Sample records for bundle handling view

  1. LWR NUCLEAR FUEL BUNDLE DATA FOR USE IN FUEL BUNDLE HANDLING

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: VegetationEquipment Surfaces and Interfaces Sample6, 2011 LOS ALAMOS,Transition and Timeline AboutCoreLWR

  2. Bundled monocapillary optics

    DOE Patents [OSTI]

    Hirsch, Gregory (1277 Linds Mar Center, Suite 128, Pacifica, CA 94044)

    2002-01-01T23:59:59.000Z

    A plurality of glass or metal wires are precisely etched to form the desired shape of the individual channels of the final polycapillary optic. This shape is created by carefully controlling the withdrawal speed of a group of wires from an etchant bath. The etched wires undergo a subsequent operation to create an extremely smooth surface. This surface is coated with a layer of material which is selected to maximize the reflectivity of the radiation being used. This reflective surface may be a single layer of material, or a multilayer coating for optimizing the reflectivity in a narrower wavelength interval. The collection of individual wires is assembled into a close-packed multi-wire bundle, and the wires are bonded together in a manner which preserves the close-pack configuration, irrespective of the local wire diameter. The initial wires are then removed by either a chemical etching procedure or mechanical force. In the case of chemical etching, the bundle is generally segmented by cutting a series of etching slots. Prior to removing the wire, the capillary array is typically bonded to a support substrate. The result of the process is a bundle of precisely oriented radiation-reflecting hollow channels. The capillary optic is used for efficiently collecting and redirecting the radiation from a source of radiation which could be the anode of an x-ray tube, a plasma source, the fluorescent radiation from an electron microprobe, a synchrotron radiation source, a reactor or spallation source of neutrons, or some other source.

  3. The Index Bundle for a Family of Dirac-Ramond Operators

    E-Print Network [OSTI]

    Chris Harris

    2012-02-09T23:59:59.000Z

    We study the index bundle of the Dirac-Ramond operator associated with a family $\\pi: Z \\to X$ of compact spin manifolds. We view this operator as the formal twisted Dirac operator $\\dd \\otimes \\bigotimes_{n=1}^{\\infty}S_{q^n}TM_{\\C}$ so that its index bundle is an element of $K(X)[[q

  4. Essays On Hybrid Bundle Pricing

    E-Print Network [OSTI]

    Meyer, Jeffrey Dean

    2011-10-21T23:59:59.000Z

    Increasingly, firms are offering hybrid bundles — products that combine both good(s) and service(s). Some hybrid bundles, such as TiVo that combines a DVR and recording management are more visible, while some, such as GE‘s Powerplant System...

  5. Fiber bundle phase conjugate mirror

    DOE Patents [OSTI]

    Ward, Benjamin G.

    2012-05-01T23:59:59.000Z

    An improved method and apparatus for passively conjugating the phases of a distorted wavefronts resulting from optical phase mismatch between elements of a fiber laser array are disclosed. A method for passively conjugating a distorted wavefront comprises the steps of: multiplexing a plurality of probe fibers and a bundle pump fiber in a fiber bundle array; passing the multiplexed output from the fiber bundle array through a collimating lens and into one portion of a non-linear medium; passing the output from a pump collection fiber through a focusing lens and into another portion of the non-linear medium so that the output from the pump collection fiber mixes with the multiplexed output from the fiber bundle; adjusting one or more degrees of freedom of one or more of the fiber bundle array, the collimating lens, the focusing lens, the non-linear medium, or the pump collection fiber to produce a standing wave in the non-linear medium.

  6. Vacuum Vessel Remote Handling

    E-Print Network [OSTI]

    and Remote Handling 4 Vacuum vessel functions · Plasma vacuum environment · Primary tritium confinement, incl ports 65 tonnes - Weight of torus shielding 100 tonnes · Coolant - Normal Operation Water, Handling 12 Vessel octant subassembly fab. (3) · Octant-to-octant splice joint requires double wall weld

  7. Theory of hair bundle motion: new insights from the simplest model of hair bundle

    E-Print Network [OSTI]

    Ji, Seung Keun

    2013-01-01T23:59:59.000Z

    2 Single Hair bundle motion and a simpleas a model of a single hair bundle motion . . . . . . . . .of mechan- otransduction in hair cells. ” Annu Rev Neurosci,

  8. Optimization Online - Composite Proximal Bundle Method

    E-Print Network [OSTI]

    Claudia Sagastizabal

    2009-07-30T23:59:59.000Z

    Jul 30, 2009 ... Composite Proximal Bundle Method. Claudia Sagastizabal (sagastiz ***at*** impa.br). Abstract: We consider minimization of nonsmooth ...

  9. Seed Cotton Handling & Storage

    E-Print Network [OSTI]

    Mukhtar, Saqib

    Seed Cotton Handling & Storage #12;S.W. Searcy Texas A&M University College Station, Texas M) Lubbock, Texas E.M. Barnes Cotton Incorporated Cary, North Carolina Acknowledgements: Special thanks for the production of this document has been provided by Cotton Incorporated, America's Cotton Producers

  10. Noether's Second Theorem on natural bundles

    E-Print Network [OSTI]

    Jose Navarro; Juan B. Sancho

    2014-07-21T23:59:59.000Z

    Following work by I. Anderson, in this note we present a formulation of Noether's Second Theorem that is valid on any natural bundle.

  11. Uranium hexafluoride handling. Proceedings

    SciTech Connect (OSTI)

    Not Available

    1991-12-31T23:59:59.000Z

    The United States Department of Energy, Oak Ridge Field Office, and Martin Marietta Energy Systems, Inc., are co-sponsoring this Second International Conference on Uranium Hexafluoride Handling. The conference is offered as a forum for the exchange of information and concepts regarding the technical and regulatory issues and the safety aspects which relate to the handling of uranium hexafluoride. Through the papers presented here, we attempt not only to share technological advances and lessons learned, but also to demonstrate that we are concerned about the health and safety of our workers and the public, and are good stewards of the environment in which we all work and live. These proceedings are a compilation of the work of many experts in that phase of world-wide industry which comprises the nuclear fuel cycle. Their experience spans the entire range over which uranium hexafluoride is involved in the fuel cycle, from the production of UF{sub 6} from the naturally-occurring oxide to its re-conversion to oxide for reactor fuels. The papers furnish insights into the chemical, physical, and nuclear properties of uranium hexafluoride as they influence its transport, storage, and the design and operation of plant-scale facilities for production, processing, and conversion to oxide. The papers demonstrate, in an industry often cited for its excellent safety record, continuing efforts to further improve safety in all areas of handling uranium hexafluoride. Selected papers were processed separately for inclusion in the Energy Science and Technology Database.

  12. Reactor physics calculation of BWR fuel bundles containing gadolinia

    E-Print Network [OSTI]

    Morales, Diego

    1977-01-01T23:59:59.000Z

    A technique for the calculation of the neutronic behavior of BWR fuel bundles has been developed and applied to a Vermont Yankee fuel bundle. The technique is based on a diffusion theory treatment of the bundle, with ...

  13. Canadian Atlas Map Bundle Data Creator /

    E-Print Network [OSTI]

    Title: Canadian Atlas Map Bundle Data Creator / Copyright Owner: DMTI Spatial Inc. Publisher: DMTI Coverage Date(s): N/A Updates: N/A Abstract: The Canadian Atlas Map Bundle consists of the National Atlas Resources Canada (NRCan) for the National Atlas of Canada publication. Also included are DMTI's Populated

  14. Mechanical Overstimulation of Hair Bundles: Suppression and Recovery of Active Motility

    E-Print Network [OSTI]

    KAO, ALBERT

    2013-01-01T23:59:59.000Z

    Hair Cell . . . . . . . . . . . . . . . . . . . . . . .Stiffness of the Hair Bundle . . . . . . . . . . . .Detection of Hair Bundle

  15. Contraction of cross-linked actomyosin bundles

    E-Print Network [OSTI]

    Natsuhiko Yoshinaga; Philippe Marcq

    2012-06-08T23:59:59.000Z

    Cross-linked actomyosin bundles retract when severed in vivo by laser ablation, or when isolated from the cell and micromanipulated in vitro in the presence of ATP. We identify the time scale for contraction as a viscoelastic time tau, where the viscosity is due to (internal) protein friction. We obtain an estimate of the order of magnitude of the contraction time tau ~ 10-100 s, consistent with available experimental data for circumferential microfilament bundles and stress fibers. Our results are supported by an exactly solvable, hydrodynamic model of a retracting bundle as a cylinder of isotropic, active matter, from which the order of magnitude of the active stress is estimated.

  16. Zipping mechanism for force-generation by growing filament bundles

    E-Print Network [OSTI]

    Torsten Kuehne; Reinhard Lipowsky; Jan Kierfeld

    2011-03-02T23:59:59.000Z

    We investigate the force generation by polymerizing bundles of filaments, which form because of short-range attractive filament interactions. We show that bundles can generate forces by a zipping mechanism, which is not limited by buckling and operates in the fully buckled state. The critical zipping force, i.e. the maximal force that a bundle can generate, is given by the adhesive energy gained during bundle formation. For opposing forces larger than the critical zipping force, bundles undergo a force-induced unbinding transition. For larger bundles, the critical zipping force depends on the initial configuration of the bundles. Our results are corroborated by Monte Carlo simulations.

  17. Sealed fiber-optic bundle feedthrough

    DOE Patents [OSTI]

    Tanner, Carol E. (Niles, MI)

    2002-01-01T23:59:59.000Z

    A sealed fiber-optic bundle feedthrough by which a multitude of fiber-optic elements may be passed through an opening or port in a wall or structure separating two environments at different pressures or temperatures while maintaining the desired pressure or temperature in each environment. The feedthrough comprises a rigid sleeve of suitable material, a bundle of individual optical fibers, and a resin-based sealing material that bonds the individual optical fibers to each other and to the rigid sleeve.

  18. Contact-Handled and Remote-Handled Transuranic Waste Packaging

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2011-08-09T23:59:59.000Z

    Provides specific instructions for packaging and/or repackaging contact-handled transuranic (CH-TRU) and remote-handled transuranic (RH-TRU) waste in a manner consistent with DOE O 435.1, Radioactive Waste Management, DOE M 435.1-1 Chg 1, Radioactive Waste Management Manual, CH-TRU and RH-TRU waste transportation requirements, and Waste Isolation Pilot Plant (WIPP) programmatic requirements. Does not cancel other directives.

  19. Oxidation induced stress-rupture of fiber bundles

    SciTech Connect (OSTI)

    Lara-Curzio, E.

    1997-03-01T23:59:59.000Z

    The effect of oxidation on the stress-rupture behavior of fiber bundles was modeled. It is shown that oxidation-induced fiber strength degradation results in the delayed failure of the associated fiber bundle and that the fiber bundle strength decreases with time as t{sup {minus}1/4}. It is also shown that the temperature dependence of the bundle loss of strength reflects the thermal dependence of the mechanism controlling the oxidation of the fibers. The effect of gauge length on the fiber bundle strength was also analyzed. Numerical examples are presented for the special case of Nicalon{trademark} fibers.

  20. MATERIAL HANDLING, STORAGE, AND DISPOSAL

    E-Print Network [OSTI]

    US Army Corps of Engineers

    Materials shall be stored in a manner that allows easy identification and access to labels, identification entering storage areas. All persons shall be in a safe position while materials are being loadedEM 385-1-1 XX Jun 13 14-1 SECTION 14 MATERIAL HANDLING, STORAGE, AND DISPOSAL 14.A MATERIAL

  1. Net bundles over posets and K-theory

    E-Print Network [OSTI]

    J. E. Roberts; G. Ruzzi; E. Vasselli

    2012-06-27T23:59:59.000Z

    We continue studying net bundles over partially ordered sets (posets), defined as the analogues of ordinary fibre bundles. To this end, we analyze the connection between homotopy, net homology and net cohomology of a poset, giving versions of classical Hurewicz theorems. Focusing our attention on Hilbert net bundles, we define the K-theory of a poset and introduce functions over the homotopy groupoid satisfying the same formal properties as Chern classes. As when the given poset is a base for the topology of a space, our results apply to the category of locally constant bundles.

  2. Annular burnout data from rod-bundle experiments. [PWR

    SciTech Connect (OSTI)

    Yoder, G.L.; Morris, D.G.; Mullins, C.B.

    1983-01-01T23:59:59.000Z

    Burnout data for annular flow in a rod bundle are presented for both transient and steady-state conditions. Tests were performed at the Oak Ridge National Laboratory in the Thermal Hydraulic Test Facility (THTF), a pressurized-water loop containing an electrically heated 64-rod bundle. The bundle configuration is typical of later generation pressurized-water reactors with 17 x 17 fuel arrays. Both axial and radial power profiles are flat. All experiments were carried out in upflow with subcooled inlet conditions, insuring accurate flow measurement. Conditions within the bundle were typical of those which could be encountered during a nuclear reactor loss-of-coolant accident.

  3. Packages in the `graphics' bundle D. P. Carlisle

    E-Print Network [OSTI]

    Packages in the `graphics' bundle D. P. Carlisle The Graphics packages 7 4.1 Package Options Graphics Files . . . . . . . . . . . . . . . . . . . . . . .* * 9 4.5 Other commands in the graphics

  4. Packages in the `graphics' bundle D. P. Carlisle

    E-Print Network [OSTI]

    Stein, William

    Packages in the `graphics' bundle D. P. Carlisle The Graphics packages 6 4.1 Package Options Graphics Files . . . . . . . . . . . . . . . . . . . . . . .* * 8 4.5 Other commands in the graphics

  5. Extension of bundles of null directions

    E-Print Network [OSTI]

    Pawel Nurowski; Lane Hughston; David Robinson

    1998-10-21T23:59:59.000Z

    The geometry of P, the bundle of null directions over an Einstein space-time, is studied. The full set of invariants of the natural G-structure on P is constructed using the Cartan method of equivalence. This leads to an extension of P which is an elliptic fibration over the space-time. Examples are given which show that such an extension, although natural, is not unique. A reinterpretation of the Petrov classification in terms of the fibres of an extension of P is presented.

  6. Geodesic Reduction via Frame Bundle Geometry

    E-Print Network [OSTI]

    Ajit Bhand

    2010-02-22T23:59:59.000Z

    A manifold with an arbitrary affine connection is considered and the geodesic spray associated with the connection is studied in the presence of a Lie group action. In particular, results are obtained that provide insight into the structure of the reduced dynamics associated with the given invariant affine connection. The geometry of the frame bundle of the given manifold is used to provide an intrinsic description of the geodesic spray. A fundamental relationship between the geodesic spray, the tangent lift and the vertical lift of the symmetric product is obtained, which provides a key to understanding reduction in this formulation.

