantly improved compared with those of gas tungsten arc welded joints without Zn metal added. Highlights: Black-Right-Pointing-Pointer Mg alloy AZ31B and Al alloy 6061 are welded successfully. Black-Right-Pointing-Pointer Zinc wire is employed as a filler metal to form the alloyed welding seam. Black-Right-Pointing-Pointer An alloyed welding seam is benefit for improving of the joint tensile strength.

  2. Lagoon Seepage Testing Procedures for Central Facilities Area (CFA) Sewage Lagoons at Idaho National Laboratory Butte County, Idaho April 2014

    SciTech Connect (OSTI)

    Alan Giesbrecht

    2014-05-01

    The lagoon seepage testing procedures are documented herein as required by the Wastewater Rules (IDAPA 58.01.16.493). The Wastewater Rules and Wastewater Reuse Permit LA-000141-03 require that the procedure used for performing a seepage test be approved by IDEQ prior to conducting the seepage test. The procedures described herein are based on a seepage testing plan that was developed by J-U-B ENGINEERS, Inc. (J-U-B) and has been accepted by several IDEQ offices for lagoons in Idaho.

  3. Lagoon Seepage Testing Report for Central Facilities Area (CFA) Sewage Lagoons at Idaho National Laboratory, Butte County, Idaho

    SciTech Connect (OSTI)

    Bridger Morrison

    2014-09-01

    J-U-B ENGINEERS, Inc. (J-U-B) performed seepage tests on the CFA Wastewater Lagoons 1, 2, and 3 between August 26th and September 22nd, 2014. The lagoons were tested to satisfy the Idaho Department of Environmental Quality (DEQ) Rules (IDAPA 58.01.16) that require all lagoons be tested at a frequency of every 10 years and the Compliance Activity CA-141-03 in the DEQ Wastewater Reuse Permit for the CFA Sewage Treatment Plant (LA-000141-03). The lagoons were tested to determine if the average seepage rates are less than 0.25 in/day, the maximum seepage rate allowed for lagoons built prior to April 15, 2007. The average seepage rates were estimated for each lagoon and are given in Table-ES1. The average seepage rates for Lagoons 1 and 2 are less than the allowable seepage rate of 0.25 in/day. Lagoon 1 and 2 passed the seepage test and will not have to be tested again until the year 20241. However, the average seepage rate for Lagoon 3 appears to exceed the allowable seepage rate of 0.25 in/day which means the potential source for the excessive leakage should be investigated further.

  4. Environmental Survey preliminary report, Idaho National Engineering Laboratory, Idaho Falls, Idaho and Component Development and Integration Facility, Butte, Montana

    SciTech Connect (OSTI)

    Not Available

    1988-09-01

    This report presents the preliminary findings of the first phase of the Environmental Survey of the United States Department of Energy's (DOE) Idaho National Engineering Laboratory (INEL) and Component Development and Integration Facility (CDIF), conducted September 14 through October 2, 1987. The Survey is being conducted by an interdisciplinary team of environmental specialists, led and managed by the Office of Environment, Safety and Health's Office of Environmental Audit. The team includes outside experts supplied by a private contractor. The objective of the Survey is to identify environmental problems and areas of environmental risk associated with the INEL and CDIF. The Survey covers all environmental media and all areas of environmental regulation. It is being performed in accordance with the DOE Environmental Survey Manual. The on-site phase of the Survey involves the review of existing site environmental data, observations of the operations' carried on at the INEL and the CDIF, and interviews with site personnel. The Survey team developed a Sampling and Analysis (S A) Plan to assist in further assessing certain of the environmental problems identified during its on-site activities. The S A Plan will be executed by the Oak Ridge National Laboratory. When completed, the S A results will be incorporated into the INEL/CDIF Survey findings for inclusion into the Environmental Survey Summary Report. 90 refs., 95 figs., 77 tabs.

  5. Carlton County, Minnesota: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    River, Minnesota Moose Lake, Minnesota North Carlton, Minnesota Scanlon, Minnesota Thomson, Minnesota Wrenshall, Minnesota Wright, Minnesota Retrieved from "http:...

  6. Customized atomic force microscopy probe by focused-ion-beam...

    Office of Scientific and Technical Information (OSTI)

    Authors: Wang, Andrew ; Butte, Manish J., E-mail: manish.butte@stanford.edu 1 + Show Author Affiliations Department of Pediatrics, Division of Immunology, Allergy and ...

  7. MyRecipe | Open Energy Information

    Open Energy Info (EERE)

    here) Ingredient Alternative Mustard Pork Butt Sugar warmed to room temp Molasses or honey. none Instructions Prepare rub. Coat butt. Refrigerate overnite. BBQ indirect heat,...

  8. Carter Co. Harding Co. Perkins Co. Dunn Co. Dawson Co. Fallon...

    U.S. Energy Information Administration (EIA) Indexed Site

    BICENTENNIAL MEDICINE POLE HILLS BIG STICK ROOSEVELT ROUGH RIDER MONARCH TREE TOP LOOKOUT BUTTE BUCKHORN MEDORA FLAT TOP BUTTE ELAND DEMORES ASH COULEE WHISKEY JOE GAS CITY DAVIS ...

  9. Carter Co. Harding Co. Perkins Co. Dunn Co. Dawson Co. Fallon...

    U.S. Energy Information Administration (EIA) Indexed Site

    MEDICINE POLE HILLS BICENTENNIAL ROOSEVELT BIG STICK ROUGH RIDER MONARCH TREE TOP LOOKOUT BUTTE BUCKHORN MEDORA FLAT TOP BUTTE ELAND DEMORES ASH COULEE WHISKEY JOE GAS CITY DAVIS ...

  10. Search for: All records | DOE PAGES

    Office of Scientific and Technical Information (OSTI)

    Cooper, Valentino R. (1) Du, Shixuan (1) Hofer, Werner A. (1) Jiang, Yuhang (1) Li, Guo ... ; Du, Shixuan ; Ouyang, Min ; Hofer, Werner A. ; Castro Neto, Antonio H. ; et al Full ...

  11. Assessment of Weld Overlays for Mitigating Primary Water Stress Corrosion Cracking at Nickel Alloy Butt Welds in Piping Systems Approved for Leak-Before-Break

    SciTech Connect (OSTI)

    Sullivan, Edward J.; Anderson, Michael T.

    2012-08-01

    This TLR provides an assessment of weld overlays as a mitigation strategy for PWSCC, and includes an assessment of the WOL-related inspection requirements of Code Case N-770-1, as conditioned in §50.55a.

  12. Assessment of the Mechanical Stress Improvement Process for Mitigating Primary Water Stress Corrosion Cracking in Nickel Alloy Butt Welds in Piping Systems Approved for Leak-Before-Break

    SciTech Connect (OSTI)

    Sullivan, Edmund J.; Anderson, Michael T.

    2013-01-01

    This report provides an assessment of the use of Mechanical Stress Improvement Process to reduce, or decrease, stress-driven degradation, i.e., primary water stress corrosion cracking.

  13. Idaho National Engineering and Environmental Laboratory, Old Waste Calcining Facility, Scoville vicinity, Butte County, Idaho -- Photographs, written historical and descriptive data. Historical American engineering record

    SciTech Connect (OSTI)

    1997-12-31

    This report describes the history of the Old Waste Calcining Facility. It begins with introductory material on the Idaho National Engineering and Environmental Laboratory, the Materials Testing Reactor fuel cycle, and the Idaho Chemical Processing Plant. The report then describes management of the wastes from the processing plant in the following chapters: Converting liquid to solid wastes; Fluidized bed waste calcining process and the Waste Calcining Facility; Waste calcining campaigns; WCF gets a new source of heat; New Waste Calcining Facility; Last campaign; Deactivation and the RCRA cap; Significance/context of the old WCF. Appendices contain a photo key map for HAER photos, a vicinity map and neighborhood of the WCF, detailed description of the calcining process, and chronology of WCF campaigns.

  14. Probing the Repulsive Core of the Nucleon-Nucleon Interaction...

    Office of Scientific and Technical Information (OSTI)

    ; Benmokhtar, Fatiha ; Bertozzi, William ; Bittner, James ; Boeglin, Werner ; ... ; de Jager, C. W. ; De, Raffaele ; Leo, R. De ; Deconinck, Wouter ; Defurne, ...

  15. Multiphysics Object Oriented Simulation Environment

    Energy Science and Technology Software Center (OSTI)

    2014-02-12

    The Multiphysics Object Oriented Simulation Environment (MOOSE) software library developed at Idaho National Laboratory is a tool. MOOSE, like other tools, doesn’t actually complete a task. Instead, MOOSE seeks to reduce the effort required to create engineering simulation applications. MOOSE itself is a software library: a blank canvas upon which you write equations and then MOOSE can help you solve them. MOOSE is comparable to a spreadsheet application. A spreadsheet, by itself, doesn’t do anything.more » Only once equations are entered into it will a spreadsheet application compute anything. Such is the same for MOOSE. An engineer or scientist can utilize the equation solvers within MOOSE to solve equations related to their area of study. For instance, a geomechanical scientist can input equations related to water flow in underground reservoirs and MOOSE can solve those equations to give the scientist an idea of how water could move over time. An engineer might input equations related to the forces in steel beams in order to understand the load bearing capacity of a bridge. Because MOOSE is a blank canvas it can be useful in many scientific and engineering pursuits.« less

  16. Multiphysics Object Oriented Simulation Environment

    SciTech Connect (OSTI)

    2014-02-12

    The Multiphysics Object Oriented Simulation Environment (MOOSE) software library developed at Idaho National Laboratory is a tool. MOOSE, like other tools, doesn’t actually complete a task. Instead, MOOSE seeks to reduce the effort required to create engineering simulation applications. MOOSE itself is a software library: a blank canvas upon which you write equations and then MOOSE can help you solve them. MOOSE is comparable to a spreadsheet application. A spreadsheet, by itself, doesn’t do anything. Only once equations are entered into it will a spreadsheet application compute anything. Such is the same for MOOSE. An engineer or scientist can utilize the equation solvers within MOOSE to solve equations related to their area of study. For instance, a geomechanical scientist can input equations related to water flow in underground reservoirs and MOOSE can solve those equations to give the scientist an idea of how water could move over time. An engineer might input equations related to the forces in steel beams in order to understand the load bearing capacity of a bridge. Because MOOSE is a blank canvas it can be useful in many scientific and engineering pursuits.

  17. Property:NEPA EA EIS Report Url | Open Energy Information

    Open Energy Info (EERE)

    + http:www.blm.govnmstenprogmorelandsrealtysanjuanbasinenergy.html + Sigurd Red Butte No2 + http:www.blm.govutstenfocedarcityplanningsigurdtoredbutte...

  18. CASL-U-2015-0073-000

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    ... analysis) Trilinos DAKOTA MOOSE PETSc Solvers Coupling SA UQ libMesh DTK STK MOAB Geometry Mesh Solution Transfer ANC Interoperability with External Components ...

  19. Microsoft Word - IceMountainFinal.docx

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Photo courtesy of Moose Larson What the term "algific talus slope" also leaves undescribed are their unusual, seemingly misplaced ecosystems, which survive by a trick of nature. ...

  20. Teton County, Wyoming: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    TriLateral Energy LLC Places in Teton County, Wyoming Alta, Wyoming Hoback, Wyoming Jackson, Wyoming Moose Wilson Road, Wyoming Rafter J Ranch, Wyoming South Park, Wyoming Teton...

  1. RELAP-7 Development | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    and a software quality assurance plan and developed component models for pipe flows, pipe junctions, and basic reactor core channels using the Moose code development framework. ...

  2. Search for: All records | SciTech Connect

    Office of Scientific and Technical Information (OSTI)

    ... Filter by Author Higinbotham, Douglas (9) Piasetzky, Eliazer (9) Boeglin, Werner (6) ... The EMC Effect and High Momentum Nucleons in Nuclei Hen, Or ; Higinbotham, Douglas ; ...

  3. Collection and Analysis of Geothermal and Volcanic Water and...

    Open Energy Info (EERE)

    of Geothermal and Volcanic Water and Gas Discharges Authors Werner F. Giggenbach and R.L. Goguel Published Department of Scientific and Industrial Research, Chemistry Division,...

  4. Search for: All records | SciTech Connect

    Office of Scientific and Technical Information (OSTI)

    ... Konrad ; Averett, Todd ; Boeglin, Werner ; Camsonne, Alexandre ; Cates, Gordon ; Chang, C. ; et al We present experimental results of the first high-precision test of ...

  5. --No Title--

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    C. Valencia, Barry Lai, Guofeng Zhang, Jill K. Paterson, Francois Rouzaud, Werner Berens, Stephen M. Wincovitch, Susan H. Garfield, Richard D. Leapman, Vincent J. Hearing, Michael...

  6. Search for: All records | SciTech Connect

    Office of Scientific and Technical Information (OSTI)

    ... Filter by Author Boeglin, Werner (16) Markowitz, Pete (15) Jones, Mark (12) Aniol, Konrad ... Separated Response Function Ratios in Exclusive, Forward pisup +- Electroproduction ...

  7. Probing the high momentum component of the deuteron at high Q...

    Office of Scientific and Technical Information (OSTI)

    Authors: Boeglin, Werner ; Ambrozewicz, Pawel ; Aniol, Konrad ; Arrington, John ; Batigne, Guillaume ; Bosted, Peter ; Camsonne, Alexandre ; Chang, C ; Chen, Jian-Ping ; Choi, ...

  8. Quark-Hadron Duality in Neutron (3He) Spin Structure (Journal...

    Office of Scientific and Technical Information (OSTI)

    Solvignon, Patricia ; Liyanage, Nilanga ; Chen, Jian-Ping ; Choi, Seonho ; Aniol, Konrad ; Averett, Todd ; Boeglin, Werner ; Camsonne, Alexandre ; Cates, Gordon ; Chang, C. ; Chang...

  9. Virtual Compton scattering and neutral pion electroproduction...

    Office of Scientific and Technical Information (OSTI)

    Berthot, J. ; Bertin, Pierre ; Bertozzi, William ; Bimbot, Louis ; Boeglin, Werner more ... ; Dale, Daniel ; De Jager, Cornelis ; De Leo, Raffaele ; Deur, Alexandre ; D'Hose, ...

  10. DOE-HDBK-1169-2003; DOE Handbook Nuclear Air Cleaning Handbook

    Office of Environmental Management (EM)

    ... Life, Werner Berman, Hazards Control Department, UCRL-AR-134141, June 1999. Nuclear Air Cleaning Handbook U.S. Department of Energy C-2 respectively, will ensure that ...

  11. Ward Co. Dunn Co. McLean Co. McHenry Co. Mountrail Co. McKenzie Co.

    U.S. Energy Information Administration (EIA) Indexed Site

    WHISKEY JOE WHITE ASH SPRING COULEE DES LACS MAGPIE HARTLAND BEICEGEL CREEK RANCH COULEE WINNER CRAZY MAN CREEK GROS VENTRE BANK W BULLSNAKE UPLAND COULEE REFUGE LARSON GARNET ALKALI CREEK PLUMER RATTLESNAKE POINT ELLSWORTH CHURCH BORDER HANSON GROVER HULSE COULEE SAKAKAWEA AURELIA ROUND TOP BUTTE GORHAM BUTTE W MARMON MANITOU SHEALEY CLAYTON SERGIS N SADDLE BUTTE HAYLAND CEDAR COULEE BOWLINE LITTLE BUTTE LONG CREEK RHOADES HEDBERG FILLMORE EIDSVOLD FAIRFIELD WOLF BAY TOBACCO GARDEN N SPRING

  12. ch_4

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    18 Affected Environment visual range of the Fort Hall Indian Reservation. The Bitterroot, Lemhi, and Lost River mountain ranges are visible to the north and west of INEEL. East Butte and Middle Butte can be seen near the southern boundary, while Circular and Antelope Buttes are visible to the northeast. Smaller volcanic buttes dot the natural landscape of INEEL, providing a striking contrast to the relatively flat ground surface. The viewscape in general consists of terrain dominated by sage-

  13. Carter Co. Harding Co. Perkins Co. Dunn Co. Dawson Co. Fallon Co.

    U.S. Energy Information Administration (EIA) Indexed Site

    PENNEL BUFFALO LITTLE KNIFE FRYBURG MONDAK PLEVNA LOOKOUT BUTTE E ELKHORN RANCH DICKINSON CADY CREEK MEDICINE POLE HILLS BICENTENNIAL ROOSEVELT BIG STICK ROUGH RIDER MONARCH TREE TOP LOOKOUT BUTTE BUCKHORN MEDORA FLAT TOP BUTTE ELAND DEMORES ASH COULEE WHISKEY JOE GAS CITY DAVIS CREEK WINDY RIDGE POKER JIM PLEVNA S KNUTSON STATE LINE BELL BEAR CREEK ELKHORN RANCH N PIERRE CREEK LONE BUTTE ZENITH MANNING SQUAW GAP AMOR STADIUM HEART S HILINE ASH MARY GAYLORD BULL CREEK HALEY SHORT PINE HILLS W

  14. Carter Co. Harding Co. Perkins Co. Dunn Co. Dawson Co. Fallon Co.

    U.S. Energy Information Administration (EIA) Indexed Site

    BUFFALO PENNEL LITTLE KNIFE FRYBURG MONDAK PLEVNA LOOKOUT BUTTE E ELKHORN RANCH DICKINSON CADY CREEK BICENTENNIAL MEDICINE POLE HILLS BIG STICK ROOSEVELT ROUGH RIDER MONARCH TREE TOP LOOKOUT BUTTE BUCKHORN MEDORA FLAT TOP BUTTE ELAND DEMORES ASH COULEE WHISKEY JOE GAS CITY DAVIS CREEK WINDY RIDGE POKER JIM PLEVNA S KNUTSON BELL STATE LINE BEAR CREEK ELKHORN RANCH N PIERRE CREEK LONE BUTTE ZENITH MANNING SQUAW GAP AMOR HEART S STADIUM HILINE ASH MARY LAKE ILO GAYLORD BULL CREEK HALEY BULLY SHORT

  15. Carter Co. Harding Co. Perkins Co. Dunn Co. Dawson Co. Fallon Co.

    U.S. Energy Information Administration (EIA) Indexed Site

    PENNEL BUFFALO LITTLE KNIFE FRYBURG MONDAK PLEVNA LOOKOUT BUTTE E ELKHORN RANCH DICKINSON CADY CREEK MEDICINE POLE HILLS BICENTENNIAL ROOSEVELT BIG STICK ROUGH RIDER MONARCH TREE TOP LOOKOUT BUTTE BUCKHORN MEDORA FLAT TOP BUTTE ELAND DEMORES ASH COULEE WHISKEY JOE GAS CITY DAVIS CREEK WINDY RIDGE POKER JIM PLEVNA S KNUTSON STATE LINE BELL BEAR CREEK ELKHORN RANCH N PIERRE CREEK LONE BUTTE ZENITH MANNING SQUAW GAP AMOR STADIUM HEART S HILINE ASH MARY GAYLORD BULL CREEK HALEY SHORT PINE HILLS W

  16. Tackling the Triple-Threat Genome of Miscanthus x giganteus (2010 JGI User Meeting)

    ScienceCinema (OSTI)

    Moose, Steve

    2011-04-25

    Steve Moose from the University of Illinois at Urbana-Champaign and the Energy Biosciences Institute on "Tackling the Triple-Threat Genome of Miscanthus x giganteus" on March 25, 2010 at the 5th Annual DOE JGI User Meeting

  17. Microsoft Word - AMF2_BAECC_Safety_Appendix_For_Web.doc

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    and thinly spread out. However, moose and reindeer are possible encounters at our work area. When you plan to go outside of a facility it will be paramount you check the immediate...

  18. CASL-U-2015-0233-000 CASL Program Highlights

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    3-000 CASL Program Highlights January 2015 Douglas Kothe Oak Ridge National Laboratory January 31, 2015 CASL-U-2015-0233-000 Computational Science Efforts Advance Fuel Performance Simulation MOOSE/Bison-CASL capability more adept at simulating the important fuel pellet-cladding contact phenomena * A new mechanical contact system in MOOSE has resulted in significantly better solution convergence for Bison-CASL * Size of models that can be run with this system had previously been limited due to

  19. CX-012790: Categorical Exclusion Determination

    Office of Energy Efficiency and Renewable Energy (EERE)

    Haystack Butte Radio Site Land Acquisition CX(s) Applied: B1.24Date: 41939 Location(s): WashingtonOffices(s): Bonneville Power Administration

  20. CX-008884: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Rattlesnake Butte Property Funding CX(s) Applied: B1.25 Date: 08/13/2012 Location(s): Oregon Offices(s): Bonneville Power Administration

  1. Domestic Uranium Production Report - Quarterly - Energy Information...

    Gasoline and Diesel Fuel Update (EIA)

    Crow Butte Operation (Nebraska) Lost Creek Project (Wyoming) Nichols Ranch ISR Project (Wyoming) Smith Ranch-Highland Operation (Wyoming) Strata Energy's Ross central processing ...

  2. Assiniboine and Sioux Tribes of the Fort Peck Indian Reservation

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Oklahoma * Certified in Socket & Butt Fusion IGSHPA Training Installer Team IGSHPA ... Enterprise GSHP Dirt Work GSHP Pipe Fusion * Takes place in the crawl space or ...

  3. Boyd County, Nebraska: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    Boyd County, Nebraska Anoka, Nebraska Bristow, Nebraska Butte, Nebraska Gross, Nebraska Lynch, Nebraska Monowi, Nebraska Naper, Nebraska Spencer, Nebraska Retrieved from "http:...

  4. MHK Projects/Whiskey Bay | Open Energy Information

    Open Energy Info (EERE)

    ","visitedicon":"" Project Profile Project Start Date 112009 Project City Butte la Rose, LA Project StateProvince Louisiana Project Country United States Project Resource...

  5. MHK Projects/Tensas | Open Energy Information

    Open Energy Info (EERE)

    ","visitedicon":"" Project Profile Project Start Date 112009 Project City Butte la Rose, LA Project StateProvince Louisiana Project Country United States Project Resource...

  6. Directory

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    BOISE STATE UNIVERSITY Darryl Butt Distinguished Professor and Associate Director for CAES Materials... (Properties) 52414 11:16 AM 52414 11:16 AM Send Document Link BOISE...

  7. CAES Home

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Calendar Microscopy and Characterization Suite (MaCS) MaCS Contacts Dr. Darryl Butt CAES Co-Associate Director Chair, Department of Materials Science and Engineering, Boise...

  8. Property:Geothermal/FundingSource | Open Energy Information

    Open Energy Info (EERE)

    + American Recovery and Reinvestment Act of 2009 + A Demonstration System for Capturing Geothermal Energy from Mine Waters beneath Butte, MT Geothermal Project + American...

  9. Property:Geothermal/FundingOpportunityAnnouncemt | Open Energy...

    Open Energy Info (EERE)

    Co., NV Geothermal Project + DE-FOA-0000109 + A Demonstration System for Capturing Geothermal Energy from Mine Waters beneath Butte, MT Geothermal Project + DE-FOA-0000116 +...

  10. Property:Geothermal/TargetsMilestones | Open Energy Information

    Open Energy Info (EERE)

    reservoir models and define drilling targets. A Demonstration System for Capturing Geothermal Energy from Mine Waters beneath Butte, MT Geothermal Project + Mine waters will...

  11. Property:Geothermal/Impacts | Open Energy Information

    Open Energy Info (EERE)

    fluid pathways in fracture-dominated systems. A Demonstration System for Capturing Geothermal Energy from Mine Waters beneath Butte, MT Geothermal Project + Successful...

  12. Property:Geothermal/AwardeeWebsite | Open Energy Information

    Open Energy Info (EERE)

    + http:www.magmaenergycorp.comsHome.asp + A Demonstration System for Capturing Geothermal Energy from Mine Waters beneath Butte, MT Geothermal Project + http:...

  13. CX-009210: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Silver Butte Fiber Burial Project CX(s) Applied: B.47 Date: 08/28/2012 Location(s): Montana, Montana Offices(s): Bonneville Power Administration

  14. Search for: All records | DOE PAGES

    Office of Scientific and Technical Information (OSTI)

    ; Schuler, Daniel ; Butt, Ryan H. ; Dibble, Robert W. Full Text Available March 2016, Elsevier Experimental and numerical investigation of ion signals in boosted HCCI combustion...

  15. Geothermal Technologies Program Annual Peer Review Presentation...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Glass Buttes, OR (DOE) Geothermal Technologies Program Annual Peer Review May 7, 2012 Doug Hollett, Program Manager Geothermal Technologies Program Office of Energy Efficiency and ...

  16. Natrona County, Wyoming: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    Wyoming Meadow Acres, Wyoming Midwest, Wyoming Mills, Wyoming Powder River, Wyoming Red Butte, Wyoming Vista West, Wyoming Retrieved from "http:en.openei.orgw...

  17. CX-012813: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Redmond-Pilot Butte #1 Wood Pole Replacements CX(s) Applied: B1.3Date: 41893 Location(s): OregonOffices(s): Bonneville Power Administration

  18. Jackson County, Oregon: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    Oregon Ashland, Oregon Butte Falls, Oregon Central Point, Oregon Eagle Point, Oregon Gold Hill, Oregon Jacksonville, Oregon Medford, Oregon Phoenix, Oregon Rogue River, Oregon...

  19. ALSNews Vol. 290

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    XRM 2008 a Rousing Success CXRO Scientist and ALS User Anne Sakdinawat Wins 2008 Werner Meyer-Ilse Award UEC Corner: 2008 Users' Meeting; the UEC Needs New Members Compass Students...

  20. Search for: All records | SciTech Connect

    Office of Scientific and Technical Information (OSTI)

    ... Then Fano was fortunate to receive postdoctoral training from two giants in modern physics: Enricomore Fermi at Rome in 1934-1936 and Werner Heisenberg at Leipzig in 1936-1937. ...

  1. Plasma Dynamo Experiments Cary Forest PPPL Colloquium

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Magnetic energy from Kinetic energy Wednesday, June 5, 13 The self-excited generator of Werner von Siemens (1866) The "dynamo electric principle" Wednesday, June 5, 13 MHD in the ...

  2. Triangle Universities Nuclear Laboratory : 2011

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Hill KamLAND: Hugon Karwowski and Ryan Rohm, UNC at Chapel Hill; Christopher Gould and Albert Young, NC State University; Diane Markoff, NC Central University; and Werner Tornow,...

  3. Working Toward a Tech Sector that Reflects America | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Working Toward a Tech Sector that Reflects America Working Toward a Tech Sector that Reflects America February 1, 2013 - 1:51pm Addthis Tech-ies mingled during a networking session after the White House Tech Inclusion Summit on January 31, 2013. (Photo credit: John Werner) Tech-ies mingled during a networking session after the White House Tech Inclusion Summit on January 31, 2013. (Photo credit: John Werner) Valerie Jarrett Senior Advisor to President Barack Obama Editor's Note: This blog was

  4. An Update on Improvements to NiCE Support for RELAP-7

    SciTech Connect (OSTI)

    McCaskey, Alex; Wojtowicz, Anna; Deyton, Jordan H.; Patterson, Taylor C.; Billings, Jay Jay

    2015-01-01

    The Multiphysics Object-Oriented Simulation Environment (MOOSE) is a framework that facilitates the development of applications that rely on finite-element analysis to solve a coupled, nonlinear system of partial differential equations. RELAP-7 represents an update to the venerable RELAP-5 simulator that is built upon this framework and attempts to model the balance-of-plant concerns in a full nuclear plant. This report details the continued support and integration of RELAP-7 and the NEAMS Integrated Computational Environment (NiCE). RELAP-7 is fully supported by the NiCE due to on-going work to tightly integrate NiCE with the MOOSE framework, and subsequently the applications built upon it. NiCE development throughout the first quarter of FY15 has focused on improvements, bug fixes, and feature additions to existing MOOSE-based application support. Specifically, this report will focus on improvements to the NiCE MOOSE Model Builder, the MOOSE application job launcher, and the 3D Nuclear Plant Viewer. This report also includes a comprehensive tutorial that guides RELAP-7 users through the basic NiCE workflow: from input generation and 3D Plant modeling, to massively parallel job launch and post-simulation data visualization.

  5. Off-diagonal Jacobian support for Nodal BCs

    SciTech Connect (OSTI)

    Peterson, John W.; Andrs, David; Gaston, Derek R.; Permann, Cody J.; Slaughter, Andrew E.

    2015-01-01

    In this brief note, we describe the implementation of o-diagonal Jacobian computations for nodal boundary conditions in the Multiphysics Object Oriented Simulation Environment (MOOSE) [1] framework. There are presently a number of applications [2{5] based on the MOOSE framework that solve complicated physical systems of partial dierential equations whose boundary conditions are often highly nonlinear. Accurately computing the on- and o-diagonal Jacobian and preconditioner entries associated to these constraints is crucial for enabling ecient numerical solvers in these applications. Two key ingredients are required for properly specifying the Jacobian contributions of nonlinear nodal boundary conditions in MOOSE and nite element codes in general: 1. The ability to zero out entire Jacobian matrix rows after \

  6. SHARP/PRONGHORN Interoperability: Mesh Generation

    SciTech Connect (OSTI)

    Avery Bingham; Javier Ortensi

    2012-09-01

    Progress toward collaboration between the SHARP and MOOSE computational frameworks has been demonstrated through sharing of mesh generation and ensuring mesh compatibility of both tools with MeshKit. MeshKit was used to build a three-dimensional, full-core very high temperature reactor (VHTR) reactor geometry with 120-degree symmetry, which was used to solve a neutron diffusion critical eigenvalue problem in PRONGHORN. PRONGHORN is an application of MOOSE that is capable of solving coupled neutron diffusion, heat conduction, and homogenized flow problems. The results were compared to a solution found on a 120-degree, reflected, three-dimensional VHTR mesh geometry generated by PRONGHORN. The ability to exchange compatible mesh geometries between the two codes is instrumental for future collaboration and interoperability. The results were found to be in good agreement between the two meshes, thus demonstrating the compatibility of the SHARP and MOOSE frameworks. This outcome makes future collaboration possible.

  7. The Multiphysics Object Oriented Simulation Environment

    Energy Science and Technology Software Center (OSTI)

    2010-05-01

    MOOSE is a software framework for the development of complex multidimensional engineering analysis applications using the finite element method. It provides a clean, extensible interface for scientists to develop analysis applications by accepting weak forms (i.e., virtual work expressions) of the mathematical models that govern the behavior of the physical system being modeled. MOOSE provides spatial and temporal discretization support for these expressions and allows them to be coupled in general ways and with generalmore » boundary and initial conditions and constraints. MOOSE also provides a solution environment that allows the parallel solution of the described problem on computer systems ranging from one processor to massively parallel systems.« less

  8. CASL-8-2015-0021-000 Contact Memory Report CASL.FY14 Rich Williamson

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    1-000 Contact Memory Report CASL.FY14 Rich Williamson Idaho National Laboratory January 31, 2015 CASL-U-2015-0021-000 Contact Memory Reduction CASL FY15 Letter Report January 30, 2015 Introduction As documented in a prior CASL milestone report [1], work has been underway to transition to a new system of contact enforcement in MOOSE, and by extension, the fuel performance codes BISON and BISON-CASL, which are based on MOOSE. This new system, known as the Constraint system, achieves significantly

  9. Microsoft Word - FOI 2013-01308.Final.doc

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    July 31, 2013 CERTIFIED MAIL Mr. Dan O'Keefe O'Keefe Drilling Company P.O. Box 3810 Butte, Montana 59702 Dear Mr. O'Keefe: FREEDOM OF INFORMATION ACT REQUEST (FOI 2013-01308) This ...

  10. National Center for Appropriate Technology | Open Energy Information

    Open Energy Info (EERE)

    Appropriate Technology Jump to: navigation, search Name: NCAT Energy Services Address: P.O. BOX 3838 Place: Butte, MT Zip: 59702 Phone Number: 800.ASK.NCAT Website: www.ncat.org...

  11. CX-003588: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Synthesis of Renewable Biofuels from BiomassCX(s) Applied: B3.6Date: 08/24/2010Location(s): Butte, MontanaOffice(s): Energy Efficiency and Renewable Energy, Golden Field Office

  12. CX-011685: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Lightspeed Network's Fiber Installation near Pilot Butte Substation CX(s) Applied: B4.7 Date: 01/15/2014 Location(s): Oregon Offices(s): Bonneville Power Administration

  13. Projects at the Western Environmental Technology Office. Quarterly technical progress report, April 1--June 30, 1995

    SciTech Connect (OSTI)

    1995-08-01

    This report contains brief outlines of the multiple projects under the responsibility of the Western Environmental Technology Office in Butte Montana. These projects include biomass remediation, remediation of contaminated soils, mine waste technology, and several other types of remediation.

  14. EA-1925: Draft Environmental Assessment | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    EA-1925: Draft Environmental Assessment Midnight Point and Mahogany Geothermal Exploration Projects, Glass Buttes, Oregon (DOI-BLM-OR-P040-2011-0021-EA; DOEEA-1925) Ormat Nevada, ...

  15. CX-012804: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Pilot Butte-La Pine #1 Wood Pole Replacements CX(s) Applied: B1.3Date: 41912 Location(s): OregonOffices(s): Bonneville Power Administration

  16. CX-013622: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Wireless- T-Mobile Mt. Zion/Biddle Butte Wireless Communication Upgrades CX(s) Applied: B4.7Date: 05/06/2015 Location(s): WashingtonOffices(s): Bonneville Power Administration

  17. CX-005579: Categorical Exclusion Determination

    Office of Energy Efficiency and Renewable Energy (EERE)

    Albion Butte Radio Station Communication UpgradeCX(s) Applied: B1.7Date: 04/04/2011Location(s): Nibbs Creek, IdahoOffice(s): Bonneville Power Administration

  18. Property:Geothermal/AwardeeCostShare | Open Energy Information

    Open Energy Info (EERE)

    Churchill Co., NV Geothermal Project + 9,571,873 + A Demonstration System for Capturing Geothermal Energy from Mine Waters beneath Butte, MT Geothermal Project + 1,082,753 + A...

  19. Property:Geothermal/TotalProjectCost | Open Energy Information

    Open Energy Info (EERE)

    Churchill Co., NV Geothermal Project + 14,571,873 + A Demonstration System for Capturing Geothermal Energy from Mine Waters beneath Butte, MT Geothermal Project + 2,155,497 + A...

  20. March 2014 Most Viewed Documents for Physics | OSTI, US Dept...

    Office of Scientific and Technical Information (OSTI)

    ... D.; Kuzay, T.M. (1993) 12 > Potential containment materials for liquid-lead and lead-bismuth eutectic spallation neutron source Park, J.J.; Butt, D.P.; Beard, C.A. (1997) 11 > ...

  1. Carter Co. Harding Co. Perkins Co. Dunn Co. Dawson Co. Fallon...

    U.S. Energy Information Administration (EIA) Indexed Site

    SCAIRT WOMAN WILLMEN JIM CREEK TAYLOR SIMON BUTTE SCHEFIELD BULL ... UTM-14, NAD-27. Authors: Samuel H. Limerick (1), Lucy Luo (1), Gary Long (2), David F. Morehouse (2), Jack Perrin ...

  2. PowerPoint Presentation

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    support plates Inconel 625 304 L SS shroud * On January 8, 2010 we found that the butt welding process coated the RF windows. - An error by our vendor of a critical e-beam setting...

  3. CX-010593: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Pilot Butte-La Pine #1 Wood Pole Replacements CX(s) Applied: B1.3 Date: 06/13/2013 Location(s): Oregon Offices(s): Bonneville Power Administration

  4. CX-011211: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Box Butte-Chadron 115-Kilovolt Transmission Line Structure Replacements CX(s) Applied: B1.3 Date: 09/26/2013 Location(s): Nebraska, Nebraska Offices(s): Western Area Power Administration-Rocky Mountain Region

  5. Displaced electrode process for welding

    DOE Patents [OSTI]

    Heichel, L.J.

    1975-08-26

    A method is described for the butt-welding of a relatively heavy mass to a relatively small mass such as a thin-wall tube. In butt-welding heat is normally applied at the joint between the two pieces which are butt-welded together. The application of heat at the joint results in overheating the tube which causes thinning of the tube walls and porosity in the tube material. This is eliminated by displacing the welding electrode away from the seam toward the heavier mass so that heat is applied to the heavy mass and not at the butt seam. Examples of the parameters used in welding fuel rods are given. The cladding and end plugs were made of Zircalloy. The electrode used was of 2 percent thoriated tungsten. (auth)

  6. CX-008792: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Alliance Substation Communication Building Installation Box Butte County, Nebraska CX(s) Applied: B4.6 Date: 08/28/2011 Location(s): Nebraska Offices(s): Western Area Power Administration-Rocky Mountain Region

  7. CX-013311: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Rattlesnake Butte Phase 3 Property Funding CX(s) Applied: B1.25Date: 01/06/2015 Location(s): OregonOffices(s): Bonneville Power Administration

  8. CX-010098: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Phoenix to Lone Butte 230 Kilovolt Transmission Line, Bird Diverter Installation CX(s) Applied: B1.3 Date: 04/08/2013 Location(s): CX: none Offices(s): Western Area Power Administration-Desert Southwest Region

  9. Notices

    U.S. Energy Information Administration (EIA) Indexed Site

    The material was originally obtained by Cameco from Cameco Resources-Crowe Butte Operation pursuant to export license XSOU8798. In accordance with section 131a. of the Atomic ...