  7. THE INDEX OF OPERATORS ON FOLIATED BUNDLES Victor Nistor

    E-Print Network [OSTI]

    Nistor, Victor

    F TV , of dimension n = dim(B), transverse at any point to the fibers of . The pair (V, F bundles. We lift each vector field i on B to a vector field i on the total space V of our flat bundle. This will allow us to construct the lift P( ) which will be an example of an elliptic differential operator along

  8. Band structure and optical properties of isolated and bundled nanotubes

    E-Print Network [OSTI]

    Nabben, Reinhard

    Band structure and optical properties of isolated and bundled nanotubes S. Reich , C. Thomsen , P of isolated and bundled single-walled nanotubes by ab initio calculations. Curvature effects on the electronic states depend on the chirality of the nanotube; the strongest deviations from the zone

  9. Cask system design guidance for robotic handling

    SciTech Connect (OSTI)

    Griesmeyer, J.M.; Drotning, W.D.; Morimoto, A.K.; Bennett, P.C.

    1990-10-01T23:59:59.000Z

    Remote automated cask handling has the potential to reduce both the occupational exposure and the time required to process a nuclear waste transport cask at a handling facility. The ongoing Advanced Handling Technologies Project (AHTP) at Sandia National Laboratories is described. AHTP was initiated to explore the use of advanced robotic systems to perform cask handling operations at handling facilities for radioactive waste, and to provide guidance to cask designers regarding the impact of robotic handling on cask design. The proof-of-concept robotic systems developed in AHTP are intended to extrapolate from currently available commercial systems to the systems that will be available by the time that a repository would be open for operation. The project investigates those cask handling operations that would be performed at a nuclear waste repository facility during cask receiving and handling. The ongoing AHTP indicates that design guidance, rather than design specification, is appropriate, since the requirements for robotic handling do not place severe restrictions on cask design but rather focus on attention to detail and design for limited dexterity. The cask system design features that facilitate robotic handling operations are discussed, and results obtained from AHTP design and operation experience are summarized. The application of these design considerations is illustrated by discussion of the robot systems and their operation on cask feature mock-ups used in the AHTP project. 11 refs., 11 figs.

  10. CANISTER HANDLING FACILITY DESCRIPTION DOCUMENT

    SciTech Connect (OSTI)

    J.F. Beesley

    2005-04-21T23:59:59.000Z

    The purpose of this facility description document (FDD) is to establish requirements and associated bases that drive the design of the Canister Handling Facility (CHF), which will allow the design effort to proceed to license application. This FDD will be revised at strategic points as the design matures. This FDD identifies the requirements and describes the facility design, as it currently exists, with emphasis on attributes of the design provided to meet the requirements. This FDD is an engineering tool for design control; accordingly, the primary audience and users are design engineers. This FDD is part of an iterative design process. It leads the design process with regard to the flowdown of upper tier requirements onto the facility. Knowledge of these requirements is essential in performing the design process. The FDD follows the design with regard to the description of the facility. The description provided in this FDD reflects the current results of the design process.

  11. CARRIER/CASK HANDLING SYSTEM DESCRIPTION DOCUMENT

    SciTech Connect (OSTI)

    E.F. Loros

    2000-06-23T23:59:59.000Z

    The Carrier/Cask Handling System receives casks on railcars and legal-weight trucks (LWTs) (transporters) that transport loaded casks and empty overpacks to the Monitored Geologic Repository (MGR) from the Carrier/Cask Transport System. Casks that come to the MGR on heavy-haul trucks (HHTs) are transferred onto railcars before being brought into the Carrier/Cask Handling System. The system is the interfacing system between the railcars and LWTs and the Assembly Transfer System (ATS) and Canister Transfer System (CTS). The Carrier/Cask Handling System removes loaded casks from the cask transporters and transfers the casks to a transfer cart for either the ATS or CTS, as appropriate, based on cask contents. The Carrier/Cask Handling System receives the returned empty casks from the ATS and CTS and mounts the casks back onto the transporters for reshipment. If necessary, the Carrier/Cask Handling System can also mount loaded casks back onto the transporters and remove empty casks from the transporters. The Carrier/Cask Handling System receives overpacks from the ATS loaded with canisters that have been cut open and emptied and mounts the overpacks back onto the transporters for disposal. If necessary, the Carrier/Cask Handling System can also mount empty overpacks back onto the transporters and remove loaded overpacks from them. The Carrier/Cask Handling System is located within the Carrier Bay of the Waste Handling Building System. The system consists of cranes, hoists, manipulators, and supporting equipment. The Carrier/Cask Handling System is designed with the tooling and fixtures necessary for handling a variety of casks. The Carrier/Cask Handling System performance and reliability are sufficient to support the shipping and emplacement schedules for the MGR. The Carrier/Cask Handling System interfaces with the Carrier/Cask Transport System, ATS, and CTS as noted above. The Carrier/Cask Handling System interfaces with the Waste Handling Building System for building structures and space allocations. The Carrier/Cask Handling System interfaces with the Waste Handling Building Electrical System for electrical power.

  12. Method of manufacturing nuclear fuel bundle spacers

    SciTech Connect (OSTI)

    White, D.W.; Muncy, D.G.; Schoenig, F.C. Jr.

    1989-09-26T23:59:59.000Z

    This patent describes a method of manufacturing nuclear fuel bundle spacers on an automated production line basis. It comprises: cutting elongated tubing stock into shorter tubular ferrules; checking the length of each ferrule and rejecting those ferrules of unacceptable lengths; cutting predetermined features in the sidewall of each ferrule; forming the sidewall of each ferrule to impart predetermined surface formations thereto; checking a critical dimension of each sidewall surface formation of each ferrule and rejecting those of unacceptable dimensions; assembling successive pairs of ferrules into subassemblies; assembling successive subassemblies into a spacer assembly fixture; assembling a peripheral band in the spacer assembly fixture; conjoining the ferrules to each other and to the peripheral band to create a structurally rigid, finished spacer; and providing a separate controller for automatically controlling and monitoring the performances of these steps.

  13. Bundle duct interaction studies for fuel assemblies. [LMFBR

    SciTech Connect (OSTI)

    Hsia, H.T.S.; Kaplan, S.

    1981-06-01T23:59:59.000Z

    It is known that the wire-wrapped rods and duct in an LMFBR are undergoing a gradual structural distortion from the initially uniform geometry under the combined effects of thermal expansion and irradiation induced swelling and creep. These deformations have a significant effect on flow characteristics, thus causing changes in thermal behavior such as cladding temperature and temperature distribution within a bundle. The temperature distribution may further enhance or retard irradiation induced deformation of the bundle. This report summarizes the results of the continuing effort in investigating the bundle-duct interaction, focusing on the need for the large development plant.

  14. EHS-Net Tomato Handling Study EHS-Net Tomato Handling Study Protocol

    E-Print Network [OSTI]

    EHS-Net Tomato Handling Study 1 EHS-Net Tomato Handling Study Protocol I. Project Overview Title EHS-Net Tomato Handling Study Protocol Summary Few studies have examined in detail the nature Health Specialists Network (EHS-Net) special study. EHS- Net is a collaboration involving the Centers

  15. The UNEP Project CD4CDM BUNDLING SMALL-SCALE CDM PROJECTS

    E-Print Network [OSTI]

    Modalities & Procedures for small-scale CDM project activities 58 #12;Bundling Small-Scale Projects ­ ReportThe UNEP Project CD4CDM BUNDLING SMALL-SCALE CDM PROJECTS December, 2004 H V Kumar S V Kulkarni;Bundling Small-Scale Projects ­ Report, October 31, 2004 - 2 - Bundling Small-Scale CDM Projects Unep Risø

  16. Superconductivity in Bundles of Double-Wall Carbon Nanotubes

    E-Print Network [OSTI]

    Shi, Wu

    We present electrical and thermal specific heat measurements that show superconductivity in double-wall carbon nanotube (DWCNT) bundles. Clear evidence, comprising a resistance drop as a function of temperature, magnetoresistance ...

  17. Hydraulic testing of accelerator-production-of-tritium rod bundles

    SciTech Connect (OSTI)

    Spatz, T.L.; Siebe, D.A.

    1999-01-01T23:59:59.000Z

    Hydraulic tests have been performed on small pitch-to-diameter-ratio rod bundles using light water (1.7 < P/D < 1.17, and d = 3.175 mm). Flows cover the range from greater-than-nominal Reynolds numbers (fully turbulent) to low-speed laminar flows. Differential pressure measurements were made across the support plates holding the rod bundles, across the rod bundles, and across the entire assembly. Flow rates, temperatures, and gauge pressures also were measured. The data from these hydraulic tests have been compared to correlating literature for tightly pitched rod bundles. The prototypic geometry of these tests did not compare directly to any geometry found in the literature because of the variety of subchannels along the outer wall of the rod bundle. Under that constraint, there was excellent comparison of the rod-bundle friction factor with those factors given in the literature. The results show a large range of the Reynolds number over which the flow is in transition from laminar to turbulent (e.g., 580 < Re{sub Tr} < 13,000). Also presented is the comparison of the overall rung pressure drop to a solution based on hydraulic-resistance handbook calculations.

  18. Design concept and testing of an in-bundle gamma densitometer for subchannel void fraction measurements in the THTF electrically heated rod bundle. [PWR

    SciTech Connect (OSTI)

    Felde, D. K.

    1982-04-01T23:59:59.000Z

    A design concept is presented for an in-bundle gamma densitometer system for measurement of subchannel average fluid density and void fraction in rod or tube bundles. This report describes (1) the application of the design concept to the Thermal-Hydraulic Test Facility (THTF) electrically heated rod bundle; and (2) results from tests conducted in the THTF.

  19. User interface handles for web objects

    E-Print Network [OSTI]

    Pham, Hubert

    2013-01-01T23:59:59.000Z

    On the desktop, users are accustomed to having visible handles to objects that they can organize, share, and manipulate. Web applications today feature many loosely defined classes of such objects, like flight itineraries, ...

  20. Compressed Gas Cylinder Safe Handling, Use and

    E-Print Network [OSTI]

    Saskatchewan, University of

    Compressed Gas Cylinder Safe Handling, Use and Storage 2012 Workplace Safety and Environmental Protection #12;i College/Unit: Workplace Safety and Environmental Protection Procedure Title: Compressed Gas................................................ 4 7 General Gas Cylinder Information

  1. 2004 Biodiesel Handling and Use Guidelines (Revised)

    SciTech Connect (OSTI)

    Not Available

    2004-11-01T23:59:59.000Z

    This document is a guide for those who blend, distribute, and use biodiesel and biodiesel blends. It is intended to fleets and individual users, blenders, distributors, and those involved in related activities understand procedures for handling and using biodiesel.

  2. Dairy Manure Handling Systems and Equipment.

    E-Print Network [OSTI]

    Sweeten, John M.

    1983-01-01T23:59:59.000Z

    The Texas A&M University System ? Texas Agricultural Extension Service Zerle L. Carpenter, Director College Station 8?1446 DAIRY MANURE HANDLING SYSTEMS AND EQUIPMENT DAIRY MANURE HANDLING SYSTEMS AND EQUIPMENT John M. Sweeten, Ph....D., P.E.* A manure management system for a modern dairy should be capable of controlling solid or liquid manure and wastewater from the open corrals (manure and rainfall runoff), free stall barn , feeding barn , holding lot or holding shed , milking...

  3. Exception Handling i C: Evaluering og videreudvikling af makrobaseret 'Exception Handling'-funktionalitet i ANSI C.

    E-Print Network [OSTI]

    Jermiin Ravn Moll, Jonas

    2005-01-01T23:59:59.000Z

    ??I dette projekt dokumenteres og evalueres det makrobaserede exception handling bibliotek "Cexcept" - udviklet i C - og funktionaliteten beskrives indga?ende. Derudover udvides implementationen med… (more)

  4. LM Records Handling System-Fernald Historical Records System...

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

    Fernald Historical Records System, Office of Legacy Management LM Records Handling System-Fernald Historical Records System, Office of Legacy Management LM Records Handling...

  5. LM Records Handling System (LMRHS01) - Rocky Flats Environmental...

    Office of Environmental Management (EM)

    LM Records Handling System (LMRHS01) - Rocky Flats Environmental Records Database, Office of Legacy Management LM Records Handling System (LMRHS01) - Rocky Flats Environmental...

  6. Location of test bundle instrumentation and anticipated experimental values for the CFTL AG-1 bundle

    SciTech Connect (OSTI)

    Sanders, J.P.

    1980-01-01T23:59:59.000Z

    The placement of instrumentation within the CFTL (Core Flow Test Loop) AG-1 test section to meet the following objective is described. The objectives are threefold: (1) to provide values for the evaluation of the performance of the test section, (2) to compare the experimental data with values determined by pretest calculations to indicate the approach to conditions that can lead to a bundle failure, and (3) to acquire data during testing that will form a data base for subsequent use in the verification of computational procedures used in the licensing of the Gas Cooled Fast Reactor. Anticipated values for the various instruments have been determined using the computational procedure, SAGAPO, modified for the AG-1 geometry. These results are used as the basis for the specification of differential pressure cells and the range of readings anticipated from the thermocouples. Part of the results for the full flow, full power case are presented.

  7. 2013 Utility Bundled Retail Sales- Commercial

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLasDelivered‰PNGExperience hands-onASTROPHYSICS H. I.Plasma Camp View largerCustomers

  8. 2013 Utility Bundled Retail Sales- Industrial

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLasDelivered‰PNGExperience hands-onASTROPHYSICS H. I.Plasma Camp View

  9. 2013 Utility Bundled Retail Sales- Residential

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLasDelivered‰PNGExperience hands-onASTROPHYSICS H. I.Plasma Camp ViewResidential (Data from

  10. 2013 Utility Bundled Retail Sales- Total

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLasDelivered‰PNGExperience hands-onASTROPHYSICS H. I.Plasma Camp ViewResidential (Data

  11. 2013 Utility Bundled Retail Sales- Transportation

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLasDelivered‰PNGExperience hands-onASTROPHYSICS H. I.Plasma Camp ViewResidential

  12. Accurate Camera Calibration from Multi-View Stereo and Bundle Adjustment Yasutaka Furukawa1

    E-Print Network [OSTI]

    Ponce2,1 Willow Team LIENS (CNRS/ENS/INRIA UMR 8548) Ecole Normale Sup´erieure, Paris, France2 Abstract the search for additional image correspondences and significantly improve camera calibration parameters using

  13. Milnor-Wood type inequalities for Higgs bundles

    E-Print Network [OSTI]

    Hartnick, Tobias

    2011-01-01T23:59:59.000Z

    We explain how the generalized Milnor-Wood inequality of Burger and Iozzi for reductive representations of a cocompact complex-hyperbolic lattice into a Hermitian Lie group translates under Simpson's non-abelian Hodge correspondence into an inequality for topological invariants of the corresponding Higgs bundles. In this way, we obtain an inequality that holds for all Hermitian Lie groups, generalizing the Milnor-Wood type inequalities for Higgs bundles that have been proved for the classical Hermitian Lie groups by Bradlow, Garcia-Prada, and Gothen and by Koziarz and Maubon.

  14. DOE handbook: Tritium handling and safe storage

    SciTech Connect (OSTI)

    NONE

    1999-03-01T23:59:59.000Z

    The DOE Handbook was developed as an educational supplement and reference for operations and maintenance personnel. Most of the tritium publications are written from a radiological protection perspective. This handbook provides more extensive guidance and advice on the null range of tritium operations. This handbook can be used by personnel involved in the full range of tritium handling from receipt to ultimate disposal. Compliance issues are addressed at each stage of handling. This handbook can also be used as a reference for those individuals involved in real time determination of bounding doses resulting from inadvertent tritium releases. This handbook provides useful information for establishing processes and procedures for the receipt, storage, assay, handling, packaging, and shipping of tritium and tritiated wastes. It includes discussions and advice on compliance-based issues and adds insight to those areas that currently possess unclear DOE guidance.

  15. Coolant mixing in LMFBR rod bundles and outlet plenum mixing transients. Progress report

    SciTech Connect (OSTI)

    Todreas, N.E.; Golay, M.W.; Wold, L.

    1981-02-01T23:59:59.000Z

    Four tasks are reported on: bundle geometry (wrapped and bare rods), subchannel geometry (bare rods), LMFBR outlet plenum flow mixing, and theoretical determination of local temperature fields in LMFBR fuel rod bundles. (DLC)

  16. E-Print Network 3.0 - anatomical double bundle Sample Search...

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

    FLOWER, AND Summary: in each locule. Note double ventral bundles (V) and ovular trace (OT). 27. Same ovary as in Fig. 17... . 39, 40), and the resulting bundles appear as...

  17. Remote-handled transuranic system assessment appendices. Volume 2

    SciTech Connect (OSTI)

    NONE

    1995-11-01T23:59:59.000Z

    Volume 2 of this report contains six appendices to the report: Inventory and generation of remote-handled transuranic waste; Remote-handled transuranic waste site storage; Characterization of remote-handled transuranic waste; RH-TRU waste treatment alternatives system analysis; Packaging and transportation study; and Remote-handled transuranic waste disposal alternatives.

  18. Coolant mixing in LMFBR rod bundles and outlet plenum mixing transients. Progress report, December 1, 1979-February 29, 1980

    SciTech Connect (OSTI)

    Todreas, N.E.; Golay, M.W.; Wolf, L.

    1980-01-01T23:59:59.000Z

    Information is presented concerning bundle geometry with wrapped and bare rods; LMFBR outlet plenum flow mixing; and theoretical determination of local temperature fields in LMFBR fuel rod bundles.

  19. Fuel bundle design for enhanced usage of plutonium fuel

    DOE Patents [OSTI]

    Reese, Anthony P. (San Jose, CA); Stachowski, Russell E. (Fremont, CA)

    1995-01-01T23:59:59.000Z

    A nuclear fuel bundle includes a square array of fuel rods each having a concentration of enriched uranium and plutonium. Each rod of an interior array of the rods also has a concentration of gadolinium. The interior array of rods is surrounded by an exterior array of rods void of gadolinium. By this design, usage of plutonium in the nuclear reactor is enhanced.

  20. Efficient selection of binary choice bundles with cost considerations

    E-Print Network [OSTI]

    Washington at Seattle, University of

    of a consumer wishing to evaluate bundles of options from a list of N independently selectable binary options to supplied utility and cost functions. Although 2N is very large (e.g., for N = 100, 2N 1030 ), we show how of the individual activity prices) and a total utility value derived according to each guest's individual utility

  1. Incremental-like Bundle Methods with Application to Energy Planning

    E-Print Network [OSTI]

    2009-10-01T23:59:59.000Z

    ‡Claudia Sagastizábal: CEPEL, Electric Energy Research Center, Eletrobrás Group. On ... of an alternative method, working with function evaluations of unknown and vanishing ... During each outage, one third of the reactor fuel is renewed. ..... Bundle data in (4) can be represented alternatively, by referring the infor-.

  2. Elasto-plastic response of reversibly crosslinked biopolymer bundles

    E-Print Network [OSTI]

    Poulomi Sadhukhan; Ole Schuman; Claus Heussinger

    2014-05-19T23:59:59.000Z

    We study the response of F-actin bundles to driving forces through a simple analytical model. We consider two filaments connected by reversibly bound crosslinks and driven by an external force. Two failure modes under load can be defined. \\textit{Brittle failure} is observed when crosslinks suddenly and collectively unbind, leading to catastrophic loss of bundle integrity. During \\textit{ductile failure}, on the other hand, bundle integrity is maintained, however at the cost of crosslink reorganization and defect formation. We present phase diagrams for the onset of failure, highlighting the importance of the crosslink stiffness for these processes. Crossing the phase boundaries, force-deflection curves display (frequency-dependent) hysteresis loops, reflecting the first-order character of the failure processes. We evidence how the introduction of defects can lead to complex elasto-plastic relaxation processes, once the force is switched off. Depending on, both, the time-scale for defect motion as well as the crosslink stiffness, bundles can remain in a quasi-permanent plastically deformed state for a very long time.

  3. Large Eddy Simulations of Jet Flow Interactions Within Rod Bundles

    E-Print Network [OSTI]

    Salpeter, Nathaniel O.

    2010-07-14T23:59:59.000Z

    The present work investigates the turbulent jet flow mixing of downward impinging jets within a staggered rod bundle based on previous experimental work. The two inlet jets had Reynold's numbers of 11,160 and 6,250 and were chosen to coincide...

  4. Packages in the `graphics' bundle D. P. Carlisle

    E-Print Network [OSTI]

    Packages in the `graphics' bundle D. P. Carlisle 1999/01/13 Contents 1 Introduction 2 2 Driver . . . . . . . . . . . . . . . . . . . . . . . . . . 6 4 The Graphics packages 7 4.1 Package Options . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 4.4 Including Graphics Files . . . . . . . . . . . . . . . . . . . . . . . 9 4.5 Other commands

  5. Packages in the `graphics' bundle D. P. Carlisle

    E-Print Network [OSTI]

    Bloch, Ethan

    Packages in the `graphics' bundle D. P. Carlisle 1999/01/13 Contents 1 Introduction 2 2 Driver Problems . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 4 The Graphics packages 7 4.1 Package Graphics Files . . . . . . . . . . . . . . . . . . . . . . . . 9 4.5 Other commands in the graphics package

  6. Packages in the `graphics' bundle D. P. Carlisle

    E-Print Network [OSTI]

    Duncan, James S.

    Packages in the `graphics' bundle D. P. Carlisle 1996/10/29 Contents 1 Introduction 1 2 Driver Problems . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 4 The Graphics packages 6 4.1 Package Graphics Files . . . . . . . . . . . . . . . . . . . . . . . . 8 4.5 Other commands in the graphics package

  7. Enhancement of sensitivity gain and frequency tuning by coupling of active hair bundles

    E-Print Network [OSTI]

    Jülicher, Frank

    Enhancement of sensitivity gain and frequency tuning by coupling of active hair bundles Kai Dierkes. A candidate for this process is active hair bundle mechanics observed, for instance, for hair cells of the bullfrog's sacculus. Hair bundles in various inner ear organs are coupled by overlying membranes. Using

  8. 340 waste handling facility interim safety basis

    SciTech Connect (OSTI)

    VAIL, T.S.

    1999-04-01T23:59:59.000Z

    This document presents an interim safety basis for the 340 Waste Handling Facility classifying the 340 Facility as a Hazard Category 3 facility. The hazard analysis quantifies the operating safety envelop for this facility and demonstrates that the facility can be operated without a significant threat to onsite or offsite people.

  9. 340 Waste handling facility interim safety basis

    SciTech Connect (OSTI)

    Stordeur, R.T.

    1996-10-04T23:59:59.000Z

    This document presents an interim safety basis for the 340 Waste Handling Facility classifying the 340 Facility as a Hazard Category 3 facility. The hazard analysis quantifies the operating safety envelop for this facility and demonstrates that the facility can be operated without a significant threat to onsite or offsite people.

  10. Easy Gardening.....Harvesting and Handling Vegetables

    E-Print Network [OSTI]

    Cotner, Sam; Masabni, Joseph; Wagner, Al

    2009-05-29T23:59:59.000Z

    Easy Gardening Joseph Masabni, Assistant Professor and Extension Horticulturist, The Texas A&M University System HARVESTING ? HANDLING ? STORING VEGETABLES -1- T ohelpensurethatthevegetables yougrowandprepareareofhigh quality.... Acknowledgments Thispublicationwasrevisedfromearlierversionswrittenby SamCotner,ProfessorEmeritusandformerExtension Horticulturist,andAlWagner,formerProfessorand ExtensionHorticulturist. -6- Produced by AgriLife Communications, The Texas A&M System Extension...

  11. Architecturing Conflict Handling of Pervasive Computing Resources

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    Architecturing Conflict Handling of Pervasive Computing Resources Henner Jakob1 , Charles Consel1 to conflict in their usage of shared resources, e.g., controlling doors for security and fire evacuation computing resources. This approach covers the software devel- opment lifecycle and consists of enriching

  12. Waste Handling and Disposal Biological Safety

    E-Print Network [OSTI]

    Pawlowski, Wojtek

    plumbing services, EHS personnel wastewater treatment plant personnel, and the general public canWaste Handling and Disposal Biological Safety General Biosafety Practices (GBP) Why You Should Care on the next experiment. Are you working with r/sNA, biological toxins, human materials, needles, plasticware

  13. Two-dimensional computational modeling of sodium boiling in simulated LMFBR fuel-pin bundles

    SciTech Connect (OSTI)

    Dearing, J.F.

    1981-01-01T23:59:59.000Z

    Extensive sodium boiling tests have been carried out in two simulated LMFBR fuel pin bundles in the Thermal-Hydraulic Out-of-Reactor Safety (THORS) Facility at Oak Ridge National Laboratory. Experimental results from a 19-pin bundle (THORS Bundle 6A) have been previously reported, and experimental results from a 61-pin bundle (THORS Bundle 9) will be reported soon. The results discussed here are from the 19-pin bundle. Preliminary analysis has shown that the computational methods used and conclusions reached are equally valid for the 61-pin bundle, as well as the 19-pin in-reactor Sodium Loop Safety Facility (SLSF) W-1 experiment. The main result of THORS sodium boiling experimentation is that boiling behavior is determined by two-dimensional effects, i.e., the rates of mass, momentum and energy transfer in the direction perpendicular to the axes of the fuel pins.

  14. Medical catheters thermally manipulated by fiber optic bundles

    DOE Patents [OSTI]

    Chastagner, Philippe (608 Aumond Rd., Augusta, GA 30909)

    1992-01-01T23:59:59.000Z

    A maneuverable medical catheter comprising a flexible tube having a functional tip. The catheter is connected to a control source. The functional tip of the catheter carries a plurality of temperature activated elements arranged in parallel and disposed about the functional tip and held in spaced relation at each end. These elements expand when they are heated. A plurality of fiber optic bundles, each bundle having a proximal end attached to the control source and a distal end attached to one of the elements carry light into the elements where the light is absorbed as heat. By varying the optic fiber that is carrying the light and the intensity of the light, the bending of the elements can be controlled and thus the catheter steered. In an alternate embodiment, the catheter carries a medical instrument for gathering a sample of tissue. The instrument may also be deployed and operated by thermal expansion and contraction of its moving parts.

  15. Quantized gauge-affine gravity in the superfiber bundle approach

    SciTech Connect (OSTI)

    Meziane, A.; Tahiri, M. [Laboratoire de Physique Theorique, Universite d'Oran Es-senia, 31100 Oran (Algeria)

    2005-05-15T23:59:59.000Z

    The quantization of gauge-affine gravity within the superfiber bundle formalism is proposed. By introducing an even pseudotensorial 1-superform over a principal superfiber bundle with superconnection, we obtain the geometrical Becchi-Rouet-Stora-Tyutin (BRST) and anti-BRST transformations of the fields occurring in such a theory. Reducing the four-dimensional general affine group double-covering GA(4,R) to the Poincare group double-covering ISO(1,3) we also find the BRST and anti-BRST transformations of the fields present in Einstein's gravity. Furthermore, we give a prescription leading to the construction of both BRST-invariant gauge-fixing action for gauge-affine gravity and Einstein's gravity.

  16. CAT reconstruction and potting comparison of a LMFBR fuel bundle

    SciTech Connect (OSTI)

    Betten, P.R.; Tow, D.M.

    1984-04-01T23:59:59.000Z

    A standard Liquid Metal Fast Breeder Reactor (LMFBR) subassembly used in the Experimental Breeder Reactor II (EBR-II) was investigated, by remote techniques, for fuel bundle distortion by both nondestructive and destructive methods, and the results from both methods were compared. The non-destructive method employed neutron tomography to reconstruct the locations of fuel elements through the use of a maximum entropy reconstruction algorithm known as MENT. The destructive method consisted of ''potting'' (a technique that embeds and permanently fixes the fuel elements in a solid matrix) the subassembly, and then cutting and polishing the individual sections. The comparison indicated that the tomography reconstruction provided good results in describing the bundle geometry and spacer-wire locations, with the overall resolution being on the order of a spacer-wire diameter. A dimensional consistency check indicated that the element and spacer-wire dimensions were accurately reproduced in the reconstruction.

  17. View Discovery in OLAP Databases through Statistical Combinatorial Optimization

    SciTech Connect (OSTI)

    Joslyn, Cliff A.; Burke, Edward J.; Critchlow, Terence J.

    2009-05-01T23:59:59.000Z

    The capability of OLAP database software systems to handle data complexity comes at a high price for analysts, presenting them a combinatorially vast space of views of a relational database. We respond to the need to deploy technologies sufficient to allow users to guide themselves to areas of local structure by casting the space of ``views'' of an OLAP database as a combinatorial object of all projections and subsets, and ``view discovery'' as an search process over that lattice. We equip the view lattice with statistical information theoretical measures sufficient to support a combinatorial optimization process. We outline ``hop-chaining'' as a particular view discovery algorithm over this object, wherein users are guided across a permutation of the dimensions by searching for successive two-dimensional views, pushing seen dimensions into an increasingly large background filter in a ``spiraling'' search process. We illustrate this work in the context of data cubes recording summary statistics for radiation portal monitors at US ports.