  10. CX-008891: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Pilot Butte-La Pine No. 1 Wood Pole Replacement Project CX(s) Applied: B4.6 Date: 07/30/2012 Location(s): Oregon Offices(s): Bonneville Power Administration

  11. CX-003037: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Mercury Removal from Clean Coal Processing Air StreamCX(s) Applied: B3.6Date: 07/13/2010Location(s): Butte, MontanaOffice(s): Fossil Energy, National Energy Technology Laboratory

  12. Property:NEPA Resource Analysis | Open Energy Information

    Open Energy Info (EERE)

    NV-063-EA06-098 NV-EA-030-07-05 North Steens 230kV Transmission O One Nevada S Sigurd Red Butte No2 Sun Valley to Morgan Transmission Line Sunzia Southwest T Tehachapi Renewable...

  13. Property:NEPA PreApplicationMeetingDate | Open Energy Information

    Open Energy Info (EERE)

    2010 + NVN-89274 + 26 October 2010 + S San Juan Basin EC + 5 November 2008 + Sigurd Red Butte No2 + 19 December 2008 + Southline Transmission Line + 4 April 2012 + Sun Valley...

  14. Property:NEPA FundingAgencyDocNumber | Open Energy Information

    Open Energy Info (EERE)

    + DOEEA-1676 + N NV-020-03-26 + DE-PS07-02ID14264 + O One Nevada + NA + S Sigurd Red Butte No2 + NA + Retrieved from "http:en.openei.orgwindex.php?titleProperty:NEPAF...

  15. RAPID/BulkTransmission/Utah | Open Energy Information

    Open Energy Info (EERE)

    Administration Current Projects Transwest Express Zephyr Populus to Ben Lomand Sigurd to Red Butte No. 2 345kV Transmission Project Print PDF RAPID-State-Summary Retrieved from...

  16. Property:NEPA EA EIS Report | Open Energy Information

    Open Energy Info (EERE)

    On Line Appendicies Volume.pdf +, ... S San Juan Basin EC + SJBEC DraftEIS.pdf + Sigurd Red Butte No2 + USFS SRB ROD 2012.pdf +, BLM SRB ROD 2012.pdf + Southline Transmission Line...

  17. CX-008162: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Redmond-Pilot Butte Number 1 Wood Pole Replacement Project CX(s) Applied: B4.6 Date: 04/13/2012 Location(s): Oregon Offices(s): Bonneville Power Administration

  18. CX-006263: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Big Eddy-Redmond and Redmond-Pilot Butte Wood Pole ReplacementsCX(s) Applied: B1.3Date: 07/07/2011Location(s): Wasco County, OregonOffice(s): Bonneville Power Administration

  19. Tank Closure and Waste Management Environmental Impact Statement...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    ... to 4,616 m and increase number of lags to 14. 121 a Lowest maximum elevation along MODFLOW flow path through Gable Mountain-Gable Butte Gap. b Grid is 200 by 200 m (harmonic mean). ...

  20. CX-010097: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Herbicide Application at Lone Butte Substation During Fiscal Year 2013 CX(s) Applied: B1.3 Date: 04/24/2013 Location(s): Arizona Offices(s): Western Area Power Administration-Desert Southwest Region

  1. CX-010585: Categorical Exclusion Determination

    Office of Energy Efficiency and Renewable Energy (EERE)

    Teakean Butte Radio Station Upgrade CX(s) Applied: B1.19, B1.24 Date: 07/03/2013 Location(s): Idaho Offices(s): Bonneville Power Administration

  2. CX-013627: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Redmond-Pilot Butte #1 Wood Pole Replacements CX(s) Applied: B1.3Date: 04/29/2015 Location(s): OregonOffices(s): Bonneville Power Administration

  3. Office Of Nuclear Energy

    Energy Savers [EERE]

    Nanostructured Bulk Thermoelectric Generator for Efficient Power Harvesting for Self-powered Sensor Networks Yanliang Zhang, Darryl Butt, Vivek Agarwal, Zhifeng Ren Boise State University NEET2 October 28-29, 2015 2 Project Overview n Goal, and Objectives * Develop high-efficiency and reliable thermoelectric generators (TEGs) * Demonstrate self-powered wireless sensor nodes (WSNs) n Participants * Yanliang Zhang, Boise State University; * Darryl P. Butt, Boise State University; * Vivek

  4. RELAP-7 Level 2 Milestone Report: Demonstration of a Steady State Single Phase PWR Simulation with RELAP-7

    SciTech Connect (OSTI)

    David Andrs; Ray Berry; Derek Gaston; Richard Martineau; John Peterson; Hongbin Zhang; Haihua Zhao; Ling Zou

    2012-05-01

    The document contains the simulation results of a steady state model PWR problem with the RELAP-7 code. The RELAP-7 code is the next generation nuclear reactor system safety analysis code being developed at Idaho National Laboratory (INL). The code is based on INL's modern scientific software development framework - MOOSE (Multi-Physics Object-Oriented Simulation Environment). This report summarizes the initial results of simulating a model steady-state single phase PWR problem using the current version of the RELAP-7 code. The major purpose of this demonstration simulation is to show that RELAP-7 code can be rapidly developed to simulate single-phase reactor problems. RELAP-7 is a new project started on October 1st, 2011. It will become the main reactor systems simulation toolkit for RISMC (Risk Informed Safety Margin Characterization) and the next generation tool in the RELAP reactor safety/systems analysis application series (the replacement for RELAP5). The key to the success of RELAP-7 is the simultaneous advancement of physical models, numerical methods, and software design while maintaining a solid user perspective. Physical models include both PDEs (Partial Differential Equations) and ODEs (Ordinary Differential Equations) and experimental based closure models. RELAP-7 will eventually utilize well posed governing equations for multiphase flow, which can be strictly verified. Closure models used in RELAP5 and newly developed models will be reviewed and selected to reflect the progress made during the past three decades. RELAP-7 uses modern numerical methods, which allow implicit time integration, higher order schemes in both time and space, and strongly coupled multi-physics simulations. RELAP-7 is written with object oriented programming language C++. Its development follows modern software design paradigms. The code is easy to read, develop, maintain, and couple with other codes. Most importantly, the modern software design allows the RELAP-7 code to evolve with time. RELAP-7 is a MOOSE-based application. MOOSE (Multiphysics Object-Oriented Simulation Environment) is a framework for solving computational engineering problems in a well-planned, managed, and coordinated way. By leveraging millions of lines of open source software packages, such as PETSC (a nonlinear solver developed at Argonne National Laboratory) and LibMesh (a Finite Element Analysis package developed at University of Texas), MOOSE significantly reduces the expense and time required to develop new applications. Numerical integration methods and mesh management for parallel computation are provided by MOOSE. Therefore RELAP-7 code developers only need to focus on physics and user experiences. By using the MOOSE development environment, RELAP-7 code is developed by following the same modern software design paradigms used for other MOOSE development efforts. There are currently over 20 different MOOSE based applications ranging from 3-D transient neutron transport, detailed 3-D transient fuel performance analysis, to long-term material aging. Multi-physics and multiple dimensional analyses capabilities can be obtained by coupling RELAP-7 and other MOOSE based applications and by leveraging with capabilities developed by other DOE programs. This allows restricting the focus of RELAP-7 to systems analysis-type simulations and gives priority to retain and significantly extend RELAP5's capabilities.

  5. Assessment of MARMOT. A Mesoscale Fuel Performance Code

    SciTech Connect (OSTI)

    Tonks, M. R.; Schwen, D.; Zhang, Y.; Chakraborty, P.; Bai, X.; Fromm, B.; Yu, J.; Teague, M. C.; Andersson, D. A.

    2015-04-01

    MARMOT is the mesoscale fuel performance code under development as part of the US DOE Nuclear Energy Advanced Modeling and Simulation Program. In this report, we provide a high level summary of MARMOT, its capabilities, and its current state of validation. The purpose of MARMOT is to predict the coevolution of microstructure and material properties of nuclear fuel and cladding. It accomplished this using the phase field method coupled to solid mechanics and heat conduction. MARMOT is based on the Multiphysics Object-Oriented Simulation Environment (MOOSE), and much of its basic capability in the areas of the phase field method, mechanics, and heat conduction come directly from MOOSE modules. However, additional capability specific to fuel and cladding is available in MARMOT. While some validation of MARMOT has been completed in the areas of fission gas behavior and grain growth, much more validation needs to be conducted. However, new mesoscale data needs to be obtained in order to complete this validation.

  6. Multidimensional Fuel Performance Code: BISON

    SciTech Connect (OSTI)

    2014-09-03

    BISON is a finite element based nuclear fuel performance code applicable to a variety of fuel forms including light water reactor fuel rods, TRISO fuel particles, and metallic rod and plate fuel (Refs. [a, b, c]). It solves the fully-coupled equations of thermomechanics and species diffusion and includes important fuel physics such as fission gas release and material property degradation with burnup. BISON is based on the MOOSE framework (Ref. [d]) and can therefore efficiently solve problems on 1-, 2- or 3-D meshes using standard workstations or large high performance computers. BISON is also coupled to a MOOSE-based mesoscale phase field material property simulation capability (Refs. [e, f]). As described here, BISON includes the code library named FOX, which was developed concurrent with BISON. FOX contains material and behavioral models that are specific to oxide fuels.

  7. Multidimensional Fuel Performance Code: BISON

    Energy Science and Technology Software Center (OSTI)

    2014-09-03

    BISON is a finite element based nuclear fuel performance code applicable to a variety of fuel forms including light water reactor fuel rods, TRISO fuel particles, and metallic rod and plate fuel (Refs. [a, b, c]). It solves the fully-coupled equations of thermomechanics and species diffusion and includes important fuel physics such as fission gas release and material property degradation with burnup. BISON is based on the MOOSE framework (Ref. [d]) and can therefore efficientlymore » solve problems on 1-, 2- or 3-D meshes using standard workstations or large high performance computers. BISON is also coupled to a MOOSE-based mesoscale phase field material property simulation capability (Refs. [e, f]). As described here, BISON includes the code library named FOX, which was developed concurrent with BISON. FOX contains material and behavioral models that are specific to oxide fuels.« less

  8. Point kinetics calculations with fully coupled thermal fluids reactivity feedback

    SciTech Connect (OSTI)

    Zhang, H.; Zou, L.; Andrs, D.; Zhao, H.; Martineau, R.

    2013-07-01

    The point kinetics model has been widely used in the analysis of the transient behavior of a nuclear reactor. In the traditional nuclear reactor system safety analysis codes such as RELAP5, the reactivity feedback effects are calculated in a loosely coupled fashion through operator splitting approach. This paper discusses the point kinetics calculations with the fully coupled thermal fluids and fuel temperature feedback implemented into the RELAP-7 code currently being developed with the MOOSE framework. (authors)

  9. Craig Thomas Discovery & Visitor Center

    High Performance Buildings Database

    Moose, WY Grand Teton National Park's rugged landscape and stunning array of wildlife attract nearly three million visitors every year, making it one of our most popular national parks. A new Grand Teton National Park visitor center near the park's headquarters north of Jackson, Wyoming, replaces an outdated building, educates an increased number of visitors, and inspires further exploration of this extraordinary landscape. The project site is located along the Snake River, between a riparian forest and a sagebrush meadow.

  10. Reactor Application for Coaching Newbies

    SciTech Connect (OSTI)

    2015-06-17

    RACCOON is a Moose based reactor physics application designed to engage undergraduate and first-year graduate students. The code contains capabilities to solve the multi group Neutron Diffusion equation in eigenvalue and fixed source form and will soon have a provision to provide simple thermal feedback. These capabilities are sufficient to solve example problems found in Duderstadt & Hamilton (the typical textbook of senior level reactor physics classes). RACCOON does not contain any advanced capabilities as found in YAK.

  11. Year End Progress Report on Rattlesnake Improvements

    SciTech Connect (OSTI)

    Wang, Yaqi; DeHart, Mark David; Gleicher, Frederick Nathan; Ortensi, Javier; Schunert, Sebastian

    2015-09-01

    Rattlesnake is a MOOSE-based radiation transport application developed at INL to support modern multi-physics simulations. At the beginning of the last year, Rattlesnake has been able to perform steady-state, transient and eigenvalue calculations for the multigroup radiation transport equations. Various discretization schemes, including continuous finite element method (FEM) with discrete ordinates method (SN) and spherical harmonics expansion method (PN) for the self-adjoint angular flux (SAAF) formulation, continuous FEM (CFEM) with SN for the least square (LS) formulation, diffusion approximation with CFEM and discontinuous FEM (DFEM), have been implemented. A separate toolkit, YAKXS, for multigroup cross section management was developed to support Rattlesnake calculations with feedback both from changes in the field variables, such as fuel temperature, coolant density, and etc., and in isotope inventory. The framework for doing nonlinear diffusion acceleration (NDA) within Rattlesnake has been set up and both NDA calculations with SAAF-SN-CFEM scheme and Monte Carlo with OpenMC have been performed. It was also used for coupling BISON and RELAP-7 for the full-core multiphysics simulations. Within the last fiscal year, significant improvements have been made in Rattlesnake. Rattlesnake development was migrated into our internal GITLAB development environment at the end of year 2014. Since then total 369 merge requests has been accepted into Rattlesnake. It is noted that the MOOSE framework that Rattlesnake is based on is under continuous developments. Improvements made in MOOSE can improve the Rattlesnake. It is acknowledged that MOOSE developers spent efforts on patching Rattlesnake for the improvements made on the framework side. This report will not cover the code restructuring for better readability and modularity and documentation improvements, which we have spent tremendous effort on. It only details some of improvements in the following sections.

  12. GRIZZLY

    Energy Science and Technology Software Center (OSTI)

    2012-12-17

    Grizzly is a simulation tool for assessing the effects of age-related degradation on systems, structures, and components of nuclear power plants. Grizzly is built on the MOOSE framework, and uses a Jacobian-free Newton Krylov method to obtain solutions to tightly coupled thermo-mechanical simulations. Grizzly runs on a wide range of hardware, from a single processor to massively parallel machines.

  13. RESRAD Computer Code - Evaluation of Radioactively Contaminated Sites

    Office of Environmental Management (EM)

    RELAP-7 Development RELAP-7 Development January 29, 2013 - 12:03pm Addthis During the second quarter, the Reactor team drafted software development guidance documents and a software quality assurance plan and developed component models for pipe flows, pipe junctions, and basic reactor core channels using the Moose code development framework. These components are now being tested for inclusion in a simplified reactor model. Addthis Related Articles Schematic of the OECD PWR benchmark used in the

  14. Snow Micro-Structure Model

    Energy Science and Technology Software Center (OSTI)

    2014-06-25

    PIKA is a MOOSE-based application for modeling micro-structure evolution of seasonal snow. The model will be useful for environmental, atmospheric, and climate scientists. Possible applications include application to energy balance models, ice sheet modeling, and avalanche forecasting. The model implements physics from published, peer-reviewed articles. The main purpose is to foster university and laboratory collaboration to build a larger multi-scale snow model using MOOSE. The main feature of the code is that it is implementedmore » using the MOOSE framework, thus making features such as multiphysics coupling, adaptive mesh refinement, and parallel scalability native to the application. PIKA implements three equations: the phase-field equation for tracking the evolution of the ice-air interface within seasonal snow at the grain-scale; the heat equation for computing the temperature of both the ice and air within the snow; and the mass transport equation for monitoring the diffusion of water vapor in the pore space of the snow.« less

  15. Assessment of PCMI Simulation Using the Multidimensional Multiphysics BISON Fuel Performance Code

    SciTech Connect (OSTI)

    Stephen R. Novascone; Jason D. Hales; Benjamin W. Spencer; Richard L. Williamson

    2012-09-01

    Since 2008, the Idaho National Laboratory (INL) has been developing a next-generation nuclear fuel performance code called BISON. BISON is built using INLs Multiphysics Object-Oriented Simulation Environment, or MOOSE. MOOSE is a massively parallel, finite element-based framework to solve systems of coupled non-linear partial differential equations using the Jacobian-FreeNewton Krylov (JFNK) method. MOOSE supports the use of complex two- and three-dimensional meshes and uses implicit time integration, which is important for the widely varied time scales in nuclear fuel simulation. MOOSEs object-oriented architecture minimizes the programming required to add new physics models. BISON has been applied to various nuclear fuel problems to assess the accuracy of its 2D and 3D capabilities. The benchmark results used in this assessment range from simulation results from other fuel performance codes to measurements from well-known and documented reactor experiments. An example of a well-documented experiment used in this assessment is the Third Ris Fission Gas Project, referred to as Bump Test GE7, which was performed on rod ZX115. This experiment was chosen because it allows for an evaluation of several aspects of the code, including fully coupled thermo-mechanics, contact, and several nonlinear material models. Bump Test GE7 consists of a base-irradiation period of a full-length rod in the Quad-Cities-1 BWR for nearly 7 years to a burnup of 4.17% FIMA. The base irradiation test is followed by a bump test of a sub-section of the original rod. The bump test takes place in the test reactor DR3 at Ris in a water-cooled HP1 rig under BWR conditions where the power level is increased by about 50% over base irradiation levels in the span of several hours. During base irradiation, the axial power profile is flat. During the bump test, the axial power profile changes so that the bottom half of the rod is at approximately 50% higher power than at the base irradiation level, while the power at the top of the rod is at about 20% of the base irradiation power level. 2D BISON simulations of the Bump Test GE7 were run using both discrete and smeared pellet geometry. Comparisons between these calculations and experimental measurements are presented for clad diameter and elongation after the base irradiation and clad profile along the length of the test section after the bump test. Preliminary comparisons between calculations and measurements are favorable, supporting the use of BISON as an accurate multiphysics fuel simulation tool.

  16. Development of an advanced process for drying fine coal in an inclined fluidized bed: Technical progress report for the second quarter, January 19--March 31, 1989

    SciTech Connect (OSTI)

    Boysen, J.E.; Cha, C.Y.; Berggren, M.H.; Jha, M.C.

    1989-05-01

    This research project is for the development of a technically and economically feasible process for drying and stabilizing of fine particles of high-moisture subbituminous coal. Research activities were initiated with efforts concentrating on characterization of the two feed coals: Eagle Butte coal from AMAX Coal Company's mine located in the Powder River Basin of Wyoming; and coal from Usibelli Coal Mine, Inc.'s mine located in central Alaska. Both of the feed coals are high-moisture subbituminous coals with ''as received'' moisture contents of 29% and 22% for the Eagle Butte and Usibelli coals, respectively. However, physical analyses of the crushed coal samples (--28-mesh particle size range) indicate many differences. The minimum fluidization velocity (MFV) of the feed coals were experimentally determined. The MFV for --28-mesh Eagle Butte coal is approximately 1 ft/min, and the MFV for --28-mesh Usibelli coal is approximately 3 ft/min. 2 refs., 16 figs., 3 tabs.

  17. Apparatus and method for harvesting woody plantations

    DOE Patents [OSTI]

    Eggen, David L.

    1988-11-15

    A tree harvester for harvesting felled trees includes a wheel mounted wood chipper which moves toward the butt ends of the tree stems to be processed. The harvester includes a plurality of rotating alignment discs in front of the chipper. These discs align the tree stems to be processed with the mouth of the chipper. A chipper infeed cylinder is rotatably mounted between the discs and the front end of the chipper, and lifts the tree stem butts up from the ground into alignment with the chipper inlet port. The chips discharge from the chipper and go into a chip hopper which moves with the tree harvester.

  18. Apparatus and method for harvesting woody plantations

    DOE Patents [OSTI]

    Eggen, D.L.

    1988-11-15

    A tree harvester for harvesting felled trees includes a wheel mounted wood chipper which moves toward the butt ends of the tree stems to be processed. The harvester includes a plurality of rotating alignment discs in front of the chipper. These discs align the tree stems to be processed with the mouth of the chipper. A chipper infeed cylinder is rotatably mounted between the discs and the front end of the chipper, and lifts the tree stem butts up from the ground into alignment with the chipper inlet port. The chips discharge from the chipper and go into a chip hopper which moves with the tree harvester. 8 figs.

  19. Fuel Cell Technologies Office Accomplishments and Progress | Department of

    Energy Savers [EERE]

    Ft. Carson Army Base, Colorado Springs, Colorado Ft. Carson Army Base, Colorado Springs, Colorado Photo of High-Bay Aviation Maintenance Facility at Butts Army Airfield Fort Carson U.S. Army Base is located south of Colorado Springs, Colorado. It was the first Federal facility to install a "solar wall"-a solar ventilation air preheating system. The solar wall heats Ft. Carson's new high-bay aviation maintenance facility at Butts Army Airfield by pre-warming air as much as 54°F and

  20. Estimate of the allowable dimensions of diagnosed defects in category III and IV welded pipeline joints{sup 1}

    SciTech Connect (OSTI)

    Grin', E. A.; Bochkarev, V. I.

    2013-01-15

    An approach for estimating the permissible dimensions of technological defects in butt welded joints in category III and IV pipelines is described. The allowable size of a welding defect is determined from the condition of compliance with the specifications on strength for a reference cross section (damaged joint) of the pipeline taking into account its weakening by a given defect.With regard to the fairly widespread discovery of technological defects in butt welded joints during diagnostics of auxiliary pipelines for thermal electric power plants, the proposed approach can be used in practice by repair and consulting organizations.

  1. Method Of Dispensing Microdoses Of A Aqueous Solutions Of S Ubstances Onto A Carrier And A Device For Carrying Out Said Method

    DOE Patents [OSTI]

    Ershov, Gennady Moiseevich; Kirillov, Eugenii Vladislavovich; Mirzabekov, Andrei Darievich

    1999-10-05

    A method and a device for dispensing microdoses of aqueous solutions are provided, whereby the substance is transferred by the free surface end of a rodlike transferring element; the temperature of the transferring element is maintained at essentially the dew point of the ambient air during the transfer. The device may comprise a plate-like base to which are affixed a plurality of rods; the unfixed butt ends of the rods are coplanar. The device further comprises a means for maintaining the temperature of the unfixed butt ends of the rods essentially equal to the dew point of the ambient air during transfer of the aqueous substance

  2. Device of dispensing micro doses of aqueous solutions of substances onto a carrier and device for carrying out said method

    DOE Patents [OSTI]

    Ershow, Gennady Moiseevich; Kirillov, Evgenii Vladislavovich; Mirzabekov, Andrei Darievich

    1998-01-01

    A device for dispensing microdoses of aqueous solutions are provided, whereby the substance is transferred by the free surface end of a rodlike transferring element; the temperature of the transferring element is maintained at essentially the dew point of the ambient air during the transfer. The device may comprise a plate-like base to which are affixed a plurality of rods; the unfixed butt ends of the rods are coplanar. The device further comprises a means for maintaining the temperature of the unfixed butt ends of the rods essentially equal to the dew point of the ambient air during transfer of the aqueous substance.

  3. Line overlap and self-shielding of molecular hydrogen in galaxies

    SciTech Connect (OSTI)

    Gnedin, Nickolay Y.; Draine, Bruce T. E-mail: andrey@oddjob.uchicago.edu

    2014-11-01

    The effect of line overlap in the Lyman and Werner bands, often ignored in galactic studies of the atomic-to-molecular transition, greatly enhances molecular hydrogen self-shielding in low metallicity environments and dominates over dust shielding for metallicities below about 10% solar. We implement that effect in cosmological hydrodynamics simulations with an empirical model, calibrated against the observational data, and provide fitting formulae for the molecular hydrogen fraction as a function of gas density on various spatial scales and in environments with varied dust abundance and interstellar radiation field. We find that line overlap, while important for detailed radiative transfer in the Lyman and Werner bands, has only a minor effect on star formation on galactic scales, which, to a much larger degree, is regulated by stellar feedback.

  4. Triangle Universities Nuclear Laboratory : 2011

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Duke Faculty Mohammad Ahmed Haiyan Gao Calvin Howell Werner Tornow Henry Weller Ying Wu Duke Researchers Chitra Bhatia Alex Crowell Connie Kalbach Walker Luke Myers Duke Graduate Students Sean Finch Forrest Friesen Adamos Kafkarkou Georgios Laskaris Jonathan Mueller Medium Energy Grads Publications INSPIRES List Useful Links HIGS TUNL Medium Energy Group Low-Energy Experimental Nuclear Physics Research at Duke/TUNL The wide range of research backgrounds, technical expertise and substantial

  5. Triangle Universities Nuclear Laboratory : 2011

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    UNC Nuclear Physics| Duke Neutrino Group| Collaborators Reyco Henning Hugon Karwowski Werner Tornow John Wilkerson Publications INSPIRES List Useful Links MAJORANA KATRIN DEAP/CLEAN Neutrinos and Dark Matter We now know from observations of neutrino oscillations in reactor, accelerator, atmospheric, and solar neutrino based experiments that neutrinos have non-zero masses and that the flavor states associated with weak interactions (νe, νμ, and ντ) are superpositions of mass states

  6. phd.dvi

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    EXTRACTION OF THE 1 S 0 NEUTRON-NEUTRON SCATTERING LENGTH FROM THE REACTION d ! nn USING MONTE-CARLO SIMULATION by Qiankun Chen Department of Physics Duke University Date: Approved: Richard L. Walter, Co-Supervisor Calvin R. Howell, Co-Supervisor Seog Oh Richard G. Palmer Werner Tornow Dissertation submitted in partial ful llment of the requirements for the degree of Doctor of Philosophy in the Department of Physics in the Graduate School of Duke University 1998 ABSTRACT (Physics | Nuclear)

  7. thesis.dvi

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Use of the 1 S 0 Neutron-Proton Scattering Length as a Probe for Three-Nucleon Forces by Frank Salinas Meneses Department of Physics Duke University Date: Approved: Calvin Howell, Supervisor Werner Tornow Seog Oh Russell Roberson Roxanne Springer Dissertation submitted in partial ful llment of the requirements for the degree of Doctor of Philosophy in the Department of Physics in the Graduate School of Duke University 1998 ABSTRACT (Physics { Nuclear) Use of the 1 S 0 Neutron-Proton Scattering

  8. Revealing the Atomic Site-Dependent g Factor within a Single Magnetic

    Office of Scientific and Technical Information (OSTI)

    Molecule via the Extended Kondo Effect (Journal Article) | DOE PAGES DOE PAGES Search Results Publisher's Accepted Manuscript: Revealing the Atomic Site-Dependent g Factor within a Single Magnetic Molecule via the Extended Kondo Effect Title: Revealing the Atomic Site-Dependent g Factor within a Single Magnetic Molecule via the Extended Kondo Effect Authors: Liu, Liwei ; Yang, Kai ; Jiang, Yuhang ; Song, Boqun ; Xiao, Wende ; Song, Shiru ; Du, Shixuan ; Ouyang, Min ; Hofer, Werner A. ;

  9. Revealing the Atomic Site-Dependent g Factor within a Single Magnetic

    Office of Scientific and Technical Information (OSTI)

    Molecule via the Extended Kondo Effect (Journal Article) | SciTech Connect Revealing the Atomic Site-Dependent g Factor within a Single Magnetic Molecule via the Extended Kondo Effect Citation Details In-Document Search Title: Revealing the Atomic Site-Dependent g Factor within a Single Magnetic Molecule via the Extended Kondo Effect Authors: Liu, Liwei ; Yang, Kai ; Jiang, Yuhang ; Song, Boqun ; Xiao, Wende ; Song, Shiru ; Du, Shixuan ; Ouyang, Min ; Hofer, Werner A. ; Castro Neto, Antonio

  10. The Strange Friendship of Pauli and Jung - When Physics Met Psychology

    ScienceCinema (OSTI)

    None

    2011-10-06

    At a key time in his scientific development, Pauli was undergoing analysis by Jung. What can we learn about Pauli's discoveries of the exclusion principle and the CPT theorem, as well as his thoughts on non-conservation of parity, and his quest with Heisenberg for a unified field theory of elementary particles from Jung?s analysis of his dreams? A very different Pauli emerges, one at odds with esteemed colleagues such as Niels Bohr and Werner Heisenberg.

  11. Stockpile Stewardship Quarterly

    National Nuclear Security Administration (NNSA)

    1, Number 3 * October 2011 Message from the Assistant Deputy Administrator for Stockpile Stewardship, Chris Deeney Comments Questions or comments regarding the Stockpile Stewardship Quarterly should be directed to Terri.Batuyong@nnsa.doe.gov Technical Editor: Chris Werner, Publication Editor: Millicent Mischo Defense Programs Stockpile Stewardship in Action Volume 1, Number 3 Inside this Issue 2 Simulation: A Window into the Detonation of High Explosives 3 Modeling of High-Explosive Detonation

  12. CX-012214: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Copper Mountain-Pilot Butte 34.5 Kilovolt Transmission Line Structure Pole Replacement Project, Fremont County, Wyoming CX(s) Applied: B1.3 Date: 05/05/2014 Location(s): Wyoming Offices(s): Western Area Power Administration-Rocky Mountain Region

  13. Ceramic joints

    DOE Patents [OSTI]

    Miller, Bradley J.; Patten, Jr., Donald O.

    1991-01-01

    Butt joints between materials having different coefficients of thermal expansion are prepared having a reduced probability of failure of stress facture. This is accomplished by narrowing/tapering the material having the lower coefficient of thermal expansion in a direction away from the joint interface and not joining the narrow-tapered surface to the material having the higher coefficient of thermal expansion.

  14. Mining into the new millennium

    SciTech Connect (OSTI)

    Buchsbaum, L.

    2009-06-15

    After more than 3 years of production and a billion tons of coal shipped, Foundation Coal West, a subsidiary of Foundation Coal Holding Inc., continues to operate two of the original surface mines in Wyoming's Powder River Basin. The article describes equipment (conveyors, trucks, surface miners etc.) deployed at Belle Ayr and Eagle Butte PRB operations. 3 photos.

  15. CX-001900: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    State Energy Program (SEP) American Recovery and Reinvestment Act (ARRA) Renewable Energy Enterprise Zone (REEZ) Milner Butte Landfill Gas ProjectCX(s) Applied: B5.1Date: 03/02/2010Location(s): Burley, IdahoOffice(s): Energy Efficiency and Renewable Energy, Golden Field Office

  16. CX-008225: Categorical Exclusion Determination

    Office of Energy Efficiency and Renewable Energy (EERE)

    Recovery Act: A Demonstration System for Capturing Geothermal Energy from Mine Waters Beneath Butte Montana CX(s) Applied: A9, B2.1, B5.19 Date: 04/18/2012 Location(s): Montana Offices(s): Golden Field Office

  17. CX-010680: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Herbicide Application at One Substation: Lone Butte, located on the Gila River Indian Community During Fiscal Year 2014 CX(s) Applied: B1.3 Date: 07/01/2013 Location(s): Arizona Offices(s): Western Area Power Administration-Desert Southwest Region

  18. Property:NEPA FundingNumber | Open Energy Information

    Open Energy Info (EERE)

    D DOI-BLM-NV-W010-2012-0057-EA + DE-PS36-08GO98008 + O One Nevada + NA + S Sigurd Red Butte No2 + NA + Retrieved from "http:en.openei.orgwindex.php?titleProperty:NEPAF...

  19. EA-1912: Midway-Benton No. 1 Rebuild Project, near town of Desert Aire, Benton County, WA

    Broader source: Energy.gov [DOE]

    This EA evaluates the environmental impacts of a proposal by DOE’s Bonneville Power Administration to rebuild its existing Midway-Benton No.1 transmission line in place, or to reroute a portion of the Midway-Benton No. 1 transmission line that currently crosses Gable Mountain and Gable Butte in order to avoid crossing these features.

  20. Modeling Constituent Redistribution in U-Pu-Zr Metallic Fuel Using the Advanced Fuel Performance Code BISON

    SciTech Connect (OSTI)

    Douglas Porter; Steve Hayes; Various

    2014-06-01

    The Advanced Fuels Campaign (AFC) metallic fuels currently being tested have higher zirconium and plutonium concentrations than those tested in the past in EBR reactors. Current metal fuel performance codes have limitations and deficiencies in predicting AFC fuel performance, particularly in the modeling of constituent distribution. No fully validated code exists due to sparse data and unknown modeling parameters. Our primary objective is to develop an initial analysis tool by incorporating state-of-the-art knowledge, constitutive models and properties of AFC metal fuels into the MOOSE/BISON (1) framework in order to analyze AFC metallic fuel tests.

  1. app_d

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    41 DOE/EIS-0287 Idaho HLW & FD EIS Document 30, Joyce E. Batezel, Moose, WY Page 1 of 1 Document 31, Tri-City Industrial Development Council (Harold Heacock), Kennewick, WA Page 1 of 2 - New Information - DOE/EIS-0287 D-42 Appendix D Document 31, Tri-City Industrial Development Council (Harold Heacock), Kennewick, WA Page 2 of 2 Document 32, U.S. Department of Commerce (Susan B. Fruchter), Washington, D.C. Page 1 of 2 - New Information - D-43 DOE/EIS-0287 Idaho HLW & FD EIS Document 32,

  2. Reactor Application for Coaching Newbies

    Energy Science and Technology Software Center (OSTI)

    2015-06-17

    RACCOON is a Moose based reactor physics application designed to engage undergraduate and first-year graduate students. The code contains capabilities to solve the multi group Neutron Diffusion equation in eigenvalue and fixed source form and will soon have a provision to provide simple thermal feedback. These capabilities are sufficient to solve example problems found in Duderstadt & Hamilton (the typical textbook of senior level reactor physics classes). RACCOON does not contain any advanced capabilities asmore » found in YAK.« less

  3. Uk'e koley - No Footprint: Chickaloon Village Traditional Council

    Energy Savers [EERE]

    Chickaloon Village Traditional Council Nay'dini'aa Na'  Nay'dini'aa Na' meaning: a log across the river  Our Tribe has long been devoted to being a good steward to the environment, understanding that it is our responsibility to take care of the land that has been loaned to us for the short time we are here.  Historically harvested resources include salmon, moose, caribou, beluga whale, grizzly and black bear, dall sheep, beaver and numerous other animals and plants for food, medicine,

  4. Uk'e koley No Footprint

    Energy Savers [EERE]

    Uk'e koley "No Footprint" Chickaloon Village Traditional Council Nay'dini'aa Na' Chickaloon Tribal Overview * Our Tribe has long been devoted to being a good steward to the environment, understanding that it is our responsibility to take care of the land that has been loaned to us for the short time we are here. * Historically harvested resources include salmon, moose, caribou, beluga whale, grizzly and black bear, dall sheep, beaver and numerous other animals and plants for food,

  5. Uk'e koley: "No Footprint"

    Energy Savers [EERE]

    Nay"dini"aa Na" Presenter: Jim Shaginoff  Nay"dini"aa Na" meaning: a log across the river  Our Tribe has long been devoted to being a good steward to the environment, understanding that it is our responsibility to take care of the land that has been loaned to us for the short time we are here.  Historically harvested resources include salmon, moose, caribou, beluga whale, grizzly and black bear, dall sheep, beaver and numerous other animals and plants for

  6. Uk'e koley: No Footprint

    Energy Savers [EERE]

    Nay'dini'aa Na' Presenter: Brian Winnestaffer For: Jim Shaginoff Before After Ø Nay'dini'aa Na' meaning: a log across the river Ø Our Tribe has long been devoted to being a good steward to the environment, understanding that it is our responsibility to take care of the land that has been loaned to us for the short time we are here. Ø Historically harvested resources include salmon, moose, caribou, beluga whale, grizzly and black bear, dall sheep, beaver and numerous other animals and plants

  7. Overview of the BISON Multidimensional Fuel Performance Code

    SciTech Connect (OSTI)

    R. L. Williamson; J. D. Hales; S. R. Novascone; B. W. Spencer; D. M. Perez; G. Pastore; R. C. Martineau

    2013-10-01

    BISON is a modern multidimensional multiphysics finite-element based nuclear fuel performance code that has been under development at the Idaho National Laboratory (USA) since 2009. A brief background is provided on the codes computational framework (MOOSE), governing equations, and material and behavioral models. Ongoing code verification and validation work is outlined, and comparative results are provided for select validation cases. Recent applications are discussed, including specific description of two applications where 3D treatment is important. A summary of future code development and validation activities is given. Numerous references to published work are provided where interested readers can find more complete information.

  8. NEAMS-Funded University Research in Support of TREAT Modeling and Simulation, FY15

    SciTech Connect (OSTI)

    Dehart, Mark; Mausolff, Zander; Goluoglu, Sedat; Prince, Zach; Ragusa, Jean; Haugen, Carl; Ellis, Matt; Forget, Benoit; Smith, Kord; Alberti, Anthony; Palmer, Todd

    2015-09-01

    This report summarizes university research activities performed in support of TREAT modeling and simulation research. It is a compilation of annual research reports from four universities: University of Florida, Texas A&M University, Massachusetts Institute of Technology and Oregon State University. The general research topics are, respectively, (1) 3-D time-dependent transport with TDKENO/KENO-VI, (2) implementation of the Improved Quasi-Static method in Rattlesnake/MOOSE for time-dependent radiation transport approximations, (3) improved treatment of neutron physics representations within TREAT using OpenMC, and (4) steady state modeling of the minimum critical core of the Transient Reactor Test Facility (TREAT).