  18. CANISTER HANDLING FACILITY CRITICALITY SAFETY CALCULATIONS

    SciTech Connect (OSTI)

    C.E. Sanders

    2005-04-07T23:59:59.000Z

    This design calculation revises and updates the previous criticality evaluation for the canister handling, transfer and staging operations to be performed in the Canister Handling Facility (CHF) documented in BSC [Bechtel SAIC Company] 2004 [DIRS 167614]. The purpose of the calculation is to demonstrate that the handling operations of canisters performed in the CHF meet the nuclear criticality safety design criteria specified in the ''Project Design Criteria (PDC) Document'' (BSC 2004 [DIRS 171599], Section 4.9.2.2), the nuclear facility safety requirement in ''Project Requirements Document'' (Canori and Leitner 2003 [DIRS 166275], p. 4-206), the functional/operational nuclear safety requirement in the ''Project Functional and Operational Requirements'' document (Curry 2004 [DIRS 170557], p. 75), and the functional nuclear criticality safety requirements described in the ''Canister Handling Facility Description Document'' (BSC 2004 [DIRS 168992], Sections 3.1.1.3.4.13 and 3.2.3). Specific scope of work contained in this activity consists of updating the Category 1 and 2 event sequence evaluations as identified in the ''Categorization of Event Sequences for License Application'' (BSC 2004 [DIRS 167268], Section 7). The CHF is limited in throughput capacity to handling sealed U.S. Department of Energy (DOE) spent nuclear fuel (SNF) and high-level radioactive waste (HLW) canisters, defense high-level radioactive waste (DHLW), naval canisters, multicanister overpacks (MCOs), vertical dual-purpose canisters (DPCs), and multipurpose canisters (MPCs) (if and when they become available) (BSC 2004 [DIRS 168992], p. 1-1). It should be noted that the design and safety analyses of the naval canisters are the responsibility of the U.S. Department of the Navy (Naval Nuclear Propulsion Program) and will not be included in this document. In addition, this calculation is valid for the current design of the CHF and may not reflect the ongoing design evolution of the facility. However, it is anticipated that design changes to the facility layout will have little or no impact on the criticality results and/or conclusions presented in this document. This calculation is subject to the ''Quality Assurance Requirements and Description'' (DOE 2004 [DIRS 171539]) because the CHF is included in the Q-List (BSC 2005 [DIRS 171190], p. A-3) as an item important to safety. This calculation is prepared in accordance with AP-3.12Q, ''Design Calculations and Analyses'' [DIRS 168413].

  19. Fuel bundle design for enhanced usage of plutonium fuel

    DOE Patents [OSTI]

    Reese, A.P.; Stachowski, R.E.

    1995-08-08T23:59:59.000Z

    A nuclear fuel bundle includes a square array of fuel rods each having a concentration of enriched uranium and plutonium. Each rod of an interior array of the rods also has a concentration of gadolinium. The interior array of rods is surrounded by an exterior array of rods void of gadolinium. By this design, usage of plutonium in the nuclear reactor is enhanced. 10 figs.

  20. The refined transfer, bundle structures and algebraic K-theory.

    E-Print Network [OSTI]

    John R. Klein; Bruce Williams

    We give new homotopy theoretic criteria for deciding when a fibration with homotopy finite fibers admits a reduction to a fiber bundle with compact topological manifold fibers. The criteria lead to a new and unexpected result about homeomorphism groups of manifolds. A tool used in the proof is a surjective splitting of the assembly map for Waldhausen's functor A(X). We also give concrete examples of fibrations having a reduction to a fiber bundle with compact topological manifold fibers but which fail to admit a compact fiber smoothing. The examples are detected by algebraic K-theory invariants. We consider a refinement of the Becker-Gottlieb transfer. We show that a version of the axioms described by Becker and Schultz uniquely determines the refined transfer for the class of fibrations admitting a reduction to a fiber bundle with compact topological manifold fibers. In an appendix, we sketch a theory of characteristic classes for fibrations. The classes are primary obstructions to finding a compact fiber smoothing.

  1. Enhanced boiling heat transfer in horizontal test bundles

    SciTech Connect (OSTI)

    Trewin, R.R.; Jensen, M.K.; Bergles, A.E.

    1994-08-01T23:59:59.000Z

    Two-phase flow boiling from bundles of horizontal tubes with smooth and enhanced surfaces has been investigated. Experiments were conducted in pure refrigerant R-113, pure R-11, and mixtures of R-11 and R-113 of approximately 25, 50, and 75% of R-113 by mass. Tests were conducted in two staggered tube bundles consisting of fifteen rows and five columns laid out in equilateral triangular arrays with pitch-to-diameter ratios of 1.17 and 1.5. The enhanced surfaces tested included a knurled surface (Wolverine`s Turbo-B) and a porous surface (Linde`s High Flux). Pool boiling tests were conducted for each surface so that reference values of the heat transfer coefficient could be obtained. Boiling heat transfer experiments in the tube bundles were conducted at pressures of 2 and 6 bar, heat flux values from 5 to 80 kW/m{sup 2}s, and qualities from 0% to 80%, Values of the heat transfer coefficients for the enhanced surfaces were significantly larger than for the smooth tubes and were comparable to the values obtained in pool boiling. It was found that the performance of the enhanced tubes could be predicted using the pool boiling results. The degradation in the smooth tube heat transfer coefficients obtained in fluid mixtures was found to depend on the difference between the molar concentration in the liquid and vapor.

  2. Human error contribution to nuclear materials-handling events

    E-Print Network [OSTI]

    Sutton, Bradley (Bradley Jordan)

    2007-01-01T23:59:59.000Z

    This thesis analyzes a sample of 15 fuel-handling events from the past ten years at commercial nuclear reactors with significant human error contributions in order to detail the contribution of human error to fuel-handling ...

  3. MATERIALS HANDLING AND TRANSPORTATION PLAN CSMRI SITE REMEDIATION

    E-Print Network [OSTI]

    MATERIALS HANDLING AND TRANSPORTATION PLAN CSMRI SITE REMEDIATION April 13, 2004 Prepared for. Wright Street Littleton, CO 80127 #12;MATERIALS HANDLING AND TRANSPORTATION PLAN CSMRI Site Remediation By: Date: Robert Krumberger Project Manager New Horizons Environmental Consultants, Inc. Approved By

  4. Rod Bundle Heat Transfer: Steady-State Steam Cooling Experiments

    SciTech Connect (OSTI)

    Spring, J.P.; McLaughlin, D.M. [The Pennsylvania State University, 201 Shields Building University Park, PA 16802 (United States)

    2006-07-01T23:59:59.000Z

    Through the joint efforts of the Pennsylvania State University and the United States Nuclear Regulatory Commission, an experimental rod bundle heat transfer (RBHT) facility was designed and built. The rod bundle consists of a 7 x 7 square pitch array with spacer grids and geometry similar to that found in a modern pressurized water reactor. From this facility, a series of steady-state steam cooling experiments were performed. The bundle inlet Reynolds number was varied from 1 400 to 30 000 over a pressure range from 1.36 to 4 bars (20 to 60 psia). The bundle inlet steam temperature was controlled to be at saturation for the specified pressure and the fluid exit temperature exceeded 550 deg. C in the highest power tests. One important quantity of interest is the local convective heat transfer coefficient defined in terms of the local bulk mean temperature of the flow, local wall temperature, and heat flux. Steam temperatures were measured at the center of selected subchannels along the length of the bundle by traversing miniaturized thermocouples. Using an analogy between momentum and energy transport, a method was developed for relating the local subchannel centerline temperature measurement to the local bulk mean temperature. Wall temperatures were measured using internal thermocouples strategically placed along the length of each rod and the local wall heat flux was obtained from an inverse conduction program. The local heat transfer coefficient was calculated from the data at each rod thermocouple location. The local heat transfer coefficients calculated for locations where the flow was fully developed were compared against several published correlations. The Weisman and El-Genk correlations were found to agree best with the RBHT steam cooling data, especially over the range of turbulent Reynolds numbers. The effect of spacer grids on the heat transfer enhancement was also determined from instrumentation placed downstream of the spacer grid locations. The local heat transfer was found to be greatest at locations immediately downstream of the grid, and as the flow moved further downstream from the grid it became more developed, thus causing the heat transfer to diminish. The amount of heat transfer enhancement was found to depend not only on the spacer grid design, but also on the local Reynolds number. It was seen that decreasing Reynolds number leads to greater heat transfer enhancement. (authors)

  5. System for handling and storing radioactive waste

    DOE Patents [OSTI]

    Anderson, John K. (San Diego, CA); Lindemann, Paul E. (Escondido, CA)

    1984-01-01T23:59:59.000Z

    A system and method for handling and storing spent reactor fuel and other solid radioactive waste, including canisters to contain the elements of solid waste, storage racks to hold a plurality of such canisters, storage bays to store these racks in isolation by means of shielded doors in the bays. This system also includes means for remotely positioning the racks in the bays and an access tunnel within which the remotely operated means is located to position a rack in a selected bay. The modular type of these bays will facilitate the construction of additional bays and access tunnel extension.

  6. System for handling and storing radioactive waste

    DOE Patents [OSTI]

    Anderson, J.K.; Lindemann, P.E.

    1982-07-19T23:59:59.000Z

    A system and method are claimed for handling and storing spent reactor fuel and other solid radioactive waste, including canisters to contain the elements of solid waste, storage racks to hold a plurality of such canisters, storage bays to store these racks in isolation by means of shielded doors in the bays. This system also includes means for remotely positioning the racks in the bays and an access tunnel within which the remotely operated means is located to position a rack in a selected bay. The modular type of these bays will facilitate the construction of additional bays and access tunnel extension.

  7. E-Print Network 3.0 - apical dendritic bundles Sample Search...

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

    Biology and Medicine 6 ORIGINAL ARTICLE Neuronal morphology in the African elephant Summary: of bifurcating apical dendritic bundles. Quantitatively, the dendrites of...

  8. Four Generated Rank 2 Arithmetically Cohen-Macaulay Vector Bundles on General Sextic Surfaces.

    E-Print Network [OSTI]

    Deng, Wei

    2013-01-01T23:59:59.000Z

    ??In this dissertation, we compute the dimension of the moduli space, of four generated indecomposable rank 2 arithmetically Cohen-Macaulay: ACM for short) bundles on a… (more)

  9. E-Print Network 3.0 - administrative bundled file Sample Search...

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

    stop or uninstall bundles. This section will describe how a suspend... is a service-oriented architecture allowing the deployment of ... Source: Ecole Polytechnique, Centre de...

  10. Stall force of polymerizing microtubules and filament bundles

    E-Print Network [OSTI]

    Jaroslaw Krawczyk; Jan Kierfeld

    2011-02-10T23:59:59.000Z

    We investigate stall force and polymerization kinetics of rigid protofilaments in a microtubule or interacting filaments in bundles under an external load force in the framework of a discrete growth model. We introduce the concecpt of polymerization cycles to describe the stochastic growth kinetics, which allows us to derive an exact expression for the stall force. We find that the stall force is independent of ensemble geometry and load distribution. Furthermore, the stall force is proportional to the number of filaments and increases linearly with the strength of lateral filament interactions. These results are corroborated by simulations, which also show a strong influence of ensemble geometry on growth kinetics below the stall force.

  11. Primer on tritium safe handling practices

    SciTech Connect (OSTI)

    Not Available

    1994-12-01T23:59:59.000Z

    This Primer is designed for use by operations and maintenance personnel to improve their knowledge of tritium safe handling practices. It is applicable to many job classifications and can be used as a reference for classroom work or for self-study. It is presented in general terms for use throughout the DOE Complex. After reading it, one should be able to: describe methods of measuring airborne tritium concentration; list types of protective clothing effective against tritium uptake from surface and airborne contamination; name two methods of reducing the body dose after a tritium uptake; describe the most common method for determining amount of tritium uptake in the body; describe steps to take following an accidental release of airborne tritium; describe the damage to metals that results from absorption of tritium; explain how washing hands or showering in cold water helps reduce tritium uptake; and describe how tritium exchanges with normal hydrogen in water and hydrocarbons.

  12. Overview on Hydrate Coring, Handling and Analysis

    SciTech Connect (OSTI)

    Jon Burger; Deepak Gupta; Patrick Jacobs; John Shillinglaw

    2003-06-30T23:59:59.000Z

    Gas hydrates are crystalline, ice-like compounds of gas and water molecules that are formed under certain thermodynamic conditions. Hydrate deposits occur naturally within ocean sediments just below the sea floor at temperatures and pressures existing below about 500 meters water depth. Gas hydrate is also stable in conjunction with the permafrost in the Arctic. Most marine gas hydrate is formed of microbially generated gas. It binds huge amounts of methane into the sediments. Worldwide, gas hydrate is estimated to hold about 1016 kg of organic carbon in the form of methane (Kvenvolden et al., 1993). Gas hydrate is one of the fossil fuel resources that is yet untapped, but may play a major role in meeting the energy challenge of this century. In June 2002, Westport Technology Center was requested by the Department of Energy (DOE) to prepare a ''Best Practices Manual on Gas Hydrate Coring, Handling and Analysis'' under Award No. DE-FC26-02NT41327. The scope of the task was specifically targeted for coring sediments with hydrates in Alaska, the Gulf of Mexico (GOM) and from the present Ocean Drilling Program (ODP) drillship. The specific subjects under this scope were defined in 3 stages as follows: Stage 1: Collect information on coring sediments with hydrates, core handling, core preservation, sample transportation, analysis of the core, and long term preservation. Stage 2: Provide copies of the first draft to a list of experts and stakeholders designated by DOE. Stage 3: Produce a second draft of the manual with benefit of input from external review for delivery. The manual provides an overview of existing information available in the published literature and reports on coring, analysis, preservation and transport of gas hydrates for laboratory analysis as of June 2003. The manual was delivered as draft version 3 to the DOE Project Manager for distribution in July 2003. This Final Report is provided for records purposes.

  13. Remote-handled transuranic waste study

    SciTech Connect (OSTI)

    NONE

    1995-10-01T23:59:59.000Z

    The Waste Isolation Pilot Plant (WIPP) was developed by the US Department of Energy (DOE) as a research and development facility to demonstrate the safe disposal of transuranic (TRU) radioactive wastes generated from the Nation`s defense activities. The WIPP disposal inventory will include up to 250,000 cubic feet of TRU wastes classified as remote handled (RH). The remaining inventory will include contact-handled (CH) TRU wastes, which characteristically have less specific activity (radioactivity per unit volume) than the RH-TRU wastes. The WIPP Land Withdrawal Act (LWA), Public Law 102-579, requires a study of the effect of RH-TRU waste on long-term performance. This RH-TRU Waste Study has been conducted to satisfy the requirements defined by the LWA and is considered by the DOE to be a prudent exercise in the compliance certification process of the WIPP repository. The objectives of this study include: conducting an evaluation of the impacts of RH-TRU wastes on the performance assessment (PA) of the repository to determine the effects of Rh-TRU waste as a part of the total WIPP disposal inventory; and conducting a comparison of CH-TRU and RH-TRU wastes to assess the differences and similarities for such issues as gas generation, flammability and explosiveness, solubility, and brine and geochemical interactions. This study was conducted using the data, models, computer codes, and information generated in support of long-term compliance programs, including the WIPP PA. The study is limited in scope to post-closure repository performance and includes an analysis of the issues associated with RH-TRU wastes subsequent to emplacement of these wastes at WIPP in consideration of the current baseline design. 41 refs.