  9. Risk Analysis Virtual ENvironment

    SciTech Connect (OSTI)

    2014-02-10

    RAVEN has 3 major functionalities: 1. Provides a Graphical User Interface for the pre- and post-processing of the RELAP-7 input and output. 2. Provides the capability to model nuclear power plants control logic for the RELAP-7 code and dynamic control of the accident scenario evolution. This capability is based on a software structure that realizes a direct connection between the RELAP-7 solver engine (MOOSE) and a python environment where the variables describing the plant status are accessible in a scripting environment. RAVEN support the generation of the probabilistic scenario control by supplying a wide range of probability and cumulative distribution functions and their inverse functions. 3. Provides a general environment to perform probability risk analysis for RELAP-7, RELAP-5 and any generic MOOSE based applications. The probabilistic analysis is performed by sampling the input space of the coupled code parameters and it is enhanced by using modern artificial intelligence algorithms that accelerate the identification of the areas of major risk (in the input parameter space). This environment also provides a graphical visualization capability to analyze the outcomes. Among other approaches, the classical Monte Carlo and Latin Hypercube sampling algorithms are available. For the acceleration of the convergence of the sampling methodologies, Support Vector Machines, Bayesian regression, and collocation stochastic polynomials chaos are implemented. The same methodologies here described could be used to solve optimization and uncertainties propagation problems using the RAVEN framework.

  10. Memory Optimization for Phase-field Simulations

    SciTech Connect (OSTI)

    Derek Gaston; John Peterson; Andrew Slaughter; Cody Permann; David Andrs

    2014-08-01

    Phase-field simulations are computationally and memory intensive applications. Many of the phase-field simulations being conducted in support of NEAMS were not capable of running on “normal clusters” with 2-4GB of RAM per core, and instead required specialized “big-memory” clusters with 64GB per core. To address this issue, the MOOSE team developed a new Python-based utility called MemoryLogger, and applied it to locate, diagnose, and eradicate memory bottlenecks within the MOOSE framework. MemoryLogger allows for a better understanding of the memory usage of an application being run in parallel across a cluster. Memory usage information is captured for every individual process in a parallel job, and communicated to the head node of the cluster. Console text output from the application itself is automatically matched with this memory usage information to produce a detailed picture of memory usage over time, making it straightforward to identify the subroutines which contribute most to the application’s peak memory usage. The information produced by the MemoryLogger quickly and effectively narrows the search for memory optimizations to the most data-intensive parts of the simulation.

  11. Risk Analysis Virtual ENvironment

    Energy Science and Technology Software Center (OSTI)

    2014-02-10

    RAVEN has 3 major functionalities: 1. Provides a Graphical User Interface for the pre- and post-processing of the RELAP-7 input and output. 2. Provides the capability to model nuclear power plants control logic for the RELAP-7 code and dynamic control of the accident scenario evolution. This capability is based on a software structure that realizes a direct connection between the RELAP-7 solver engine (MOOSE) and a python environment where the variables describing the plant statusmore » are accessible in a scripting environment. RAVEN support the generation of the probabilistic scenario control by supplying a wide range of probability and cumulative distribution functions and their inverse functions. 3. Provides a general environment to perform probability risk analysis for RELAP-7, RELAP-5 and any generic MOOSE based applications. The probabilistic analysis is performed by sampling the input space of the coupled code parameters and it is enhanced by using modern artificial intelligence algorithms that accelerate the identification of the areas of major risk (in the input parameter space). This environment also provides a graphical visualization capability to analyze the outcomes. Among other approaches, the classical Monte Carlo and Latin Hypercube sampling algorithms are available. For the acceleration of the convergence of the sampling methodologies, Support Vector Machines, Bayesian regression, and collocation stochastic polynomials chaos are implemented. The same methodologies here described could be used to solve optimization and uncertainties propagation problems using the RAVEN framework.« less

  12. RELAP-7 and PRONGHORN Initial Integration Plan

    SciTech Connect (OSTI)

    J. Ortensi; D. Andrs; A.A. Bingham; R.C. Martineau; J.W. Peterson

    2012-05-01

    Modern nuclear reactor safety codes require the ability to solve detailed coupled neutronicthermal fluids problems. For larger cores, this implies fully coupled 3-D spatial dynamics with appropriate feedback models that can provide enough resolution to accurately compute core heat generation and removal during steady and unsteady conditions. The reactor analyis code PRONGHORN is being coupled to RELAP-7 as a first step to extend RELAP's current capabilities. This report details the mathematical models, the type of coupling, and the testing that will be used to produce an integrated system. RELAP-7 is a MOOSE-based application that solves the continuity, momentum, and energy equations in 1-D for a compressible fluid. The pipe and joint capabilities enable it to model parts of the PCU system. The PRONGHORN application, also developed on the MOOSE infrastructure, solves the coupled equations that define the neutron diffusion, fluid flow, and heat transfer in a 3-D core model. Initially, the two systems will be loosely coupled to simplify the transition towards a more complex infrastructure. The integration will be tested with the OECD/NEA MHTGR-350 Coupled Neutronics-Thermal Fluids benchmark model.

  13. Initial Coupling of the RELAP-7 and PRONGHORN Applications

    SciTech Connect (OSTI)

    J. Ortensi; D. Andrs; A.A. Bingham; R.C. Martineau; J.W. Peterson

    2012-10-01

    Modern nuclear reactor safety codes require the ability to solve detailed coupled neutronic- thermal fluids problems. For larger cores, this implies fully coupled higher dimensionality spatial dynamics with appropriate feedback models that can provide enough resolution to accurately compute core heat generation and removal during steady and unsteady conditions. The reactor analysis code PRONGHORN is being coupled to RELAP-7 as a first step to extend RELAPs current capabilities. This report details the mathematical models, the type of coupling, and the testing results from the integrated system. RELAP-7 is a MOOSE-based application that solves the continuity, momentum, and energy equations in 1-D for a compressible fluid. The pipe and joint capabilities enable it to model parts of the power conversion unit. The PRONGHORN application, also developed on the MOOSE infrastructure, solves the coupled equations that define the neutron diffusion, fluid flow, and heat transfer in a full core model. The two systems are loosely coupled to simplify the transition towards a more complex infrastructure. The integration is tested on a simplified version of the OECD/NEA MHTGR-350 Coupled Neutronics-Thermal Fluids benchmark model.

  14. MASSIVE HYBRID PARALLELISM FOR FULLY IMPLICIT MULTIPHYSICS

    SciTech Connect (OSTI)

    Cody J. Permann; David Andrs; John W. Peterson; Derek R. Gaston

    2013-05-01

    As hardware advances continue to modify the supercomputing landscape, traditional scientific software development practices will become more outdated, ineffective, and inefficient. The process of rewriting/retooling existing software for new architectures is a Sisyphean task, and results in substantial hours of development time, effort, and money. Software libraries which provide an abstraction of the resources provided by such architectures are therefore essential if the computational engineering and science communities are to continue to flourish in this modern computing environment. The Multiphysics Object Oriented Simulation Environment (MOOSE) framework enables complex multiphysics analysis tools to be built rapidly by scientists, engineers, and domain specialists, while also allowing them to both take advantage of current HPC architectures, and efficiently prepare for future supercomputer designs. MOOSE employs a hybrid shared-memory and distributed-memory parallel model and provides a complete and consistent interface for creating multiphysics analysis tools. In this paper, a brief discussion of the mathematical algorithms underlying the framework and the internal object-oriented hybrid parallel design are given. Representative massively parallel results from several applications areas are presented, and a brief discussion of future areas of research for the framework are provided.

  15. Energy Dependence of Fission Product Yields for 239Pu, 235U, and 238U

    Office of Scientific and Technical Information (OSTI)

    (Technical Report) | SciTech Connect Dependence of Fission Product Yields for 239Pu, 235U, and 238U Citation Details In-Document Search Title: Energy Dependence of Fission Product Yields for 239Pu, 235U, and 238U Authors: Tornow, Werner [1] ; Bredeweg, Todd Allen [2] ; Wilhelmy, Jerry B. [2] ; Vieira, David J. [2] ; Tonchev, Anton Penev [2] + Show Author Affiliations Duke University Los Alamos National Laboratory Publication Date: 2014-10-31 OSTI Identifier: 1160114 Report Number(s):

  16. Integrated Deployment Model: A Comprehensive Approach to Transforming the Energy Economy

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Integrated Deployment Model: A Comprehensive Approach to Transforming the Energy Economy Mary Werner Technical Report NREL/TP-7A20-49230 November 2010 NREL is a national laboratory of the U.S. Department of Energy, Office of Energy Efficiency & Renewable Energy, operated by the Alliance for Sustainable Energy, LLC. National Renewable Energy Laboratory 1617 Cole Boulevard Golden, Colorado 80401 303-275-3000 * www.nrel.gov Contract No. DE-AC36-08GO28308 Integrated Deployment Model: A

  17. MPP-2005-1 LBNL-56798

    Office of Scientific and Technical Information (OSTI)

    MPP-2005-1 LBNL-56798 hep-ph/0502134 Perturbative corrections to the determination of V ub from the P + spectrum in B → X u ¯ ν Andre H. Hoang, 1 Zoltan Ligeti, 2 and Michael Luke 3 1 Max-Planck-Institut f¨ ur Physik, Werner-Heisenberg-Institut, F¨ ohringer Ring 6, 80805 M¨ unchen, Germany 2 Ernest Orlando Lawrence Berkeley National Laboratory, University of California, Berkeley, CA 94720 3 Department of Physics, University of Toronto, 60 St. George Street, Toronto, Ontario, Canada M5S

  18. Manhattan Project: Atomic Rivals and the ALSOS Mission, 1938-1945

    Office of Scientific and Technical Information (OSTI)

    Werner Heisenberg, the leader of the German atomic weapons program. ATOMIC RIVALS AND THE ALSOS MISSION (Germany and Japan, 1938-1945) Events > Bringing It All Together, 1942-1945 Establishing Los Alamos, 1942-1943 Early Bomb Design, 1943-1944 Basic Research at Los Alamos, 1943-1944 Implosion Becomes a Necessity, 1944 Oak Ridge and Hanford Come Through, 1944-1945 Final Bomb Design, 1944-1945 Atomic Rivals and the ALSOS Mission, 1938-1945 Espionage and the Manhattan Project, 1940-1945 For most

  19. final-thesis.dvi

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Neutron-Proton Analyzing Power at E n = 7.6 and 12 MeV and the NN Coupling Constant by Richard T. Braun Department of Physics Duke University Date: Approved: Werner Tornow, Supervisor Al Goshaw Berndt Muller Richard Walter Henry Weller Dissertation submitted in partial ful llment of the requirements for the degree of Doctor of Philosophy in the Department of Physics in the Graduate School of Duke University 1998 ABSTRACT (Physics { Nuclear) The Neutron-Proton Analyzing Power at E n = 7.6 and 12

  20. CaseStudyTemplate

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    1.1. Electromagnetic M odeling o f A ccelerator S tructures Prepared by: David Bruhwiler, TechX Corp. Contributors: J.R. Cary, K. Amyx, T. Austin, B. Cowan, P. Messmer, P. Mullowney, K. Paul, P. Stoltz, D. Smithe and S. Veitzer, Tech-X Corp.; G. Werner, U. of Colorado Supports the following HEP funded NERSC repositories: "Community Petascale Project for Accelerator Science and Simulation (m778)," Principal Investigator: P. Spentzouris "Particle simulation of laser wakefield

  1. YIA2 - Rodríguez-Calero > Young Investigator Program > Research > The

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Energy Materials Center at Cornell Three Dimensionally Integrated Architecture for Ultra-High Rate Li-Ion Batteries Gabriel Rodríguez-Calero (Abruña) and Joerg Werner (Wiesner) are taking a closer look at Li-Ion batteries. Conventional lithium ion batteries (LIBs) are built in a macroscopically layered structure consisting of an anode, an electrolyte/separator and a cathode with dimensions of the order of microns. One of the main constraints for fast charge/discharge is the diffusion

  2. Atmospheric Radiation Measurement (ARM) Data from Steamboat Springs, Colorado, for the Storm Peak Laboratory Cloud Property Validation Experiment (STORMVEX)

    DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

    In October 2010, the initial deployment of the second ARM Mobile Facility (AMF2) took place at Steamboat Springs, Colorado, for the Storm Peak Laboratory Cloud Property Validation Experiment (STORMVEX). The objective of this field campaign was to obtain data about liquid and mixed-phase clouds using AMF2 instruments in conjunction with Storm Peak Laboratory (located at an elevation of 3220 meters on Mt. Werner), a cloud and aerosol research facility operated by the Desert Research Institute. STORMVEX datasets are freely available for viewing and download. Users are asked to register with the ARM Archive; the user's email address is used from that time forward as the login name.

  3. Award Name Org(s) Sponsor(s)

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Award Name Org(s) Sponsor(s) Petr A nisimov AOT---HPE Carlsten, B ruce Nina L anza ISR---2 C---PCS Wiens, R oger Clegg, S am Jonathan M acCarthy EES---17 Anderson, D ale S hea M osby LANSCE---NS Couture, A aron Brad R amshaw MPA---CMMS NSEC Harrison, N eil Migliori, A lbert William R ice MPA---CMMS Crooker, S cott Douglas S hepherd MPA---CINT CCS---3 Werner, J ames Munsky, B rian Neil T omson MPA---MSID Boncella, J ames Sibel E bru Y alcin MPA---CINT Doorn, S tephen Htoon, H an Honorable M

  4. Coiled tubing working life prediction

    SciTech Connect (OSTI)

    Wu, J.

    1995-12-31

    Failure of coiled tubing, due to the repeated bending and plastic deformation of coiled tubing on and off the reel and gooseneck, is of great concern in coiled tubing operations. This paper discusses the coiled tubing working life based on one of the coiled tubing life models published in the literature, and compares the results with other models. Certain agreements are found among these models. A group of curves is presented to illustrate the coiled tubing working life affected by coiled tubing size and wall thickness, internal pressure, yield strength, reel diameter, gooseneck radius, operation condition (corrosion) and butt-welded connection (stress concentration). The results show that coiled tubing life can be greatly increased by increasing CT wall thickness and CT strength, while the coiled tubing working life decreases under high internal pressure, corrosion, and butt-weld conditions. These curves can be easily used in estimating coiled tubing life for the field use.

  5. Analytical and Experimental Evaluation of Joining Silicon Carbide to Silicon Carbide and Silicon Nitride to Silicon Nitride for Advanced Heat Engine Applications Phase II

    SciTech Connect (OSTI)

    Sundberg, G.J.

    1994-01-01

    Techniques were developed to produce reliable silicon nitride to silicon nitride (NCX-5101) curved joins which were used to manufacture spin test specimens as a proof of concept to simulate parts such as a simple rotor. Specimens were machined from the curved joins to measure the following properties of the join interlayer: tensile strength, shear strength, 22 C flexure strength and 1370 C flexure strength. In parallel, extensive silicon nitride tensile creep evaluation of planar butt joins provided a sufficient data base to develop models with accurate predictive capability for different geometries. Analytical models applied satisfactorily to the silicon nitride joins were Norton's Law for creep strain, a modified Norton's Law internal variable model and the Monkman-Grant relationship for failure modeling. The Theta Projection method was less successful. Attempts were also made to develop planar butt joins of siliconized silicon carbide (NT230).

  6. EERE B-Roll footage | Department of Energy

    Energy Savers [EERE]

    Energy Dosimetry Records System PIA, bechtel Jacobs Company, LLC Dosimetry Records System PIA, bechtel Jacobs Company, LLC Dosimetry Records System PIA, bechtel Jacobs Company, LLC PDF icon Dosimetry Records System PIA, bechtel Jacobs Company, LLC More Documents & Publications Electronic Document Management System PIA, BechtelJacobs Company, LLC Pension Estimate System PIA, Bechtel Jacobs Company, LLC Medgate, PIA, Bechtel Jacobs Company, LLC

    Calvin O. Butts, III About Us Dr. Calvin

  7. Integrating Renewable Energy into the Transmission and Distribution System of the U.S. Virgin Islands

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Integrating Renewable Energy into the Transmission and Distribution System of the U.S. Virgin Islands Kari Burman, Dan Olis, Vahan Gevorgian, Adam Warren, and Robert Butt National Renewable Energy Laboratory Peter Lilienthal and John Glassmire HOMER Energy LLC Technical Report NREL/TP-7A20-51294 September 2011 NREL is a national laboratory of the U.S. Department of Energy, Office of Energy Efficiency & Renewable Energy, operated by the Alliance for Sustainable Energy, LLC. Contract No.

  8. Thanks to Our Neighbors in Fighting Fire on INL

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Textiles (2010 MECS) Textiles (2010 MECS) Manufacturing Energy and Carbon Footprint for Textiles Sector (NAICS 313-316) Energy use data source: 2010 EIA MECS (with adjustments) Footprint Last Revised: February 2014 View footprints for other sectors here. Manufacturing Energy and Carbon Footprint PDF icon Textiles More Documents & Publications MECS 2006 - Textiles

    Thanks to Our Neighbors in Fighting Fire on INL Idaho Bureau of Homeland Security view of the Twin Buttes Wildland fire

  9. On Extended-Term Dynamic Simulations

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Extended-Term Dynamic Simulations with High Penetrations of Photovoltaic Generation Ricky Concepcion, Ryan Elliott Sandia National Laboratories Albuquerque, NM 87185 {rconcep, rtellio}@sandia.gov Matt Donnelly Montana Tech Butte, MT 59701 mdonnelly@mtech.edu Juan Sanchez-Gasca GE Energy Schenectady, NY 12345 juan1.sanchez@ge.com Abstract-The uncontrolled intermittent availability of renew- able energy sources makes integration of such devices into today's grid a challenge. Thus, it is imperative

  10. Visiting Speaker Program - October 30, 2008. | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    30, 2008. Visiting Speaker Program - October 30, 2008. Dr. Susan Butts is Senior Director of External Science and Technology Programs at The Dow Chemical Company. In this capacity she is responsible for Dow's contract research activities with US and European government agencies and sponsored research programs at over 100 universities, institutes, and national laboratories worldwide. She has also held the role of Global Staffing Leader in which she managed recruiting and hiring activities for the

  11. Projects at the Component Development and Integration Facility. Quarterly technical progress report, April 1--June 30, 1993

    SciTech Connect (OSTI)

    Not Available

    1993-12-01

    This quarterly technical progress report presents progress on the projects at the Component Development and Integration Facility (CDIF) during the third quarter of FY93. The CDIF is a major US Department of Energy test facility in Butte, Montana, operated by MSE, Inc. Projects in progress include: MHD Proof-of-Concept Project; Mine Waste Technology Program; Plasma Projects; Resource Recovery Project; Sodium Sulfide/Ferrous Sulfate Project; Soil Washing Project; and Spray Casting Project.

  12. DE-FC26-03NT41882 | netl.doe.gov

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Inspection of Fusion Joints in Plastic Pipe DE-FC26-03NT41882 Goal: The goal is to develop, demonstrate and validate an in situ non-destructive inspection method for butt fusion joints in plastic pipe that employs a laser-based inspection technology to digitally recognize images of pipe joints and interpret their condition in an effort to maintain the nation's natural gas infrastructure through enhanced inspection capability for polyethylene pipe to improve the overall safety and reliability of

  13. Projects at the Component Development and Integration Facility. Quarterly technical progress report, January 1, 1994--March 31, 1994

    SciTech Connect (OSTI)

    Not Available

    1994-08-01

    This quarterly technical progress report presents progress on the projects at the Component Development and Integration Facility (CDIF) during the second quarter of FY94. The CDIF is a major US Department of Energy test facility in Butte, Montana, operated by MSE, Inc. Projects in progress include: Biomass Remediation Project; Heavy Metal-Contaminated Soil Project; MHD Shutdown; Mine Waste Technology Pilot Program; Plasma Projects; Resource Recovery Project; Sodium Sulfide/Ferrous Sulfate Project; and Spray Casting Project.

  14. Projects at the Component Development and Integration Facility. Quarterly technical progress report, October 1--December 31, 1992

    SciTech Connect (OSTI)

    Not Available

    1992-12-31

    This quarterly technical progress report presents progress on the projects at the component Development and Integration Facility (CDIF) during the first quarter of FY93. The CDIF is a major US Department of Energy (DOE) test facility in Butte, Montana, operated by MSE, Inc. Projects in progress include: MHD proof-of-concept project; mine waste pilot program; plasma projects; resource recovery project; sodium sulfide/ferrous sulfate project; soil washing project; and spray casting project.

  15. 1st Quarter 2016 Domestic Uranium Production Report

    U.S. Energy Information Administration (EIA) Indexed Site

    2015 1st quarter 2016 AUC LLC Reno Creek Campbell, Wyoming 2,000,000 Partially Permitted And Licensed Partially Permitted And Licensed Azarga Uranium Corp Dewey Burdock Project Fall River and Custer, South Dakota 1,000,000 Partially Permitted And Licensed Partially Permitted And Licensed Cameco Crow Butte Operation Dawes, Nebraska 1,000,000 Operating Operating Hydro Resources, Inc. Church Rock McKinley, New Mexico 1,000,000 Partially Permitted And Licensed Partially Permitted And Licensed Hydro

  16. 2014 Domestic Uranium Production Report

    U.S. Energy Information Administration (EIA) Indexed Site

    Domestic Uranium Production Report 2015 Domestic Uranium Production Report Release Date: May 5, 2016 Next Release Date: May 2017 2011 2012 2013 2014 2015 AUC LLC Reno Creek Campbell, Wyoming 2,000,000 - - Developing Developing Partially Permitted and Licensed Azarga Uranium Corp Dewey Burdock Project Fall River and Custer, South Dakota 1,000,000 Undeveloped Developing Developing Partially Permitted And Licensed Partially Permitted And Licensed Cameco Crow Butte Operation Dawes, Nebraska

  17. Nuclear qualified in-containment electrical connectors and method of connecting electrical conductors

    DOE Patents [OSTI]

    Powell, J. G.

    1991-01-01

    A nuclear qualified in-containment electrical connection comprises an insulated, sheathed instrument lead having electrical conductors extending from one end thereof to provide two exposed lead wires, a watertight cable having electrical conducting wires therein and extending from one end of the cable to provide two lead wires therefrom, two butt splice connectors each connecting the ends of respective ones of the lead wires from the instrument lead and cable, a length of heat shrinkable plastic tubing positioned over each butt splice connector and an adjacent portion of a respective lead wire from the cable and heat shrunk into position, a length of heat shrinkable plastic tubing on the end portion of the instrument lead adjacent the lead wires therefrom and heat shrunk thereon and a length of outer heat shrinkable plastic tubing extending over the end portion of the instrument lead and the heat shrinkable tubing thereon and over the butt splice connectors and a portion of the cable adjacent the cable lead lines, the outer heat shrinkable tubing being heat shrunk into sealing position on the instrument lead and cable.

  18. Petrography, age, and paleomagnetism of basaltic lava flows in coreholes at Test Area North (TAN), Idaho National Engineering Laboratory

    SciTech Connect (OSTI)

    Lanphere, M.A.; Champion, D.E.; Kuntz, M.A.

    1994-12-31

    The petrography, age, and paleomagnetism were determined on basalt from 21 lava flows comprising about 1,700 feet of core from two coreholes (TAN CH No. 1 and TAN CH No. 2) in the Test Area North (TAN) area of the Idaho National Engineering Laboratory (INEL). Paleomagnetic studies were made on two additional cores from shallow coreholes in the TAN area. K-Ar ages and paleomagnetism also were determined on nearby surface outcrops of Circular Butte. Paleomagnetic measurements were made on 416 samples from four coreholes and on a single site in surface lava flows of Circular Butte. K-Ar ages were measured on 9 basalt samples from TAN CH No. 1 and TAN CH No. 2 and one sample from Circular Butte. K-Ar ages ranged from 1.044 Ma to 2.56 Ma. All of the samples have reversed magnetic polarity and were erupted during the Matuyama Reversed Polarity Epoch. The purpose of investigations was to develop a three-dimensional stratigraphic framework for geologic and hydrologic studies including potential volcanic hazards to facilities at the INEL and movement of radionuclides in the Snake River Plain aquifer.

  19. RESERVOIR CHARACTERIZATION OF THE LOWER GREEN RIVER FORMATION, SOUTHWEST UINTA BASIN, UTAH

    SciTech Connect (OSTI)

    Milind D. Deo

    2003-02-11

    Reservoir simulations of different fields in the Green River Formation are reported. Most extensive simulations were performed on the Monument Butte Northeast unit. Log data were used to construct detailed geostatistical models, which were upscaled to obtain reasonable number of grid blocks for reservoir simulation. Porosities, permeabilities, and water saturations required for reservoir simulation were thus generated. Comparison of the production results with the field data revealed that there was a phenomenological deficiency in the model. This was addressed by incorporating hydraulic fractures into the models. With this change, much better agreement between simulation results and field data was obtained. Two other fields, Brundage Canyon and Uteland Butte, were simulated in primary production. Only preliminary simulations were undertaken since a number of critical data elements were missing and could not be obtained from the operators. These studies revealed that the production performance of the Brundage Canyon field is much better than what can be predicted from simulations of a typical non-fractured, undersaturated reservoir. Uteland Butte field performance was that of a typical undersaturated reservoir.

  20. Physics Integration KErnels (PIKE)

    Energy Science and Technology Software Center (OSTI)

    2014-07-31

    Pike is a software library for coupling and solving multiphysics applications. It provides basic interfaces and utilities for performing code-to-code coupling. It provides simple “black-box” Picard iteration methods for solving the coupled system of equations including Jacobi and Gauss-Seidel solvers. Pike was developed originally to couple neutronics and thermal fluids codes to simulate a light water nuclear reactor for the Consortium for Simulation of Light-water Reactors (CASL) DOE Energy Innovation Hub. The Pike library containsmore » no physics and just provides interfaces and utilities for coupling codes. It will be released open source under a BSD license as part of the Trilinos solver framework (trilinos.org) which is also BSD. This code provides capabilities similar to other open source multiphysics coupling libraries such as LIME, AMP, and MOOSE.« less

  1. RELAP-7 Beta Release: Summary of Capabilities

    SciTech Connect (OSTI)

    Martineau, Richard C.; Zhang, Hongbin; Zhao, Haihua

    2014-12-01

    RELAP-7 is a nuclear systems safety analysis code being developed at the Idaho National Laboratory (INL). Building upon the decades of software development at the INL, we began the development of RELAP-7 in 2011 to support the Risk Informed Safety Margins Characterization (RISMC) Pathway. As part of this development, the first lines of RELAP-7 code were committed to the software revision control repository on November 7th, 2011. The overall design goal of RELAP-7 is to take advantage of the previous thirty years of advancements in computer architecture, software design, numerical methods, and physical models in order to provide capabilities needed for the RISMC methodology and to support nuclear power safety analysis. RELAP-7 is built using the INL’s modern scientific software development framework, MOOSE (Multi-physics Object Oriented Simulation Environment). MOOSE provides improved numerical calculations (including higher-order integration in both space and time, yielding converged second-order accuracy). The RELAP-7 code structure is based on multiple physical component models such as pipes, junctions, pumps, etc. Each component can have options for different fluid models such as single- and two-phase flow. This component-based and physics-based software architecture allows RELAP-7 to adopt different physical models for different applications. A relatively new two-phase hydrodynamic model, termed the ''7-Equation model'' for two phasic pressures, velocities, energies, and volumetric fraction, is incorporated into RELAP-7 for liquid-gas (water-steam) flows. This new model allows second-order integration because it is well-posed, which will reduce the numerical error associated with traditional systems analysis codes. In this paper, we provide a RELAP-7 capability list describing analysis features, range of applicability, and reactor components that will be available for the December 15th, 2014 beta release of the software.

  2. Unsaturated Zone and Saturated Zone Transport Properties (U0100)

    SciTech Connect (OSTI)

    J. Conca

    2000-12-20

    This Analysis/Model Report (AMR) summarizes transport properties for the lower unsaturated zone hydrogeologic units and the saturated zone at Yucca Mountain and provides a summary of data from the Busted Butte Unsaturated Zone Transport Test (UZTT). The purpose of this report is to summarize the sorption and transport knowledge relevant to flow and transport in the units below Yucca Mountain and to provide backup documentation for the sorption parameters decided upon for each rock type. Because of the complexity of processes such as sorption, and because of the lack of direct data for many conditions that may be relevant for Yucca Mountain, data from systems outside of Yucca Mountain are also included. The data reported in this AMR will be used in Total System Performance Assessment (TSPA) calculations and as general scientific support for various Process Model Reports (PMRs) requiring knowledge of the transport properties of different materials. This report provides, but is not limited to, sorption coefficients and other relevant thermodynamic and transport properties for the radioisotopes of concern, especially neptunium (Np), plutonium (Pu), Uranium (U), technetium (Tc), iodine (I), and selenium (Se). The unsaturated-zone (UZ) transport properties in the vitric Calico Hills (CHv) are discussed, as are colloidal transport data based on the Busted Butte UZTT, the saturated tuff, and alluvium. These values were determined through expert elicitation, direct measurements, and data analysis. The transport parameters include information on interactions of the fractures and matrix. In addition, core matrix permeability data from the Busted Butte UZTT are summarized by both percent alteration and dispersion.

  3. Buildings Energy Data Book: 3.7 Retail Markets and Companies

    Buildings Energy Data Book [EERE]

    3 2010 Top Supermarkets, by Sales 2010 All Commodity Supermarket Wal-Mart Stores 3,001 Kroger Co. 2,460 Safeway, Inc. 1,461 Supervalu, Inc. 1,504 Ahold USA, Inc. (Stop and Shop, Giant) 746 Publix Super Markets, Inc. 1,035 Delhaize America, Inc. (Food Lion) 1,641 H.E. Butt Grocery Co. (HEB) 291 Meijer Inc. 195 Great Atlantic & Pacific Tea Co. (Pathmark) 373 Note(s): Source(s): All commodity volume in this example represents the "annualized range of the estimated retail sales volume of

  4. U.S. Energy Information Administration | Annual Coal Report 2014

    U.S. Energy Information Administration (EIA) Indexed Site

    9. Major U.S. Coal Mines, 2014 Rank Mine Name / Operating Company Mine Type State Production (short tons) 1 North Antelope Rochelle Mine / Peabody Powder River Mining LLC Surface Wyoming 117,965,515 2 Black Thunder / Thunder Basin Coal Company LLC Surface Wyoming 101,016,860 3 Cordero Mine / Cordero Mining LLC Surface Wyoming 34,809,101 4 Antelope Coal Mine / Antelope Coal LLC Surface Wyoming 33,646,960 5 Eagle Butte Mine / Alpha Coal West, Inc. Surface Wyoming 20,690,237 6 Spring Creek Coal

  5. DOE HQ Special Needs in an Emergency

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    ) Go to Stairwell or Area of Refuge 2) Contact Emergency Responders 3) Follow Instructions Key Points to remember During an Emergency What an employee should do during an emergency: 1) Go to the nearest stairwell or area of refuge. 2) Contact emergency responders using the emergency call butt on or a telephone. Provide responders with your name, the name of anyone with you, your locati on and the assistance you need. 3) Follow the instructi ons provided. You may be told:  Remain in your

  6. Monte Carlo Fundamentals E B. BROWN and T M. S N

    Office of Scientific and Technical Information (OSTI)

    Monte Carlo Fundamentals E B. BROWN and T . M. S - N February 1996 Preparedby Lockheed M a r t i n Company KNOLLS ATOMIC POWER LABORATORY Schenectady, New York Contract No. DE-AC12-76-SN-00052 KAPL-4823 UC-32 (DOE/TIC-4500-R75) DISTRlBUTtON OF T H I S DOCUMENT IS UNLIMITED kw Disclaimer This report was prepared as an account of work sponsored by an agency of the United States Gov- ernment. Neither the United States Government nor any agency thereof, nor any of their employ- ees, m a k e s any

  7. Probability of pipe fracture in the primary coolant loop of a PWR plant. Volume 5: probabilistic fracture mechanics analysis. Final report

    SciTech Connect (OSTI)

    Harris, D.O.; Lim, E.Y.; Dedhia, D.D.

    1981-08-01

    The purpose of the portion of the Load Combination Program covered in this volume was to estimate the probability of a seismic induced loss-of-coolant accident (LOCA) in the primary piping of a commercial pressurized water reactor (PWR). Such results are useful in rationally assessing the need to design reactor primary piping systems for the simultaneous occurrence of these two potentially high stress events. The primary piping system at Zion I was selected for analysis. Attention was focussed on the girth butt welds in the hot leg, cold leg and cross-over leg, which are centrifugally cast austenitic stainless steel lines with nominal outside diameters of 32 - 37 inches.

  8. Projects at the Component Development and Integration Facility. Quarterly technical progress report, January 1--March 31, 1993

    SciTech Connect (OSTI)

    Not Available

    1993-09-01

    This quarterly technical progress report presents progress on several different projects at the Component Development and Integration Facility (CDIF) during the second quarter of FY93. The CDIF is a major US Department of Energy test facility in Butte, Montana, operated by MSE, Inc. Projects in progress include: MHD Proof-of-Concept Project; Mine Waste Technology Pilot Program; Plasma Furnace Projects for waste destruction; Resource Recovery Project; Sodium Sulfide/Ferrous Sulfate Project; Soil Washing Project for removal of radioactive materials; and Spray Casting Project.

  9. Nonenzymatic Role for WRN in Preserving Nascent DNA Strands after Replication Stress

    SciTech Connect (OSTI)

    Su, Fengtao; Mukherjee, Shibani; Yang, Yanyong; Mori, Eiichiro; Bhattacharya, Souparno; Kobayashi, Junya; Yannone, Steven  M.; Chen, David  J.; Asaithamby, Aroumougame

    2014-11-20

    WRN, the protein defective in Werner syndrome (WS), is a multifunctional nuclease involved in DNA damage repair, replication, and genome stability maintenance. It was assumed that the nuclease activities of WRN were critical for these functions. Here, we report a nonenzymatic role for WRN in preserving nascent DNA strands following replication stress. We found that lack of WRN led to shortening of nascent DNA strands after replication stress. Furthermore, we discovered that the exonuclease activity of MRE11 was responsible for the shortening of newly replicated DNA in the absence of WRN. Mechanistically, the N-terminal FHA domain of NBS1 recruits WRN to replication-associated DNA double-stranded breaks to stabilize Rad51 and to limit the nuclease activity of its C-terminal binding partner MRE11. Thus, this previously unrecognized nonenzymatic function of WRN in the stabilization of nascent DNA strands sheds light on the molecular reason for the origin of genome instability in WS individuals.

  10. PP//-80-077 ORO//-250A-309 MEASURB>ENT OF ULTRACOLD NEUTRONS PRODUCED BY USING DOPPLER-

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    PP//-80-077 ORO//-250A-309 MEASURB>ENT OF ULTRACOLD NEUTRONS PRODUCED BY USING DOPPLER- SHIFTED BRAGG REFLECTION AT A PULSED-NEUTRON SOURCE T.O. Brim, J.M. C a r p e n t e r , V.E. Krohn, and G.R. Ringo Afgonne N a t i o n a l L a b o r a t o r y , Argonne, I l l i n o i s 60439 and J.W. Cronin U n i v e r s i t y of Chicago, Chicago, I l l i n o i s 60637 and T.W. Dombeck, and J.W. Lynn U n i v e r s i t y of Maryland, C o l l e g e P a r k , Maryland 20742 and S.A. Werner U n i v e r s i t

  11. Entanglement swapping of noisy states: A kind of superadditivity in nonclassicality

    SciTech Connect (OSTI)

    Sen, Aditi; Sen, Ujjwal; Brukner, Caslav; Buzek, Vladimir; Zukowski, Marek

    2005-10-15

    We address the question as to whether an entangled state that satisfies local realism will give a violation of the same after entanglement swapping in a suitable scenario. We consider such a possibility as a kind of superadditivity in nonclassicality. Importantly, it will indicate that checking for violation of local realism, in the state obtained after entanglement swapping, can be a method for detecting entanglement in the input state of the swapping procedure. We investigate various entanglement swapping schemes, which involve mixed initial states. The strength of violation of local realism by the state obtained after entanglement swapping is compared with the one for the input states. We obtain a kind of superadditivity of violation of local realism for Werner states, consequent upon entanglement swapping involving Greenberger-Horne-Zeilinger-state measurements. We also discuss whether entanglement swapping of specific states may be used in quantum repeaters with a substantially reduced need to perform the entanglement distillation step.

  12. Temperature dependent transport characteristics of graphene/n-Si diodes

    SciTech Connect (OSTI)

    Parui, S.; Ruiter, R.; Zomer, P. J.; Wojtaszek, M.; Wees, B. J. van; Banerjee, T.

    2014-12-28

    Realizing an optimal Schottky interface of graphene on Si is challenging, as the electrical transport strongly depends on the graphene quality and the fabrication processes. Such interfaces are of increasing research interest for integration in diverse electronic devices as they are thermally and chemically stable in all environments, unlike standard metal/semiconductor interfaces. We fabricate such interfaces with n-type Si at ambient conditions and find their electrical characteristics to be highly rectifying, with minimal reverse leakage current (<10{sup ?10}?A) and rectification of more than 10{sup 6}. We extract Schottky barrier height of 0.69?eV for the exfoliated graphene and 0.83?eV for the CVD graphene devices at room temperature. The temperature dependent electrical characteristics suggest the influence of inhomogeneities at the graphene/n-Si interface. A quantitative analysis of the inhomogeneity in Schottky barrier heights is presented using the potential fluctuation model proposed by Werner and Gttler.

  13. Dynamic Event Tree advancements and control logic improvements

    SciTech Connect (OSTI)

    Alfonsi, Andrea; Rabiti, Cristian; Mandelli, Diego; Sen, Ramazan Sonat; Cogliati, Joshua Joseph

    2015-09-01

    The RAVEN code has been under development at the Idaho National Laboratory since 2012. Its main goal is to create a multi-purpose platform for the deploying of all the capabilities needed for Probabilistic Risk Assessment, uncertainty quantification, data mining analysis and optimization studies. RAVEN is currently equipped with three different sampling categories: Forward samplers (Monte Carlo, Latin Hyper Cube, Stratified, Grid Sampler, Factorials, etc.), Adaptive Samplers (Limit Surface search, Adaptive Polynomial Chaos, etc.) and Dynamic Event Tree (DET) samplers (Deterministic and Adaptive Dynamic Event Trees). The main subject of this document is to report the activities that have been done in order to: start the migration of the RAVEN/RELAP-7 control logic system into MOOSE, and develop advanced dynamic sampling capabilities based on the Dynamic Event Tree approach. In order to provide to all MOOSE-based applications a control logic capability, in this Fiscal Year an initial migration activity has been initiated, moving the control logic system, designed for RELAP-7 by the RAVEN team, into the MOOSE framework. In this document, a brief explanation of what has been done is going to be reported. The second and most important subject of this report is about the development of a Dynamic Event Tree (DET) sampler named “Hybrid Dynamic Event Tree” (HDET) and its Adaptive variant “Adaptive Hybrid Dynamic Event Tree” (AHDET). As other authors have already reported, among the different types of uncertainties, it is possible to discern two principle types: aleatory and epistemic uncertainties. The classical Dynamic Event Tree is in charge of treating the first class (aleatory) uncertainties; the dependence of the probabilistic risk assessment and analysis on the epistemic uncertainties are treated by an initial Monte Carlo sampling (MCDET). From each Monte Carlo sample, a DET analysis is run (in total, N trees). The Monte Carlo employs a pre-sampling of the input space characterized by epistemic uncertainties. The consequent Dynamic Event Tree performs the exploration of the aleatory space. In the RAVEN code, a more general approach has been developed, not limiting the exploration of the epistemic space through a Monte Carlo method but using all the forward sampling strategies RAVEN currently employs. The user can combine a Latin Hyper Cube, Grid, Stratified and Monte Carlo sampling in order to explore the epistemic space, without any limitation. From this pre-sampling, the Dynamic Event Tree sampler starts its aleatory space exploration. As reported by the authors, the Dynamic Event Tree is a good fit to develop a goal-oriented sampling strategy. The DET is used to drive a Limit Surface search. The methodology that has been developed by the authors last year, performs a Limit Surface search in the aleatory space only. This report documents how this approach has been extended in order to consider the epistemic space interacting with the Hybrid Dynamic Event Tree methodology.

  14. Automatic UT inspection of economizer at TVA`s Paradise plant

    SciTech Connect (OSTI)

    Brophy, J.W.; Chang, P.

    1995-12-31

    In March 1995, Tennessee Valley Authority (TVA) and Southwest Research Institute (SwRi) conducted testing of a multi-element ultrasonic probe designed to inspect economizer tubing in the Paradise power plant during the spring outage. This evaluation was to determine general loss of wall thickness due to erosion/corrosion and preferential inside diameter (ID) corrosion at butt welds in straight sections of the tube. The erosion/corrosion wall loss occurs during service while the butt weld corrosion occurs out-of-service when water collects in the weld groove during outages and results in localized pitting in the weld groove. The ultrasonic (UT) probe was designed to acquire thickness measurements from the ID of the economizer tubes and to be accurate, very rapid UT inspection. To attain a high rate of speed inside the tubes, an eight-element circular array of transducers were designed into the probe head. Thickness data and location data are collected automatically by a portable computer.

  15. Remedial Design/Remedial Action Work Plan for Operable Units 6-05 and 10-04, Phase IV

    SciTech Connect (OSTI)

    R. P. Wells

    2006-11-14

    This Phase IV Remedial Design/Remedial Action Work Plan addresses the remediation of areas with the potential for UXO at the Idaho National Laboratory. These areas include portions of the Naval Proving Ground, the Arco High-Altitude Bombing Range, and the Twin Buttes Bombing Range. Five areas within the Naval Proving Ground that are known to contain UXO include the Naval Ordnance Disposal Area, the Mass Detonation Area, the Experimental Field Station, The Rail Car Explosion Area, and the Land Mine Fuze Burn Area. The Phase IV remedial action will be concentrated in these five areas. For other areas, such as the Arco High-Altitude Bombing Range and the Twin Buttes Bombing Range, ordnance has largely consisted of sand-filled practice bombs that do not pose an explosion risk. Ordnance encountered in these areas will be addressed under the Phase I Operations and Maintenance Plan that allows for the recovery and disposal of ordnance that poses an imminent risk to human health or the environment.

  16. Development of an advanced process for drying fine coal in an inclined fluidized bed: Technical progress report for the third quarter, April 1, 1989-June 30, 1989

    SciTech Connect (OSTI)

    Boysen, J.E.; Barbour, F.A.; Turner, T.F.; Cha, C.Y.; Berggren, M.H.; Jha, M.C.

    1989-07-01

    This research project is for the development of a technical and economical feasible process for drying and stability fine particles of high-moisture subbituminous coal. Research conducted in this quarter focused upon thermogravimetric analysis (TGA) of both feed coals; continuation of the bench-scale IFB drying experiments; and initiation of the characterization of the products from the bench-scale drying experiments to determine their moisture reabsorption, dustiness, and spontaneous ignition properties. Thirty 4-hr and six 12-hr bench-scale IFB drying tests were conducted this quarter making a total of forty-one 4-hr (19 using Eagle Butte feed coal and 22 using Usibelli feed coal) and six 12-hr (3 using each feed coal) tests conducted thus far. IFB reactor slopes of 3, 6, 9, 12, and 15 degrees were investigated for each feed coal. During the tests using Eagle Butte coal, gas-to-solids ratios ranging from approximately 0.7 to 9.7 lb/lb (kg/kg) and average IFB reactor temperatures ranging from approximately 370 to 700/degree/F (188 to 371/degree/C) were tested. 5 refs., 41 figs., 7 tabs.

  17. Laser-ultrasonic inspection of hybrid laser-arc welded HSLA-65 steel

    SciTech Connect (OSTI)

    Lvesque, D.; Rousseau, G.; Monchalin, J.-P. [National Research Council Canada, Boucherville, QC (Canada); Wanjara, P.; Cao, X. [National Research Council Canada, Montreal, QC (Canada)

    2014-02-18

    The hybrid laser-arc welding (HLAW) process is a relatively low heat input joining technology that combines the synergistic qualities of both the high energy density laser beam for deep penetration and the arc for wide fit-up gap tolerance. This process is especially suitable for the shipbuilding industry where thick-gauge section, long steel plates have been widely used in a butt joint configuration. In this study, preliminary exploration was carried out to detect and visualize the welding defects using laser ultrasonics combined with the synthetic aperture focusing technique (SAFT). Results obtained on 9.3 mm thick butt-welded HSLA-65 steel plates indicated that the laser-ultrasonic SAFT inspection technique can successfully detect and visualize the presence of porosity, lack of fusion and internal crack defects. This was further confirmed by X-ray digital radiography and metallography. The results obtained clearly show the potential of using the laser-ultrasonic technology for the automated inspection of hybrid laser-arc welds.

  18. The Calculated and Measured Resistance for Splices between Conductors in a MICE Superconducting Coil

    SciTech Connect (OSTI)

    Green, Michael A.; Dietderich, Dan; Higley, Hugh; Pan, Heng; Tam, Darren; Trillaud, Federic; Wang, Li; Wu, Hong; Xu, Feng Yu

    2009-03-19

    The resistance of superconducting joints within MICE coils is an important issue particularly for the coupling coils. The MICE tracker solenoids have only two superconducting joints in the three spectrometer set (end coil 1, the center coil and end coil 2). The AFC magnets may have only a single joint within the coil. The coupling coils may have as many as fifteen joints within the coil, due to relatively short piece lengths of the superconductor. LBNL and ICST looked at three types of coil joints. They are: (1) cold fusion butt joints, (2) side-by-side lap joints, and (3) up-down lap joints. A theoretical calculation of the joint resistance was done at LBNL and checked by ICST. After looking at the theoretical resistance of the three types of joints, it was decided that the cold welded butt joint was not an attractive alternative for joints within a MICE superconducting magnet coil. Side-by-side and up-down lap joints were fabricated at ICST using two types of soft solder between the conductors. These conductor joints were tested at LBNL at liquid helium temperatures over a range of magnetic fields. The joint resistance was compared with the theoretical calculations. Measurements of splice strength were also made at 300 K and 77 K.

  19. RELAP-7 Development Updates

    SciTech Connect (OSTI)

    Zhang, Hongbin; Zhao, Haihua; Gleicher, Frederick Nathan; DeHart, Mark David; Zou, Ling; Andrs, David; Martineau, Richard Charles

    2015-09-01

    RELAP-7 is a nuclear systems safety analysis code being developed at the Idaho National Laboratory, and is the next generation tool in the RELAP reactor safety/systems analysis application series. RELAP-7 development began in 2011 to support the Risk Informed Safety Margins Characterization (RISMC) Pathway of the Light Water Reactor Sustainability (LWRS) program. The overall design goal of RELAP-7 is to take advantage of the previous thirty years of advancements in computer architecture, software design, numerical methods, and physical models in order to provide capabilities needed for the RISMC methodology and to support nuclear power safety analysis. The code is being developed based on Idaho National Laboratory’s modern scientific software development framework – MOOSE (the Multi-Physics Object-Oriented Simulation Environment). The initial development goal of the RELAP-7 approach focused primarily on the development of an implicit algorithm capable of strong (nonlinear) coupling of the dependent hydrodynamic variables contained in the 1-D/2-D flow models with the various 0-D system reactor components that compose various boiling water reactor (BWR) and pressurized water reactor nuclear power plants (NPPs). During Fiscal Year (FY) 2015, the RELAP-7 code has been further improved with expanded capability to support boiling water reactor (BWR) and pressurized water reactor NPPs analysis. The accumulator model has been developed. The code has also been coupled with other MOOSE-based applications such as neutronics code RattleSnake and fuel performance code BISON to perform multiphysics analysis. A major design requirement for the implicit algorithm in RELAP-7 is that it is capable of second-order discretization accuracy in both space and time, which eliminates the traditional first-order approximation errors. The second-order temporal is achieved by a second-order backward temporal difference, and the one-dimensional second-order accurate spatial discretization is achieved with the Galerkin approximation of Lagrange finite elements. During FY-2015, we have done numerical verification work to verify that the RELAP-7 code indeed achieves 2nd-order accuracy in both time and space for single phase models at the system level.

  20. Synchrotron characterization of nanograined UO2 grain growth

    SciTech Connect (OSTI)

    Mo, Kun; Miao, Yinbin; Yun, Di; Jamison, Laura M.; Lian, Jie; Yao, Tiankei

    2015-09-30

    This activity is supported by the US Nuclear Energy Advanced Modeling and Simulation (NEAMS) Fuels Product Line (FPL) and aims at providing experimental data for the validation of the mesoscale simulation code MARMOT. MARMOT is a mesoscale multiphysics code that predicts the coevolution of microstructure and properties within reactor fuel during its lifetime in the reactor. It is an important component of the Moose-Bison-Marmot (MBM) code suite that has been developed by Idaho National Laboratory (INL) to enable next generation fuel performance modeling capability as part of the NEAMS Program FPL. In order to ensure the accuracy of the microstructure based materials models being developed within the MARMOT code, extensive validation efforts must be carried out. In this report, we summarize our preliminary synchrotron radiation experiments at APS to determine the grain size of nanograin UO2. The methodology and experimental setup developed in this experiment can directly apply to the proposed in-situ grain growth measurements. The investigation of the grain growth kinetics was conducted based on isothermal annealing and grain growth characterization as functions of duration and temperature. The kinetic parameters such as activation energy for grain growth for UO2 with different stoichiometry are obtained and compared with molecular dynamics (MD) simulations.

  1. Supplying materials needed for grain growth characterizations of nano-grained UO2

    SciTech Connect (OSTI)

    Mo, Kun; Miao, Yinbin; Yun, Di; Jamison, Laura M.; Lian, Jie; Yao, Tiankei

    2015-09-30

    This activity is supported by the US Nuclear Energy Advanced Modeling and Simulation (NEAMS) Fuels Product Line (FPL) and aims at providing experimental data for the validation of the mesoscale simulation code MARMOT. MARMOT is a mesoscale multiphysics code that predicts the coevolution of microstructure and properties within reactor fuel during its lifetime in the reactor. It is an important component of the Moose-Bison-Marmot (MBM) code suite that has been developed by Idaho National Laboratory (INL) to enable next generation fuel performance modeling capability as part of the NEAMS Program FPL. In order to ensure the accuracy of the microstructure based materials models being developed within the MARMOT code, extensive validation efforts must be carried out. In this report, we summarize our preliminary synchrotron radiation experiments at APS to determine the grain size of nanograin UO2. The methodology and experimental setup developed in this experiment can directly apply to the proposed in-situ grain growth measurements. The investigation of the grain growth kinetics was conducted based on isothermal annealing and grain growth characterization as functions of duration and temperature. The kinetic parameters such as activation energy for grain growth for UO2 with different stoichiometry are obtained and compared with molecular dynamics (MD) simulations.

  2. Advanced Pellet Cladding Interaction Modeling Using the US DOE CASL Fuel Performance Code: Peregrine

    SciTech Connect (OSTI)

    Jason Hales; Various

    2014-06-01

    The US DOEs Consortium for Advanced Simulation of LWRs (CASL) program has undertaken an effort to enhance and develop modeling and simulation tools for a virtual reactor application, including high fidelity neutronics, fluid flow/thermal hydraulics, and fuel and material behavior. The fuel performance analysis efforts aim to provide 3-dimensional capabilities for single and multiple rods to assess safety margins and the impact of plant operation and fuel rod design on the fuel thermomechanical- chemical behavior, including Pellet-Cladding Interaction (PCI) failures and CRUD-Induced Localized Corrosion (CILC) failures in PWRs. [1-3] The CASL fuel performance code, Peregrine, is an engineering scale code that is built upon the MOOSE/ELK/FOX computational FEM framework, which is also common to the fuel modeling framework, BISON [4,5]. Peregrine uses both 2-D and 3-D geometric fuel rod representations and contains a materials properties and fuel behavior model library for the UO2 and Zircaloy system common to PWR fuel derived from both open literature sources and the FALCON code [6]. The primary purpose of Peregrine is to accurately calculate the thermal, mechanical, and chemical processes active throughout a single fuel rod during operation in a reactor, for both steady state and off-normal conditions.

  3. Physics-based multiscale coupling for full core nuclear reactor simulation

    SciTech Connect (OSTI)

    Gaston, Derek R.; Permann, Cody J.; Peterson, John W.; Slaughter, Andrew E.; Andrš, David; Wang, Yaqi; Short, Michael P.; Perez, Danielle M.; Tonks, Michael R.; Ortensi, Javier; Zou, Ling; Martineau, Richard C.

    2015-10-01

    Numerical simulation of nuclear reactors is a key technology in the quest for improvements in efficiency, safety, and reliability of both existing and future reactor designs. Historically, simulation of an entire reactor was accomplished by linking together multiple existing codes that each simulated a subset of the relevant multiphysics phenomena. Recent advances in the MOOSE (Multiphysics Object Oriented Simulation Environment) framework have enabled a new approach: multiple domain-specific applications, all built on the same software framework, are efficiently linked to create a cohesive application. This is accomplished with a flexible coupling capability that allows for a variety of different data exchanges to occur simultaneously on high performance parallel computational hardware. Examples based on the KAIST-3A benchmark core, as well as a simplified Westinghouse AP-1000 configuration, demonstrate the power of this new framework for tackling—in a coupled, multiscale manner—crucial reactor phenomena such as CRUD-induced power shift and fuel shuffle. 2014 The Authors. Published by Elsevier Ltd. This is an open access article under the CC BY-NC-SA license

  4. Status Report on NEAMS System Analysis Module Development

    SciTech Connect (OSTI)

    Hu, R.; Fanning, T. H.; Sumner, T.; Yu, Y.

    2015-12-01

    Under the Reactor Product Line (RPL) of DOE-NE’s Nuclear Energy Advanced Modeling and Simulation (NEAMS) program, an advanced SFR System Analysis Module (SAM) is being developed at Argonne National Laboratory. The goal of the SAM development is to provide fast-running, improved-fidelity, whole-plant transient analyses capabilities. SAM utilizes an object-oriented application framework MOOSE), and its underlying meshing and finite-element library libMesh, as well as linear and non-linear solvers PETSc, to leverage modern advanced software environments and numerical methods. It also incorporates advances in physical and empirical models and seeks closure models based on information from high-fidelity simulations and experiments. This report provides an update on the SAM development, and summarizes the activities performed in FY15 and the first quarter of FY16. The tasks include: (1) implement the support of 2nd-order finite elements in SAM components for improved accuracy and computational efficiency; (2) improve the conjugate heat transfer modeling and develop pseudo 3-D full-core reactor heat transfer capabilities; (3) perform verification and validation tests as well as demonstration simulations; (4) develop the coupling requirements for SAS4A/SASSYS-1 and SAM integration.

  5. An Update on NiCE Support for BISON

    SciTech Connect (OSTI)

    McCaskey, Alex; Billings, Jay Jay; Deyton, Jordan H.; Wojtowicz, Anna

    2015-09-01

    The Nuclear Energy Advanced Modeling and Simulation program (NEAMS) from the Department of Energy s Office of Nuclear Energy has funded the development of a modeling and simulation workflow environment to support the various codes in its nuclear energy scientific computing toolkit. This NEAMS Integrated Computational Environment (NiCE) provides extensible tools and services that enable efficient code execution, input generation, pre-processing visualizations, and post-simulation data analysis and visualization for a large portion of the NEAMS Toolkit. A strong focus for the NiCE development team throughout FY 2015 has been support for the Multiphysics Object Oriented Simulation Environment (MOOSE) and the NEAMS nuclear fuel performance modeling application built on that environment, BISON. There is a strong desire in the program to enable and facilitate the use of BISON throughout nuclear energy research and industry. A primary result of this desire is the need for strong support for BISON in NiCE. This report will detail improvements to NiCE support for BISON. We will present a new and improved interface for interacting with BISON simulations in a variety of ways: (1) improved input model generation, (2) embedded mesh and solution data visualizations, and (3) local and remote BISON simulation launch. We will also show how NiCE has been extended to provide support for BISON code development.

  6. Initial RattleSnake Calculations of the Hot Zero Power BEAVRS

    SciTech Connect (OSTI)

    M. Ellis; J. Ortensi; Y. Wang; K. Smith; R.C. Martineau

    2014-01-01

    The validation of the Idaho National Laboratory's next generation of reactor physics analysis codes is an essential and ongoing task. The validation process requires a large undertaking and includes detailed, realistic models that can accurately predict the behavior of an operational nuclear reactor. Over the past few years the INL has developed the RattleSnake application and supporting tools on the MOOSE framework to perform these reactor physics calculations. RattleSnake solves the linearized Boltzmann transport equation with a variety of solution meth­ ods. Various traditional reactor physics benchmarks have already been performed, but a more realistic light water reactor comparison was needed to solidify the status of the code and deter­ mine its fidelity. The INL team decided to use the Benchmark for Evaluation and Validation of Reactor Simulations, which was made available in early 2013. This benchmark is a one­ of-a-kind document assembled by the Massachusetts Institute of Technology, which includes two cycles of detailed, measured PWR operational data. The results from this initial study of the hot zero power conditions show the current INL analysis procedure with DRAGON4 cross section preparation and using the low order diffusion solver in RattleSnake for the whole core calculations yield very encouraging results for PWR analysis. The radial assembly power distributions, radial detector measurements and control rod worths were computed with good accuracy. The computation of the isothermal temperature coefficients of reactivity require further study.

  7. Nonlinear diffusion acceleration for the multigroup transport equation discretized with S{sub N} and continuous FEM with rattlesnake

    SciTech Connect (OSTI)

    Wang, Y.

    2013-07-01

    Nonlinear diffusion acceleration (NDA) can improve the performance of a neutron transport solver significantly especially for the multigroup eigenvalue problems. The high-order transport equation and the transport-corrected low-order diffusion equation form a nonlinear system in NDA, which can be solved via a Picard iteration. The consistency of the correction of the low-order equation is important to ensure the stabilization and effectiveness of the iteration. It also makes the low-order equation preserve the scalar flux of the high-order equation. In this paper, the consistent correction for a particular discretization scheme, self-adjoint angular flux (SAAF) formulation with discrete ordinates method (S{sub N}) and continuous finite element method (CFEM) is proposed for the multigroup neutron transport equation. Equations with the anisotropic scatterings and a void treatment are included. The Picard iteration with this scheme has been implemented and tested with RattleS{sub N}ake, a MOOSE-based application at INL. Convergence results are presented. (authors)

  8. Proof-of-Concept Demonstrations for Computation-Based Human Reliability Analysis. Modeling Operator Performance During Flooding Scenarios

    SciTech Connect (OSTI)

    Joe, Jeffrey Clark; Boring, Ronald Laurids; Herberger, Sarah Elizabeth Marie; Mandelli, Diego; Smith, Curtis Lee

    2015-09-01

    The United States (U.S.) Department of Energy (DOE) Light Water Reactor Sustainability (LWRS) program has the overall objective to help sustain the existing commercial nuclear power plants (NPPs). To accomplish this program objective, there are multiple LWRS “pathways,” or research and development (R&D) focus areas. One LWRS focus area is called the Risk-Informed Safety Margin and Characterization (RISMC) pathway. Initial efforts under this pathway to combine probabilistic and plant multi-physics models to quantify safety margins and support business decisions also included HRA, but in a somewhat simplified manner. HRA experts at Idaho National Laboratory (INL) have been collaborating with other experts to develop a computational HRA approach, called the Human Unimodel for Nuclear Technology to Enhance Reliability (HUNTER), for inclusion into the RISMC framework. The basic premise of this research is to leverage applicable computational techniques, namely simulation and modeling, to develop and then, using RAVEN as a controller, seamlessly integrate virtual operator models (HUNTER) with 1) the dynamic computational MOOSE runtime environment that includes a full-scope plant model, and 2) the RISMC framework PRA models already in use. The HUNTER computational HRA approach is a hybrid approach that leverages past work from cognitive psychology, human performance modeling, and HRA, but it is also a significant departure from existing static and even dynamic HRA methods. This report is divided into five chapters that cover the development of an external flooding event test case and associated statistical modeling considerations.

  9. Physics-based multiscale coupling for full core nuclear reactor simulation

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Gaston, Derek R.; Permann, Cody J.; Peterson, John W.; Slaughter, Andrew E.; Andrš, David; Wang, Yaqi; Short, Michael P.; Perez, Danielle M.; Tonks, Michael R.; Ortensi, Javier; et al

    2015-10-01

    Numerical simulation of nuclear reactors is a key technology in the quest for improvements in efficiency, safety, and reliability of both existing and future reactor designs. Historically, simulation of an entire reactor was accomplished by linking together multiple existing codes that each simulated a subset of the relevant multiphysics phenomena. Recent advances in the MOOSE (Multiphysics Object Oriented Simulation Environment) framework have enabled a new approach: multiple domain-specific applications, all built on the same software framework, are efficiently linked to create a cohesive application. This is accomplished with a flexible coupling capability that allows for a variety of different datamore » exchanges to occur simultaneously on high performance parallel computational hardware. Examples based on the KAIST-3A benchmark core, as well as a simplified Westinghouse AP-1000 configuration, demonstrate the power of this new framework for tackling—in a coupled, multiscale manner—crucial reactor phenomena such as CRUD-induced power shift and fuel shuffle. 2014 The Authors. Published by Elsevier Ltd. This is an open access article under the CC BY-NC-SA license« less

  10. Fracturing And Liquid CONvection

    Energy Science and Technology Software Center (OSTI)

    2012-02-29

    FALCON has been developed to enable simulation of the tightly coupled fluid-rock behavior in hydrothermal and engineered geothermal system (EGS) reservoirs, targeting the dynamics of fracture stimulation, fluid flow, rock deformation, and heat transport in a single integrated code, with the ultimate goal of providing a tool that can be used to test the viability of EGS in the United States and worldwide. Reliable reservoir performance predictions of EGS systems require accurate and robust modelingmore » for the coupled thermal-hydrological-mechanical processes. Conventionally, these types of problems are solved using operator-splitting methods, usually by coupling a subsurface flow and heat transport simulator with a solid mechanics simulator via input files. FALCON eliminates the need for using operator-splitting methods to simulate these systems, and the scalability of the underlying MOOSE architecture allows for simulating these tightly coupled processes at the reservoir scale, allowing for examination of the system as a whole (something the operator-splitting methodologies generally cannot do).« less

  11. Pentek concrete scabbling system: Baseline report; Greenbook (chapter)

    SciTech Connect (OSTI)

    1997-07-31

    The Pentek scabbling technology was tested at Florida International University (FIU) and is being evaluated as a baseline technology. This report evaluates it for safety and health issues. It is a commercially available technology and has been used for various projects at locations throughout the country. The Pentek concrete scabbling system consisted of the MOOSE, SQUIRREL-I, and SQUIRREL-III scabblers. The scabblers are designed to scarify concrete floors and slabs using cross-section, tungsten carbide tipped bits. The bits are designed to remove concrete in 318 inch increments. The bits are either 9-tooth or demolition type. The scabblers are used with a vacuum system designed to collect and filter the concrete dust and contamination that is removed from the surface. The safety and health evaluation conducted during the testing demonstration focused on two main areas of exposure: dust and noise. Dust exposure was minimal, but noise exposure was significant. Further testing for each of these exposures is recommended. Because of the outdoor environment where the testing demonstration took place, results may be inaccurate. It is feasible that the dust and noise levels will be higher in an enclosed operating environment. Other areas of concern were arm-hand vibration, whole-body vibration, ergonomics, heat stress, tripping hazards, electrical hazards, machine guarding, and lockout/tagout.

  12. LIGHT WATER REACTOR ACCIDENT TOLERANT FUELS IRRADIATION TESTING

    SciTech Connect (OSTI)

    Carmack, William Jonathan; Barrett, Kristine Eloise; Chichester, Heather Jean MacLean

    2015-09-01

    The purpose of Accident Tolerant Fuels (ATF) experiments is to test novel fuel and cladding concepts designed to replace the current zirconium alloy uranium dioxide (UO2) fuel system. The objective of this Research and Development (R&D) is to develop novel ATF concepts that will be able to withstand loss of active cooling in the reactor core for a considerably longer time period than the current fuel system while maintaining or improving the fuel performance during normal operations, operational transients, design basis, and beyond design basis events. It was necessary to design, analyze, and fabricate drop-in capsules to meet the requirements for testing under prototypic LWR temperatures in Idaho National Laboratory's Advanced Test Reactor (ATR). Three industry led teams and one DOE team from Oak Ridge National Laboratory provided fuel rodlet samples for their new concepts for ATR insertion in 2015. As-built projected temperature calculations were performed on the ATF capsules using the BISON fuel performance code. BISON is an application of INL’s Multi-physics Object Oriented Simulation Environment (MOOSE), which is a massively parallel finite element based framework used to solve systems of fully coupled nonlinear partial differential equations. Both 2D and 3D models were set up to examine cladding and fuel performance.

  13. RELAP-7 Numerical Stabilization: Entropy Viscosity Method

    SciTech Connect (OSTI)

    R. A. Berry; M. O. Delchini; J. Ragusa

    2014-06-01

    The RELAP-7 code is the next generation nuclear reactor system safety analysis code being developed at the Idaho National Laboratory (INL). The code is based on the INL's modern scientific software development framework, MOOSE (Multi-Physics Object Oriented Simulation Environment). The overall design goal of RELAP-7 is to take advantage of the previous thirty years of advancements in computer architecture, software design, numerical integration methods, and physical models. The end result will be a reactor systems analysis capability that retains and improves upon RELAP5's capability and extends the analysis capability for all reactor system simulation scenarios. RELAP-7 utilizes a single phase and a novel seven-equation two-phase flow models as described in the RELAP-7 Theory Manual (INL/EXT-14-31366). The basic equation systems are hyperbolic, which generally require some type of stabilization (or artificial viscosity) to capture nonlinear discontinuities and to suppress advection-caused oscillations. This report documents one of the available options for this stabilization in RELAP-7 -- a new and novel approach known as the entropy viscosity method. Because the code is an ongoing development effort in which the physical sub models, numerics, and coding are evolving, so too must the specific details of the entropy viscosity stabilization method. Here the fundamentals of the method in their current state are presented.

  14. FASTGRASS implementation in BISON and Fission gas behavior characterization in UO2 and connection to validating MARMOT

    SciTech Connect (OSTI)

    Yun, Di; Mo, Kun; Ye, Bei; Jamison, Laura M.; Miao, Yinbin; Lian, Jie; Yao, Tiankei

    2015-09-30

    This activity is supported by the US Nuclear Energy Advanced Modeling and Simulation (NEAMS) Fuels Product Line (FPL). Two major accomplishments in FY 15 are summarized in this report: (1) implementation of the FASTGRASS module in the BISON code; and (2) a Xe implantation experiment for large-grained UO2. Both BISON AND MARMOT codes have been developed by Idaho National Laboratory (INL) to enable next generation fuel performance modeling capability as part of the NEAMS Program FPL. To contribute to the development of the Moose-Bison-Marmot (MBM) code suite, we have implemented the FASTGRASS fission gas model as a module in the BISON code. Based on rate theory formulations, the coupled FASTGRASS module in BISON is capable of modeling LWR oxide fuel fission gas behavior and fission gas release. In addition, we conducted a Xe implantation experiment at the Argonne Tandem Linac Accelerator System (ATLAS) in order to produce the needed UO2 samples with desired bubble morphology. With these samples, further experiments to study the fission gas diffusivity are planned to provide validation data for the Fission Gas Release Model in MARMOT codes.

  15. WHERE MULTIFUNCTIONAL DNA REPAIR PROTEINS MEET: MAPPING THE INTERACTION DOMAINS BETWEEN XPG AND WRN

    SciTech Connect (OSTI)

    Rangaraj, K.; Cooper, P.K.; Trego, K.S.

    2009-01-01

    The rapid recognition and repair of DNA damage is essential for the maintenance of genomic integrity and cellular survival. Multiple complex and interconnected DNA damage responses exist within cells to preserve the human genome, and these repair pathways are carried out by a specifi c interplay of protein-protein interactions. Thus a failure in the coordination of these processes, perhaps brought about by a breakdown in any one multifunctional repair protein, can lead to genomic instability, developmental and immunological abnormalities, cancer and premature aging. This study demonstrates a novel interaction between two such repair proteins, Xeroderma pigmentosum group G protein (XPG) and Werner syndrome helicase (WRN), that are both highly pleiotropic and associated with inherited genetic disorders when mutated. XPG is a structure-specifi c endonuclease required for the repair of UV-damaged DNA by nucleotide excision repair (NER), and mutations in XPG result in the diseases Xeroderma pigmentosum (XP) and Cockayne syndrome (CS). A loss of XPG incision activity results in XP, whereas a loss of non-enzymatic function(s) of XPG causes CS. WRN is a multifunctional protein involved in double-strand break repair (DSBR), and consists of 3’–5’ DNA-dependent helicase, 3’–5’ exonuclease, and single-strand DNA annealing activities. Nonfunctional WRN protein leads to Werner syndrome, a premature aging disorder with increased cancer incidence. Far Western analysis was used to map the interacting domains between XPG and WRN by denaturing gel electrophoresis, which separated purifi ed full length and recombinant XPG and WRN deletion constructs, based primarily upon the length of each polypeptide. Specifi c interacting domains were visualized when probed with the secondary protein of interest which was then detected by traditional Western analysis using the antibody of the secondary protein. The interaction between XPG and WRN was mapped to the C-terminal region of XPG as well as the C-terminal region of WRN. The physical interaction between XPG and WRN links NER, (made evident by the disease XP) with DSBR, which imparts additional knowledge of the overlapping nature of these two proteins and the previously distinct DNA repair pathways they are associated with. Since genomic integrity is constantly threatened by both endogenous and exogenous (internal and external) damage, understanding the roles of these proteins in coordinating DNA repair processes with replication will signifi cantly further understanding how defects instigate physiological consequences in response to various DNA damaging sources. This ultimately contributes to our understanding of cancer and premature aging.

  16. Joining SI3N4 for Advanced Turbomachinery Applications

    SciTech Connect (OSTI)

    GLASS, S. JILL; LOEHMAN, RONALD E.; HOSKING, F. MICHAEL; STEPHENS JR., JOHN J.; VIANCO, PAUL T.; NEILSEN, MICHAEL K.; WALKER, CHARLES A.; POLLINGER, J.P.; MAHONEY, F.M.; QUILLEN, B.G.

    2000-07-01

    The main objective of this project was to develop reliable, low-cost techniques for joining silicon nitride (Si{sub 3}N{sub 4}) to itself and to metals. For Si{sub 3}N{sub 4} to be widely used in advanced turbomachinery applications, joining techniques must be developed that are reliable, cost-effective, and manufacturable. This project addressed those needs by developing and testing two Si{sub 3}N{sub 4} joining systems; oxynitride glass joining materials and high temperature braze alloys. Extensive measurements were also made of the mechanical properties and oxidation resistance of the braze materials. Finite element models were used to predict the magnitudes and positions of the stresses in the ceramic regions of ceramic-to-metal joints sleeve and butt joints, similar to the geometries used for stator assemblies.

  17. 3D Model of the Neal Hot Springs Geothermal Area

    DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

    Faulds, James E.

    The Neal Hot Springs geothermal system lies in a left-step in a north-striking, west-dipping normal fault system, consisting of the Neal Fault to the south and the Sugarloaf Butte Fault to the north (Edwards, 2013). The Neal Hot Springs 3D geologic model consists of 104 faults and 13 stratigraphic units. The stratigraphy is sub-horizontal to dipping <10 degrees and there is no predominant dip-direction. Geothermal production is exclusively from the Neal Fault south of, and within the step-over, while geothermal injection is into both the Neal Fault to the south of the step-over and faults within the step-over.

  18. 3D Model of the Neal Hot Springs Geothermal Area

    SciTech Connect (OSTI)

    Faulds, James E.

    2013-12-31

    The Neal Hot Springs geothermal system lies in a left-step in a north-striking, west-dipping normal fault system, consisting of the Neal Fault to the south and the Sugarloaf Butte Fault to the north (Edwards, 2013). The Neal Hot Springs 3D geologic model consists of 104 faults and 13 stratigraphic units. The stratigraphy is sub-horizontal to dipping <10 degrees and there is no predominant dip-direction. Geothermal production is exclusively from the Neal Fault south of, and within the step-over, while geothermal injection is into both the Neal Fault to the south of the step-over and faults within the step-over.

  19. Diode laser welding of aluminum to steel

    SciTech Connect (OSTI)

    Santo, Loredana; Quadrini, Fabrizio; Trovalusci, Federica [University of Rome Tor Vergata, Department of Mechanical Engineering, Via del Politecnico 1, 00133 Rome (Italy)

    2011-05-04

    Laser welding of dissimilar materials was carried out by using a high power diode laser to join aluminum to steel in a butt-joint configuration. During testing, the laser scan rate was changed as well as the laser power: at low values of fluence (i.e. the ratio between laser power and scan rate), poor joining was observed; instead at high values of fluence, an excess in the material melting affected the joint integrity. Between these limiting values, a good aesthetics was obtained; further investigations were carried out by means of tensile tests and SEM analyses. Unfortunately, a brittle behavior was observed for all the joints and a maximum rupture stress about 40 MPa was measured. Apart from the formation of intermeltallic phases, poor mechanical performances also depended on the chosen joining configuration, particularly because of the thickness reduction of the seam in comparison with the base material.

  20. Central Facilities Area Sewage Lagoon Evaluation

    SciTech Connect (OSTI)

    Giesbrecht, Alan

    2015-03-01

    The Central Facilities Area (CFA) located in Butte County, Idaho at Idaho National Laboratory (INL) has an existing wastewater system to collect and treat sanitary wastewater and non contact cooling water from the facility. The existing treatment facility consists of three cells: Cell 1 has a surface area of 1.7 acres, Cell 2 has a surface area of 10.3 acres, and Cell 3 has a surface area of 0.5 acres. If flows exceed the evaporative capacity of the cells, wastewater is discharged to a 73.5 acre land application site that utilizes a center pivot irrigation sprinkler system. The purpose of this current study is to update the analysis and conclusions of the December 2013 study. In this current study, the new seepage rate and influent flow rate data have been used to update the calculations, model, and analysis.

  1. Field Sampling Plan for the Operable Units 6-05 and 10-04 Remedial Action, Phase IV

    SciTech Connect (OSTI)

    R. Wells

    2006-11-14

    This Field Sampling Plan outlines the collection and analysis of samples in support of Phase IV of the Waste Area Group 10, Operable Units 6-05 and 10-04 remedial action. Phase IV addresses the remedial actions to areas with the potential for unexploded ordnance at the Idaho National Laboratory Site. These areas include portions of the Naval Proving Ground, the Arco High-Altitude Bombing Range, and the Twin Buttes Bombing Range. The remedial action consists of removal and disposal of ordnance by high-order detonation, followed by sampling to determine the extent, if any, of soil that might have been contaminated by the detonation activities associated with the disposal of ordnance during the Phase IV activities and explosives during the Phase II activities.