  14. Safety Enhancements for TRU Waste Handling - 12258

    SciTech Connect (OSTI)

    Cannon, Curt N. [Perma-Fix Northwest Richland, Inc., Richland, WA 99354 (United States)

    2012-07-01T23:59:59.000Z

    For years, proper Health Physics practices and 'As Low As Reasonably Achievable' (ALARA) principles have fostered the use of glove boxes or other methods of handling (without direct contact) high activities of radioactive material. The physical limitations of using glove boxes on certain containers have resulted in high-activity wastes being held in storage awaiting a path forward. Highly contaminated glove boxes and other remote handling equipment no longer in use have also been added to the growing list of items held for storage with no efficient method of preparation for proper disposal without creating exposure risks to personnel. This is especially true for wastes containing alpha-emitting radionuclides such as Plutonium and Americium that pose significant health risks to personnel if these Transuranic (TRU) wastes are not controlled effectively. Like any good safety program or root cause investigation PFNW has found that the identification of the cause of a negative change, if stopped, can result in a near miss and lessons learned. If this is done in the world of safety, it is considered a success story and is to be shared with others to protect the workers. PFNW believes that the tools, equipment and resources have improved over the past number of years but that the use of them has not progressed at the same rate. If we use our tools to timely identify the effect on the work environment and immediately following or possibly even simultaneously identify the cause or some of the causal factors, we may have the ability to continue to work rather than succumb to the start and stop-work mentality trap that is not beneficial in waste minimization, production efficiency or ALARA. (authors)

  15. LMFBR fuel bundle distortion characterization using neutron tomography and potting

    SciTech Connect (OSTI)

    Betten, P.R.; Tow, D.M.

    1984-05-01T23:59:59.000Z

    A standard liquid metal fast breeder reactor (LMFBR) subassembly used in the Experimental Breeder Reactor II (EBRII) was investigated for fuel bundle distortion by both nondestructive and destructive methods, and the results from both methods were compared. The nondestructive method employed neutron tomography to reconstruct the locations of fuel elements through the use of a maximum entropy reconstruction algorithm known as MENT. The destructive method consisted of ''potting'' (a technique that embeds and permanently fixes the fuel elements in a solid matrix) the subassembly and then cutting and polishing the individual sections. The comparison indicated that the tomography reconstruction provided good results in describing the bundle geometry and spacer-wire locations, with the overall resolution being on the order of a spacer-wire diameter. A dimensional consistency check indicated that the element and spacer-wire dimensions were accurately reproduced in the reconstruction. It was found that in situ fuel elements deform axially in a helical spiral and that the reconstruction was able to identify this helical distortion to within approximately half of a spacerwire diameter.

  16. Motor-free actin bundle contractility driven by molecular crowding

    E-Print Network [OSTI]

    Jörg Schnauß; Tom Golde; Carsten Schuldt; B. U. Sebastian Schmidt; Martin Glaser; Dan Strehle; Claus Heussinger; Josef A. Käs

    2015-03-10T23:59:59.000Z

    Modeling approaches of suspended, rod-like particles and recent experimental data have shown that depletion forces display different signatures depending on the orientation of these particles. It has been shown that axial attraction of two rods yields contractile forces of 0.1pN that are independent of the relative axial shift of the two rods. Here, we measured depletion-caused interactions of actin bundles extending the phase space of single pairs of rods to a multi-particle system. In contrast to a filament pair, we found forces up to 3pN . Upon bundle relaxation forces decayed exponentially with a mean decay time of 3.4s . These different dynamics are explained within the frame of a mathematical model by taking pairwise interactions to a multi-filament scale. The macromolecular content employed for our experiments is well below the crowding of cells. Thus, we propose that arising forces can contribute to biological force generation without the need to convert chemical energy into mechanical work.

  17. Classification of "Quaternionic" Bloch-bundles: Topological Insulators of type AII

    E-Print Network [OSTI]

    Giuseppe De Nittis; Kiyonori Gomi

    2014-04-23T23:59:59.000Z

    We provide a classification of type AII topological insulators in dimension d=1,2,3,4. Our analysis is based on the construction of a topological invariant, the FKMM-invariant, which completely classifies "Quaternionic" vector bundles (a.k.a. "symplectic" vector bundles) in dimension dtopological invariant.

  18. Anisotropic decay dynamics of photoexcited aligned carbon nanotube bundles Y. Hashimoto,1,2,

    E-Print Network [OSTI]

    Kono, Junichiro

    , and magnetic proper- ties are under intensive investigations world wide.1 Various types of recent opticalAnisotropic decay dynamics of photoexcited aligned carbon nanotube bundles Y. Hashimoto,1,2, * Y-probe spectroscopy of a film of aligned single- walled carbon nanotube bundles. By taking into account imperfect

  19. OPTIMAL BUNDLING STRATEGY FOR DIGITAL INFORMATION GOODS: NETWORK DELIVERY OF ARTICLES AND SUBSCRIPTIONS

    E-Print Network [OSTI]

    Sirbu, Marvin

    OPTIMAL BUNDLING STRATEGY FOR DIGITAL INFORMATION GOODS: NETWORK DELIVERY OF ARTICLES in the academic journal context. These results provide strong incentives for academic journal publishers to engage in mixed bundling, i.e. offer both individual articles and journal subscriptions, when selling

  20. Electronic band structure of isolated and bundled carbon nanotubes S. Reich and C. Thomsen

    E-Print Network [OSTI]

    Nabben, Reinhard

    for nanotubes with larger diameters 1­1.5 nm a shift of the energy levels of 100 meV is obtained in our abElectronic band structure of isolated and bundled carbon nanotubes S. Reich and C. Thomsen Institut in chiral and achiral isolated nanotubes as well as in carbon nanotube bundles. The curvature

  1. Evaluation of Fiber Bundle Rotation for Enhancing Gas Exchange in a Respiratory Assist Catheter

    E-Print Network [OSTI]

    Federspiel, William J.

    of a rotating densely packed bundle of hollow fiber membranes, water and blood gas exchange levels were the concept of an intravenous respiratory assist device, in which a bundle of hollow fiber membranes (HFMs short blind- ended HFMs along its length in a "bottle-brush" configura- tion.11­14 Our group first

  2. Polymerization and Bundling Kinetics of FtsZ Filaments Ganhui Lan,* Alex Dajkovic,y

    E-Print Network [OSTI]

    Sun, Sean

    Polymerization and Bundling Kinetics of FtsZ Filaments Ganhui Lan,* Alex Dajkovic,y Denis Wirtz a kinetic model that describes the polymerization and bundling mechanism of FtsZ filaments. The model polymerization kinetics data of another researcher, and explains the cooperativity observed in FtsZ kinetics

  3. Overhead electric power transmission line jumpering system for bundles of five or more subconductors

    DOE Patents [OSTI]

    Winkelman, Paul F. (Beaverton, OR)

    1982-01-01T23:59:59.000Z

    Jumpering of electric power transmission lines at a dead end tower. Two transmission line conductor bundles each contain five or more spaced apart subconductors (5) arranged in the shape of a cylinder having a circular cross section. The ends of each bundle of subconductors are attached with insulators to a dead end tower (1). Jumpering allows the electric current to flow between the two bundles of subconductors using jumper buses, internal jumper conductors, and external jumper conductors. One or more current collecting jumper buses (37) are located inside each bundle of subconductors with each jumper bus being attached to the end of a subconductor. Small-diameter internal jumper conductors (33) are located in the inherently electrically shielded area inside each bundle of subconductors with each subconductor (except ones having an attached jumper bus) having one internal jumper conductor connected between that subconductor's end and a jumper bus. Large-diameter external jumper conductors (9) are located outside each bundle of subconductors with one or more external jumper conductors being connected between the jumper buses in one bundle of subconductors and the jumper buses in the other bundle.

  4. Bundles of carbon nanotubes generated by vapor-phase growth Maohui Ge and Klaus Sattler

    E-Print Network [OSTI]

    Sattler, Klaus

    show that another hollow carbon structure is possible to form under such high density conditions. We report the observation of assemblies of carbon nano- tubes in the form of bundles. The bundles. It is located horizontally on the flat graphite substrate. It is separated from other deposited carbon nano

  5. Hair-bundle movements elicited by transepithelial electrical stimulation of hair cells in the sacculus

    E-Print Network [OSTI]

    Hudspeth, A. James

    Hair-bundle movements elicited by transepithelial electrical stimulation of hair cells transduction by the inner ear. We present evidence for a single-cell correlate of this phenomenon, hair motion that incorporates the negative stiffness of the hair bundle as well as its two mechanisms

  6. Negative hair-bundle stiffness betrays a mechanism for mechanical amplification by the hair cell

    E-Print Network [OSTI]

    Hudspeth, A. James

    Negative hair-bundle stiffness betrays a mechanism for mechanical amplification by the hair cell P. Hudspeth, August 15, 2000 Hearing and balance rely on the ability of hair cells in the inner ear to sense miniscule mechanical stimuli. In each cell, sound or acceleration deflects the mechanosensitive hair bundle

  7. Rapid, Active Hair Bundle Movements in Hair Cells from the Bullfrog's Sacculus

    E-Print Network [OSTI]

    Hudspeth, A. James

    Rapid, Active Hair Bundle Movements in Hair Cells from the Bullfrog's Sacculus Michael E. Benser Neuroscience, The Rockefeller University, New York, New York 10021 Hair bundles, the mechanically sensitive organelles of hair cells in the auditory and vestibular systems, are elastic structures that are deflected

  8. Unifying the Various Incarnations of Active Hair-Bundle Motility by the Vertebrate Hair Cell

    E-Print Network [OSTI]

    Jülicher, Frank

    Unifying the Various Incarnations of Active Hair-Bundle Motility by the Vertebrate Hair Cell Jean of the hair cells' responsiveness to small stimuli. As revealed by spontaneous oscillations and forms of mechanical excitability in response to force steps, the hair bundle that adorns each hair cell is both

  9. Cellular/Molecular Vestibular Hair Bundles Control pH with (Na , K )/H

    E-Print Network [OSTI]

    Rao, Rajini

    Cellular/Molecular Vestibular Hair Bundles Control pH with (Na , K )/H Exchangers NHE6 and NHE9 21205, and 3Graduate School of Life Science, University of Hyogo, Ako, Hyogo 678-1297, Japan In hair acidify mechani- cally sensitive hair bundles without efficient removal of H . We found that, whereas

  10. Handbook for Handling, Storing, and Dispensing E85

    SciTech Connect (OSTI)

    Not Available

    2008-04-01T23:59:59.000Z

    Guidebook contains information about EPAct alternative fuels regulations for fleets, flexible fuel vehicles, E85 properties and specifications, and E85 handling and storage guidelines.

  11. LM Records Handling System (LMRHS01) - Electronic Records Keeping...

    Energy Savers [EERE]

    System (LMRHS01) - Electronic Records Keeping System, Office of Legacy Management, LM Records Handling System (LMRHS01) - Electronic Records Keeping System, Office of Legacy...

  12. LM Records Handling System (LMRHS01) - Energy Employees Occupational...

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

    Employees Occupational Illness Compensation Program Act, Office of Legacy Management LM Records Handling System (LMRHS01) - Energy Employees Occupational Illness Compensation...

  13. Impacts of capture and handling on wild birds.

    E-Print Network [OSTI]

    Duarte, Leila

    2013-01-01T23:59:59.000Z

    ??Bird ringing is a key ecological research technique that involves the capture and handling of birds. It is used extensively to obtain information on population… (more)

  14. Biodiesel Handling and Use Guide: Fourth Edition (Revised)

    SciTech Connect (OSTI)

    Not Available

    2009-01-01T23:59:59.000Z

    Intended for those who blend, distribute, and use biodiesel and its blends, this guide contains procedures for handling and using these fuels.

  15. Coolant mixing in LMFBR rod bundles and outlet plenum mixing transients. Progress report, March 1, 1980-May 31, 1980

    SciTech Connect (OSTI)

    Todreas, N.E.; Golay, M.W.; Wolf, L.

    1980-01-01T23:59:59.000Z

    Experimental and theoretical work is reported on four tasks: bundle geometry (wrapped and bare rods), subchannel geometry (bare rods), LMFBR outlet plenum flow mixing, and theoretical local temperature files in LMFBR fuel rod bundles. (DLC)

  16. Coolant mixing in LMFBR rod bundles and outlet plenum mixing transients. Progress report, September 1, 1980-November 30, 1980

    SciTech Connect (OSTI)

    Todreas, N.E.; Golay, M.W.; Wolf, L.

    1981-02-01T23:59:59.000Z

    Four tasks are reported: bundle geometry (wrapped and bare rods), subchannel geometry (bare rods), subchannel geometry (bare rods), LMFBR outlet plenum flow mixing, and theoretical determination of local temperature fields in LMFBR fuel rod bundles. (DLC)

  17. Coolant mixing in LMFBR rod bundles and outlet plenum mixing transients. Progress report, December 1, 1980-February 28, 1981

    SciTech Connect (OSTI)

    Todreas, N.E.

    1981-04-01T23:59:59.000Z

    Information is presented concerning coolant mixing for wrapped and bare rod bundle geometry; bare rod subchannel geometry; LMFBR outlet plenum flow mixing; and theoretical determination of local temperature fields in LMFBR fuel rod bundles.

  18. Coolant mixing in LMFBR rod bundles and outlet plenum mixing transients. Progress report, March 1-May 31, 1981

    SciTech Connect (OSTI)

    Todreas, N.E.

    1981-08-01T23:59:59.000Z

    Information is presented concerning wrapped and bare rod bundle geometry; bare rod subchannel geometry; LMFBR outlet plenum flow mixing; and theoretical determination of local temperature fields in LMFBR fuel rod bundles.

  19. Remote-Handled Transuranic Content Codes

    SciTech Connect (OSTI)

    Washington TRU Solutions

    2006-12-01T23:59:59.000Z

    The Remote-Handled Transuranic (RH-TRU) Content Codes (RH-TRUCON) document describes the inventory of RH-TRU waste within the transportation parameters specified by the Remote-Handled Transuranic Waste Authorized Methods for Payload Control (RH-TRAMPAC).1 The RH-TRAMPAC defines the allowable payload for the RH-TRU 72-B. This document is a catalog of RH-TRU 72-B authorized contents by site. A content code is defined by the following components: • A two-letter site abbreviation that designates the physical location of the generated/stored waste (e.g., ID for Idaho National Laboratory [INL]). The site-specific letter designations for each of the sites are provided in Table 1. • A three-digit code that designates the physical and chemical form of the waste (e.g., content code 317 denotes TRU Metal Waste). For RH-TRU waste to be transported in the RH-TRU 72-B, the first number of this three-digit code is “3.” The second and third numbers of the three-digit code describe the physical and chemical form of the waste. Table 2 provides a brief description of each generic code. Content codes are further defined as subcodes by an alpha trailer after the three-digit code to allow segregation of wastes that differ in one or more parameter(s). For example, the alpha trailers of the subcodes ID 322A and ID 322B may be used to differentiate between waste packaging configurations. As detailed in the RH-TRAMPAC, compliance with flammable gas limits may be demonstrated through the evaluation of compliance with either a decay heat limit or flammable gas generation rate (FGGR) limit per container specified in approved content codes. As applicable, if a container meets the watt*year criteria specified by the RH-TRAMPAC, the decay heat limits based on the dose-dependent G value may be used as specified in an approved content code. If a site implements the administrative controls outlined in the RH-TRAMPAC and Appendix 2.4 of the RH-TRU Payload Appendices, the decay heat or FGGR limits based on a 10-day shipping period (rather than the standard 60-day shipping period) may be used as specified in an approved content code.

  20. Coolant mixing in LMFBR rod bundles and outlet plenum mixing transients. Progress report, December 1, 1981-February 28, 1982

    SciTech Connect (OSTI)

    Todreas, N.A.