  2. 2012 - 05 | Jefferson Lab

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    5 May 2012 Thu, 2012-05-31 15:00 Call for Preliminary LDRD Letters of Intent (LOI) Thu, 2012-05-31 15:00 Reminder: Proper Work Clothing Required During Long Shutdown Thu, 2012-05-31 15:00 JLab Celebrates 6 GeV End of an Era on June 6 Thu, 2012-05-31 15:00 Cigarette Butt Causes Fire Outside of CEBAF Center Wed, 2012-05-23 15:00 Jefferson Lab Unveils New Emergency Management Webpage Tue, 2012-05-22 15:00 New JLab Requirement for SAF100 - ES&H Orientation Training Sat, 2012-05-12 15:00 Survey

  3. MHD generator component development. Quarterly report, July 1983-September 1983

    SciTech Connect (OSTI)

    Not Available

    1983-11-01

    The overall objectives of this program are two-fold: (1) To contribute, by appropriate systematic experimental and analytical investigations, to the engineering data base necessary for the design and construction of MHD generators at CDIF-scale (50 MW/sub th/) and baseload scale (2000 MW/sub th/). (2) To design and fabricate specific hardware items to be tested at the CDIF site in Butte, Montana. The program consists of a series of related tasks: (1) MHD channel design and performance; (2) MHD channel construction and lifetime; (3) MHD channel loading and control; (4) facility operation; (5) CDIF related hardware; and (6) high interaction tests of a supersonic channel. Progress is reported. (WHK)

  4. Repository site definition in basalt: Pasco Basin, Washington

    SciTech Connect (OSTI)

    Guzowski, R.V.; Nimick, F.B.; Muller, A.B.

    1982-03-01

    Discussion of the regional setting, geology, hydrology, and geochemistry of the Pasco Basin are included in this report. Pasco basin is a structural and topographic basin of approximately 2000 mi/sup 2/ (5180 km/sup 2/) located within the Yakima Fold Belt Subprovince of the Columbia Plateau. The stratigraphic sequence within the basin consists of an undetermined thickness of lower Miocene and younger flood basalts with interbedded and overlying sedimentary units. This sequence rests upon a basement of probably diverse rock types that may range in age from precambrian through early Tertiary. Although a large amount of information is available on the hydrology of the unconfined aquifer system, ground-water flow within the basin is, in general, poorly understood. Recharge areas for the Mabton interbed and the Saddle Mountains Formation are the highlands surrounding the basin with the flow for these units toward Gable Butte - Gable Mountain and Lake Wallula. Gable Butte - Gable Mountain probably is a ground-water sink, although the vertical flow direction in this zone is uncertain. The amount of upward vertical leakage from the Saddle Mountains Formation into the overlying sediments or to the Columbia River is unknown. Units underlying the Mabton interbed may have a flow scheme similar to those higher units or a flow scheme dominated by interbasin flow. Upward vertical leakage either throughout the basin, dominantly to the Columbia River, or dominantly to Lake Wallula has been proposed for the discharge of the lower units. None of these proposals is verified. The lateral and vertical distribution of major and minor ions in solution, Eh and pH, and ion exchange between basalt and ground-water are not well defined for the basin. Changes in the redox potential from the level of the subsurface facility to the higher stratigraphic levels along with the numerous other factors influencing K/sub d/, result in a poor understanding of the retardation process.

  5. Green River Formation water flood demonstration project. Report for the period October 1992--March 1994

    SciTech Connect (OSTI)

    Pennington, B.I.; Lomax, J.D.; Neilson, D.L.; Deo, M.D.

    1994-12-01

    The current project targeted three fluvial deltaic reservoirs in the Uinta Basin, Utah. In primary recovery, the performance of the Monument Butte unit was typical of an undersaturated reservoir whose initial pressure was close to the bubble point pressure. The unit was producing at a rate of 40 stb/day when the water flood was initiated. The unit has been producing at more than 300 stb/day for the past four years. The reservoir characteristics of Monument Butte were established in the geologic characterization study. The reservoir fluid properties were measured in the engineering study. Results of a comprehensive reservoir simulation study using these characteristics provided excellent match with the field production data. Extended predictions using the model showed that it would be possible to recover a total of 20--25% of the oil in place. In the Travis unit, logs from the newly drilled 14a-28 showed extensively fractured zones. A new reservoir was discovered and developed on the basis of the information provided by the formation micro imaging logs. This reservoir also behaved in a manner similar to undersaturated reservoirs with initial reservoir pressures close to the reservoir fluid bubble point. The water flood activity was enhanced in the Travis unit. Even through the reservoir continued to be gradually pressurized, the water flood in the Travis unit appeared to be significantly affected by existing or created fractures. A dual-porosity, dual permeability reservoir model provided a good match with the primary production history. The well drilled in the Boundary unit did not intersect any producible zones, once again illustrating the unique challenges to developing fluvial deltaic reservoirs.

  6. Inspection of Fusion Joints in Plastic Pipe

    SciTech Connect (OSTI)

    Connie Reichert

    2005-09-01

    The standard method of joining plastic pipe in the field is the butt fusion process. As in any pipeline application, joint quality greatly affects overall operational safety of the system. Currently no simple, reliable, cost-effective method exists for assessing the quality of fusion joints in the field. Visual examination and pressure testing are current nondestructive approaches, which do not provide any assurance about the long-term pipeline performance. This project developed, demonstrated, and validated an in-situ nondestructive inspection method for butt fusion joints in gas distribution plastic pipelines. The inspection system includes a laser-based image-recognition system that automatically generates and interprets digital images of pipe joints and assigns them a pass/fail rating, which eliminates operator bias in evaluating joint quality. An EWI-patented process, the Weld Zone Inspection Method (WZIM) was developed in which local heat is applied to the joint region to relax the residual stresses formed by the original joining operation, which reveals the surface condition of the joint. In cases where the joint is not formed under optimal conditions, and the intermolecular forces between contacting surfaces are not strong enough, the relaxation of macromolecules in the surface layer causes the material to pull back, revealing a fusion line. If the joint is sound, the bond line image does not develop. To establish initial feasibility of the approach, welds were performed under standard and nonstandard conditions. These welds were subjected to the WZIM and two destructive forms of testing: short-term tensile testing and long-term creep rupture testing. There appears to be a direct correlation between the WZIM and the destructive testing results. Although WZIM appears to be more sensitive than destructive testing can verify, the approach appears valid.

  7. Oil Recovery Increases by Low-Salinity Flooding: Minnelusa and Green River Formations

    SciTech Connect (OSTI)

    Eric P. Robertson

    2010-09-01

    Waterflooding is by far the most widely used method in the world to increase oil recovery. Historically, little consideration has been given in reservoir engineering practice to the effect of injection brine composition on waterflood displacement efficiency or to the possibility of increased oil recovery through manipulation of the composition of the injected water. However, recent work has shown that oil recovery can be significantly increased by modifying the injection brine chemistry or by injecting diluted or low salinity brine. This paper reports on laboratory work done to increase the understanding of improved oil recovery by waterflooding with low salinity injection water. Porous media used in the studies included outcrop Berea sandstone (Ohio, U.S.A.) and reservoir cores from the Green River formation of the Uinta basin (Utah, U.S.A.). Crude oils used in the experimental protocols were taken from the Minnelusa formation of the Powder River basin (Wyoming, U.S.A.) and from the Green River formation, Monument Butte field in the Uinta basin. Laboratory corefloods using Berea sandstone, Minnelusa crude oil, and simulated Minnelusa formation water found a significant relationship between the temperature at which the oil- and water-saturated cores were aged and the oil recovery resulting from low salinity waterflooding. Lower aging temperatures resulted in very little to no additional oil recovery, while cores aged at higher temperatures resulted in significantly higher recoveries from dilute-water floods. Waterflood studies using reservoir cores and fluids from the Green River formation of the Monument Butte field also showed significantly higher oil recoveries from low salinity waterfloods with cores flooded with fresher water recovering 12.4% more oil on average than those flooded with undiluted formation brine.

  8. Nonenzymatic Role for WRN in Preserving Nascent DNA Strands after Replication Stress

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Su, Fengtao; Mukherjee, Shibani; Yang, Yanyong; Mori, Eiichiro; Bhattacharya, Souparno; Kobayashi, Junya; Yannone, Steven  M.; Chen, David  J.; Asaithamby, Aroumougame

    2014-11-20

    WRN, the protein defective in Werner syndrome (WS), is a multifunctional nuclease involved in DNA damage repair, replication, and genome stability maintenance. It was assumed that the nuclease activities of WRN were critical for these functions. Here, we report a nonenzymatic role for WRN in preserving nascent DNA strands following replication stress. We found that lack of WRN led to shortening of nascent DNA strands after replication stress. Furthermore, we discovered that the exonuclease activity of MRE11 was responsible for the shortening of newly replicated DNA in the absence of WRN. Mechanistically, the N-terminal FHA domain of NBS1 recruits WRNmore » to replication-associated DNA double-stranded breaks to stabilize Rad51 and to limit the nuclease activity of its C-terminal binding partner MRE11. Thus, this previously unrecognized nonenzymatic function of WRN in the stabilization of nascent DNA strands sheds light on the molecular reason for the origin of genome instability in WS individuals.« less

  9. WRNIP1 functions upstream of DNA polymerase ? in the UV-induced DNA damage response

    SciTech Connect (OSTI)

    Yoshimura, Akari; Kobayashi, Yume; Tada, Shusuke; Seki, Masayuki; Enomoto, Takemi

    2014-09-12

    Highlights: The UV sensitivity of POLH{sup ?/?} cells was suppressed by disruption of WRNIP1. In WRNIP1{sup ?/?/?}/POLH{sup ?/?} cells, mutation frequencies and SCE after irradiation reduced. WRNIP1 defect recovered rate of fork progression after irradiation in POLH{sup ?/?} cells. WRNIP1 functions upstream of Pol? in the translesion DNA synthesis pathway. - Abstract: WRNIP1 (WRN-interacting protein 1) was first identified as a factor that interacts with WRN, the protein that is defective in Werner syndrome (WS). WRNIP1 associates with DNA polymerase ? (Pol?), but the biological significance of this interaction remains unknown. In this study, we analyzed the functional interaction between WRNIP1 and Pol? by generating knockouts of both genes in DT40 chicken cells. Disruption of WRNIP1 in Pol?-disrupted (POLH{sup ?/?}) cells suppressed the phenotypes associated with the loss of Pol?: sensitivity to ultraviolet light (UV), delayed repair of cyclobutane pyrimidine dimers (CPD), elevated frequency of mutation, elevated levels of UV-induced sister chromatid exchange (SCE), and reduced rate of fork progression after UV irradiation. These results suggest that WRNIP1 functions upstream of Pol? in the response to UV irradiation.

  10. Smith River Rancheria's Development of an Energy Organization Investigation

    SciTech Connect (OSTI)

    W.G Buehler & Associates

    2007-08-27

    Smith River Rancheria (SRR), for some time, has had a strong commitment to attaining energy selfsufficiency, to reduce overall energy costs and concurrently initiate economic development within the community. Early on it was recognized that the development of an energy organization was important and for this reason was made part of the SRR's strategic review not only for economic development but also the reduction of energy costs. Towards this end, SRR retained Werner G. Buehler of W.G. Buehler & Associates to investigate the many phases or steps required to establish such an energy organization and determine, if in fact, it could benefit the Tribe. The basic phases are delineated as: (1) Identify potential sources of wholesale power and transmission paths; (2) Evaluating the various forms of energy organizations; (3) Determining the benefits (and disadvantages) of each form of organization; (4) Gathering costs to organize and operate the selected form or energy organization; (5) Performing an economic analysis of forming and operating an energy organization; and (6) Develop an implementation plan.

  11. Radiative feedback by low-mass stars in the first generation

    SciTech Connect (OSTI)

    Whalen, Daniel James; Hueckstaedt, Robert; Mcconkie, Thomas

    2009-01-01

    The survival of cosmological minihalos in both ionizing and Lyman-Werner (LW) UV fields from nearby and distant sources has attracted recent attention for its role in regulating the rise of stellar populations at high red-shifts. Numerical models suggest that the first stars form in isolation in small dark matter halos of {approx} 10{sup 5}-10{sup 7} M{sub {circle_dot}} at z {approx} 20-30 and that they are very massive, 25-500 M{sub {circle_dot}}. These stars form large H II regions 2.5-5 kpc in radius capable of engulfing nearby halos. With the rise of Population III stars throughout the cosmos also comes a global LW background that sterilizes mini-halos of H{sub 2}, delaying or preventing new star formation in them. At high redshifts, ionizaing radiation is therefore relatively local while LW photons can originate from many megaparsects away because their energies lie below the ionization limit of H.

  12. Sorption Modeling and Verification for Off-Gas Treatment

    SciTech Connect (OSTI)

    Tavlarides, Lawrence L.; Lin, Ronghong; Nan, Yue; Yiacoumi, Sotira; Tsouris, Costas; Ladshaw, Austin; Sharma, Ketki; Gabitto, Jorge; DePaoli, David

    2015-04-29

    The project has made progress toward developing a comprehensive modeling capability for the capture of target species in off gas evolved during the reprocessing of nuclear fuel. The effort has integrated experimentation, model development, and computer code development for adsorption and absorption processes. For adsorption, a modeling library has been initiated to include (a) equilibrium models for uptake of off-gas components by adsorbents, (b) mass transfer models to describe mass transfer to a particle, diffusion through the pores of the particle and adsorption on the active sites of the particle, and (c) interconnection of these models to fixed bed adsorption modeling which includes advection through the bed. For single-component equilibria, a Generalized Statistical Thermodynamic Adsorption (GSTA) code was developed to represent experimental data from a broad range of isotherm types; this is equivalent to a Langmuir isotherm in the two-parameter case, and was demonstrated for Kr on INL-engineered sorbent HZ PAN, water sorption on molecular sieve A sorbent material (MS3A), and Kr and Xe capture on metal-organic framework (MOF) materials. The GSTA isotherm was extended to multicomponent systems through application of a modified spreading pressure surface activity model and generalized predictive adsorbed solution theory; the result is the capability to estimate multicomponent adsorption equilibria from single-component isotherms. This advance, which enhances the capability to simulate systems related to off-gas treatment, has been demonstrated for a range of real-gas systems in the literature and is ready for testing with data currently being collected for multicomponent systems of interest, including iodine and water on MS3A. A diffusion kinetic model for sorbent pellets involving pore and surface diffusion as well as external mass transfer has been established, and a methodology was developed for determining unknown diffusivity parameters from transient uptake data. Two parallel approaches have been explored for integrating the kernels described above into a mass-transport model for adsorption in fixed beds. In one, the GSTA isotherm kernel has been incorporated into the MOOSE framework; in the other approach, a focused finite-difference framework and PDE kernels have been developed. Issues, including oscillatory behavior in MOOSE solutions to advection-diffusion problems, and opportunities have been identified for each approach, and a path forward has been identified toward developing a stronger modeling platform. Experimental systems were established for collection of microscopic kinetics and equilibria data for single and multicomponent uptake of gaseous species on solid sorbents. The systems, which can operate at ambient temperature to 250°C and dew points from -69 to 17°C, are useful for collecting data needed for modeling performance of sorbents of interest. Experiments were conducted to determine applicable models and parameters for isotherms and mass transfer for water and/or iodine adsorption on MS3A. Validation experiments were also conducted for water adsorption on fixed beds of MS3A. For absorption, work involved modeling with supportive experimentation. A dynamic model was developed to simulate CO2 absorption with chemical reaction using high alkaline content water solutions. A computer code was developed to implement the model based upon transient mass and energy balances. Experiments were conducted in a laboratory-scale column to determine model parameters. The influence of geometric parameters and operating variables on CO2 absorption was studied over a wide range of conditions. This project has resulted in 7 publications, with 3 manuscripts in preparation. Also, 15 presentations were given at national meetings of ANS and AIChE and at Material Recovery and Waste Forms Campaign Working Group meetings.

  13. Dynamic Event Tree Analysis Through RAVEN

    SciTech Connect (OSTI)

    A. Alfonsi; C. Rabiti; D. Mandelli; J. Cogliati; R. A. Kinoshita; A. Naviglio

    2013-09-01

    Conventional Event-Tree (ET) based methodologies are extensively used as tools to perform reliability and safety assessment of complex and critical engineering systems. One of the disadvantages of these methods is that timing/sequencing of events and system dynamics is not explicitly accounted for in the analysis. In order to overcome these limitations several techniques, also know as Dynamic Probabilistic Risk Assessment (D-PRA), have been developed. Monte-Carlo (MC) and Dynamic Event Tree (DET) are two of the most widely used D-PRA methodologies to perform safety assessment of Nuclear Power Plants (NPP). In the past two years, the Idaho National Laboratory (INL) has developed its own tool to perform Dynamic PRA: RAVEN (Reactor Analysis and Virtual control ENvironment). RAVEN has been designed in a high modular and pluggable way in order to enable easy integration of different programming languages (i.e., C++, Python) and coupling with other application including the ones based on the MOOSE framework, developed by INL as well. RAVEN performs two main tasks: 1) control logic driver for the new Thermo-Hydraulic code RELAP-7 and 2) post-processing tool. In the first task, RAVEN acts as a deterministic controller in which the set of control logic laws (user defined) monitors the RELAP-7 simulation and controls the activation of specific systems. Moreover, RAVEN also models stochastic events, such as components failures, and performs uncertainty quantification. Such stochastic modeling is employed by using both MC and DET algorithms. In the second task, RAVEN processes the large amount of data generated by RELAP-7 using data-mining based algorithms. This paper focuses on the first task and shows how it is possible to perform the analysis of dynamic stochastic systems using the newly developed RAVEN DET capability. As an example, the Dynamic PRA analysis, using Dynamic Event Tree, of a simplified pressurized water reactor for a Station Black-Out scenario is presented.

  14. OSPREY Model

    SciTech Connect (OSTI)

    Veronica J. Rutledge

    2013-01-01

    The absence of industrial scale nuclear fuel reprocessing in the U.S. has precluded the necessary driver for developing the advanced simulation capability now prevalent in so many other countries. Thus, it is essential to model complex series of unit operations to simulate, understand, and predict inherent transient behavior and feedback loops. A capability of accurately simulating the dynamic behavior of advanced fuel cycle separation processes will provide substantial cost savings and many technical benefits. The specific fuel cycle separation process discussed in this report is the off-gas treatment system. The off-gas separation consists of a series of scrubbers and adsorption beds to capture constituents of interest. Dynamic models are being developed to simulate each unit operation involved so each unit operation can be used as a stand-alone model and in series with multiple others. Currently, an adsorption model has been developed within Multi-physics Object Oriented Simulation Environment (MOOSE) developed at the Idaho National Laboratory (INL). Off-gas Separation and REcoverY (OSPREY) models the adsorption of off-gas constituents for dispersed plug flow in a packed bed under non-isothermal and non-isobaric conditions. Inputs to the model include gas, sorbent, and column properties, equilibrium and kinetic data, and inlet conditions. The simulation outputs component concentrations along the column length as a function of time from which breakthrough data is obtained. The breakthrough data can be used to determine bed capacity, which in turn can be used to size columns. It also outputs temperature along the column length as a function of time and pressure drop along the column length. Experimental data and parameters were input into the adsorption model to develop models specific for krypton adsorption. The same can be done for iodine, xenon, and tritium. The model will be validated with experimental breakthrough curves. Customers will be given access to OSPREY to used and evaluate the model.

  15. Off-gas Adsorption Model and Simulation - OSPREY

    SciTech Connect (OSTI)

    Veronica J Rutledge

    2013-10-01

    The absence of industrial scale nuclear fuel reprocessing in the U.S. has precluded the necessary driver for developing the advanced simulation capability now prevalent in so many other countries. Thus, it is essential to model complex series of unit operations to simulate, understand, and predict inherent transient behavior. A capability of accurately simulating the dynamic behavior of advanced fuel cycle separation processes is expected to provide substantial cost savings and many technical benefits. To support this capability, a modeling effort focused on the off-gas treatment system of a used nuclear fuel recycling facility is in progress. The off-gas separation consists of a series of scrubbers and adsorption beds to capture constituents of interest. Dynamic models are being developed to simulate each unit operation involved so each unit operation can be used as a stand-alone model and in series with multiple others. Currently, an adsorption model has been developed within Multi-physics Object Oriented Simulation Environment (MOOSE) developed at the Idaho National Laboratory (INL). Off-gas Separation and REcoverY (OSPREY) models the adsorption of offgas constituents for dispersed plug flow in a packed bed under non-isothermal and non-isobaric conditions. Inputs to the model include gas composition, sorbent and column properties, equilibrium and kinetic data, and inlet conditions. The simulation outputs component concentrations along the column length as a function of time from which breakthrough data can be obtained. The breakthrough data can be used to determine bed capacity, which in turn can be used to size columns. In addition to concentration data, the model predicts temperature along the column length as a function of time and pressure drop along the column length. A description of the OSPREY model, results from krypton adsorption modeling and plans for modeling the behavior of iodine, xenon, and tritium will be discussed.

  16. Episodic mass loss from the hydrogen-deficient central star of the planetary nebula Longmore 4

    SciTech Connect (OSTI)

    Bond, Howard E.

    2014-09-01

    A spectacular transient mass-loss episode from the extremely hot, hydrogen-deficient central star of the planetary nebula (PN) Longmore 4 (Lo 4) was discovered in 1992 by Werner et al. During that event, the star temporarily changed from its normal PG 1159 spectrum to that of an emission-line low-luminosity early-type Wolf-Rayet [WCE] star. After a few days, Lo 4 reverted to its normal, predominantly absorption-line PG 1159 type. To determine whether such events recur, and if so how often, I monitored the optical spectrum of Lo 4 from early 2003 to early 2012. Out of 81 spectra taken at random dates, 4 of them revealed mass-loss outbursts similar to that seen in 1992. This indicates that the episodes recur approximately every 100 days (if the recurrence rate has been approximately constant and the duration of a typical episode is ?5 days), and that the star is in a high-mass-loss state about 5% of the time. Since the enhanced stellar wind is hydrogen-deficient, it arises from the photosphere and is unlikely to be related to phenomena such as a binary or planetary companion or infalling dust. I speculate on plausible mechanisms for these unique outbursts, including the possibility that they are related to the non-radial GW Vir-type pulsations exhibited by Lo 4. The central star of the PN NGC 246 has stellar parameters similar to those of Lo 4, and it is also a GW Vir-type pulsator with similar pulsation periods. I obtained 167 spectra of NGC 246 between 2003 and 2011, but no mass ejections were found.

  17. WIDESPREAD METHANOL EMISSION FROM THE GALACTIC CENTER: THE ROLE OF COSMIC RAYS

    SciTech Connect (OSTI)

    Yusef-Zadeh, F.; Royster, M.; Cotton, W.; Viti, S.; Wardle, M.

    2013-02-20

    We report the discovery of a widespread population of collisionally excited methanol J = 4{sub -1} to 3{sub 0} E sources at 36.2 GHz from the inner 66' Multiplication-Sign 18' (160 Multiplication-Sign 43 pc) of the Galactic center. This spectral feature was imaged with a spectral resolution of 16.6 km s{sup -1} taken from 41 channels of a Very Large Array continuum survey of the Galactic center region. The revelation of 356 methanol sources, most of which are maser candidates, suggests a large abundance of methanol in the gas phase in the Galactic center region. There is also spatial and kinematic correlation between SiO (2-1) and CH{sub 3}OH emission from four Galactic center clouds: the +50 and +20 km s{sup -1} clouds and G0.13-0.13 and G0.25 + 0.01. The enhanced abundance of methanol is accounted for in terms of induced photodesorption by cosmic rays as they travel through a molecular core, collide, dissociate, ionize, and excite Lyman Werner transitions of H{sub 2}. A time-dependent chemical model in which cosmic rays drive the chemistry of the gas predicts CH{sub 3}OH abundance of 10{sup -8} to 10{sup -7} on a chemical timescale of 5 Multiplication-Sign 10{sup 4} to 5 Multiplication-Sign 10{sup 5} years. The average methanol abundance produced by the release of methanol from grain surfaces is consistent with the available data.

  18. MHD Integrated Topping Cycle Project

    SciTech Connect (OSTI)

    Not Available

    1992-01-01

    The overall objective of the project is to design and construct prototypical hardware for an integrated MHD topping cycle, and conduct long duration proof-of-concept tests of integrated system at the US DOE Component Development and Integration Facility in Butte, Montana. The results of the long duration tests will augment the existing engineering design data base on MHD power train reliability, availability, maintainability, and performance, and will serve as a basis for scaling up the topping cycle design to the next level of development, an early commercial scale power plant retrofit. The components of the MHD power train to be designed, fabricated, and tested include: A slagging coal combustor with a rated capacity of 50 MW thermal input, capable of operation with an Eastern (Illinois {number sign}6) or Western (Montana Rosebud) coal, a segmented supersonic nozzle, a supersonic MHD channel capable of generating at least 1.5 MW of electrical power, a segmented supersonic diffuser section to interface the channel with existing facility quench and exhaust systems, a complete set of current control circuits for local diagonal current control along the channel, and a set of current consolidation circuits to interface the channel with the existing facility inverter.

  19. MHD Integrated Topping Cycle Project. Thirteenth quarterly technical progress report, August 1, 1990--October 31, 1990

    SciTech Connect (OSTI)

    Not Available

    1992-01-01

    The overall objective of the project is to design and construct prototypical hardware for an integrated MHD topping cycle, and conduct long duration proof-of-concept tests of integrated system at the US DOE Component Development and Integration Facility in Butte, Montana. The results of the long duration tests will augment the existing engineering design data base on MHD power train reliability, availability, maintainability, and performance, and will serve as a basis for scaling up the topping cycle design to the next level of development, an early commercial scale power plant retrofit. The components of the MHD power train to be designed, fabricated, and tested include: A slagging coal combustor with a rated capacity of 50 MW thermal input, capable of operation with an Eastern (Illinois {number_sign}6) or Western (Montana Rosebud) coal, a segmented supersonic nozzle, a supersonic MHD channel capable of generating at least 1.5 MW of electrical power, a segmented supersonic diffuser section to interface the channel with existing facility quench and exhaust systems, a complete set of current control circuits for local diagonal current control along the channel, and a set of current consolidation circuits to interface the channel with the existing facility inverter.

  20. Supplement Analysis for the Transmission System Vegetation Management Program FEIS

    SciTech Connect (OSTI)

    N /A

    2001-03-27

    BPA proposes to clear unwanted vegetation from a section of BPA's Ponderosa--Pilot Butte Transmission Line Right-of-way to facilitate relocation of structure 18/3. Work would begin in mid-March and end in April, 2001. (1) Description of right-of-way and vegetation management needed--The project involves cutting all tall growing trees and brush within BPA's 100-foot wide transmission line right-of-way. An encroachment by the City of Bend Sewer Treatment facility, and future expansion plans, compelled the relocation of this portion of the right-of-way. Structures 18/2 and 18/4 will be modified in place to accommodate the new angle of the right-of-way. Structure 18/3 will be moved approximately 300 feet westerly to allow for the expansion of the sewer treatment facility. Only vegetation within the new portion of the right-of-way, totaling approximately 3.5 acres, will be controlled. No herbicides will be used on this project. Vegetation to be controlled: Juniper trees are the only tall growing tree species within this portion of the right-of-way requiring treatment. The density of vegetation within the new right-of-way is light to medium. The right-of-way boundaries will be examined for danger trees and if found, danger trees will be marked and cut according to danger tree policy.

  1. Completion Report for Well ER-8-1

    SciTech Connect (OSTI)

    Bechtel Nevada

    2004-11-01

    Well ER-8-1 was drilled for the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office in support of the Nevada Environmental Restoration Project at the Nevada Test Site, Nye County, Nevada. This well was drilled in October and November of 2002 as part of a Hydrogeologic investigation program for the Yucca Flat/Climax Mine Corrective Action Unit in the northeastern portion of the Nevada Test Site. Well ER-8-1 is located at the north end of Yucca Flat approximately 580 meters south-southeast of the surface exposure of the Climax granitic intrusive. Detailed lithologic descriptions with stratigraphic assignments are included in this report. These are based on composite drill cuttings samples collected every 3 meters, and 21 sidewall samples taken at various depths between 351.1 and 573.0 meters, supplemented by incomplete geophysical log data. Detailed petrographic, geochemical, and mineralogical studies of rock samples were conducted on 22 samples of drill cuttings. Drilling began in tuffaceous alluvium, and the borehole penetrated Tertiary age bedded tuffs of the Volcanics of Oak Spring Butte and carbonate sediments of Paleozoic age, which were encountered at a depth of 334 meters. The borehole unexpectedly penetrated granite at the depth of 538.9 meters in which drilling was stopped. Contact metamorphic rocks and intrusive dikes associated with the Cretaceous-age granitic intrusive and at least one significant fault zone were encountered.

  2. The intermountain power project commissioning - Subsynchronous torsional interaction tests

    SciTech Connect (OSTI)

    Wu, C.T.; Peterson, K.J. ); Pinko, R.J.; Kankam, M.D.; Baker, D.H. )

    1988-10-01

    Subsyncronous torsional vibration as a result of electrochemical interaction between the HVDC controls and a turbine-generator was first discovered during the commissioning of the Square Butte Project in 1977. The level of interaction between the HVDC controls and the turbine-generator depends on several interacting factors: the characteristic torsional frequencies of the turbine-generator, the bandwidth of the HVDC controls and the relative strength of the connecting ac system. For the Intermountain Power Project (IPP), early analysis of these interacting factors indicated that there exist definite potential for subsynchronous oscillation to occur. The calculated torsional frequencies of the IPP units showed that the first mode frequency is 14.0 Hz and is within the typical bandwidth of an HVDC control which is between 10-20 Hz. The HVDC controls, therefore, can influence the torsional stability of the IPP units. Further, the IPP turbine-generators are required to operate isolated on the HVDC rectifier terminal, with no other interconnecting ac network. This ''radial'' mode of operation will result in maximum interaction between the converter station and the IPP units. It became obvious that special measure must be implemented in the design of the IPP HVDC control system to modify its typical characteristics to avoid the occurrence of the subsynchronous oscillation. This paper presents the results of the subsynchronous torsional interaction (SSTI) tests that were performed during the commissioning of the IPP Unit 1 and the HVDC Transmission system.

  3. Turbine vane structure

    DOE Patents [OSTI]

    Irwin, John A.

    1980-08-19

    A liquid cooled stator blade assembly for a gas turbine engine includes an outer shroud having a pair of liquid inlets and a pair of liquid outlets supplied through a header and wherein means including tubes support the header radially outwardly of the shroud and also couple the header with the pair of liquid inlets and outlets. A pair of turbine vanes extend radially between the shroud and a vane platform to define a gas turbine motive fluid passage therebetween; and each of the vanes is cooled by an internal body casting of super alloy material with a grooved layer of highly heat conductive material that includes spaced apart flat surface trailing edges in alignment with a flat trailing edge of the casting joined to wall segments of the liner which are juxtaposed with respect to the internal casting to form an array of parallel liquid inlet passages on one side of the vane and a second plurality of parallel liquid return passages on the opposite side of the vane; and a superalloy heat and wear resistant imperforate skin covers the outer surface of the composite blade including the internal casting and the heat conductive layer; a separate trailing edge section includes an internal casting and an outer skin butt connected to the end surfaces of the internal casting and the heat conductive layer to form an easily assembled liquid cooled trailing edge section in the turbine vane.

  4. Characterization of Multilayered Multipass Friction Stir Weld on ASTM A572 G50 Steel

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Lim, Yong Chae; Sanderson, Samuel; Mahoney, Murray; Yu, Xinghua; Qiao, Dongxiao; Wang, Yanli; Zhang, Wei; Feng, Zhili

    2014-01-01

    A multilayered multipass friction stir weld (MM-FSW) on ASTM A572 Grade 50 steel was characterized to understand its potential application for thick-section structures. The 15-mm-thick section was fabricated by stacking up three steel plates and then friction stir welding the plates together in a total of 5 passes. The unique butt/lap joint configuration encountered in the multilayer weld was examined to understand the effect of tool rotation direction on the joint quality especially the formation of hooking defect. Charpy V-notch impact toughness tests showed generally higher impact toughness energy for the stir zone than the base metal with a ductilemore » fracture mode. The microhardness value was measured from 195 to 220 HV in the stir zone, while the base metal showed an average value of 170 HV. The microstructure in the stir zone and the adjacent heat affected zone was quantified using Optical and Scanning Electron Microscopy (SEM) including Electron Backscatter Diffraction (EBSD). The increased toughness and hardness were correlated with the refined microstructure in stir zone, resulting from severe plastic deformation and subsequent dynamic recrystallization during friction stir welding.« less

  5. Development of an advanced process for drying fine coal in an inclined fluidized bed

    SciTech Connect (OSTI)

    Boysen, J.E.; Cha, C.Y.; Barbour, F.A.; Turner, T.F.; Kang, T.W.; Berggren, M.H.; Hogsett, R.F.; Jha, M.C.

    1990-02-01

    The objective of this research project was to demonstrate a technically feasible and economically viable process for drying and stabilizing high-moisture subbituminous coal. Controlled thermal drying of coal fines was achieved using the inclined fluidized-bed drying and stabilization process developed by the Western Research Institute. The project scope of work required completion of five tasks: (1) project planning, (2) characterization of two feed coals, (3) bench-scale inclined fluidized-bed drying studies, (4) product characterization and testing, and (5) technical and economic evaluation of the process. High moisture subbituminous coals from AMAX Eagle Butte mine located in the Powder River Basin of Wyoming and from Usibelli Coal Mine, Inc. in Healy, Alaska were tested in a 10-lb/hr bench-scale inclined fluidized-bed. Experimental results show that the dried coal contains less than 1.5% moisture and has a heating value over 11,500 Btu/lb. The coal fines entrainment can be kept below 15 wt % of the feed. The equilibrium moisture of dried coal was less than 50% of feed coal equilibrium moisture. 7 refs., 60 figs., 47 tabs.

  6. Geophysical interpretations west of and within the northwestern part of the Nevada Test Site

    SciTech Connect (OSTI)

    Grauch, V.J.; Sawyer, D.A.; Fridrich, C.J.; Hudson, M.R.

    1997-12-31

    This report focuses on interpretation of gravity and new magnetic data west of the Nevada Test Site (NTS) and within the northwestern part of NTS. The interpretations integrate the gravity and magnetic data with other geophysical, geological, and rock property data to put constraints on tectonic and magmatic features not exposed at the surface. West of NTS, where drill hole information is absent, these geophysical data provide the best available information on the subsurface. Interpreted subsurface features include calderas, intrusions, basalt flows and volcanoes, Tertiary basins, structurally high pre-Tertiary rocks, and fault zones. New features revealed by this study include (1) a north-south buried tectonic fault east of Oasis Mountain, which the authors call the Hogback fault; (2) an east striking fault or accommodation zone along the south side of Oasis Valley basin, which they call the Hot Springs fault; (3) a NNE striking structural zone coinciding with the western margins of the caldera complexes; (4) regional magnetic highs that probably represent a thick sequence of Tertiary volcanic rocks; and (5) two probable buried calderas that may be related to the tuffs of Tolicha Peak and of Sleeping Butte, respectively.

  7. Effect of tool pin features on process response variables during friction stir welding of dissimilar aluminum alloys

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Rabby, Reza; Tang, Wei; Reynolds, A. P.

    2015-07-01

    In this article, the effect of pin features and orientation/placement of the materials on advancing side were investigated for friction stir welding (FSW) of dissimilar aluminum alloys AA2050 and AA6061. Pins for FSW were produced with a 2.12 mm pitch thread having three flats/flutes. Three sets of rotational speed/welding speed were used to perform a series of welds in a butt joint arrangement. The results show that, joint quality, process response variables and welding temperature are highly affected by pin features and material orientation in FSW. Defect free joints with effective material transportation in the weld nugget zone were obtainedmore » when welding was performed with AA2050 on the advancing side. The tool also encounters less in-plane reaction force for welding with 2050 on the advancing side. Pin with thread+3 flats produces quality welds at low rotational and travel speed regardless of the location of alloys on advancing or retreating side.« less

  8. Characterization of Multilayered Multipass Friction Stir Weld on ASTM A572 G50 Steel

    SciTech Connect (OSTI)

    Lim, Yong Chae [ORNL; Sanderson, Samuel [MegaStir Technologies LLC; Mahoney, Murray [Consultant; Yu, Xinghua [ORNL; Qiao, Dongxiao [ORNL; Wang, Yanli [ORNL; Zhang, Wei [ORNL; Feng, Zhili [ORNL

    2014-01-01

    A multilayered multipass friction stir weld (MM-FSW) on ASTM A572 Grade 50 steel was characterized to understand its potential application for thick-section structures. The 15-mm-thick section was fabricated by stacking up three steel plates and then friction stir welding the plates together in a total of 5 passes. The unique butt/lap joint configuration encountered in the multilayer weld was examined to understand the effect of tool rotation direction on the joint quality especially the formation of hooking defect. Charpy V-notch impact toughness tests showed generally higher impact toughness energy for the stir zone than the base metal with a ductile fracture mode. The microhardness value was measured from 195 to 220 HV in the stir zone, while the base metal showed an average value of 170 HV. The microstructure in the stir zone and the adjacent heat affected zone was quantified using Optical and Scanning Electron Microscopy (SEM) including Electron Backscatter Diffraction (EBSD). The increased toughness and hardness were correlated with the refined microstructure in stir zone, resulting from severe plastic deformation and subsequent dynamic recrystallization during friction stir welding.