    1982-07-01T23:59:59.000Z

    Information is presented concerning wrapped and bare rod bundle geometry; bare rod subchannel geometry; and LMFBR outlet plenum flow mixing.

  1. Z .Journal of Neuroscience Methods 69 1996 163169 A novel carbon fiber bundle microelectrode and modified brain slice

    E-Print Network [OSTI]

    Gillette, Martha U.

    Z .Journal of Neuroscience Methods 69 1996 163­169 A novel carbon fiber bundle microelectrode micropipette with a 20­50 mm thick wax-coated bundle of 5-mm diameter carbon fibers extending 2.5 cm from nucleus brain slice. Preliminary data suggest that this novel carbon fiber bundle electrode

  2. CONSTRUCTION OF LOW RANK VECTOR BUNDLES ON P4 N. MOHAN KUMAR, CHRIS PETERSON, AND A. PRABHAKAR RAO

    E-Print Network [OSTI]

    Kumar, N. Mohan

    CONSTRUCTION OF LOW RANK VECTOR BUNDLES ON P4 AND P5 N. MOHAN KUMAR, CHRIS PETERSON, AND A. PRABHAKAR RAO Abstract. We describe a technique which permits a uniform construction of a number of low rank bundles, both known and new. In characteristic two, we obtain rank two bundles on P5. In characteristic p

  3. H dli dHandling and Safety Training

    E-Print Network [OSTI]

    Farritor, Shane

    HendershotPam Hendershot Praxair Distribution Inc. Praxair Distribution Inc., Quality Department .Copyright © 2000, Praxair Technology, Inc. All rights reserved. .Rev. Date 04/24/2006-A 1 #12;Safe Handling Dangers Proper PPEp Proper Handling and Transporting of cryogen liquidscryogen liquids Praxair

  4. Operating Experience Level 3, Losing Control: Material Handling Dangers

    Broader source: Energy.gov [DOE]

    This Operating Experience Level 3 (OE-3) document provides information about the dangers inherent in material handling and the role hazard analysis, work planning, and walkdowns can play in preventing injuries during heavy equipment moves. More than 200 material handling events reported to the Occurrence Reporting and Processing System (ORPS) from January 1, 2010, through August 31, 2014.

  5. NIH POLICY MANUAL 1345 -HANDLING AND SAFEGUARDING OF CONTROLLED SUBSTANCES

    E-Print Network [OSTI]

    Bandettini, Peter A.

    NIH POLICY MANUAL 1345 - HANDLING AND SAFEGUARDING OF CONTROLLED SUBSTANCES FOR NONHUMAN USE: This Chapter describes NIH policies and procedures for handling and safeguarding controlled substances the chapter in compliance with the NIH Office of Management Assessment standardized format. The revised

  6. Guidance Document Safe Handling of Sulfides and Hydrogen Sulfide

    E-Print Network [OSTI]

    Guidance Document Safe Handling of Sulfides and Hydrogen Sulfide [This is a brief summary. Read concern would be hydrogen sulfide, whether handling in the pure gaseous form or by generation from various threshold level, the oxidative enzymes would be overwhelmed. Uses: Sulfides and hydrogen sulfide are used

  7. Investigation of Swirling Flow in Rod Bundle Subchannels Using Computational Fluid Dynamics

    SciTech Connect (OSTI)

    Holloway, Mary V. [United States Naval Academy, 117 Decatur Road, Annapolis, MD 21402-5018 (United States); Beasley, Donald E. [Clemson University, Clemson, S.C. 29634 (United States); Conner, Michael E. [Westinghouse Nuclear Fuel (United States)

    2006-07-01T23:59:59.000Z

    The fluid dynamics for turbulent flow through rod bundles representative of those used in pressurized water reactors is examined using computational fluid dynamics (CFD). The rod bundles of the pressurized water reactor examined in this study consist of a square array of parallel rods that are held on a constant pitch by support grids spaced axially along the rod bundle. Split-vane pair support grids are often used to create swirling flow in the rod bundle in an effort to improve the heat transfer characteristics for the rod bundle during both normal operating conditions and in accident condition scenarios. Computational fluid dynamics simulations for a two subchannel portion of the rod bundle were used to model the flow downstream of a split-vane pair support grid. A high quality computational mesh was used to investigate the choice of turbulence model appropriate for the complex swirling flow in the rod bundle subchannels. Results document a central swirling flow structure in each of the subchannels downstream of the split-vane pairs. Strong lateral flows along the surface of the rods, as well as impingement regions of lateral flow on the rods are documented. In addition, regions of lateral flow separation and low axial velocity are documented next to the rods. Results of the CFD are compared to experimental particle image velocimetry (PIV) measurements documenting the lateral flow structures downstream of the split-vane pairs. Good agreement is found between the computational simulation and experimental measurements for locations close to the support grid. (authors)

  8. Subchannel thermal-hydraulic modeling of an APT tungsten target rod bundle

    SciTech Connect (OSTI)

    Hamm, L.L.; Shadday, M.A. Jr.

    1997-09-01T23:59:59.000Z

    The planned target for the Accelerator Production of Tritium (APT) neutron source consists of an array of tungsten rod bundles through which D{sub 2}O coolant flows axially. Here, a scoping analysis of flow through an APT target rod bundle was conducted to demonstrate that lateral cross-flows are important, and therefore subchannel modeling is necessary to accurately predict thermal-hydraulic behavior under boiling conditions. A local reactor assembly code, FLOWTRAN, was modified to model axial flow along the rod bundle as flow through three concentric heated annular passages.

  9. Laboratory manual for static pressure drop experiments in LMFBR wire wrapped rod bundles

    SciTech Connect (OSTI)

    Burns, K.J.; Todreas, N.E.

    1980-07-01T23:59:59.000Z

    Purpose of this experiment is to determine both interior and edge subchannel axial pressure drops for a range of Reynolds numbers. The subchannel static pressure drop is used to calculate subchannel and bundle average friction factors, which can be used to verify existing friction factor correlations. The correlations for subchannel friction factors are used as input to computer codes which solve the coupled energy, continuity, and momentum equations, and are also used to develop flow split correlations which are needed as input to codes which solve only the energy equation. The bundle average friction factor is used to calculate the overall bundle pressure drop, which determines the required pumping power.

  10. Remote-Handled Transuranic Content Codes

    SciTech Connect (OSTI)

    Washington TRU Solutions

    2001-08-01T23:59:59.000Z

    The Remote-Handled Transuranic (RH-TRU) Content Codes (RH-TRUCON) document representsthe development of a uniform content code system for RH-TRU waste to be transported in the 72-Bcask. It will be used to convert existing waste form numbers, content codes, and site-specificidentification codes into a system that is uniform across the U.S. Department of Energy (DOE) sites.The existing waste codes at the sites can be grouped under uniform content codes without any lossof waste characterization information. The RH-TRUCON document provides an all-encompassing|description for each content code and compiles this information for all DOE sites. Compliance withwaste generation, processing, and certification procedures at the sites (outlined in this document foreach content code) ensures that prohibited waste forms are not present in the waste. The contentcode gives an overall description of the RH-TRU waste material in terms of processes and|packaging, as well as the generation location. This helps to provide cradle-to-grave traceability ofthe waste material so that the various actions required to assess its qualification as payload for the72-B cask can be performed. The content codes also impose restrictions and requirements on themanner in which a payload can be assembled.The RH-TRU Waste Authorized Methods for Payload Control (RH-TRAMPAC), Appendix 1.3.7of the 72-B Cask Safety Analysis Report (SAR), describes the current governing procedures|applicable for the qualification of waste as payload for the 72-B cask. The logic for this|classification is presented in the 72-B Cask SAR. Together, these documents (RH-TRUCON,|RH-TRAMPAC, and relevant sections of the 72-B Cask SAR) present the foundation and|justification for classifying RH-TRU waste into content codes. Only content codes described in thisdocument can be considered for transport in the 72-B cask. Revisions to this document will be madeas additional waste qualifies for transport. |Each content code uniquely identifies the generated waste and provides a system for tracking theprocess and packaging history. Each content code begins with a two-letter site abbreviation thatindicates the shipper of the RH-TRU waste. The site-specific letter designations for each of the|DOE sites are provided in Table 1. Not all of the sites listed in Table 1 have generated/stored RH-|TRU waste.

  11. Studies and research concerning BNFP: cask handling equipment standardization

    SciTech Connect (OSTI)

    McCreery, Paul N.

    1980-10-01T23:59:59.000Z

    This report covers the activities of one of the sub-tasks within the Spent LWR Fuel Transportation Receiving, Handling, and Storage program. The sub-task is identified as Cask Handling Equipment Standardization. The objective of the sub-task specifies: investigate and identify opportunities for standardization of cask interface equipment. This study will examine the potential benefits of standardized yokes, decontamination barriers and special tools, and, to the extent feasible, standardized methods and software for handling the variety of casks presently available in the US fleet. The result of the investigations is a compilation of reports that are related by their common goal of reducing cask turnaround time.

  12. Forward viewing OCT endomicroscopy

    E-Print Network [OSTI]

    Liang, Kaicheng

    2014-01-01T23:59:59.000Z

    A forward viewing fiber optic-based imaging probe device was designed and constructed for use with ultrahigh speed optical coherence tomography in the human gastrointestinal tract. The light source was a MEMS-VCSEL at 1300 ...

  13. Strategic Bundling: Incentive Compatible and Content Aware Replication Strategies in P2P Networks under

    E-Print Network [OSTI]

    Massachusetts at Amherst, University of

    providers, namely how to combine (or bun- dle) files into packages so as to reduce the server costs while, it is not feasible to have an abstract bun- dle with a single provider, because abstract bundles are huge collections

  14. 0 + 0 = 1 : the appliance model of selling software bundled with hardware

    E-Print Network [OSTI]

    Hein, Bettina

    2007-01-01T23:59:59.000Z

    The business model of selling software bundled with hardware is called the appliance model. As hardware becomes less and less expensive and open source software is being offered for free, the traditional business model of ...

  15. Nondestructive assay and nondestructive examination of remote-handled transuranic waste at the ORNL waste handling and packaging plant

    SciTech Connect (OSTI)

    Schultz, F.J.; Caldwell, J.T. (Oak Ridge National Lab., TN (USA); Pajarito Scientific Corp. (USA))

    1989-01-01T23:59:59.000Z

    The purpose of this investigation is to examine the use of an electron linear accelerator (LINAC) in the performance of nondestructive assay (NDA) and nondestructive examination (NDE) measurements of remote-handled transuranic wastes. The system will be used to perform waste characterization and certification activities at the Oak Ridge National Laboratory's proposed Waste Handling and Packaging Plant. The NDA and NDE technologies which were developed for contact-handled wastes are inadequate to perform such measurements on high gamma and neutron dose-rate wastes. A single LINAC will provide the interrogating fluxes required for both NDA and NDE measurements of the wastes. 11 refs., 6 figs.

  16. air handling unit: Topics by E-print Network

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

    case of fans, or indirectly, in the case of heat exchangers, which impose loads on the chiller and boiler plant. Air-handling units can comprise a myriad of subsystems (fans,...

  17. air handling units: Topics by E-print Network

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

    case of fans, or indirectly, in the case of heat exchangers, which impose loads on the chiller and boiler plant. Air-handling units can comprise a myriad of subsystems (fans,...

  18. Centralized processing of contact-handled TRU waste feasibility analysis

    SciTech Connect (OSTI)

    Not Available

    1986-12-01T23:59:59.000Z

    This report presents work for the feasibility study of central processing of contact-handled TRU waste. Discussion of scenarios, transportation options, summary of cost estimates, and institutional issues are a few of the subjects discussed. (JDL)

  19. Turbulence prediction in two- and three-dimensional bundle flows using Large Eddy Simulation

    E-Print Network [OSTI]

    Ibrahim, Wael Abdul-Hamid

    1994-01-01T23:59:59.000Z

    TURBULENCE PREDICTION IN TWO- AND THREE-DIMENSIONAL BUNDLE FLOWS USING LARGE EDDY SIMULATION A Thesis by WAEL ABDUL-HAMID IBRAHIM Submitted to Texas A&M University in partial fulfillment of the requirements for the degree of MASTER... Prediction in Two- and Three-Dimensional Bundle Flows Using Large Eddy Simulation. (May 1994) Wael Abdul-Hamid Ibrahim, B. S. Alexandria University Chair of Advisory Committee: Dr. Yassin A. Hassan Flow turbulence is a familiar phenomenon in everyday life...

  20. Laboratory manual for salt-mixing test in 37- and 217-pin bundles. [LMFBR

    SciTech Connect (OSTI)

    Chan, Y.N.; Todreas, N.E.

    1980-08-01T23:59:59.000Z

    This laboratory manual deals with the procedure employed during salt tracer experiments used in evaluating the hydraulic characteristics of a rod bundle. A description of the standard equipment used is given together with the details of manufacture of probes used for detecting the salt concentration. Details of the bundle construction have been excluded as they are availble in the reference cited. An attempt has been made to point out potential trouble areas and procedures.

  1. Uranium hexafluoride: A manual of good handling practices. Revision 7

    SciTech Connect (OSTI)

    NONE

    1995-01-01T23:59:59.000Z

    The United States Enrichment Corporation (USEC) is continuing the policy of the US Department of Energy (DOE) and its predecessor agencies in sharing with the nuclear industry their experience in the area of uranium hexafluoride (UF{sub 6}) shipping containers and handling procedures. The USEC has reviewed Revision 6 or ORO-651 and is issuing this new edition to assure that the document includes the most recent information on UF{sub 6} handling procedures and reflects the policies of the USEC. This manual updates the material contained in earlier issues. It covers the essential aspects of UF{sub 6} handling, cylinder filling and emptying, general principles of weighing and sampling, shipping, and the use of protective overpacks. The physical and chemical properties of UF{sub 6} are also described. The procedures and systems described for safe handling of UF{sub 6} presented in this document have been developed and evaluated during more than 40 years of handling vast quantities of UF{sub 6}. With proper consideration for its nuclear properties, UF{sub 6} may be safely handled in essentially the same manner as any other corrosive and/or toxic chemical.

  2. WIPP Remote Handled Waste Facility: Performance Dry Run Operations

    SciTech Connect (OSTI)

    Burrington, T. P.; Britain, R. M.; Cassingham, S. T.

    2003-02-24T23:59:59.000Z

    The Remote Handled (RH) TRU Waste Handling Facility at the Waste Isolation Pilot Plant (WIPP) was recently upgraded and modified in preparation for handling and disposal of RH Transuranic (TRU) waste. This modification will allow processing of RH-TRU waste arriving at the WIPP site in two different types of shielded road casks, the RH-TRU 72B and the CNS 10-160B. Washington TRU Solutions (WTS), the WIPP Management and Operation Contractor (MOC), conducted a performance dry run (PDR), beginning August 19, 2002 and successfully completed it on August 24, 2002. The PDR demonstrated that the RHTRU waste handling system works as designed and demonstrated the handling process for each cask, including underground disposal. The purpose of the PDR was to develop and implement a plan that would define in general terms how the WIPP RH-TRU waste handling process would be conducted and evaluated. The PDR demonstrated WIPP operations and support activities required to dispose of RH-TRU waste in the WIPP underground.

  3. Viewing biology in action | EMSL

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

    Viewing biology in action Viewing biology in action DOE-funded pilot program will create mesoscale biological imaging platform James Evans EMSL received first-year funding of...

  4. Elevated temperature triggers human respiratory syncytial virus F protein six-helix bundle formation

    SciTech Connect (OSTI)

    Yunus, Abdul S.; Jackson, Trent P.; Crisafi, Katherine; Burimski, Irina; Kilgore, Nicole R.; Zoumplis, Dorian; Allaway, Graham P.; Wild, Carl T. [Panacos Pharmaceuticals, Inc., 209 Perry Parkway, Suite 7, Gaithersburg, MD 20877 (United States); Salzwedel, Karl, E-mail: salzwedelkd@niaid.nih.go [Panacos Pharmaceuticals, Inc., 209 Perry Parkway, Suite 7, Gaithersburg, MD 20877 (United States)

    2010-01-20T23:59:59.000Z

    Human respiratory syncytial virus (RSV) is a major cause of severe lower respiratory tract infection in infants, immunocompromised patients, and the elderly. The RSV fusion (F) protein mediates fusion of the viral envelope with the target cell membrane during virus entry and is a primary target for antiviral drug and vaccine development. The F protein contains two heptad repeat regions, HR1 and HR2. Peptides corresponding to these regions form a six-helix bundle structure that is thought to play a critical role in membrane fusion. However, characterization of six-helix bundle formation in native RSV F protein has been hindered by the fact that a trigger for F protein conformational change has yet to be identified. Here we demonstrate that RSV F protein on the surface of infected cells undergoes a conformational change following exposure to elevated temperature, resulting in the formation of the six-helix bundle structure. We first generated and characterized six-helix bundle-specific antibodies raised against recombinant peptides modeling the RSV F protein six-helix bundle structure. We then used these antibodies as probes to monitor RSV F protein six-helix bundle formation in response to a diverse array of potential triggers of conformational changes. We found that exposure of 'membrane-anchored' RSV F protein to elevated temperature (45-55 deg. C) was sufficient to trigger six-helix bundle formation. Antibody binding to the six-helix bundle conformation was detected by both flow cytometry and cell-surface immunoprecipitation of the RSV F protein. None of the other treatments, including interaction with a number of potential receptors, resulted in significant binding by six-helix bundle-specific antibodies. We conclude that native, untriggered RSV F protein exists in a metastable state that can be converted in vitro to the more stable, fusogenic six-helix bundle conformation by an increase in thermal energy. These findings help to better define the mechanism of RSV F-mediated membrane fusion and have important implications for the identification of therapeutic strategies and vaccines targeting RSV F protein conformational changes.

  5. View dependent fluid dynamics

    E-Print Network [OSTI]

    Barran, Brian Arthur

    2006-08-16T23:59:59.000Z

    VIEW DEPENDENT FLUID DYNAMICS A Thesis by BRIAN ARTHUR BARRAN Submitted to the Office of Graduate Studies of Texas A&M University in partial fulfillment of the requirements for the degree of MASTER OF SCIENCE May 2006 Major Subject: Visualization... Sciences VIEW DEPENDENT FLUID DYNAMICS A Thesis by BRIAN ARTHUR BARRAN Submitted to the Office of Graduate Studies of Texas A&M University in partial fulfillment of the requirements for the degree of MASTER OF SCIENCE Approved by: Chair of Committee, Donald...

  6. LM Records Handling System-Freedom of Information/Privacy Act...

    Energy Savers [EERE]

    Freedom of InformationPrivacy Act, Office of Legacy management LM Records Handling System-Freedom of InformationPrivacy Act, Office of Legacy management LM Records Handling...

  7. Direct observation of stress accumulation and relaxation in small bundles of superconducting vortices in tungsten thin-films

    E-Print Network [OSTI]

    I. Guillamon; H. Suderow; S. Vieira; J. Sese; R. Cordoba; J. M. De Teresa; M. R. Ibarra

    2011-01-12T23:59:59.000Z

    We study the behavior of bundles of superconducting vortices when increasing the magnetic field using scanning tunneling microscopy and spectroscopy (STM/S) at 100 mK. Pinning centers are given by features on the surface corrugation. We find strong net vortex motion in a bundle towards a well defined direction. We observe continuos changes of the vortex arrangements, and identify small displacements, which stress and deform the vortex bundle, separated by larger re-arrangements or avalanches, which release accumulated stress.

  8. Arrival condition of spent fuel after storage, handling, and transportation

    SciTech Connect (OSTI)

    Bailey, W.J.; Pankaskie, P.J.; Langstaff, D.C.; Gilbert, E.R.; Rising, K.H.; Schreiber, R.E.

    1982-11-01T23:59:59.000Z

    This report presents the results of a study conducted to determine the probable arrival condition of spent light-water reactor (LWR) fuel after handling and interim storage in spent fuel storage pools and subsequent handling and accident-free transport operations under normal or slightly abnormal conditions. The objective of this study was to provide information on the expected condition of spent LWR fuel upon arrival at interim storage or fuel reprocessing facilities or at disposal facilities if the fuel is declared a waste. Results of a literature survey and data evaluation effort are discussed. Preliminary threshold limits for storing, handling, and transporting unconsolidated spent LWR fuel are presented. The difficulty in trying to anticipate the amount of corrosion products (crud) that may be on spent fuel in future shipments is also discussed, and potential areas for future work are listed. 95 references, 3 figures, 17 tables.

  9. Remote-Handled Low Level Waste Disposal Project Alternatives Analysis

    SciTech Connect (OSTI)

    David Duncan

    2010-10-01T23:59:59.000Z

    This report identifies, evaluates, and compares alternatives for meeting the U.S. Department of Energy’s mission need for management of remote-handled low-level waste generated by the Idaho National Laboratory and its tenants. Each alternative identified in the Mission Need Statement for the Remote-Handled Low-Level Waste Treatment Project is described and evaluated for capability to fulfill the mission need. Alternatives that could meet the mission need are further evaluated and compared using criteria of cost, risk, complexity, stakeholder values, and regulatory compliance. The alternative for disposal of remote-handled low-level waste that has the highest confidence of meeting the mission need and represents best value to the government is to build a new disposal facility at the Idaho National Laboratory Site.

  10. Status of ITER neutral beam cell remote handling system

    E-Print Network [OSTI]

    Sykes, N; Choi, C-H; Crofts, O; Crowe, R; Damiani, C; Delavalle, S; Meredith, L; Mindham, T; Raimbach, J; Tesini, A; Van Uffelen, M

    2013-01-01T23:59:59.000Z

    The ITER neutral beam cell will contain up to three heating neutral beams and one diagnostic neutral beam, and four upper ports. Though manual maintenance work is envisaged within the cell, when containment is breached, or the radiological protection is removed the maintenance must be conducted remotely. This maintenance constitutes the removal and replacement of line replaceable units, and their transport to and from a cask docked to the cell. A design of the remote handling system has been prepared to concept level which this paper describes including the development of a beam line transporter, beam source remote handling equipment, upper port remote handling equipment and equipment for the maintenance of the neutral shield. This equipment has been developed complete the planned maintenance tasks for the components of the neutral beam cell and to have inherent flexibility to enable as yet unforeseen tasks and recovery operations to be performed.

  11. Space effect on liquid film flow in a BWR fuel bundle

    SciTech Connect (OSTI)

    Nishida, Koji; Kanazawa, Toru; Yokomizo, Osamu (Hitachi Ltd., Ibaraki (Japan))

    1991-01-01T23:59:59.000Z

    Critical power at boiling transition is an important factor in a boiling water reactor (BWR) fuel bundle design. Boiling transition under high quality accounts for dryout as the result of the complete disappearance of film flow on a fuel rod. This liquid film vanishing process can be calculated by the liquid film model, which takes into account the evaporation due to heat from the rod surface, liquid film entrainment by steam flow, and liquid droplet deposition. It is known that spacers affect liquid film entrainment and liquid droplet deposition, so the detailed study of spacer effects on hydrodynamic characteristics is necessary for critical power prediction based on the film flow model. Many studies have been conducted to examine spacer effects on liquid film flow. However, most of them are restricted to simple test sections such as a rectangular conduit. There are a few reports on fuel bundle geometry; however the bundle studied was only a 3 by 3 rod array. It is known that spacers affect not only deposition and entrainment but also flow distribution among the subchannels. Therefore, in this research, liquid film thickness measurements were performed to clarify the deposition and entrainment at a spacer in a full-sized fuel bundle. Furthermore, critical power predictions on a BWR fuel bundle were carried out with a film flow model that included a spacer model.

  12. Certification document for newly generated contact-handled transuranic waste

    SciTech Connect (OSTI)

    Box, W.D.; Setaro, J.

    1984-01-01T23:59:59.000Z

    The US Department of Energy has requested that all national laboratories handling defense waste develop and augment a program whereby all newly generated contact-handled transuranic (TRU) waste be contained, stored, and then shipped to the Waste Isolation Pilot Plant (WIPP) in accordance with the requirements set forth in WIPP-DOE-114. The program described in this report delineates how Oak Ridge National Laboratory intends to comply with these requirements and lists the procedures used by each generator to ensure that their TRU wastes are certifiable for shipment to WIPP.

  13. Bulk Handling of Milk on Texas Dairy Farms.

    E-Print Network [OSTI]

    Parker, Cecil A.; Stelly, Randall, Moore, Donald S.

    1958-01-01T23:59:59.000Z

    areas dur- tem of handling milk. ing the spring and summer of 1957 on dairy - farms which have converted their operations to Dairymen interviewed in North Texas had tanks ranging from 150 gallons to 1,000 gallons, , the bulk system of producing... and handling milk. while tanks in the Corous Christi area raneDd Texas dairy farmers are operating larger from 200 gallons to 1,000 gallons. The average units, milking more cows, selling more milk and tank in North Texas had a capacity of 400 gal. generally...

  14. Stereoscopic optical viewing system

    DOE Patents [OSTI]

    Tallman, Clifford S. (Walnut Creek, CA)

    1987-01-01T23:59:59.000Z

    An improved optical system which provides the operator a stereoscopic viewing field and depth of vision, particularly suitable for use in various machines such as electron or laser beam welding and drilling machines. The system features two separate but independently controlled optical viewing assemblies from the eyepiece to a spot directly above the working surface. Each optical assembly comprises a combination of eye pieces, turning prisms, telephoto lenses for providing magnification, achromatic imaging relay lenses and final stage pentagonal turning prisms. Adjustment for variations in distance from the turning prisms to the workpiece, necessitated by varying part sizes and configurations and by the operator's visual accuity, is provided separately for each optical assembly by means of separate manual controls at the operator console or within easy reach of the operator.

  15. Stereoscopic optical viewing system

    DOE Patents [OSTI]

    Tallman, C.S.

    1986-05-02T23:59:59.000Z

    An improved optical system which provides the operator with a stereoscopic viewing field and depth of vision, particularly suitable for use in various machines such as electron or laser beam welding and drilling machines. The system features two separate but independently controlled optical viewing assemblies from the eyepiece to a spot directly above the working surface. Each optical assembly comprises a combination of eye pieces, turning prisms, telephoto lenses for providing magnification, achromatic imaging relay lenses and final stage pentagonal turning prisms. Adjustment for variations in distance from the turning prisms to the workpiece, necessitated by varying part sizes and configurations and by the operator's visual accuity, is provided separately for each optical assembly by means of separate manual controls at the operator console or within easy reach of the operator.

  16. Technical Evaluations of Proposed Remote-Handled Transuranic Waste Characterization Requirements at WIPP

    SciTech Connect (OSTI)

    Anastas, G.; Channell, J. K.

    2002-02-26T23:59:59.000Z

    Characterization, packaging, transport, handling and disposal of remotely handled transuranic (RH TRU) waste at WIPP will be different than similar operations with contact handled transuranic (CH TRU) waste. This paper presents results of technical evaluations associated with the planned disposal of remotely handled transuranic waste at the Waste Isolation Pilot Plant (WIPP).

  17. Coolant mixing in LMFBR rod bundles and outlet plenum mixing transients. Final report

    SciTech Connect (OSTI)

    Todreas, N.E.; Cheng, S.K.; Basehore, K.

    1984-08-01T23:59:59.000Z

    This project principally undertook the investigation of the thermal hydraulic performance of wire wrapped fuel bundles of LMFBR configuration. Results obtained included phenomenological models for friction factors, flow split and mixing characteristics; correlations for predicting these characteristics suitable for insertion in design codes; numerical codes for analyzing bundle behavior both of the lumped subchannel and distributed parameter categories and experimental techniques for pressure velocity, flow split, salt conductivity and temperature measurement in water cooled mockups of bundles and subchannels. Flow regimes investigated included laminar, transition and turbulent flow under forced convection and mixed convection conditions. Forced convections conditions were emphasized. Continuing efforts are underway at MIT to complete the investigation of the mixed convection regime initiated here. A number of investigations on outlet plenum behavior were also made. The reports of these investigations are identified.

  18. Distributions of velocity and turbulence in a parallel flow along an asymmetric rod bundle

    SciTech Connect (OSTI)

    Rehme, K.

    1982-10-01T23:59:59.000Z

    An experimental investigation was performed to obtain detailed information on the velocity and turbulence distributions in a parallel turbulent flow through an asymmetric rod bundle. The rod bundle consisted of four parallel rods arranged asymmetrically in a rectangular channel. The pitch-to-diameter (P/D) ratio of the rods was P/D = 1.072. Experimental results were obtained in two wall subchannels with wall-to-diameter (W/D) ratios of W/D = 1.096 and 1.048, respectively. The experimental results showed high anisotropy of the momentum transport, particularly in the gaps of the rod bundle. Comparisons between the measured wall shear stresses and data computed by the VELASCO code show considerable differences, particularly for the wall subchannel with W/D = 1.048.

  19. An experimental investigation on turbulent flow through symmetric wall subchannels of two rod bundles

    SciTech Connect (OSTI)

    Wu, S.R. (Inst. of Nuclear Energy Technology, Tsinghua Univ., P.O. Box 1021, Beijing (CN)); Rehme, K. (Kernforschungszentrum Karlsruhe GmbH (Germany, F.R.). Inst. fuer Neutronenphysik und Reaktortechnik)

    1990-01-01T23:59:59.000Z

    Measurements of the mean velocity, wall shear stresses, and turbulent Reynolds stresses have been performed in wall subchannels of two rod bundles. The rod bundle of four parallel rods was arranged symmetrically in a rectangular channel. The pitch-to-diameter ratio was 1.148, and the wall-to-diameter ratios were 1.045 and 1.074, respectively. The Reynolds numbers in these investigations were 6.11 {times} 10{sup 4} and 7.07 {times} 10{sup 4}, respectively. The experimental results demonstrate that the structure of turbulence in rod bundles differs greatly from the structure in circular tubes. Especially in the narrow gaps between the rods and channel walls, there are increased levels of turbulence intensities in both the axial and azimuthal directions and, hence, of the kinetic energy of turbulence, caused by a strong turbulent momentum transport through the gaps.