  9. Joining of 14YWT and F82H by Friction Stir Welding

    SciTech Connect (OSTI)

    Hoelzer, David T [ORNL] [ORNL; Unocic, Kinga A [ORNL] [ORNL; Sokolov, Mikhail A [ORNL] [ORNL; Feng, Zhili [ORNL] [ORNL

    2013-01-01

    The feasibility of using friction stir welding (FSW) to join specimens of the advanced oxide dispersion strengthened (ODS) 14YWT nanostructured ferritic alloy (NFA) and a plate of F82H tempered martensitic steel (TMS) was investigated. The sample used in the FSW experiment consisted of spot welding four specimens 14YWT prepared from prior tested dual notch fracture toughness bend bars in a corresponding slot that was machined in the F82H plate. The FSW run was successfully performed on the sample using a polycrystalline boron nitride tool (PCBN) that resulted in joints showing good bonding between butt joints of 14YWT specimens and 14YWT specimens and F82H plate. The joints were characterized by light microscopy and SEM analysis and were observed to be relatively narrow in width. The ultra-fine grain size associated with 14YWT increased by a factor of up to 3 while that of F82H was refined by a considerable amount in the thermomechanically affected zones (TMAZ) due to FSW. In addition, porosity was observed in the TMAZ of 14YWT on the advancing side of the FSW joint and at the interface between F82H and 14YWT. Vickers hardness (VH) measurements showed a decrease of ~120 VH from ~500 VH (~20% decrease) for 14YWT and an increase of ~220 VH from ~220 VH (~100% increase) for F82H in the FSW zones. Further refinements in the FSW process will be required to minimize defects including porosity.

  10. Multiple pass and multiple layer friction stir welding and material enhancement processes

    DOE Patents [OSTI]

    Feng, Zhili [Knoxville, TN; David, Stan A. [Knoxville, TN; Frederick, David Alan [Harriman, TN

    2010-07-27

    Processes for friction stir welding, typically for comparatively thick plate materials using multiple passes and multiple layers of a friction stir welding tool. In some embodiments a first portion of a fabrication preform and a second portion of the fabrication preform are placed adjacent to each other to form a joint, and there may be a groove adjacent the joint. The joint is welded and then, where a groove exists, a filler may be disposed in the groove, and the seams between the filler and the first and second portions of the fabrication preform may be friction stir welded. In some embodiments two portions of a fabrication preform are abutted to form a joint, where the joint may, for example, be a lap joint, a bevel joint or a butt joint. In some embodiments a plurality of passes of a friction stir welding tool may be used, with some passes welding from one side of a fabrication preform and other passes welding from the other side of the fabrication preform.

  11. Advanced austenitic alloys for fossil power systems. CRADA final report

    SciTech Connect (OSTI)

    Swindeman, R.W.; Cole, N.C.; Canonico, D.A.; Henry, J.F.

    1998-08-01

    In 1993, a Cooperative Research and Development Agreement (CRADA) was undertaken between Oak Ridge National Laboratory and ABB Combustion Engineering t examine advanced alloys for fossil power systems. Specifically, the use of advanced austenitic stainless steels for superheater/reheater construction in supercritical boilers was examined. The strength of cold-worked austenitic stainless steels was reviewed and compared to the strength and ductility of advanced austenitic stainless steels. The advanced stainless steels were found to retain their strength to very long times at temperatures where cold-worked standard grades of austenitic stainless steels became weak. Further, the steels exhibited better long-time stability than the stabilized 300 series stainless steels in either the annealed or cold worked conditions. Type 304H mill-annealed tubing was provided to ORNL for testing of base metal and butt welds. The tubing was found to fall within range of expected strength for 304H stainless steel. The composite 304/308 stainless steel was found to be stronger than typical for the weldment. Boiler tubing was removed from a commercial boiler for replacement by newer steels, but restraints imposed by the boiler owners did not permit the installation of the advanced steels, so a standard 32 stainless steel was used as a replacement. The T91 removed from the boiler was characterized.

  12. Idaho National Laboratory Cultural Resource Monitoring Report for Fiscal Year 2007

    SciTech Connect (OSTI)

    Brenda R. Pace

    2007-10-01

    This report describes the cultural resource monitoring activities of the Idaho National Laboratorys (INL) Cultural Resource Management (CRM) Office during fiscal year 2007 (FY 2007). In FY 2007, 40 localities were revisited: two locations of heightened Shoshone-Bannock tribal sensitivity, four caves, three butte/craters, twelve prehistoric archaeological sites, two historic stage stations, nine historic homesteads, a portion of Goodales Cutoff of the Oregon Trail, a portion of historic trail T-16, one World War II dump, four buildings from the World War II period, and Experimental Breeder Reactor I, a modern scientific facility and National Historic Landmark. Several INL project areas were also monitored in FY 2007. This included direct observation of ground disturbing activities within the Power Burst Facility (PBF, now designated as the Critical Infrastructure Test Range Complex CITRC), backfilling operations associated with backhoe trenches along the Big Lost River, and geophysical surveys designed to pinpoint subsurface unexploded ordnance in the vicinity of the Naval Ordnance Disposal Area. Surprise checks were also made to three ongoing INL projects to ensure compliance with INL CRM Office recommendations to avoid impacts to cultural resources. Although some impacts were documented, no significant adverse effects that would threaten the National Register eligibility of any resource were observed at any location.

  13. Geothermal-resource assessment of Ranger Warm Spring, Colorado. Resources Series 24

    SciTech Connect (OSTI)

    Zacharakis, T.G.; Pearl, R.H.; Ringrose, C.D.

    1983-01-01

    In 1977 a program was initiated to delineate the geological features controlling the occurrence of geothermal resources in Colorado. This program consisted of literature search, reconnaissance geologic and hydrogeologic mapping and geophysical and geochemical surveys. During 1980 and 1981 geothermal resource assessment efforts were conducted in the Cement Creek Valley south of Crested Butte. In this valley are two warm springs, Cement Creek and Ranger, about 4 mi (6.4 km) apart. The temperature of both springs is 77 to 79/sup 0/F (25 to 26/sup 0/C) and the discharge ranges from 60 to 195 gallons per minute. Due to access problems no work was conducted in the Cement Creek Warm Springs area. At Ranger Warm Springs electrical resistivity and soil mercury surveys were conducted. The warm springs are located in the Elk Mountains of west central Colorado. The bedrock of the area consists of sedimentary rocks ranging in age from Precambrian to Recent. Several faults with displacements of up to 3000 ft (194 m) are found in the area. One of these faults passes close to the Ranger Warm Springs. The electrical resistivity survey indicated that the waters of Ranger Warm Springs are moving up along a buried fault which parallels Cement Creek.

  14. Central Facilities Area Sewage Lagoon Evaluation

    SciTech Connect (OSTI)

    Mark R. Cole

    2013-12-01

    The Central Facilities Area (CFA), located in Butte County, Idaho, at the Idaho National Laboratory has an existing wastewater system to collect and treat sanitary wastewater and non-contact cooling water from the facility. The existing treatment facility consists of three cells: Cell #1 has a surface area of 1.7 acres, Cell #2 has a surface area of 10.3 acres, and Cell #3 has a surface area of 0.5 acres. If flows exceed the evaporative capacity of the cells, wastewater is discharged to a 73.5-acre land application site that uses a center-pivot irrigation sprinkler system. As flows at CFA have decreased in recent years, the amount of wastewater discharged to the land application site has decreased from 13.64 million gallons in 2004 to no discharge in 2012 and 2013. In addition to the decreasing need for land application, approximately 7.7 MG of supplemental water was added to the system in 2013 to maintain a water level and prevent the clay soil liners in the cells from drying out and “cracking.” The Idaho National Laboratory is concerned that the sewage lagoons and land application site may be oversized for current and future flows. A further concern is the sustainability of the large volumes of supplemental water that are added to the system according to current operational practices. Therefore, this study was initiated to evaluate the system capacity, operational practices, and potential improvement alternatives, as warranted.

  15. Energy Efficiency Strategies for Municipal Wastewater Treatment Facilities

    SciTech Connect (OSTI)

    Daw, J.; Hallett, K.; DeWolfe, J.; Venner, I.

    2012-01-01

    Water and wastewater systems are significant energy consumers with an estimated 3%-4% of total U.S. electricity consumption used for the movement and treatment of water and wastewater. Water-energy issues are of growing importance in the context of water shortages, higher energy and material costs, and a changing climate. In this economic environment, it is in the best interest for utilities to find efficiencies, both in water and energy use. Performing energy audits at water and wastewater treatment facilities is one way community energy managers can identify opportunities to save money, energy, and water. In this paper the importance of energy use in wastewater facilities is illustrated by a case study of a process energy audit performed for Crested Butte, Colorado's wastewater treatment plant. The energy audit identified opportunities for significant energy savings by looking at power intensive unit processes such as influent pumping, aeration, ultraviolet disinfection, and solids handling. This case study presents best practices that can be readily adopted by facility managers in their pursuit of energy and financial savings in water and wastewater treatment. This paper is intended to improve community energy managers understanding of the role that the water and wastewater sector plays in a community's total energy consumption. The energy efficiency strategies described provide information on energy savings opportunities, which can be used as a basis for discussing energy management goals with water and wastewater treatment facility managers.

  16. Gas turbine fuel from low-rank coal

    SciTech Connect (OSTI)

    Maas, D.J.; Smith, F.J.

    1986-06-01

    Five low-rank coals from the western United States were cleaned in a bench-scale heavy media separation procedures followed by acid leaching and hydrothermal processing. The objective of these cleaning steps was to determine the amenability of preparing gas turbine quality fuel from low-rank coal. The best candidate for scale-up was determined to be a Wyoming subbituminous coal from the eagle Butte mine. Two hundred thirty kilograms of cleaned and micronized coal/water fuel were prepared in pilot-scale equipment to determine process parameters and fuel characteristics. After establishing operating conditions, two thousand kilograms of cleaned and micronized coal/water and powdered coal fuel were produced for testing in a pilot-scale gas turbine combustor. An economic analysis was completed for a commercial-scale plant designed to produce clean gas turbine fuel from low-rank coal using the most promising process steps identified form the bench- and pilot-scale studies. 21 refs., 12 figs., 20 tabs.

  17. Plugged grids: A new solution

    SciTech Connect (OSTI)

    Barron, M.F.

    1993-12-31

    Blocked Truck Dump Grids are a coal industry country-wide problem. It does not matter if you operate a western state multi-million ton per year mega-mine or one of the many 500 ton per hour eastern ones. Forcing oversize coal through the grizzly has been a labor intensive problem for both, causing: reduced production throughput because of increased downtime; unnecessary use of maintenance or operational personnel with usually expensive ancillary equipment; and introduction of a hazardous situation with a potential safety problem. Operators have developed numerous techniques to address the problem with varying degrees of success. During 1989, AMAX Coal and Gundlach Machinery personnel developed the concept of a semi-automatic, unmanned breaker which would traverse back and forth across the top of a grizzly, breaking up the oversize chunks of coal allowing them to fall through the grizzly openings. A small test unit was built in early 1990, and the technique successfully demonstrated. In March, 1991, the first commercial unit was installed on the 26 foot {times} 123 foot grizzly at AMAX Coal`s Eagle Butte Mine located north of Gillette, Wyoming, which processes LIP to 8,000 tons per hour of raw coal. After minor adjustments, the unit was put into operation in mid-April, 1991, and is performing two years later as planned.

  18. Qualification of the Joints for the ITER Central Solenoid

    SciTech Connect (OSTI)

    Martovetsky, N; Berryhill, A; Kenney, S

    2011-09-01

    The ITER Central Solenoid has 36 interpancake joints, 12 bus joints, and 12 feeder joints in the magnet. The joints are required to have resistance below 4 nOhm at 45 kA at 4.5 K. The US ITER Project Office developed two different types of interpancake joints with some variations in details in order to find a better design, qualify the joints, and establish a fabrication process. We built and tested four samples of the sintered joints and two samples with butt-bonded joints (a total of eight joints). Both designs met the specifications. Results of the joint development, test results, and selection of the baseline design are presented and discussed in the paper. The ITER Central Solenoid (CS) consists of six modules. Each module is composed of six wound hexapancakes and one quadrapancake. The multipancakes are connected electrically and hydraulically by in-line interpancake joints. The joints are located at the outside diameter (OD) of the module. Cable in conduit conductor (CICC) high-current joints are critical elements in the CICC magnets. In addition to low resistivity, the CS joints must fit a space envelope equivalent to the regular conductor cross section and must have low hydraulic impedance and enough structural strength to withstand the hoop and compressive forces during operation, including cycling. This paper is the continuation of the work reported on the intermodule joints.

  19. Center for Volcanic and Tectonic Studies, Department of Geoscience annual report, October 1, 1989--September 30, 1990

    SciTech Connect (OSTI)

    Smith, E.I. [Nevada Univ., Las Vegas, NV (United States). Center for Volcanic and Tectonic Studies

    1990-11-01

    This report summarizes our activities during the period October 1, 1989 to September 30, 1990. Our goal was to develop an understanding of late-Miocene and Pliocene volcanism in the Great Basin by studying Pliocene volcanoes in the vicinity of the proposed high-level nuclear waste repository at Yucca Mountain, Nevada. Field studies during this period concentrated on the Quaternary volcanoes in Crater Flat, Yucca Mountain, Fortification Hill, at Buckboard Mesa and Sleeping Butte, and in the Reveille Range. Also, a study was initiated on structurally disrupted basaltic rocks in the northern White Hills of Mohave County, Arizona. As well as progress reports of our work in Crater Flat, Fortification Hill and the Reveille Range, this paper also includes a summary of model that relates changing styles of Tertiary extension to changing magmatic compositions, and a summary of work being done in the White Hills, Arizona. In the Appendix, we include copies of published papers not previously incorporated in our monthly reports.

  20. Fusion, mechanical joining methods pros, cons--Part 2. [Natural gas pipelines use of mechanical and fusion joints

    SciTech Connect (OSTI)

    Gunther, K.M. )

    1993-10-01

    Two basic techniques accepted by gas distribution utility companies for joining polyethylene pipe underground are fusion methods and mechanical joining. Washington Gas Light Co., uses the fusion methods for the most part and uses mechanical joints for repair and final tie-ins where fusion methods are impractical or impossible to use. Fusion methods used by gas industry users of plastic pipe are: butt fusion; socket fusion; saddle fusion; electrofusion. Mechanical pipe joining techniques or procedures include: factory made mechanical joints such as meter risers and transition fittings; hydraulic compression couplings; bolted and screwed compression couplings; stab type compression couplings; interior seal couplings. Every joining method has strengths, weaknesses, pitfalls and ways they can fail in service. The key is making the best selection based on such factors as location, temperature, conditions, available equipment, personnel training level and cost. No one method will do it all or every company would be using that particular method. Part 2 focuses on strengths, weaknesses, pitfalls and failure possibilities of the five mechanical techniques.

  1. Effect of tool pin features on process response variables during friction stir welding of dissimilar aluminum alloys

    SciTech Connect (OSTI)

    Rabby, Reza; Tang, Wei; Reynolds, A. P.

    2015-07-01

    In this article, the effect of pin features and orientation/placement of the materials on advancing side were investigated for friction stir welding (FSW) of dissimilar aluminum alloys AA2050 and AA6061. Pins for FSW were produced with a 2.12 mm pitch thread having three flats/flutes. Three sets of rotational speed/welding speed were used to perform a series of welds in a butt joint arrangement. The results show that, joint quality, process response variables and welding temperature are highly affected by pin features and material orientation in FSW. Defect free joints with effective material transportation in the weld nugget zone were obtained when welding was performed with AA2050 on the advancing side. The tool also encounters less in-plane reaction force for welding with 2050 on the advancing side. Pin with thread+3 flats produces quality welds at low rotational and travel speed regardless of the location of alloys on advancing or retreating side.

  2. Idaho National Laboratory Cultural Resource Monitoring Report for FY 2008

    SciTech Connect (OSTI)

    Brenda R. Pace

    2009-01-01

    This report describes the cultural resource monitoring activities of the Idaho National Laboratorys (INL) Cultural Resource Management (CRM) Office during fiscal year 2008 (FY 2008). Throughout the year, 45 cultural resource localities were revisited including: two locations of heightened Shoshone-Bannock tribal sensitivity, four caves, one butte, twenty-eight prehistoric archaeological sites, three historic homesteads, two historic stage stations, one historic canal construction camp, three historic trails, and Experimental Breeder Reactor-I, which is a designated National Historic Landmark. Several INL project areas were also monitored in FY 2008 to assess project compliance with cultural resource recommendations, confirm the locations of previously recorded cultural resources in relation to project activities, to assess the damage caused by fire-fighting efforts, and to watch for cultural materials during ground disturbing activities. Although impacts were documented at a few locations, no significant adverse effects that would threaten the National Register eligibility of any resource were observed. Monitoring also demonstrated that INL projects generally remain in compliance with recommendations to protect cultural resources

  3. Preliminary report on shallow research drilling in the Salton Sea region

    SciTech Connect (OSTI)

    Newmark, R.L.; Kasameyer, P.W.; Younker, L.W.

    1988-01-14

    During two shallow thermal drilling programs, thermal measurements were obtained in 56 shallow (76.2 m) and one intermediate (457.3 m) depth holes located both onshore and offshore along the southern margin of the Salton Sea in the Imperial Valley, California. These data complete the surficial coverage of the thermal anomaly, revealing the shape and lateral extent of the hydrothermal system. The thermal data show the region of high thermal gradients to extend only a short distance offshore to the north of the Quaternary volcanic domes which are exposed along the southern shore of the Salton Sea. The central thermal anomaly has an arcuate shape, about 4 km wide and 12 km long. Across the center of the anomaly, the transition zone between locations exhibiting high thermal gradients and those exhibiting regional thermal gradients is quite narrow. Thermal gradients rise from near regional (0.09/degree/C/m) to extreme (0.83/degree/C/m) in only 2.4 km. The heat flow in the central part of the anomaly is greater than 600 mW/m/sup 2/ and in some areas exceeds 1200 mW/m/sup 2/. The shape of the thermal anomaly is asymmetric with respect to the line of volcanoes previously thought to represent the center of the field, with its center line offset south of the volcanic buttes. There is no broad thermal anomaly associated with the magnetic high that extends offshore to the northeast from the volcanic domes.

  4. Hydrogeologic Model for the Gable Gap Area, Hanford Site

    SciTech Connect (OSTI)

    Bjornstad, Bruce N.; Thorne, Paul D.; Williams, Bruce A.; Last, George V.; Thomas, Gregory S.; Thompson, Michael D.; Ludwig, Jami L.; Lanigan, David C.

    2010-09-30

    Gable Gap is a structural and topographic depression between Gable Mountain and Gable Butte within the central Hanford Site. It has a long and complex geologic history, which includes tectonic uplift synchronous with erosional downcutting associated with the ancestral Columbia River during both Ringold and Cold Creek periods, and by the later Ice Age (mostly glacial Lake Missoula) floods. The gap was subsequently buried and partially backfilled by mostly coarse-grained, Ice Age flood deposits (Hanford formation). Erosional remnants of both the Ringold Formation and Cold Creek unit locally underlie the high-energy flood deposits. A large window exists in the gap where confined basalt aquifers are in contact with the unconfined suprabasalt aquifer. Several paleochannels, of both Hanford and Ringold Formation age, were eroded into the basalt bedrock across Gable Gap. Groundwater from the Central Plateau presently moves through Gable Gap via one or more of these shallow paleochannels. As groundwater levels continue to decline in the region, groundwater flow may eventually be cut off through Gable Gap.

  5. Geopressured-geothermal well report. Volume I. Drilling and completion

    SciTech Connect (OSTI)

    Not Available

    1982-01-01

    Gladys McCall site activities are covered through the completion of the test well and salt water disposal well. The test well was drilled to a total depth of 16,510 feet, then plugged back to 15,831 feet. Three 4'' diameter diamond cores were taken for analysis. An existing well on site, the Getty-Butts Gladys McCall No. 1, was reentered and completed to a depth of 3514 feet as a salt water disposal well. The geologic interpretation of the Gladys McCall site indicated target sands for testing at 15,080 feet through 15, 831 feet. Reservoir fluid temperature at this depth is estimated to be approximately 313/sup 0/F and pressure is estimated to be +-12,800 psi. The preliminary reservoir volume estimate is 3.6 billion barrels of brine. The design wells program includes environmental monitoring of the Gladys McCall site by Louisiana State University. Field stations are set up to monitor surface and ground water quality, subsidence, land loss and shoreline erosion, and seismicity. As of December 31, 1981 the study shows no significant impact on the environment by site operations.

  6. MHD Integrated Topping Cycle Project. Sixteenth quarterly technical progress report, May 1991--July 1991

    SciTech Connect (OSTI)

    Not Available

    1992-03-01

    The Magnetohydrodynamics (MHD) Integrated Topping Cycle (ITC) Project represents the culmination of the proof-of-concept (POC) development stage in the US Department of Energy (DOE) program to advance MHD technology to early commercial development stage utility power applications. The project is a joint effort, combining the skills of three topping cycle component developers: TRW, Avco/TDS, and Westinghouse. TRW, the prime contractor and system integrator, is responsible for the 50 thermal megawatt (50 MW{sub t}) slagging coal combustion subsystem. Avco/TDS is responsible for the MHD channel subsystem (nozzle, channel, diffuser, and power conditioning circuits), and Westinghouse is responsible for the current consolidation subsystem. The ITC Project will advance the state-of-the-art in MHD power systems with the design, construction, and integrated testing of 50 MW{sub t} power train components which are prototypical of the equipment that will be used in an early commercial scale MHD utility retrofit. Long duration testing of the integrated power train at the Component Development and Integration Facility (CDIF) in Butte, Montana will be performed, so that by the early 1990`s, an engineering data base on the reliability, availability, maintainability and performance of the system will be available to allow scaleup of the prototypical designs to the next development level. This Sixteenth Quarterly Technical Progress Report covers the period May 1, 1991 to July 31, 1991.

  7. MHD Advanced Power Train Phase I, Final Report, Volume 6

    SciTech Connect (OSTI)

    A. R. Jones

    1985-08-01

    Under contract to the Department of Energy, Westinghouse has prepared the definition of a program plan for the development of an MHD Advanced Power Train (APT). The scope of work of this contract includes conceptual designs of early commercial MHD/steam electric plants (topping/bottoming) ranging from 200 to 1000 Mw(e). These plant designs were prepared during 1982 and made use of a system analysis model that provides performance and design information and economic estimates. In early April 1984, DOE requested westinghouse to perform special studies under the existing APT contract to aid the Department in evaluating MHD program options. Two tasks were defined by DOE: the first task was to evaluate an 80 MW(t) integrated test system (with steam electric bottoming cycle) for installation at the CDIF in Butte, Montana; the second task was to investigate placing a 50 MW(e) MHD topping stage onto an existing steam electric plant (as a retrofit). This volume of the final report documents the results of these special studies. Highlights of the studies were presented orally to DOE on May 15, 1984.

  8. MHD Integrated Topping Cycle Project

    SciTech Connect (OSTI)

    Not Available

    1992-03-01

    The Magnetohydrodynamics (MHD) Integrated Topping Cycle (ITC) Project represents the culmination of the proof-of-concept (POC) development stage in the US Department of Energy (DOE) program to advance MHD technology to early commercial development stage utility power applications. The project is a joint effort, combining the skills of three topping cycle component developers: TRW, Avco/TDS, and Westinghouse. TRW, the prime contractor and system integrator, is responsible for the 50 thermal megawatt (50 MW{sub t}) slagging coal combustion subsystem. Avco/TDS is responsible for the MHD channel subsystem (nozzle, channel, diffuser, and power conditioning circuits), and Westinghouse is responsible for the current consolidation subsystem. The ITC Project will advance the state-of-the-art in MHD power systems with the design, construction, and integrated testing of 50 MW{sub t} power train components which are prototypical of the equipment that will be used in an early commercial scale MHD utility retrofit. Long duration testing of the integrated power train at the Component Development and Integration Facility (CDIF) in Butte, Montana will be performed, so that by the early 1990's, an engineering data base on the reliability, availability, maintainability and performance of the system will be available to allow scaleup of the prototypical designs to the next development level. This Sixteenth Quarterly Technical Progress Report covers the period May 1, 1991 to July 31, 1991.

  9. INITIAL ANALYSIS OF TRANSIENT POWER TIME LAG DUE TO HETEROGENEITY WITHIN THE TREAT FUEL MATRIX.

    SciTech Connect (OSTI)

    D.M. Wachs; A.X. Zabriskie, W.R. Marcum

    2014-06-01

    The topic Nuclear Safety encompasses a broad spectrum of focal areas within the nuclear industry; one specific aspect centers on the performance and integrity of nuclear fuel during a reactivity insertion accident (RIA). This specific accident has proven to be fundamentally difficult to theoretically characterize due to the numerous empirically driven characteristics that quantify the fuel and reactor performance. The Transient Reactor Test (TREAT) facility was designed and operated to better understand fuel behavior under extreme (i.e. accident) conditions; it was shutdown in 1994. Recently, efforts have been underway to commission the TREAT facility to continue testing of advanced accident tolerant fuels (i.e. recently developed fuel concepts). To aid in the restart effort, new simulation tools are being used to investigate the behavior of nuclear fuels during facility’s transient events. This study focuses specifically on the characterizing modeled effects of fuel particles within the fuel matrix of the TREAT. The objective of this study was to (1) identify the impact of modeled heterogeneity within the fuel matrix during a transient event, and (2) demonstrate acceptable modeling processes for the purpose of TREAT safety analyses, specific to fuel matrix and particle size. Hypothetically, a fuel that is dominantly heterogeneous will demonstrate a clearly different temporal heating response to that of a modeled homogeneous fuel. This time difference is a result of the uniqueness of the thermal diffusivity within the fuel particle and fuel matrix. Using MOOSE/BISON to simulate the temperature time-lag effect of fuel particle diameter during a transient event, a comparison of the average graphite moderator temperature surrounding a spherical particle of fuel was made for both types of fuel simulations. This comparison showed that at a given time and with a specific fuel particle diameter, the fuel particle (heterogeneous) simulation and the homogeneous simulation were related by a multiplier relative to the average moderator temperature. As time increases the multiplier is comparable to the factor found in a previous analytical study from literature. The implementation of this multiplier and the method of analysis may be employed to remove assumptions and increase fidelity for future research on the effect of fuel particles during transient events.

  10. MODELING OF THE GROUNDWATER TRANSPORT AROUND A DEEP BOREHOLE NUCLEAR WASTE REPOSITORY

    SciTech Connect (OSTI)

    N. Lubchenko; M. Rodríguez-Buño; E.A. Bates; R. Podgorney; E. Baglietto; J. Buongiorno; M.J. Driscoll

    2015-04-01

    The concept of disposal of high-level nuclear waste in deep boreholes drilled into crystalline bedrock is gaining renewed interest and consideration as a viable mined repository alternative. A large amount of work on conceptual borehole design and preliminary performance assessment has been performed by researchers at MIT, Sandia National Laboratories, SKB (Sweden), and others. Much of this work relied on analytical derivations or, in a few cases, on weakly coupled models of heat, water, and radionuclide transport in the rock. Detailed numerical models are necessary to account for the large heterogeneity of properties (e.g., permeability and salinity vs. depth, diffusion coefficients, etc.) that would be observed at potential borehole disposal sites. A derivation of the FALCON code (Fracturing And Liquid CONvection) was used for the thermal-hydrologic modeling. This code solves the transport equations in porous media in a fully coupled way. The application leverages the flexibility and strengths of the MOOSE framework, developed by Idaho National Laboratory. The current version simulates heat, fluid, and chemical species transport in a fully coupled way allowing the rigorous evaluation of candidate repository site performance. This paper mostly focuses on the modeling of a deep borehole repository under realistic conditions, including modeling of a finite array of boreholes surrounded by undisturbed rock. The decay heat generated by the canisters diffuses into the host rock. Water heating can potentially lead to convection on the scale of thousands of years after the emplacement of the fuel. This convection is tightly coupled to the transport of the dissolved salt, which can suppress convection and reduce the release of the radioactive materials to the aquifer. The purpose of this work has been to evaluate the importance of the borehole array spacing and find the conditions under which convective transport can be ruled out as a radionuclide transport mechanism. Preliminary results show that modeling of the borehole array, including the surrounding rock, predicts convective flow in the system with physical velocities of the order of 10-5 km/yr over 105 years. This results in an escape length on the order of kilometers, which is comparable to the repository depth. However, a correct account of the salinity effects reduces convection velocity and escape length of the radionuclides from the repository.

  11. Atomistic Simulations of Mass and Thermal Transport in Oxide Nuclear Fuels

    SciTech Connect (OSTI)

    Andersson, Anders D.; Uberuaga, Blas P.; Du, Shiyu; Liu, Xiang-Yang; Nerikar, Pankaj; Stanek, Christopher R.; Tonks, Michael; Millet, Paul; Biner, Bulent

    2012-06-04

    In this talk we discuss simulations of the mass and thermal transport in oxide nuclear fuels. Redistribution of fission gases such as Xe is closely coupled to nuclear fuel performance. Most fission gases have low solubility in the fuel matrix, specifically the insolubility is most pronounced for large fission gas atoms such as Xe, and as a result there is a significant driving force for segregation of gas atoms to grain boundaries or dislocations and subsequently for nucleation of gas bubbles at these sinks. The first step of the fission gas redistribution is diffusion of individual gas atoms through the fuel matrix to existing sinks, which is governed by the activation energy for bulk diffusion. Fission gas bubbles are then formed by either separate nucleation events or by filling voids that were nucleated at a prior stage; in both cases their formation and latter growth is coupled to vacancy dynamics and thus linked to the production of vacancies via irradiation or thermal events. In order to better understand bulk Xe behavior (diffusion mechanisms) in UO{sub 2{+-}x} we first calculate the relevant activation energies using density functional theory (DFT) techniques. By analyzing a combination of Xe solution thermodynamics, migration barriers and the interaction of dissolved Xe atoms with U, we demonstrate that Xe diffusion predominantly occurs via a vacancy-mediated mechanism, though other alternatives may exist in high irradiation fields. Since Xe transport is closely related to diffusion of U vacancies, we have also studied the activation energy for this process. In order to explain the low value of 2.4 eV found for U migration from independent damage experiments (not thermal equilibrium) the presence of vacancy clusters must be included in the analysis. Next a continuum transport model for Xe and U is formulated based on the diffusion mechanisms established from DFT. After combining this model with descriptions of the interaction between Xe and grain boundaries derived from separate atomistic calculations, we simulate Xe redistribution for a few simple microstructures using finite element methods (FEM), as implemented in the MOOSE framework from Idaho National Laboratory. Thermal transport together with the power distribution determines the temperature distribution in the fuel rod and it is thus one of the most influential properties on nuclear fuel performance. The fuel thermal conductivity changes as function of time due to microstructure evolution (e.g. fission gas redistribution) and compositional changes. Using molecular dynamics simulations we have studied the impact of different types of grain boundaries and fission gas bubbles on UO{sub 2} thermal conductivity.

  12. Significance of Dynamic and Transient Analysis in the Design and Operation of Hybrid Energy Systems

    SciTech Connect (OSTI)

    Panwar, Mayank; Mohanpurkar, Manish; Hovsapian, Rob; Osorio, Julian D.

    2015-02-01

    Energy systems were historically designed and operated with a specific energy conversion objective, while managing loads and resources. In the recent years, the increased utilization of non-dispatchable renewable sources such as wind and solar has played a role in power quality and the reliability of power systems. In order to mitigate the risk associated with the non-dispatchable resources an integrated approach, such as Hybrid Energy Systems (HES), has to be taken, integrating the loads and resource management between the traditional thermal power plants and the non-dispatchable resources. As our electric energy becomes more diverse in its generation resources, the HES with its operational control system, its real-time view and its dynamic decisions making will become an essential part of the integrated energy systems and improve the overall grid reliability. The operational constraints of the energy sources on both the thermal power plants and the non-dispatchable resources in HES, plays a vital role in the planning and design stage. It is an established fact that the choice of energy source depends on the available natural resources and possible infrastructure. A critical component of decision-making depends on the complementary nature and controllability of the energy sources to supply the load demands with high reliability. Controllability of complex HES to achieve desired performance and flexibility is implemented via coordinated control systems while simultaneously generating electricity and other useful products such as useful heat or hydrogen. These systems are based on instrumentation, signal processing, control theory, and engineering system design. The entire HES along with the control systems are characterized by widely varying time constants. Hence, for a well-coordinated control and operation, we propose physics based modeling of the subsystems to assist in a dynamic and transient analysis. Dynamic and transient analysis in real and non-real time domain of the potential sources is capable of providing satisfactory results at the feasibility analysis stage. A simplified HES consisting of complementary energy sources is used to demonstrate the proposed approach. Suitable real time simulations to perform dynamic and transient analysis will be performed to verify results from the non-real time analysis. The role of such analyses, especially the real time dynamic and transient analysis for manual controls is elaborated. It is also discussed that faster than real time simulation will pave the future for controller rooms and hence manual control procedures. Multiple tools such as Real Time Simulator, Matlab®, Simulink®, PSCAD®, MOOSE, etc. are expected to be used for the HES analysis.

  13. NEAMS update quarterly report for January - March 2012.

    SciTech Connect (OSTI)

    Bradley, K.S.; Hayes, S.; Pointer, D.; Summers, R.; Sadasivan, P.; Sun, X.; Bernholdt, D.; Miller, M.; Stewart, J.

    2012-05-10

    Quarterly highlights are: (1) The integration of Denovo and AMP was demonstrated in an AMP simulation of the thermo-mechanics of a complete fuel assembly; (2) Bison was enhanced with a mechanistic fuel cracking model; (3) Mechanistic algorithms were incorporated into various lower-length-scale models to represent fission gases and dislocations in UO2 fuels; (4) Marmot was improved to allow faster testing of mesoscale models using larger problem domains; (5) Component models of reactor piping were developed for use in Relap-7; (6) The mesh generator of Proteus was updated to accept a mesh specification from Moose and equations were formulated for the intermediate-fidelity Proteus-2D1D module; (7) A new pressure solver was implemented in Nek5000 and demonstrated to work 2.5 times faster than the previous solver; (8) Work continued on volume-holdup models for two fuel reprocessing operations: voloxidation and dissolution; (9) Progress was made on a pyroprocessing model and the characterization of pyroprocessing emission signatures; (10) A new 1D groundwater waste transport code was delivered to the used fuel disposition (UFD) campaign; (11) Efforts on waste form modeling included empirical simulation of sodium-borosilicate glass compositions; (12) The Waste team developed three prototypes for modeling hydride reorientation in fuel cladding during very long-term fuel storage; (13) A benchmark demonstration problem (fission gas bubble growth) was modeled to evaluate the capabilities of different meso-scale numerical methods; (14) Work continued on a hierarchical up-scaling framework to model structural materials by directly coupling dislocation dynamics and crystal plasticity; (15) New 'importance sampling' methods were developed and demonstrated to reduce the computational cost of rare-event inference; (16) The survey and evaluation of existing data and knowledge bases was updated for NE-KAMS; (17) The NEAMS Early User Program was launched; (18) The Nuclear Regulatory Commission (NRC) Office of Regulatory Research was introduced to the NEAMS program; (19) The NEAMS overall software quality assurance plan (SQAP) was revised to version 1.5; and (20) Work continued on NiCE and its plug-ins and other utilities, such as Cubit and VisIt.

  14. FRAGMENTATION IN THE FIRST GALAXIES

    SciTech Connect (OSTI)

    Safranek-Shrader, Chalence; Bromm, Volker; Milosavljevic, Milos

    2010-11-10

    Motivated by recent simulations of galaxy formation in which protogalaxies acquire their baryonic content through cold accretion, we study the gravitational fragmentation of cold streams flowing into a typical first galaxy. We use a one-zone hydrodynamical model to examine the thermal evolution of the gas flowing into a 10{sup 8} M{sub sun} dark matter halo at redshift z = 10. The goal is to gain an understanding of the expected fragmentation mass scale and thus the characteristic mass of the first population of stars to form by shock fragmentation. Our model accurately describes the chemical and thermal evolution of the gas as we are specifically concerned with how the chemical abundances and initial conditions of the low-density, metal-enriched, cold accretion streams that pass an accretion shock alter the cooling properties and tendency to fragment in the post-shock gas. Cold accretion flows are not shock heated at the virial radius but instead flow along high-baryonic-density filaments of the cosmic web and penetrate deep into the host halo of the protogalaxy. In this physical regime, if molecular cooling is absent because of a strong Lyman-Werner background, we find there to be a sharp drop in the fragmentation mass at a metallicity of Z {approx} 10{sup -4} Z{sub sun}. If, however, H{sub 2} and HD molecules are present, they dominate the cooling at T < 10{sup 4} K, and metallicity then has no effect on the fragmentation properties of the cold stream. For a solar abundance pattern of metallicity, O is the most effective metal coolant throughout the evolution, while for a pair instability supernova (PISN) metallicity yield, Si{sup +} is the most effective coolant. PISN abundance patterns also exhibit a slightly smaller critical metallicity. Dust grains are not included in our chemical model, but we argue that their inclusion would not significantly alter the results. We also find that this physical scenario allows for the formation of stellar clusters and large, 10{sup 4} M{sub sun} bound fragments, possibly the precursors to globular clusters and supermassive black holes. Finally, we conclude that the usual assumption of isobaricity for galactic shocks breaks down in gas of a sufficiently high metallicity, suggesting that metal cooling leads to thermal instabilities.

  15. PHOTOELECTRIC CHARGING OF DUST GRAINS IN THE ENVIRONMENT OF YOUNG STELLAR OBJECTS

    SciTech Connect (OSTI)

    Pedersen, Andreas; Gomez de Castro, Ana I.

    2011-10-20

    The evolution of disks around young stellar objects (YSOs) is deeply affected by the YSOs' ultraviolet (UV) radiation field especially in the 500-1100 A spectral range. The two dominant processes are: the photodissociation of H{sub 2} molecules in the Werner and Lyman bands, and the emission of photoelectrons from dust grains when high energy photons are absorbed. Photoelectrons are an important source of gas heating. In this paper, dust grain charging when exposed to various possible UV fields in the YSOs' environment is investigated. Numerical simulations of the evolution of photoelectrons in the electric field created by the charged dust grains are carried out to obtain the charging profile of dust grains. From the simulations it appears that the different spectra produce significant quantitative and qualitative differences in the charging processes. Both the UV background and the Ae-Herbig star radiation field produce a relatively slow charging of dust grains due to the low fraction of sufficiently energetic photons. The radiation field of T Tauri stars (TTSs) is harder due to the release of magnetic energy in the dense magnetospheric environment. These numerical results have been used to propose a new simple analytical model for grain charging in the atmosphere of protostellar disks around TTSs susceptible to be used in any disk modeling. It has been found that the yield decreases exponentially with the dust charge and that two populations of photoelectrons are produced: a low energy population with mean kinetic energy E = 2.5 eV and a high energy population with E = 5.5-6 eV; the energy dispersion within the populations is {approx}1.3 eV (T {approx} 1.5 x 10{sup 4} K). The high energy population is susceptible of dissociating the H{sub 2} and ionizing some low ionization potential species, such as the Mg. These results add an additional role to dust on the chemistry of the layers just below the H{sub 2} photoionization front. This photoelectic yield has been applied to a simple evaluation of the dust charge in the atmospheres of accretion disks ({alpha}-disks).

  16. Final report on SNAC 11

    SciTech Connect (OSTI)

    Huber, Patrick

    2013-06-26

    This report details how the $5,000 DOE grant to support the workshop titled Sterile Neutrinos at the Crossroads (or SNAC11) was allocated and spent. The SNAC11 workshop covered three days during which there were 28 talks, multiple discussion sessions, a poster session with 9 posters delivered, and an impromptu public lecture on the OPERA superluminal neutrino result by the former project manager of OPERA (this was the first official OPERA talk on the subject in North America). The workshop scientific agenda can be viewed at http://www.cpe.vt.edu/snac/program.html. Emerging out of the workshop discussions, was the idea to write a comprehensive white paper describing the current state of the light sterile neutrino. This effort soon became an international collaboration. The final document, titled Light Sterile Neutrinos: A White Paper has nearly 200 authors, is 267 pages long, and cites 730 unique references. It has been posted the preprint archive as arXiv:1204.5379 [hep-ph]. Workshop local organizing committee co-chairs, Patrick Huber and Jonathan Link, are the white papers head editors. The white papers sections and section editors are as follows: 1. Theory and Motivation (Gabriela Barenboim, Valencia and Werner Rodejohann, MPI Heidelberg) 2. Astrophysical Evidence (Kev Abazajian, UC Irvine and Yvonne Wong, Aachen) 3. Evidence from Oscillation Experiments (Joachim Kopp, FNAL and Bill Louis, LANL) 4. Global Picture (Thierry Lasserre, CEA Saclay and Thomas Schwetz, MPI Heidelberg) 5. Requirements for Future Measurements (Bonnie Fleming, Yale and Joe Formaggio, MIT) 6. Appendix: Possible Future Experiments (Patrick Huber, Virginia Tech and Jon Link, Virginia Tech) In all 56 people participated in the workshop, of these 11 were young scientists. The workshop was covered in a feature article in Science (Science, 334, (2011), 304-306.). The DOE award was spent, as budgeted, as contractual services to VT CPE, which is the unit within the University which organizes conferences. Specifically, the travel cost of the speakers P. Langacker, K. Schreckenbach and P. Vogel was covered as well as bus transportation to KURF and to/from the airport.

  17. Habitat Evaluation Procedures (HEP) Report : Hellsgate Project, 1999-2000 Technical Report.

    SciTech Connect (OSTI)

    Berger, Matthew

    2000-05-01

    A Habitat Evaluation Procedure (HEP) study was conducted on lands acquired and/or managed (4,568 acres total) by the Hellsgate Big Game Winter Range Wildlife Mitigation Project (Hellsgate project) to mitigate some of the losses associated with the original construction and operation of Grand Coulee Dam and inundation of habitats behind the dams. Three separate properties, totaling 2,224 acres were purchased in 1998. One property composed of two separate parcels, mostly grassland lies southeast of the town of Nespelem in Okanogan County (770 acres) and was formerly called the Hinman property. The former Hinman property lies within an area the Tribes have set aside for the protection and preservation of the sharp-tailed grouse (Agency Butte unit). This special management area minus the Hinman acquisition contains 2,388 acres in a long-term lease with the Tribes. The second property lies just south of the Silver Creek turnoff (Ferry County) and is bisected by the Hellsgate Road (part of the Friedlander unit). This parcel contains 60 acres of riparian and conifer forest cover. The third property (now named the Sand Hills unit) acquired for mitigation (1,394 acres) lies within the Hellsgate Reserve in Ferry County. This new acquisition links two existing mitigation parcels (the old Sand Hills parcels and the Lundstrum Flat parcel, all former Kuehne purchases) together forming one large unit. HEP team members included individuals from the Colville Confederated Tribes Fish and Wildlife Department (CTCR), Washington Department of Fish and Wildlife (WDFW), and Bureau of Land Management (BLM). The HEP team conducted a baseline habitat survey using the following HEP species models: mule deer (Odocoileus hemionus), mink (Mustela vison), downy woodpecker (Picoides pubescens), bobcat (Lynx rufus), yellow warbler (Dendroica petechia), and sharp-tailed grouse (Tympanuchus phasianellus columbianus). HEP analysis and results are discussed within the body of the text. The cover types evaluated for this study were grasslands, shrub-steppe, rock, conifer forest and woodland, and riparian. These same cover types were evaluated for other Hellsgate Project acquisitions within the same geographic area. Mule deer habitat on the Sand Hills unit rated good overall for winter food and cover in the shrub-steppe and conifer woodland cover types. Sharp-tailed grouse habitat on the former Hinman property and special management area rated good for nesting and brood rearing in the grassland cover type. Mink habitat on the Friedlander parcel rated poor due to lack of food and cover in and along the riparian cover type. The Downy woodpecker rated poor for food and cover on the Friedlander parcel in the conifer forest cover type. This species also rated poor on the conifer woodland habitat on the Hinman parcel. Yellow warbler habitat on the Agency Butte Special Management area rated very poor due to lack of shrubs for cover and reproduction around the scattered semi/permanent ponds that occur on the area. Bobcat habitat on this same area rated poor due to lack of cover and food. Fragmentation of existing quality habitat is also a problem for both these species. This report is an analysis of baseline habitat conditions on mitigation and managed lands, and provides estimated habitat units for mitigation crediting purposes. In addition, this information will be used to manage these lands for the benefit of wildlife.

  18. A comparative evaluation of laser and GTA welds in a high-strength titanium alloy -- Ti-6-22-22S

    SciTech Connect (OSTI)

    Baeslack, W.A. III; Hurley, J.; Paskell, T.

    1994-12-31

    Titanium alloy Ti-6Al-2Sn-2Zr-2Mo-2Cr-025Si (hereafter designated Ti-6-22-22S)is an alpha-beta titanium alloy developed for deep hardenability, high strength, intermediate temperature creep resistance, and moderate toughness. As a potential structural material for next-generation aircraft and aerospace systems, the weldability of Ti-6-22-22S has recently become a subject of increasing importance and concern. In the welding of titanium sheet, achieving satisfactory ductility is the principal limitation to alloy weldability, with poor ductility promoted by a coarse beta grain structure in the weld fusion and near-heat-affected zones. Square-butt welds were produced in 1.6 mm thick Ti-6-22-22S sheet using automatic GTA and CO{sub 2} laser welding systems. Microstructure analysis and DPH hardness traverses were performed on mounted. polished and etched specimens. Three-point bend and tensile tests were performed on transverse-weld and longitudinal-weld oriented specimens. Microstructure analysis of the laser welds revealed a fine, columnar fusion zone beta grain macrostructure and a fully-martensitic transformed-beta microstructure. Consistent with the microstructural similarities, fusion zone hardnesses of the laser welds were comparable (385 and 390 DPG, respectively) and greater than that of the base metal (330 DPH). In general, laser welds did not exhibit markedly superior ductilities relative to the GTAW, which was attributed to differences in the nature of the intragranular transformed-beta microstructures, being coarser and softer for the GTAW, the response of these as-welded microstructures to heat treatment, and interactions between the transformed-beta microstructure and the beta grain macrostructure.

  19. Experimental Investigations on Pulsed Nd:YAG Laser Welding of C17300 Copper-Beryllium and 49Ni-Fe Soft Magnetic Alloys

    SciTech Connect (OSTI)

    Mousavi, S. A. A. Akbari [School of Metallurgy and Materials Engineering, School of Engineering University of Tehran, Tehran (Iran, Islamic Republic of); School of Metallurgy and Materials Engineering, School of Engineering University of Tehran, Tehran (Iran, Islamic Republic of); Ebrahimzadeh, H. [School of Metallurgy and Materials Engineering, School of Engineering University of Tehran, Tehran (Iran, Islamic Republic of)

    2011-01-17

    Copper-beryllium and soft magnetic alloys must be joined in electrical and electro-mechanical applications. There is a high difference in melting temperatures of these alloys which cause to make the joining process very difficult. In addition, copper-beryllium alloys are of age hardenable alloys and precipitations can brittle the weld. 49Ni-Fe alloy is very hot crack sensitive. Moreover, these alloys have different heat transfer coefficients and reflection of laser beam in laser welding process. Therefore, the control of welding parameters on the formation of adequate weld puddle composition is very difficult. Laser welding is an advanced technique for joining of dissimilar materials since it can precisely control and adjust the welding parameters. In this study, a 100W Nd:YAG pulsed laser machine was used for joining 49Ni-Fe soft magnetic to C17300 copper-beryllium alloys. Welding of samples was carried out autogenously by changing the pulse duration, diameter of beam, welding speed, voltage and frequency. The spacing between samples was set to almost zero. The ample were butt welded. It was required to apply high voltage in this study due to high reflection coefficient of copper alloys. Metallography, SEM analysis, XRD and microhardness measurement was used for survey of results. The results show that the weld strength depends upon the chemical composition of the joints. To change the wells composition and heat input of the welds, it was attempted to deviate the laser focus away from the weld centerline. The best strength was achieved by deviation of the laser beam away about 0.1mm from the weld centerline. The result shows no intermetallic compounds if the laser beam is deviated away from the joint.

  20. Volcanic hazards of the Idaho National Engineering Laboratory and adjacent areas

    SciTech Connect (OSTI)

    Hackett, W.R.; Smith, R.P.

    1994-12-01

    Potential volcanic hazards are assessed, and hazard zone maps are developed for the Idaho National Engineering Laboratory (INEL) and adjacent areas. The basis of the hazards assessment and mapping is the past volcanic history of the INEL region, and the apparent similarity of INEL volcanism with equivalent, well-studied phenomena in other regions of active volcanism, particularly Hawaii and Iceland. The most significant hazards to INEL facilities are associated with basaltic volcanism, chiefly lava flows, which move slowly and mainly threaten property by inundation or burning. Related hazards are volcanic gases and tephra, and ground disturbance associated with the ascent of magma under the volcanic zones. Several volcanic zones are identified in the INEL area. These zones contain most of the volcanic vents and fissures of the region and are inferred to be the most probable sites of future INEL volcanism. Volcanic-recurrence estimates are given for each of the volcanic zones based on geochronology of the lavas, together with the results of field and petrographic investigations concerning the cogenetic relationships of INEL volcanic deposits and associated magma intrusion. Annual probabilities of basaltic volcanism within the INEL volcanic zones range from 6.2 {times} 10{sup {minus}5} per year (average 16,000-year interval between eruptions) for the axial volcanic zone near the southern INEL boundary and the Arco volcanic-rift zone near the western INEL boundary, to 1 {times} 10{sup {minus}5} per year (average 100,000-year interval between eruptions) for the Howe-East Butte volcanic rift zone, a geologically old and poorly defined feature of the central portion of INEL. Three volcanic hazard zone maps are developed for the INEL area: lava flow hazard zones, a tephra (volcanic ash) and gas hazard zone, and a ground-deformation hazard zone. The maps are useful in land-use planning, site selection, and safety analysis.

  1. Quarterly technical progress report for the period ending June 30, 1984

    SciTech Connect (OSTI)

    Not Available

    1984-10-01

    The Magnetohydrodynamics Program (Component Development and Integration Facility) in Butte, Montana, continued its site preparation for the TRW first-stage combustor installation. In the area of flue gas cleanup, our in-house research program is continuing its investigation into the causes of sorbent attrition in PETC's fluidized-bed copper oxide process for simultaneous SO/sub 2//NO/sub x/ removal. Interwoven with these tests is a series of spray dryer/electrostatic precipitator tests that are being conducted with the cooperation of Wheelabrator-Frye, Inc. This test series was completed this quarter, and the data show that when using a Kentucky coal, Wheelabrator-Frye's electrostatic precipitator provides excellent particulate control efficiency while using a spray dryer for sulfur dioxide removal. A unique project at Carnegie-Mellon University is looking at the concept of integrated environmental control for coal-fired power plants making use of precombustion, combustion, and postcombustion control, including systems for the simultaneous removal of more than one pollutant. The objective of this research is to develop a computer model and assessment for integrated environmental control systems that utilize conventional or advanced systems. The Liquid Phase Methanol Project Development Unit in LaPorte, Texas, was restarted after a successful shakedown run was completed. PETC has recently begun an in-house research project aimed at exploring the basic chemistry of liquefying coal in the presence of water under supercritical conditions. In the Alternative Fuels Technology Program, the Gulf Research and Development Company has completed the preliminary testing phase of its erosion test loop. Their results indicate that when pumping a coal-water slurry fuel through a flow loop, the erosion rate increases as velocity increases, suggesting a well-defined relationship between these two parameters.

  2. Laser welding and post weld treatment of modified 9Cr-1MoVNb steel.

    SciTech Connect (OSTI)

    Xu, Z.

    2012-04-03

    Laser welding and post weld laser treatment of modified 9Cr-1MoVNb steels (Grade P91) were performed in this preliminary study to investigate the feasibility of using laser welding process as a potential alternative to arc welding methods for solving the Type IV cracking problem in P91 steel welds. The mechanical and metallurgical testing of the pulsed Nd:YAG laser-welded samples shows the following conclusions: (1) both bead-on-plate and circumferential butt welds made by a pulsed Nd:YAG laser show good welds that are free of microcracks and porosity. The narrow heat affected zone has a homogeneous grain structure without conventional soft hardness zone where the Type IV cracking occurs in conventional arc welds. (2) The laser weld tests also show that the same laser welder has the potential to be used as a multi-function tool for weld surface remelting, glazing or post weld tempering to reduce the weld surface defects and to increase the cracking resistance and toughness of the welds. (3) The Vicker hardness of laser welds in the weld and heat affected zone was 420-500 HV with peak hardness in the HAZ compared to 240 HV of base metal. Post weld laser treatment was able to slightly reduce the peak hardness and smooth the hardness profile, but failed to bring the hardness down to below 300 HV due to insufficient time at temperature and too fast cooling rate after the time. Though optimal hardness of weld made by laser is to be determined for best weld strength, methods to achieve the post weld laser treatment temperature, time at the temperature and slow cooling rate need to be developed. (4) Mechanical testing of the laser weld and post weld laser treated samples need to be performed to evaluate the effects of laser post treatments such as surface remelting, glazing, re-hardening, or tempering on the strength of the welds.

  3. Shallow drilling in the Salton Sea region: The thermal anomaly

    SciTech Connect (OSTI)

    Newmark, R.L.; Kasameyer, P.W.; Younker, L.W.

    1988-11-10

    During two shallow thermal drilling programs, thermal measurements were obtained in 56 shallow (76.2 m) and one intermediate (457.3 m) depth holes located both onshore and offshore along the southern margin of the Salton Sea in the Imperial Valley, California. These data complete the surficial coverage of the thermal anomaly, revealing the shape and lateral extent of the hydrothermal system. The thermal data show the region of high thermal gradients to extend only a short distance offshore to the north of the Quaternary volcanic domes which are exposed along the southern shore of the Salton Sea. The central thermal anomaly has an arcuate shape, about 4 km wide and 12 km long. Across the center of the anomaly, the transition zone between locations exhibiting high thermal gradients and those exhibiting regional thermal gradients is quite narrow. Thermal gradients rise from near regional (0.09 /sup 0/C/m) to extreme (0.83 /sup 0/C/m) in only 2.4 km. The heat flow in the central part of the anomaly is greater than 600 mW/m/sup 2/ and in the two local anomalies exceeds 1200 mW/m/sup 2/. The shape of the thermal anomaly is asymmetric with respect to the line of volcanoes previously thought to represent the center of the field, with its center line offset south of the volcanic buttes. There is no broad thermal anomaly associated with the magnetic high that extends offshore to the northeast from the volcanic domes.

  4. Shallow Drilling In The Salton Sea Region, The Thermal Anomaly

    SciTech Connect (OSTI)

    Newmark, R. L.; Kasameyer, P. W.; Younker, L. W.

    1987-01-01

    During two shallow thermal drilling programs, thermal measurements were obtained in 56 shallow (76.2 m) and one intermediate (457.3 m) depth holes located both onshore and offshore along the southern margin of the Salton Sea in the Imperial Valley, California. These data complete the surficial coverage of the thermal anomaly, revealing the shape and lateral extent of the hydrothermal system. The thermal data show the region of high thermal gradients to extend only a short distance offshore to the north of the Quaternary volcanic domes which are exposed along the southern shore of the Salton Sea. The thermal anomaly has an arcuate shape, about 4 km wide and 12 km long. Across the center of the anomaly, the transition zone between locations exhibiting high thermal gradients and those exhibiting regional thermal gradients is quite narrow. Thermal gradients rise from near regional (0.09 C/m) to extreme (0.83 C/m) in only 2.4 km. The heat flow in the central part of the anomaly is >600 mW/m{sup 2} and in some areas exceeds 1200 mW/m{sup 2}. The shape of the thermal anomaly is asymmetric with respect to the line of volcanoes previously thought to represent the center of the field, with its center line offset south of the volcanic buttes. There is no broad thermal anomaly associated with the magnetic high that extends offshore to the northeast from the volcanic domes. These observations of the thermal anomaly provide important constraints for models of the circulation of the hydrothermal system. Thermal budgets based on a simple model for this hydrothermal system indicate that the heat influx rate for local ''hot spots'' in the region may be large enough to account for the rate of heat flux from the entire Salton Trough.

  5. Late Quaternary paleodune deposits in Abu Dhabi Emirate, UAF: Paleoclimatic implications

    SciTech Connect (OSTI)

    Brouwers, E.M.; Bown, T.M. (Geological Survey, Denver, CO (United States)); Hadley, D.G. (Geological Survey, Reston, VA (United States))

    1993-04-01

    Remnants of late Quaternary paleodunes are exposed near the coast of the Arabian Gulf and in large inland playas and interdunal areas in central and western Abu Dhabi Emirate over a distance of >45 km normal to the coast. Paleodunes occur south of Madinat Zayed (lat. 23[degree]35 N), which marks the northern limit of a modern dune field that grades into the mega-dune sand sea of the ar Rub al Khali, Saudi Arabia. Coastal paleodunes are composed of weakly cemented millolid foraminifers, ooids, and rounded biogenic grains, whereas inland and southward the paleodunes show a progressive increase in the proportion of eolian quartz sand. The paleodunes exhibit large-scale trough foresets in remnant exposures 0.5 to 10 m thick, indicating paleowind directions from 65[degree] to 184[degree] (dominantly southeast transport). Scattered paleoplaya remnants provide paleodune scale. Paleoplaya deposits form buttes 30--50 m high. If coeval with the Paleodunes, large-scale paleodune fields are implied (100+ m high), comparable to star dunes and sand mountains at the northwestern edge of the ar Rub al Khali. Based on U-Th isotopic analyses, the carbonate paleodune sands are >160ka and probably >250ka. The carbonate source was a shallow, nearly dry Arabian Gulf at a time when large areas were exposed during a low sea-level stand. Paleowind direction indicates that Pleistocene prevailing winds were northwesterly, the direction of the dominant (winter shamal) wind today. The geographic extend and implied magnitude of the paleodunes suggest large-scale eolian transport of carbonate sand during the Pleistocene disiccation, and admixed quartz sand identifies a youthful stage of contemporaneous evolution of the ar Rub al Khali. Wave-eroded paleodunes probably floor much of the present-day Gulf and extend beneath the modern dunes and sand mountains.

  6. MHD-generator-component development. Quarterly report, July 1980-September 1980

    SciTech Connect (OSTI)

    Not Available

    1980-12-01

    The overall objectives of this program are twofold: to contribute, by appropriate systematic experimental and analytical investigations, to the engineering database necessary for the design and construction of MHD generators at CDIF-scale (50 MW/sub th/) and baseload scale (2000 MW/sub th/), and to design and fabricate specific hardware items to be tested at the CDIF site in Butte, Montana. The overall program consists of a series of inter-related tasks, described as follows: (1) perform experimental investigations related to MHD channel design and performance by testing existing channel hardware and by fabricating and testing new channel hardware; (2) perform experimental investigations related to MHD channel perform and lifetime, with the principal aim of systematically obtaining data on the prototype electrodes for the coal-fired, subsonic, long-duration CDIF Generator 1B3; (3) perform testing on channel loading and control utilizing the supersonic Reference Channel No. 4 and other appropriate channels and/or test modules, at magnetic fields to 4 T; (4) provide for facility operation and maintenance of the Mk VI and Mk VII test bays; (5) design and fabricate the following items of CDIF hardware: CDIF Generator 1B2, CDIF Generator 1B3, CDIF 1B Ash Injection Combustor (AIC), CDIF Generator 1A2, and diagonal current control and load consolidation for the 1A2, 1B2 and 1B3 generators; and (4) compare the performance and durability characteristics of coal-fired versus (Mk VI-type) AIC-fired supersonic channels, using existing facilities at the AERL Haverhill site. Progress is described. (WHK)

  7. Light Water Reactor Sustainability Program Grizzly Year-End Progress Report

    SciTech Connect (OSTI)

    Benjamin Spencer; Yongfeng Zhang; Pritam Chakraborty; S. Bulent Biner; Marie Backman; Brian Wirth; Stephen Novascone; Jason Hales

    2013-09-01

    The Grizzly software application is being developed under the Light Water Reactor Sustainability (LWRS) program to address aging and material degradation issues that could potentially become an obstacle to life extension of nuclear power plants beyond 60 years of operation. Grizzly is based on INL’s MOOSE multiphysics simulation environment, and can simultaneously solve a variety of tightly coupled physics equations, and is thus a very powerful and flexible tool with a wide range of potential applications. Grizzly, the development of which was begun during fiscal year (FY) 2012, is intended to address degradation in a variety of critical structures. The reactor pressure vessel (RPV) was chosen for an initial application of this software. Because it fulfills the critical roles of housing the reactor core and providing a barrier to the release of coolant, the RPV is clearly one of the most safety-critical components of a nuclear power plant. In addition, because of its cost, size and location in the plant, replacement of this component would be prohibitively expensive, so failure of the RPV to meet acceptance criteria would likely result in the shutting down of a nuclear power plant. The current practice used to perform engineering evaluations of the susceptibility of RPVs to fracture is to use the ASME Master Fracture Toughness Curve (ASME Code Case N-631 Section III). This is used in conjunction with empirically based models that describe the evolution of this curve due to embrittlement in terms of a transition temperature shift. These models are based on an extensive database of surveillance coupons that have been irradiated in operating nuclear power plants, but this data is limited to the lifetime of the current reactor fleet. This is an important limitation when considering life extension beyond 60 years. The currently available data cannot be extrapolated with confidence further out in time because there is a potential for additional damage mechanisms (i.e. late blooming phases) to become active later in life beyond the current operational experience. To develop a tool that can eventually serve a role in decision-making, it is clear that research and development must be perfomed at multiple scales. At the engineering scale, a multiphysics analysis code that can capture the thermomechanical response of the RPV under accident conditions, including detailed fracture mechanics evaluations of flaws with arbitrary geometry and orientation, is needed to assess whether the fracture toughness, as defined by the master curve, including the effects of embrittlement, is exceeded. At the atomistic scale, the fundamental mechanisms of degradation need to be understood, including the effects of that degradation on the relevant material properties. In addition, there is a need to better understand the mechanisms leading to the transition from ductile to brittle fracture through improved continuum mechanics modeling at the fracture coupon scale. Work is currently being conducted at all of these levels with the goal of creating a usable engineering tool informed by lower length-scale modeling. This report summarizes progress made in these efforts during FY 2013.

  8. Case Study of The ARRA-Funded GSHP Demonstration at the Natural Sources Building, Montana Tech

    SciTech Connect (OSTI)

    Malhotra, Mini; Liu, Xiaobing

    2015-04-01

    Under the American Recovery and Reinvestment Act (ARRA), 26 ground source heat pump (GSHP) projects were competitively selected in 2009 to demonstrate the benefits of GSHP systems and innovative technologies for cost reduction and/or performance improvement. One of the selected demonstration projects was proposed by Montana Tech of the University of Montana for a 56,000 sq ft, newly constructed, on-campus research facility – the Natural Resources Building (NRB) located in Butte, Montana. This demonstrated GSHP system consists of a 50 ton water-to-water heat pump and a closed-loop ground heat exchanger with two redundant 7.5 hp constant-speed pumps to use water in the nearby flooded mines as a heat source or heat sink. It works in conjunction with the originally installed steam HX and an aircooled chiller to provide space heating and cooling. It is coupled with the existing hot water and chilled water piping in the building and operates in the heating or cooling mode based on the outdoor air temperature. The ground loop pumps operate in conjunction with the existing pumps in the building hot and chilled water loops for the operation of the heat pump unit. The goal of this demonstration project is to validate the technical and economic feasibility of the demonstrated commercial-scale GSHP system in the region, and illustrate the feasibility of using mine waters as the heat sink and source for GSHP systems. Should the demonstration prove satisfactory and feasible, it will encourage similar GSHP applications using mine water, thus help save energy and reduce carbon emissions. The actual performance of the system is analyzed with available measured data for January through July 2014. The annual energy performance is predicted and compared with a baseline scenario, with the heating and cooling provided by the originally designed systems. The comparison is made in terms of energy savings, operating cost savings, cost-effectiveness, and environmental benefits. Finally, limitations in conducting the analysis are identified and recommendations for improvement in the control and operation of such systems are made.

  9. Effect of Nd:YAG laser welding on microstructure and hardness of an Al-Li based alloy

    SciTech Connect (OSTI)

    Cui, Li, E-mail: cuili@bjut.edu.cn [Beijing University of Technology (China)] [Beijing University of Technology (China); Li, Xiaoyan, E-mail: xyli@bjut.edu.cn [Beijing University of Technology (China)] [Beijing University of Technology (China); He, Dingyong, E-mail: dyhe@bjut.edu.cn [Beijing University of Technology (China)] [Beijing University of Technology (China); Chen, Li, E-mail: ouchenxi@163.com [AVIC Beijing Aeronautical Manufacturing Technology Research Institute (China)] [AVIC Beijing Aeronautical Manufacturing Technology Research Institute (China); Gong, Shuili, E-mail: gongshuili@sina.com [AVIC Beijing Aeronautical Manufacturing Technology Research Institute (China)] [AVIC Beijing Aeronautical Manufacturing Technology Research Institute (China)

    2012-09-15

    Butt joints of 3.0 mm thick sheets of an Al-Li based alloy have been produced using Nd:YAG laser welding without filler metals. The hardness distribution and microstructure of the alloy and welded joints were investigated. The changes in the grain shapes, grain orientations, microtexture, and precipitates of the fusion zone were analyzed using optical microscope, electron back scattered diffraction (EBSD) and transmission electron microscopy (TEM). The results show that Nd:YAG laser welding leads to a change of the microhardness, grain shape, grain orientations, and a disappearance of the microtexture and precipitates. A narrow band of EQZ along the fusion boundary and a predominantly equiaxed dendritic structure are developed in the fusion zone. The formation of the predominately equiaxed dendritic grains is due to a heterogeneous nucleation mechanism aided by equilibrium A1{sub 3}Zr phases as well as the growth of pre-existing nuclei created by dendrite fragmentation, or by grain detachment resulted from Nd:YAG laser welding processes. In addition, Nd:YAG laser welding produces lower Vickers hardness than that of the base metal due to the decrease in the in quantity of {delta} Prime precipitates in the fusion zone. - Graphical Abstract: The grain shapes, grain orientations, microtexture, and precipitates of the solidified fusion zone were investigated and compared with the base metal using optical microscope, electron back scattered diffraction (EBSD) and transmission electron microscope (TEM). EBSD orientation map of laser welded joint in 5A90 alloys is presented in Fig. 3. It clearly shows that a narrow band EQZ along the fusion boundary and the predominantly equiaxed grains have been developed in the fusion zone of 5A90 alloys. Also, it is clear that the microstructure of the base metal is characterized by laminated grains with preferred orientations, whereas the fusion zone is predominately equiaxed grains in different colors having random orientations. Highlights: Black-Right-Pointing-Pointer The predominantly equiaxed dendritic structure is developed in the fusion zone. Black-Right-Pointing-Pointer The fusion zone with equiaxed grains shows random orientations and microtexture. Black-Right-Pointing-Pointer The loss in hardness in the fusion zone is due to the decrease in {delta} Prime precipitates. Black-Right-Pointing-Pointer The non-epitaxial growth occurs at fusion boundary. Black-Right-Pointing-Pointer The equilibrium A1{sub 3}Zr phases maybe the nuclei of new grains in the fusion zone.

  10. Continuation of Studies on Development of ODS Heat Exchanger Tubing

    SciTech Connect (OSTI)

    Lawrence Brown; David Workman; Bimal Kad; Gaylord Smith; Archie Robertson; Ian Wright

    2008-04-15

    The Department of Energy (DOE), National Energy Technology Center (NETL), has initiated a strategic plan for the development of advanced technologies needed to design and build fossil fuel plants with very high efficiency and environmental performance. These plants, referred to as 'Vision 21' and FutureGen programs by DOE, will produce electricity, chemicals, fuels, or a combination of these products, and possibly secondary products such as steam/heat for industrial use. MA956 is a prime candidate material being considered for a high temperature heat exchanger in the 'Vision 21' and FutureGen programs. This material is an oxide dispersion strengthened (ODS) alloy; however, there are some gaps in the data required to commit to the use of these alloys in a full-size plant. To fill the technology gaps for commercial production and use of the material for 'Advanced Power Generation Systems' this project has performed development activity to significant increase in circumferential strength of MA956 as compared to currently available material, investigated bonding technologies for bonding tube-to-tube joints through joining development, and performed tensile, creep and fire-side corrosion tests to validate the use and fabrication processes of MA956 to heat exchanger tubing applications. Development activities within this projected has demonstrated increased circumferential strength of MA956 tubes through flow form processing. Of the six fabrication technologies for bonding tube-to-tube joints, inertia friction welding (IFW) and flash butt welding (FBW) were identified as processes for joining MA956 tubes. Tensile, creep, and fire-side corrosion test data were generated for both base metal and weld joints. The data can be used for design of future systems employing MA956. Based upon the positive development activities, two test probes were designed and fabricated for field exposure testing at 1204 C ({approx}2200 F) flue gas. The probes contained tube portions with FBW and IFW welded MA956. Field testing of the probes and remaining heat exchanger design activity will be performed by Oak Ridge National Laboratory under DOE Contract DE-AC05-00OR22725.

  11. Bonding Low-density Nanoporous Metal Foams Using Sputtered Solder

    SciTech Connect (OSTI)

    Bono, M; Cervantes, O; Akaba, C; Hamza, A; Foreman, R; Teslich, N

    2007-08-21

    A method has been developed for bonding low-density nanoporous metal foam components to a substrate using solder that is sputtered onto the surfaces. Metal foams have unusual properties that make them excellent choices for many applications, and as technologies for processing these materials are evolving, their use in industry is increasing dramatically. Metal foams are lightweight and have advantageous dynamic properties, which make them excellent choices for many structural applications. They also provide good acoustic damping, low thermal conductivity, and excellent energy absorption characteristics. Therefore, these materials are commonly used in the automotive, aerospace, construction, and biomedical industries. The synthesis of nanoporous metal foams with a cell size of less then 1 {micro}m is an emerging technology that is expected to lead to widespread application of metal foams in microdevices, such as sensors and actuators. One of the challenges to manufacturing components from metal foams is that they can be difficult to attach to other structures without degrading their properties. For example, traditional liquid adhesives cannot be used because they are absorbed into foams. The problem of bonding or joining can be particularly difficult for small-scale devices made from nanoporous foam, due to the requirement for a thin bond layer. The current study addresses this problem and develops a method of soldering a nanoporous metal foam to a substrate with a bond thickness of less than 2 {micro}m. There are many applications that require micro-scale metal foams precisely bonded to substrates. This study was motivated by a physics experiment that used a laser to drive a shock wave through an aluminum foil and into a copper foam, in order to determine the speed of the shock in the copper foam. To avoid disturbing the shock, the interface between the copper foam and the aluminum substrate had to be as thin as possible. There are many other applications that could benefit from the bonding technology developed in this study, such as small-scale lightweight structural members, high-strength thermal insulating layers for electronics, and micro-scale mechanical dampers, to name but a few. Each of these applications requires one or more small metal foam components precisely bonded to a substrate. Several methods for bonding metal foam components have been developed by previous researchers. Macroscopic metal foam parts have been successfully bonded by laser welding to create T-sections and butt joints. Ultrasonic welding has been used to join aluminum sheet metal to aluminum foam for structural applications. These methods work well for bonding large foam components, but reducing these methods to a smaller length scale would be challenging. One method that has shown great potential for bonding layers of metal foams to substrates is a brazing process that uses a sputter-deposited interface material. Shirzadi et al.[9] have demonstrated bonds between stainless steel foam and a stainless steel substrate using a layer of copper-titanium filler metal that is sputtered onto the interface surfaces. The foam pieces that they bonded were approximately 10 mm in diameter and 10 mm thick with a cell size of approximately 200 {micro}m. After depositing the filler material, pressing the materials together, and heating them with an induction heater, bonds were achieved without causing significant damage to the foam. The current study also uses a sputter-deposited interface material to bond foam to a substrate. However, in contrast to previous work, the current study examines bonding microscale pieces of fragile nanoporous metal foam. In this study, a method is developed to bond a thin sheet of fragile, low-density nanoporous copper foam to an aluminum foil substrate of thickness 40 {micro}m. By sputter depositing an indium-silver alloy onto the foam and the substrate, a solder joint with a thickness of less than 2 {micro}m was achieved.

  12. Sequestration and Enhanced Coal Bed Methane: Tanquary Farms Test Site, Wabash County, Illinois

    SciTech Connect (OSTI)

    Scott Frailey; Thomas Parris; James Damico; Roland Okwen; Ray McKaskle; Charles Monson; Jonathan Goodwin; E. Beck; Peter Berger; Robert Butsch; Damon Garner; John Grube; Keith Hackley; Jessica Hinton; Abbas Iranmanesh; Christopher Korose; Edward Mehnert; Charles Monson; William Roy; Steven Sargent; Bracken Wimmer

    2012-05-01

    The Midwest Geological Sequestration Consortium (MGSC) carried out a pilot project to test storage of carbon dioxide (CO{sub 2}) in the Springfield Coal Member of the Carbondale Formation (Pennsylvanian System), in order to gauge the potential for large-scale CO{sub 2} sequestration and/or enhanced coal bed methane recovery from Illinois Basin coal beds. The pilot was conducted at the Tanquary Farms site in Wabash County, southeastern Illinois. A four-well design— an injection well and three monitoring wells—was developed and implemented, based on numerical modeling and permeability estimates from literature and field data. Coal cores were taken during the drilling process and were characterized in detail in the lab. Adsorption isotherms indicated that at least three molecules of CO{sub 2} can be stored for each displaced methane (CH{sub 4}) molecule. Microporosity contributes significantly to total porosity. Coal characteristics that affect sequestration potential vary laterally between wells at the site and vertically within a given seam, highlighting the importance of thorough characterization of injection site coals to best predict CO{sub 2} storage capacity. Injection of CO{sub 2} gas took place from June 25, 2008, to January 13, 2009. A “continuous” injection period ran from July 21, 2008, to December 23, 2008, but injection was suspended several times during this period due to equipment failures and other interruptions. Injection equipment and procedures were adjusted in response to these problems. Approximately 92.3 tonnes (101.7 tons) of CO{sub 2} were injected over the duration of the project, at an average rate of 0.93 tonne (1.02 tons) per day, and a mode injection rate of 0.6–0.7 tonne/day (0.66–0.77 ton/day). A Monitoring, Verification, and Accounting (MVA) program was set up to detect CO{sub 2 leakage. Atmospheric CO{sub 2} levels were monitored as were indirect indicators of CO{sub 2} leakage such as plant stress, changes in gas composition at wellheads, and changes in several shallow groundwater characteristics (e.g., alkalinity, pH, oxygen content, dissolved solids, mineral saturation indices, and isotopic distribution). Results showed that there was no CO{sub 2} leakage into groundwater or CO{sub 2} escape at the surface. Post-injection cased hole well log analyses supported this conclusion. Numerical and analytical modeling achieved a relatively good match with observed field data. Based on the model results the plume was estimated to extend 152 m (500 ft) in the face cleat direction and 54.9 m (180 ft) in the butt cleat direction. Using the calibrated model, additional injection scenarios—injection and production with an inverted five-spot pattern and a line drive pattern—could yield CH{sub 4} recovery of up to 70%.

  13. IN SITU FIELD TESTING OF PROCESSES

    SciTech Connect (OSTI)

    J.S.Y. YANG

    2004-11-08

    The purpose of this scientific analysis report is to update and document the data and subsequent analyses from ambient field-testing activities performed in underground drifts and surface-based boreholes through unsaturated zone (UZ) tuff rock units. In situ testing, monitoring, and associated laboratory studies are conducted to directly assess and evaluate the waste emplacement environment and the natural barriers to radionuclide transport at Yucca Mountain. This scientific analysis report supports and provides data to UZ flow and transport model reports, which in turn contribute to the Total System Performance Assessment (TSPA) of Yucca Mountain, an important document for the license application (LA). The objectives of ambient field-testing activities are described in Section 1.1. This report is the third revision (REV 03), which supercedes REV 02. The scientific analysis of data for inputs to model calibration and validation as documented in REV 02 were developed in accordance with the Technical Work Plan (TWP) ''Technical Work Plan for: Performance Assessment Unsaturated Zone'' (BSC 2004 [DIRS 167969]). This revision was developed in accordance with the ''Technical Work Plan for: Unsaturated Zone Flow Analysis and Model Report Integration'' (BSC 2004 [DIRS 169654], Section 1.2.4) for better integrated, consistent, transparent, traceable, and more complete documentation in this scientific analysis report and associated UZ flow and transport model reports. No additional testing or analyses were performed as part of this revision. The list of relevant acceptance criteria is provided by ''Technical Work Plan for: Unsaturated Zone Flow Analysis and Model Report Integration'' (BSC 2004 [DIRS 169654]), Table 3-1. Additional deviations from the TWP regarding the features, events, and processes (FEPs) list are discussed in Section 1.3. Documentation in this report includes descriptions of how, and under what conditions, the tests were conducted. The descriptions and analyses provide data useful for refining and confirming the understanding of flow, drift seepage, and transport processes in the UZ. The UZ testing activities included measurement of permeability distribution, quantification of the seepage of water into the drifts, evaluation of fracture-matrix interaction, study of flow along faults, testing of flow and transport between drifts, characterization of hydrologic heterogeneity along drifts, estimation of drying effects on the rock surrounding the drifts due to ventilation, monitoring of moisture conditions in open and sealed drifts, and determination of the degree of minimum construction water migration below drift. These field tests were conducted in two underground drifts at Yucca Mountain, the Exploratory Studies Facility (ESF) drift, and the cross-drift for Enhanced Characterization of the Repository Block (ECRB), as described in Section 1.2. Samples collected in boreholes and underground drifts have been used for additional hydrochemical and isotopic analyses for additional understanding of the UZ setting. The UZ transport tests conducted at the nearby Busted Butte site (see Figure 1-4) are also described in this scientific analysis report.

  14. Interwell Connectivity and Diagnosis Using Correlation of Production and Injection Rate Data in Hydrocarbon Production

    SciTech Connect (OSTI)

    Jerry L. Jensen; Larry W. Lake; Ali Al-Yousef; Dan Weber; Ximing Liang; T.F. Edgar; Nazli Demiroren; Danial Kaviani

    2007-03-31

    This report details progress and results on inferring interwell communication from well rate fluctuations. Starting with the procedure of Albertoni and Lake (2003) as a foundation, the goal of the project was to develop further procedures to infer reservoir properties through weights derived from correlations between injection and production rates. A modified method, described in Yousef and others (2006a,b), and herein referred to as the 'capacitance model', is the primary product of this research project. The capacitance model (CM) produces two quantities, {lambda} and {tau}, for each injector-producer well pair. For the CM, we have focused on the following items: (1) Methods to estimate {lambda} and {tau} from simulated and field well rates. The original method uses both non-linear and linear regression and lacks the ability to include constraints on {lambda} and {tau}. The revised method uses only non-linear regression, permitting constraints to be included as well as accelerating the solution so that problems with large numbers of wells are more tractable. (2) Approaches to integrate {lambda} and {tau} to improve connectivity evaluations. Interpretations have been developed using Lorenz-style and log-log plots to assess heterogeneity. Testing shows the interpretations can identify whether interwell connectivity is controlled by flow through fractures, high-permeability layers, or due to partial completion of wells. Applications to the South Wasson and North Buck Draw Fields show promising results. (3) Optimization of waterflood injection rates using the CM and a power law relationship for watercut to maximize economic return. Tests using simulated data and a range of oil prices show the approach is working. (4) Investigation of methods to increase the robustness of {lambda} and {tau} estimates. Human interventions, such as workovers, also cause rate fluctuations and can be misinterpreted by the model if bottom hole pressure data are not available. A revised method, called the 'segmented capacitance model', identifies times when production changes might not be caused strictly by water injection changes. Application to data from Monument Butte Field shows encouraging results. Our results show the CM and its modified forms can be an important tool for waterflood management. We have moved beyond the proof of principle stage to show it can actually be applied to assess connectivity in field situations. Several shortcomings, however, remain to be addressed before the CM can be routinely applied by field operators. The CM and its modifications analyze well rates in the time domain. We also explored the assessment of interwell connectivity in the spectral domain. We applied conventional methods, based on analyzing passive linear electrical networks, to the analysis of injection and production data. In particular, we assessed the effects of near-wellbore gas on the apparent connectivity. With only oil and water in the system, the results were as expected, giving good connectivity estimates. In the presence of gas, however, the methods could not produce useful estimates of connectivity.

  15. Modeling and Optimization of Direct Chill Casting to Reduce Ingot Cracking

    SciTech Connect (OSTI)

    Das, S.K.; Ningileri, S.; Long, Z.; Saito, K.; Khraisheh, M.; Hassan, M.H.; Kuwana, K.; Han, Q.; Viswanathan, S.; Sabau, A.S.; Clark, J.; Hyrn, J. (ANL)

    2006-08-15

    Approximately 68% of the aluminum produced in the United States is first cast into ingots prior to further processing into sheet, plate, extrusions, or foil. The direct chill (DC) semi-continuous casting process has been the mainstay of the aluminum industry for the production of ingots due largely to its robust nature and relative simplicity. Though the basic process of DC casting is in principle straightforward, the interaction of process parameters with heat extraction, microstructural evolution, and development of solidification stresses is too complex to analyze by intuition or practical experience. One issue in DC casting is the formation of stress cracks [1-15]. In particular, the move toward larger ingot cross-sections, the use of higher casting speeds, and an ever-increasing array of mold technologies have increased industry efficiencies but have made it more difficult to predict the occurrence of stress crack defects. The Aluminum Industry Technology Roadmap [16] has recognized the challenges inherent in the DC casting process and the control of stress cracks and selected the development of 'fundamental information on solidification of alloys to predict microstructure, surface properties, and stresses and strains' as a high-priority research need, and the 'lack of understanding of mechanisms of cracking as a function of alloy' and 'insufficient understanding of the aluminum solidification process', which is 'difficult to model', as technology barriers in aluminum casting processes. The goal of this Aluminum Industry of the Future (IOF) project was to assist the aluminum industry in reducing the incidence of stress cracks from the current level of 5% to 2%. Decreasing stress crack incidence is important for improving product quality and consistency as well as for saving resources and energy, since considerable amounts of cast metal could be saved by eliminating ingot cracking, by reducing the scalping thickness of the ingot before rolling, and by eliminating butt sawing. Full-scale industrial implementation of the results of the proposed research would lead to energy savings in excess of 6 trillion Btu by the year 2020. The research undertaken in this project aimed to achieve this objective by a collaboration of industry, university, and national laboratory personnel through Secat, Inc., a consortium of aluminum companies. During the four-year project, the industrial partners and the research team met in 16 quarterly meetings to discuss research results and research direction. The industrial partners provided guidance, facilities, and experience to the research team. The research team went to two industrial plants to measure temperature distributions in commercial 60,000-lb DC casting ingot production. The project focused on the development of a fundamental understanding of ingot cracking and detailed models of thermal conditions, solidification, microstructural evolution, and stress development during the initial transient in DC castings of the aluminum alloys 3004 and 5182. The microstructure of the DC casting ingots was systematically characterized. Carefully designed experiments were carried out at the national laboratory and university facilities as well as at the industrial locations using the industrial production facilities. The advanced computational capabilities of the national laboratories were used for thermodynamic and kinetic simulations of phase transformation, heat transfer and fluid flow, solidification, and stress-strain evolution during DC casting. The achievements of the project are the following: (1) Identified the nature of crack formation during DC casting; (2) Developed a novel method for determining the mechanical properties of an alloy at the nonequilibrium mushy zone of the alloy; (3) Measured heat transfer coefficients (HTCs) between the solidifying ingot and the cooling water jet; (4) Determined the material constitutive model at high temperatures; and (5) Developed computational capabilities for the simulation of cracking formation in DC casting ingot. The models and the database de

  16. Worksheet

    U.S. Energy Information Administration (EIA) Indexed Site

    UTILITY_ID","UTILITY_NAME","TRANSLINE_NO","TERMINAL_LOC_FROM","TERMINAL_LOC_TO","PERCENT_OWNED","LINE_LENGTH","LINE_TYPE","VOLTAGE_TYPE","VOLTAGE_OPERATING","VOLTAGE_DESIGN","CONDUCTOR_SIZE","CONDUCTOR_MAT_TYPE","CONDUCTOR_CONFIG","CIRCUIT_PERSTRUCT_PRES","CIRCUIT_PERSTRUCT_ULT","POLE_TOWER_TYPE","RATED_CAPACITY","LAND_LANDRIGHT_COSTS","POLE_TOWER_FIXTURE_COSTS","CONDUCTOR_DEVICE_COSTS","CONSTRUCTION_ETC_COSTS","TOTAL_LINE_COSTS","IN_SERVICE_DATE" 2003,1015,"Austin City of",1,"Northland","Magnesium Plant",100,4.11,"OH","AC",138,138,795,"ACSR Drake/ACSS Rail","Single",1,2,"Steel & Wood Poles",215,0,17500,8000,19500,45000,"application/vnd.ms-excel" 2003,1015,"Austin City of",2,"Grove","Met Center",100,3.1,"OH","AC",138,138,795,"ASCR Drake","Double",1,1,"Steel Pole",430,0,30000,10000,35000,75000,"application/vnd.ms-excel" 2003,1015,"Austin City of",3,"Dessau","Daffin Gin",100,6.01,"OH","AC",138,138,795,"ASCR Drake","Single",1,1,"Steel Pole",215,0,60000,15000,40000,115000,"application/vnd.ms-excel" 2003,1015,"Austin City of",4,"Burleson","AMD",100,2.2,"OH","AC",138,138,795,"ACR Drake","Double",2,2,"Steel Pole",430,0,75000,55000,120000,250000,"application/vnd.ms-excel" 2003,1015,"Austin City of",5,"Bergstrom","Kingsberry",100,4.2,"OH","AC",138,138,795,"ASCR Drake/AAAC","Single",1,2,"Steel & Wood Poles",215,0,75000,35000,340000,450000,"application/vnd.ms-excel" 2003,1015,"Austin City of",6,"Mcneil","Magnesium Plant",100,3.24,"OH","AC",138,138,795,"ACSR Drake","Double",1,2,"Steel Pole & Steel Tower",430,0,380000,76000,644000,1100000,"application/vnd.ms-excel" 2003,1015,"Austin City of",7,"Summit","Magnesium Plant",100,2.18,"OH","AC",138,138,795,"ACSR Drake","Double",1,2,"Steel Pole & Steel Tower",430,0,265000,125000,410000,800000,"application/vnd.ms-excel" 2003,1307,"Basin Electric Power Coop",1,"Rapid City","New Underwood",65,18.55,"OH","AC",230,230,1272,"ACSR","Single",1,1,"Single Pole, Steel",460,0,0,0,5300000,5300000,"application/vnd.ms-excel" 2003,1586,"Bentonville City of",1,"AEP/SWEPCO","City Substation F",100,1,"OH","AC",161,161,477,"ACSR","Single",1,1,"Wood and Steel Single Pole",199,18000,81522,28082,214516,342120,"application/vnd.ms-excel" 2003,2172,"Brazos Electric Power Coop",1,"Coppell","Lewisville",100,7.03,"OH","AC",138,138,1033,"ACSR","Double",1,1,"Concrete/Steel Single Pole",485,17577.55,2527717,537265.96,956475.39,4039035.9,"application/vnd.ms-excel" 2003,2172,"Brazos Electric Power Coop",2,"Boyd","Newark",100,1.8,"OH","AC",138,138,795,"ACSR","Single",2,2,"Concrete/Steel Single Pole",215,133929.08,538282.3,131112.75,246577.6,1049901.73,"application/vnd.ms-excel" 2003,2172,"Brazos Electric Power Coop",3,"Cedar Hill","Sardis",100,5.1,"OH","AC",138,138,795,"ACSR","Single",1,1,"Concrete Si ngle Ploe",215,24515.26,652910.22,246676.96,560582.43,1484684.87,"application/vnd.ms-excel" 2003,5580,"East Kentucky Power Coop Inc",1,"Jamestown Tap","Jamestown Tap",100,0.47,"OH","AC",161,161,556.5,"ACSR","Single",1,1,"Wood Single Pole",292,43326,160508,68789,0,272623,"application/vnd.ms-excel" 2003,5580,"East Kentucky Power Coop Inc",2,"Pulaski Co. Tap","Pulaski Co. Tap",100,5.88,"OH","AC",161,161,795,"ACSR","Single",1,1,"Wood H-Frame Structure",367,494183,1092462,468198,0,2054843,"application/vnd.ms-excel" 2003,7197,"Georgia Transmission Corp",1,"Shoal Creek","Spout Spring",100,10.83,"OH","AC",230,230,1351,"ACSR","Single",1,1,"Concrete, Single Pole & Steel",602,1277945,1685271,444690,6047603,9455509,"application/vnd.ms-excel" 2003,7197,"Georgia Transmission Corp",2,"Dresden","Yellowdirt",100,9.5,"OH","AC",230,230,795,"ACSR","Double",1,1,"Concrete, Single Pole",866,870826,772876,375515,3649376,5668593,"application/vnd.ms-excel" 2003,7197,"Georgia Transmission Corp",3,"East Moultrie","West Valdosta",100,38.46,"OH","AC",230,230,1622,"ACSR","Single",1,1,"Concrete, Single Pole",596,1191168,2829632,1476802,10279078,15776680,"application/vnd.ms-excel" 2003,7490,"Grand River Dam Authority",1,"Cowskin","Grove PSO",100,4.5,"OH","AC",138,138,795,"ACSR","Single/Twisted",1,1,"Wood Pole",223,287671,135402,156769,880890,1460732,"application/vnd.ms-excel" 2003,11269,"Lower Colorado River Authority",1,"BASTROP","AUSTIN",100,0.32,"OH","AC",138,138,795,"ACSR","Single",1,1,"Wood Pole",,9155828,155817297,37044659,47228709,249246493,"application/vnd.ms-excel" 2003,11269,"Lower Colorado River Authority",2,"BASTROP","AUSTROP",100,0.32,"OH","AC",138,138,795,"ACSR","Single",1,1,"Wood Pole",,0,0,0,0,0,"application/vnd.ms-excel" 2003,11269,"Lower Colorado River Authority",3,"BASTROP","AUSTROP",100,0.32,"OH","AC",138,138,795,"ACSR","Single",1,1,"Wood Pole",,0,0,0,0,0,"application/vnd.ms-excel" 2003,11269,"Lower Colorado River Authority",4,"BASTROP","AUSTROP",100,0.32,"OH","AC",138,138,795,"ACSR","Single",1,1,"Wood Pole",,0,0,0,0,0,"application/vnd.ms-excel" 2003,11269,"Lower Colorado River Authority",5,"CANYON","SAN MARCOS/LOCKHART",100,0.31,"OH","AC",138,138,795,"ACSR","Single",1,1,"Wood Pole",,0,0,0,0,0,"application/vnd.ms-excel" 2003,11269,"Lower Colorado River Authority",6,"CANYON","SAN MARCOS/LOCKHART",100,0.31,"OH","AC",138,138,795,"ACSR","Single",1,1,"Wood Pole",,0,0,0,0,0,"application/vnd.ms-excel" 2003,11269,"Lower Colorado River Authority",7,"CANYON","SAN MARCOS/LOCKHART",100,0.31,"OH","AC",138,138,795,"ACSR","Single",1,1,"Wood Pole",,0,0,0,0,0,"application/vnd.ms-excel" 2003,11269,"Lower Colorado River Authority",8,"CANYON","SAN MARCOS/LOCKHART",100,0.31,"OH","AC",138,138,795,"ACSR","Single",1,1,"Wood Pole",,0,0,0,0,0,"application/vnd.ms-excel" 2003,11269,"Lower Colorado River Authority",9,"CANYON","SAN MARCOS/LOCKHART",100,0.31,"OH","AC",138,138,795,"ACSR","Single",1,1,"Wood Pole",,0,0,0,0,0,"application/vnd.ms-excel" 2003,11269,"Lower Colorado River Authority",10,"CICO","HELOTES",100,4,"OH","AC",138,138,795,"ACSR","Single",1,1,"Steel Tower",,0,0,0,0,0,"application/vnd.ms-excel" 2003,11269,"Lower Colorado River Authority",11,"CICO","HELOTES",100,4,"OH","AC",138,138,795,"ACSR","Single",1,1,"Steel Tower",,0,0,0,0,0,"application/vnd.ms-excel" 2003,11269,"Lower Colorado River Authority",12,"CICO","HELOTES",100,4,"OH","AC",138,138,795,"ACSR","Single",1,1,"Steel Tower",,0,0,0,0,0,"application/vnd.ms-excel" 2003,11269,"Lower Colorado River Authority",13,"CICO","HELOTES",100,4,"OH","AC",138,138,795,"ACSR","Single",1,1,"Steel Tower",,0,0,0,0,0,"application/vnd.ms-excel" 2003,11269,"Lower Colorado River Authority",14,"CICO","HELOTES",100,4,"OH","AC",138,138,795,"ACSR","Single",1,1,"Steel Tower",,0,0,0,0,0,"application/vnd.ms-excel" 2003,11269,"Lower Colorado River Authority",15,"CICO","HELOTES",100,4,"OH","AC",138,138,795,"ACSR","Single",1,1,"Steel Tower",,0,0,0,0,0,"application/vnd.ms-excel" 2003,11269,"Lower Colorado River Authority",16,"LOCKHART","DUMP HILL",100,1.6,"OH","AC",138,138,795,"ACSR","Single",1,1,"Concrete Pole",,0,0,0,0,0,"application/vnd.ms-excel" 2003,11269,"Lower Colorado River Authority",17,"HILL POWER STATION","NUECES BAY",100,17.3,"OH","AC",138,138,795,"ACSR","Double",1,1,"Wood Pole",,0,0,0,0,0,"application/vnd.ms-excel" 2003,11269,"Lower Colorado River Authority",18,"NORTH OAK PARK","LON HILL",100,14.9,"OH","AC",138,138,795,"ACSR","Double",1,1,"Wood Pole",,0,0,0,0,0,"application/vnd.ms-excel" 2003,11269,"Lower Colorado River Authority",19,"STATE HIGHTWAY 80",,100,0.38,"OH","AC",138,138,211.5,"ACSR","Single",1,1,"Wood H-Frame Structure",,0,0,0,0,0,"application/vnd.ms-excel" 2003,11269,"Lower Colorado River Authority",20,"STATE HIGHWAY 80",,100,0.38,"OH","AC",138,138,211.5,"ACSR","Single",1,1,"Wood H-Frame Structure",,0,0,0,0,0,"application/vnd.ms-excel" 2003,11269,"Lower Colorado River Authority",21,"STERLING/MITCHELL LINE","TWINN BUTTES",100,135.08,"OH","AC",345,345,1590,"ACSR","Single",1,1,"Steel Tower",,0,0,0,0,0,"application/vnd.ms-excel" 2003,11269,"Lower Colorado River Authority",22,"VERDE CREEK","KERRVILLE STADIUM",100,0.1,"OH","AC",138,138,336,"ACSR","Double",1,1,"Steel Tower",,0,0,0,0,0,"application/vnd.ms-excel" 2003,11269,"Lower Colorado River Authority",23,"VERDE CREEK","KERRVILLE STADIUM",100,0.1,"OH","AC",138,138,336,"ACSR","Double",1,1,"Steel Tower",,0,0,0,0,0,"application/vnd.ms-excel" 2003,11269,"Lower Colorado River Authority",24,"VERDE CREEK","KERRVILLE STADIUM",100,0.1,"OH","AC",138,138,336,"ACSR","Double",1,1,"Steel Tower",,0,0,0,0,0,"application/vnd.ms-excel" 2003,11269,"Lower Colorado River Authority",25,"VERDE CREEK","KERRVILLE STADIUM",100,0.1,"OH","AC",138,138,336,"ACSR","Double",1,1,"Steel Tower",,0,0,0,0,0,"application/vnd.ms-excel" 2003,11269,"Lower Colorado River Authority",26,"ZORN","MCCARTY LANE",100,4.2,"OH","AC",138,138,1433.6,"ACSR","Single",1,1,"Steel Tower",,0,0,0,0,0,"application/vnd.ms-excel" 2003,11269,"Lower Colorado River Authority",27,"ZORN","MCCARTY LANE",100,4.2,"OH","AC",138,138,1433.6,"ACSR","Single",1,1,"Steel Tower",,0,0,0,0,0,"application/vnd.ms-excel" 2003,11269,"Lower Colorado River Authority",28,"ZORN","MCCARTY LANE",100,4.2,"OH","AC",138,138,1433.6,"ACSR","Single",1,1,"Steel Tower",,0,0,0,0,0,"application/vnd.ms-excel" 2003,11269,"Lower Colorado River Authority",29,"ZORN","MCCARTY LANE",100,4.2,"OH","AC",138,138,1433.6,"ACSR","Single",1,1,"Steel Tower",,0,0,0,0,0,"application/vnd.ms-excel" 2003,11269,"Lower Colorado River Authority",30,"ZORN","MCCARTY LANE",100,4.2,"OH","AC",138,138,1433.6,"ACSR","Single",1,1,"Steel Tower",,0,0,0,0,0,"application/vnd.ms-excel" 2003,11269,"Lower Colorado River Authority",31,"ZORN","MCCARTY LANE",100,4.2,"OH","AC",138,138,1433.6,"ACSR","Single",1,1,"Steel Tower",,0,0,0,0,0,"application/vnd.ms-excel" 2003,15143,"Platte River Power Authority",1,"Rawhide","Timberline West",100,31.63,"OH","AC",230,230,954,"ACSR","Single",2,2,"Steel/Tower & Pole",378,5553,1928767,2385430,251850,4571600,"application/vnd.ms-excel" 2003,15159,"Plymouth City of",1,"Mullet River Sub","Sub # 1",100,0.8,"OH","AC",138,138,336.4,"ACSR","SINGLE",1,1,"Steel Double Pole",33,0,0,0,1492139,1492139,"application/vnd.ms-excel" 2003,16534,"Sacramento Municipal Util Dist",1,"Natomas","Elverta",100,4.3,"OH","AC",230,230,954,"Aluminum","Single",1,1,"Steel Tower",316,0,0,0,0,0,"application/vnd.ms-excel" 2003,17543,"South Carolina Pub Serv Auth",1,"Rainey - Anderson (Duke) #1","Rainey - Anderson (Duke) #1",100,9.51,"OH","AC",230,230,1272,"ACSR","Double",2,2,"Steel / Tower",956,840152,1230361,1207282,22364,3300159,"application/vnd.ms-excel" 2003,17543,"South Carolina Pub Serv Auth",2,"Rainey - Anderson (Duke) #2","Rainey - Anderson (Duke) #2",100,9.51,"OH","AC",230,230,1272,"ACSR","Double",2,2,"Steel / Tower",956,840152,1230361,1207282,22364,3300159,"application/vnd.ms-excel" 2003,18642,"Tennessee Valley Authority",1,"West Ringgold","Center Point",100,7.94,"OH","AC",115,230,954,"ASCR","Single",1,2,"Steel Tower",,2086252,5658529,1502763,3053959,12301503,"application/vnd.ms-excel" 2003,18642,"Tennessee Valley Authority",2,"NE Johnson City--Erwin 161kV T","Jonesborough 161 kV SS",100,0.28,"OH","AC",161,161,954,"ASCR","Single",1,1,"Steel Tower",,11050,191917,894933,714987,1812887,"application/vnd.ms-excel" 2003,18642,"Tennessee Valley Authority",3,"Elizabethton","Pandara-Shouns",100,15.12,"OH","AC",161,161,636,"ASCR","Single",1,1,"Steel Tower",,282232,1797686,537733,2057572,4675223,"application/vnd.ms-excel" 2003,18642,"Tennessee Valley Authority",4,"Sullivan","Blountville",100,0.63,"OH","AC",161,161,1590,"ASCR","Single",2,2,"Steel Tower",,547521,1134556,788061,1224067,3694205,"application/vnd.ms-excel" 2003,18642,"Tennessee Valley Authority",5,"Pin Hook","Structure E 104A (NES)",100,1.74,"OH","DC",161,161,2034.5,"ASCR","Single",1,2,"Steel Tower",,179775,881877,641976,270782,1974410,"application/vnd.ms-excel" 2003,18642,"Tennessee Valley Authority",6,"Dug Gap 115 kV SS","Center Point 230 kV SS",100,4.49,"OH","AC",115,230,954,"ASCR","Single",2,2,"Steel Tower",,3939251,3451555,545558,1026021,8962385,"application/vnd.ms-excel" 2003,18642,"Tennessee Valley Authority",7,"Chickamauga-Ridgedale","Hawthorne 161 kV SS",100,2.82,"OH","AC",161,161,1590,"ASCR","Single",2,2,"Steel Tower",,87206,533582,342640,584799,1548227,"application/vnd.ms-excel" 2003,18642,"Tennessee Valley Authority",8,"Ft. Loudoun-Elza 161 kV TL","Spallation Neutron Source 161",100,3.92,"OH","AC",161,161,954,"ASCR","Single",1,1,"Steel Tower",,2972,639541,373150,469765,1485428,"application/vnd.ms-excel" 2003,18642,"Tennessee Valley Authority",9,"Leake","Sebastapol SW STA 161 kV",100,0.77,"OH","AC",161,161,636,"ASCR","Single",2,2,"Steel Tower",,36158,236368,103374,167311,543211,"application/vnd.ms-excel" 2003,18642,"Tennessee Valley Authority",10,"Sebasatpol 161 kV Switching St","Five Point 161 kV Substation",100,0.13,"OH","AC",161,230,954,"ASCR","Single",1,1,"Steel Tower",,917304,1772761,931352,1477668,5099085,"application/vnd.ms-excel" 2003,18642,"Tennessee Valley Authority",11,"Structure 170A","Structure 174",100,0.73,"OH","AC",161,161,636,"ASCR","Single",1,1,"Steel Tower",,0,445863,79638,194574,720075,"application/vnd.ms-excel" 2003,18642,"Tennessee Valley Authority",12,"Ramer-Hickory Valley 161 kV TL","Middleton 46 kV SS",100,6.81,"OH","AC",161,161,954,"ASCR","Single",1,1,"Steel Tower",,566805,1162854,447607,787813,2965079,"application/vnd.ms-excel" 2003,18642,"Tennessee Valley Authority",13,"Lowndes-Miller","Valley View",100,0.46,"OH","AC",500,500,954,"ASCR","Triple",1,2,"Steel Tower",,0,688737,255237,341129,1285103,"application/vnd.ms-excel" 2003,18642,"Tennessee Valley Authority",14,"Sweetwater 161 kV SS","Madisonville 161 kV SS",100,8.95,"OH","AC",161,161,954,"ASCR","Single",1,1,"Steel Tower",,1066219,1474937,466681,797814,3805651,"application/vnd.ms-excel" 2003,18642,"Tennessee Valley Authority",15,"East Point 500 kV SS","Hanceville 161 kV TL",100,11.25,"OH","AC",161,161,1351.5,"ASCR","Single",1,2,"Steel Tower",,1416513,1442382,606534,1427424,4892853,"application/vnd.ms-excel" 2003,18642,"Tennessee Valley Authority",16,"W Cookeville-Crossville 161 kV","W. Crossville SS",100,4.37,"OH","AC",161,161,954,"ASCR","Single",1,2,"Steel Tower",,267463,1112667,651963,964407,2996500,"application/vnd.ms-excel" 2003,18642,"Tennessee Valley Authority",17,"East Shelbyville-Unionville","Deason 161 kV SS",100,5.09,"OH","AC",161,161,636,"ASCR","Single",1,1,"Steel Tower",,1071199,931797,430714,320721,2754431,"application/vnd.ms-excel" 2003,18642,"Tennessee Valley Authority",18,"Kentucky Hydro","Barkley Hydro",100,2,"OH","AC",161,161,2034.5,"ACSR","Single",1,1,"Steel Tower",,2845,406947,90111,155401,655304,"application/vnd.ms-excel" 2003,18642,"Tennessee Valley Authority",19,"MEC Sw Station","Trinity Substation",100,2.9,"OH","AC",161,161,954,"ACSS","Single",2,2,"Steel Tower",,0,604526,474640,608702,1687868,"application/vnd.ms-excel" 2003,18642,"Tennessee Valley Authority",20,"Hickory Valley Selmer 161 kV T","North Selmer 161 kV SS",100,4.88,"OH","AC",161,161,636,"ASCR","Single",1,1,"Steel Tower",,357578,632244,368993,899046,2257861,"application/vnd.ms-excel" 2003,18642,"Tennessee Valley Authority",21,"Trinity","Morgan Energy Center",100,2.98,"OH","AC",161,161,1590,"ASCR","Single",2,2,"Steel Tower",,7155,647789,386671,513831,1555446,"application/vnd.ms-excel" 2003,18642,"Tennessee Valley Authority",22,"MEC","Finley",100,0.61,"OH","AC",161,161,954,"ASCR","Single",1,2,"Steel Tower",,9879,303540,156165,181613,651197,"application/vnd.ms-excel" 2003,18642,"Tennessee Valley Authority",23,"Pickwick-South Jackson","Magic Valley",100,1.38,"OH","AC",161,161,954,"ASCR","Single",1,1,"Steel Pole",,78377,284367,113237,237716,713697,"application/vnd.ms-excel" 2003,18642,"Tennessee Valley Authority",24,"Wolf Creek-Choctaw 500 kV TL","Reliant French Camp Gener Plt",100,0.11,"OH","AC",500,500,954,"ASCR","Triple",1,2,"Steel Tower",,0,863770,411493,891161,2166424,"application/vnd.ms-excel" 2003,18642,"Tennessee Valley Authority",25,"Widows Creek Ft. Payne 161 kV","Flat Rock 161 kV SS",100,2.05,"OH","AC",161,161,397.5,"ASCR","Single",1,1,"Steel Tower",,130460,443384,182965,410228,1167037,"application/vnd.ms-excel" 2003,18642,"Tennessee Valley Authority",26,"Volunteer-Cherokee HP 161 kV T","Oakland 161 kV SS",100,0.5,"OH","AC",161,161,1351,"ASCR","Single",1,2,"Steel Tower",,0,159020,71787,133784,364591,"application/vnd.ms-excel" 2003,18642,"Tennessee Valley Authority",27,"Cordell-Hull-Carthage 161 kV","South Carthage 161 kV SS",100,1.68,"OH","AC",161,161,636,"ASCR","Single",1,2,"Steel Tower",,0,209664,102390,256537,568591,"application/vnd.ms-excel" 2003,20447,"Western Farmers Elec Coop Inc",1,"Arco","Sprectrum",100,5.89,"OH","AC",138,138,336.4,"ACSR","Single",1,1,"Wood Pole",91,37547.56,399750.8,416067.16,0,853365.52,"application/vnd.ms-excel" 2003,20447,"Western Farmers Elec Coop Inc",2,"Hazel Dell Jct","Hazel Dell",100,3.12,"OH","AC",138,138,795,"ACSR","Single",1,1,"Wood Pole",158,72967.09,417464.37,285659.16,0,776090.62,"application/vnd.ms-excel" 2003,20447,"Western Farmers Elec Coop Inc",3,"Red River","Tenaska Kiowa Sw",100,75.75,"OH","AC",345,345,795,"ACSR","Single",1,1,"Combination Pole",158,0,0,0,47569327.23,47569327.23,"application/vnd.ms-excel" 2003,20447,"Western Farmers Elec Coop Inc",4,"Washita Sw","Blue Canyon",100,23.96,"OH","AC",138,138,1590,"ACSR","Single",1,1,"Wood Pole",239,0,0,0,5092171.22,5092171.22,"application/vnd.ms-excel" 2003,20447,"Western Farmers Elec Coop Inc",5,"Limestone Jct","Limestone",100,0.5,"OH","AC",138,138,336.4,"ACSR","Single",1,1,"Wood Pole",91,25673.08,159253.08,77468.07,0,262394.23,"application/vnd.ms-excel" 2003,20447,"Western Farmers Elec Coop Inc",6,"OGE Sunset Jct","Sunset Corner",100,0.15,"OH","AC",161,161,336.4,"ACSR","Singel",1,1,"Wood Pole",91,0,29315.87,35224.01,0,64539.88,"application/vnd.ms-excel" 2003,27000,"Western Area Power Admin",1,"Shiprock","Four Corners",100,8.2,"OH","AC",345,345,,"ASCR",,1,1,"Steel Lattice",,0,0,0,0,0 2003,27000,"Western Area Power Admin",2,"Coolidge","Sundance 1 and 2",100,9.8,"OH","AC",230,230,954,"ASCR",,2,2,"Steel Lattice",,0,0,0,0,0 2003,27000,"Western Area Power Admin",3,"Structure 96/4","O/Banion 1",100,38,"OH","AC",230,230,,"ASCR",,2,2,"Steel Lattice",,0,0,0,0,0 2003,27000,"Western Area Power Admin",4,"Mead","Market Place",100,12.9,"OH","AC",525,525,,"ASCR",,1,1,"Steel Lattice",,0,0,0,0,0 2003,27000,"Western Area Power Admin",5,"Bears Ears","Craig",100,1,"OH","AC",345,345,,"ASCR",,1,1,"Steel Lattice",,0,0,0,0,0 2003,27000,"Western Area Power Admin",6,"Glen Canyon Pumping Plant","Glen Canyon SW Yard",100,1,"OH","AC",345,345,,"ASCR",,1,1,"Steel Lattice",,0,0,0,0,0 2003,27000,"Western Area Power Admin",7,"Baker","Bowman",22.96,53.96,"OH","AC",230,230,954,"ASCR",,1,1,"Wood H",,0,0,0,0,0 2003,27000,"Western Area Power Admin",8,"Basin Tap #2","Washburn",100,2.23,"OH","AC",230,230,795,"ASCR",,1,1,"Steel Lattice",,0,0,0,0,0 2003,27000,"Western Area Power Admin",9,"Craig","Rifle",100,96,"OH","AC",230,230,1272,"ASCR",,1,1,"Steel Lattice",,0,0,0,0,0 2003,27000,"Western Area Power Admin",10,"Garrison","Basin Tap #1",100,20.97,"OH","AC",230,230,795,"ASCR",,1,1,"Steel Lattice",,0,0,0,0,0 2003,27000,"Western Area Power Admin",11,"Everta","Roseville",100,13.3,"OH","AC",230,230,,"ASCR",,1,1,"Steel Lattice",,0,0,0,0,0 2003,27000,"Western Area Power Admin",12,"Griffith","McConnico",100,8,"OH","AC",230,230,1272,"ASCR",,1,1,"Steel Lattice",,0,0,0,0,0 2003,27000,"Western Area Power Admin",13,"McConnico","Peacock",100,29.4,"OH","AC",230,230,795,"ASCR",,1,1,"Steel Lattice",,0,0,0,0,0 2003,27000,"Western Area Power Admin",14,"Liberty","Buckeye",100,6.7,"OH","AC",230,230,1272,"ASCR",,2,2,"Steel Lattice",,0,0,0,0,0 2003,27000,"Western Area Power Admin",15,"Liberty","Parker",100,118.7,"OH","AC",230,230,1272,"ASCR",,1,1,"Steel Lattice",,0,0,0,0,0 2003,27000,"Western Area Power Admin",16,"Liberty","Estrella",100,10.8,"OH","AC",230,230,954,"ASCR",,2,2,"Steel Lattice",,0,0,0,0,0 2003,27000,"Western Area Power Admin",17,"Liberty","Lone Batte",100,38.2,"OH","AC",230,230,954,"ASCR",,1,1,"Steel Lattice",,0,0,0,0,0 2003,27000,"Western Area Power Admin",18,"Lone Butte","Sundance",100,38.4,"OH","AC",230,230,954,"ASCR",,1,1,"Steel Lattice",,0,0,0,0,0 2003,27000,"Western Area Power Admin",19,"New Waddell","West Wing",100,10.1,"OH","AC",230,230,954,"ASCR",,1,1,"Steel Lattice",,0,0,0,0,0 2003,27000,"Western Area Power Admin",20,"South Point","Topock #1",100,6.46,"OH","AC",230,230,1590,"ASCR",,1,1,"Steel Lattice",,0,0,0,0,0 2003,27000,"Western Area Power Admin",21,"South Point","Topock #2",100,6.34,"OH","AC",230,230,1590,"ASCR",,1,1,"Steel Lattice",,0,0,0,0,0