  20. Analysis of the FLECHT SEASET unblocked bundle steam-cooling and boiloff tests. [PWR

    SciTech Connect (OSTI)

    Wong, S.; Hochreiter, L.E.

    1981-05-01T23:59:59.000Z

    A series of forced convection steam cooling tests at low Reynolds numbers and bundle boiloff tests were conducted in the unblocked bundle task of the FLECHT SEASET program. The COBRA-IV-I computer code was utilized to simulate the steam cooling tests, so that the effects of the housing, disconnected heater rods in the bundle, and subchannel mixing were accurately accounted for. After careful data screening, a steady-state forced convection steam cooling heat transfer correlation was developed using the measured heater rod power, heater rod surface temperatures calculated from the measured cladding inner surface temperature by an inverse conduction code, and the vapor temperatures at various subchannels calculated by the COBRA-IV-I code The new correlation was found to give higher heat transfer than the conventional Dittus-Boelter correlation in the low Reynolds number region. At higher Reynolds numbers, the data begin to merge with the Dittus-Boelter correlation.

  1. Relative stereociliary motion in a hair bundle opposes amplification at distortion frequencies

    E-Print Network [OSTI]

    Andrei S. Kozlov; Thomas Risler; Armin J. Hinterwirth; A. J. Hudspeth

    2012-03-08T23:59:59.000Z

    Direct gating of mechanoelectrical-transduction channels by mechanical force is a basic feature of hair cells that assures fast transduction and underpins the mechanical amplification of acoustic inputs. But the associated nonlinearity - the gating compliance - inevitably distorts signals. Because reducing distortion would make the ear a better detector, we sought mechanisms with that effect. Mimicking in vivo stimulation, we used stiff probes to displace individual hair bundles at physiological amplitudes and measured the coherence and phase of the relative stereociliary motions with a dual-beam differential interferometer. Although stereocilia moved coherently and in phase at the stimulus frequencies, large phase lags at the frequencies of the internally generated distortion products indicated dissipative relative motions. Tip links engaged these relative modes and decreased the coherence in both stimulated and free hair bundles. These results show that a hair bundle breaks into a highly dissipative serial arrangement of stereocilia at distortion frequencies, precluding their amplification.

  2. Challenges of Handling Storm Water Runoff Through Municipal Sewer Systems

    E-Print Network [OSTI]

    Illinois at Urbana-Champaign, University of

    cleaned and retained as a Best Management Practice (BMP). Receives only non-industrial storm water on storm water are leading municipalities to change permitting practices. As a result, facilitiesChallenges of Handling Storm Water Runoff Through Municipal Sewer Systems A South Carolina Case

  3. Calculations of the radiological environment for handling of ISOLDE targets

    E-Print Network [OSTI]

    McDonald, Kirk

    Vehicle (AGV): Fully autonomous vehicle Integrated robot arm Robot mounted vision system for precise robot control Control + battery Shielded transport box Robot arm Vision system 4th High Power Targetry Workshop, May 2-6 2011 #12;Current target handling system J. Vollaire5 Two robots mounted on rails (located

  4. Method of preparing and handling chopped plant materials

    DOE Patents [OSTI]

    Bransby, David I. (2668 Wire Rd., Auburn, AL 36832)

    2002-11-26T23:59:59.000Z

    The method improves efficiency of harvesting, storage, transport, and feeding of dry plant material to animals, and is a more efficient method for harvesting, handling and transporting dry plant material for industrial purposes, such as for production of bioenergy, and composite panels.

  5. A Modal Calculus for Exception Handling Aleksandar Nanevski 1

    E-Print Network [OSTI]

    Nanevski, Aleksandar

    = inl e let comp x = e1 in e2 def = case e1 of inl x e2 | inr y inr y The typing rules . raise : E A = e. inr e handle : A (E A) A = e. h. case e of inl v v | inr exn h (exn

  6. Breeder Spent Fuel Handling Program multipurpose cask design basis document

    SciTech Connect (OSTI)

    Duckett, A.J.; Sorenson, K.B.

    1985-09-01T23:59:59.000Z

    The Breeder Spent Fuel Handling (BSFH) Program multipurpose cask Design Basis Document defines the performance requirements essential to the development of a legal weight truck cask to transport FFTF spent fuel from reactor to a reprocessing facility and the resultant High Level Waste (HLW) to a repository. 1 ref.

  7. Pipelined Memory Controllers for DSP Applications Handling Unpredictable Data Accesses

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    Pipelined Memory Controllers for DSP Applications Handling Unpredictable Data Accesses Bertrand Le pipelined memory access controllers can be generated improving the pipeline access mode to RAM. We focus as unpredictable ones (dynamic address computations) in a pipeline way. 1 Introduction Actual researches

  8. SOLIS Data Handling Christoph Keller, Steve Wampler, Carl Henney

    E-Print Network [OSTI]

    SOLIS Data Handling Christoph Keller, Steve Wampler, Carl Henney National Solar Observatory #12;May, 2003 FASR Data System Workshop 3 Science What causes the solar cycle? How is energy stored and released in the solar atmosphere? How does the solar radiative and non- radiative output vary? Vector

  9. Sample handling for kinetics and molecular assembly in flow cytometry

    SciTech Connect (OSTI)

    Sklar, L.A. [Los Alamos National Lab., NM (United States). National Flow Cytometry Resource]|[Univ. of New Mexico, Albuquerque, NM (United States). School of Medicine; Seamer, L.C.; Kuckuck, F.; Prossnitz, E.; Edwards, B. [Univ. of New Mexico, Albuquerque, NM (United States). School of Medicine; Posner, G. [Northern Arizona Univ., Flagstaff, AZ (United States). Dept. of Chemistry

    1998-07-01T23:59:59.000Z

    Flow cytometry discriminates particle associated fluorescence from the fluorescence of the surrounding medium. It permits assemblies of macromolecular complexes on beads or cells to be detected in real-time with precision and specificity. The authors have investigated two types of robust sample handling systems which provide sub-second resolution and high throughput: (1) mixers which use stepper-motor driven syringes to initiate chemical reactions in msec time frames; and (2) flow injection controllers with valves and automated syringes used in chemical process control. In the former system, the authors used fast valves to overcome the disparity between mixing 100 {micro}ls of sample in 100 msecs and delivering sample to a flow cytometer at 1 {micro}l/sec. Particles were detected within 100 msec after mixing, but turbulence was created which lasted for 1 sec after injection of the sample into the flow cytometer. They used optical criteria to discriminate particles which were out of alignment due to the turbulent flow. Complex sample handling protocols involving multiple mixing steps and sample dilution have also been achieved. With the latter system they were able to automate sample handling and delivery with intervals of a few seconds. The authors used a fluidic approach to defeat turbulence caused by sample introduction. By controlling both sheath and sample with individual syringes, the period of turbulence was reduced to {approximately} 200 msecs. Automated sample handling and sub-second resolution should permit broad analytical and diagnostic applications of flow cytometry.

  10. MERCURY HANDLING FOR THE TARGET SYSTEM FOR A MUON COLLIDER

    E-Print Network [OSTI]

    McDonald, Kirk

    MERCURY HANDLING FOR THE TARGET SYSTEM FOR A MUON COLLIDER (IPAC12, WEPPD038) The target station a 15-20 T superconducting magnet. The target itself is a free mercury jet, moving at 20 m/s at an small angle to the magnetic axis, so as later to be collected in a mercury pool/beam dump. The replaceable

  11. MERCURY HANDLING FOR THE TARGET SYSTEM FOR A MUON COLLIDER

    E-Print Network [OSTI]

    McDonald, Kirk

    MERCURY HANDLING FOR THE TARGET SYSTEM FOR A MUON COLLIDER Van Graves , ORNL, Oak Ridge, TN 37830 Factory is a free-stream mercury jet within a 20-T magnetic field being impacted by an 8-GeV proton beam. A pool of mercury serves as a receiving reservoir for the mercury and a dump for the unexpended proton

  12. Certification Plan, low-level waste Hazardous Waste Handling Facility

    SciTech Connect (OSTI)

    Albert, R.

    1992-06-30T23:59:59.000Z

    The purpose of this plan is to describe the organization and methodology for the certification of low-level radioactive waste (LLW) handled in the Hazardous Waste Handling Facility (HWHF) at Lawrence Berkeley Laboratory (LBL). This plan also incorporates the applicable elements of waste reduction, which include both up-front minimization and end-product treatment to reduce the volume and toxicity of the waste; segregation of the waste as it applies to certification; an executive summary of the Waste Management Quality Assurance Implementing Management Plan (QAIMP) for the HWHF and a list of the current and planned implementing procedures used in waste certification. This plan provides guidance from the HWHF to waste generators, waste handlers, and the Waste Certification Specialist to enable them to conduct their activities and carry out their responsibilities in a manner that complies with the requirements of WHC-WAC. Waste generators have the primary responsibility for the proper characterization of LLW. The Waste Certification Specialist verifies and certifies that LBL LLW is characterized, handled, and shipped in accordance with the requirements of WHC-WAC. Certification is the governing process in which LBL personnel conduct their waste generating and waste handling activities in such a manner that the Waste Certification Specialist can verify that the requirements of WHC-WAC are met.

  13. STABILIZING LINEAR MPC WITH EFFICIENT PRIORITIZED INFEASIBILITY HANDLING

    E-Print Network [OSTI]

    Foss, Bjarne A.

    is illustrated on a simulated distillation column, and we present a novel stability result for this infeasibilitySTABILIZING LINEAR MPC WITH EFFICIENT PRIORITIZED INFEASIBILITY HANDLING Jostein Vada Olav predictive controller fails to compute a control input, all practical MPC implementations should havea means

  14. Microfluidic Facility, Harvard Medical School LIQUID NITROGEN TANK HANDLING

    E-Print Network [OSTI]

    Paulsson, Johan

    Microfluidic Facility, Harvard Medical School LIQUID NITROGEN TANK HANDLING HMS microfluidics/microfabrication facility has one high pressure liquid nitrogen tank which supplies the nitrogen for some equipment normal operation. In case the liquid nitrogen tank is malfunctioning and requires to be shut down or replaced make

  15. Evaluation of nonequilibrium effects in bundle dispersed-flow film boiling. [PWR; BWR

    SciTech Connect (OSTI)

    Morris, D.G.; Mullins, C.B.; Yoder, G.L.

    1983-01-01T23:59:59.000Z

    The effects of thermodynamic nonequilibrium in dispersed flow film boiling heat transfer are examined. Steady-state and transient rod-bundle data are used to evaluate several empirical heat-transfer models commonly employed to predict post-CHF behavior. The models that account for thermodynamic nonequilibrium perform adequately, while those that ignore nonequilibrium effects incur errors in wall superheat as high as 190/sup 0/K. Nonequilibrium effects can also be treated by explicitly modeling the phenomena. The thermal-hydraulic code COBRA-TF employs this approach. Using bundle data, the models in the code are evaluated. Analysis suggests that the interfacial heat transfer is overpredicted.

  16. Structure and heat capacity of Ne and Xe adsorbed on a bundle of carbon nanotubes

    E-Print Network [OSTI]

    Daniel E. Shai; Nathan M. Urban; Milton W. Cole

    2007-02-08T23:59:59.000Z

    The structural and thermal properties of Ne and Xe gases adsorbed on the outer surface of a large nanotube bundle have been evaluated with computer simulation. The potential energy model and numerical techniques were used previously to study Ar [N. M. Urban, S. M. Gatica, M. W. Cole, and J. L. Riccardo, ``Correlation functions and thermal properties of Ar adsorbed on the external surface of a bundle of carbon nanotubes'', Phys. Rev. B 71, 245410 (2005)]. Heat capacity results for Ne and Xe exhibit peaks associated with reordering and ``stripe'' melting transitions for these gases.

  17. Synthetic peptides that cause F-actin bundling and block actin depolymerization

    DOE Patents [OSTI]

    Sederoff, Heike (Raleigh, NC); Huber, Steven C (Savoy, IL); Larabell, Carolyn A (Berkeley, CA)

    2011-10-18T23:59:59.000Z

    Synthetic peptides derived from sucrose synthase, and having homology to actin and actin-related proteins, sharing a common motif, useful for causing acting bundling and preventing actin depolymerization. Peptides exhibiting the common motif are described, as well as specific synthetic peptides which caused bundled actin and inhibit actin depolymerization. These peptides can be useful for treating a subject suffering from a disease characterized by cells having neoplastic growth, for anti-cancer therapeutics, delivered to subjects solely, or concomitantly or sequentially with other known cancer therapeutics. These peptides can also be used for stabilizing microfilaments in living cells and inhibiting growth of cells.

  18. On Parallel Transport in Quantum Bundles over Robertson-Walker Spacetimes

    E-Print Network [OSTI]

    James Coleman

    1996-12-03T23:59:59.000Z

    A recently-developed theory of quantum general relativity provides a propagator for free-falling particles in curved spacetimes. These propagators are constructed by parallel-transporting quantum states within a quantum bundle associated to the Poincare frame bundle. We consider such parallel transport in the case that the spacetime is a classical Robertson-Walker universe. An explicit integral formula is developed which expresses the propagators for parallel transport between any two points of such a spacetime. The integrals in this formula are evaluated in closed form for a particular spatially-flat model.

  19. The shape of a ponytail and the statistical physics of hair fiber bundles

    E-Print Network [OSTI]

    Raymond E. Goldstein; Patrick B. Warren; Robin C. Ball

    2012-04-02T23:59:59.000Z

    A general continuum theory for the distribution of hairs in a bundle is developed, treating individual fibers as elastic filaments with random intrinsic curvatures. Applying this formalism to the iconic problem of the ponytail, the combined effects of bending elasticity, gravity, and orientational disorder are recast as a differential equation for the envelope of the bundle, in which the compressibility enters through an 'equation of state'. From this, we identify the balance of forces in various regions of the ponytail, extract a remarkably simple equation of state from laboratory measurements of human ponytails, and relate the pressure to the measured random curvatures of individual hairs.

  20. Multi-view kernel construction

    E-Print Network [OSTI]

    Sa, Virginia R.; Gallagher, Patrick W.; Lewis, Joshua M.; Malave, Vicente L.

    2010-01-01T23:59:59.000Z

    5157-z Multi-view kernel construction Virginia R. de Sa ·multiple different graph construction algorithms. The Ng et

  1. On rank 2 vector bundles on Fano manifolds Roberto Mu~noz, Gianluca Occhetta, and Luis E. Sola Conde

    E-Print Network [OSTI]

    Occhetta, Gianluca

    On rank 2 vector bundles on Fano manifolds Roberto Mu~noz, Gianluca Occhetta, and Luis E. Sol´a~NOZ, GIANLUCA OCCHETTA, AND LUIS E. SOL´A CONDE setting of rank two vector bundles on Fano manifolds of Picard

  2. Transfer-matrix simulations of field emission from bundles of open and closed ,,5,5... carbon nanotubes

    E-Print Network [OSTI]

    Mayer, Alexandre

    Transfer-matrix simulations of field emission from bundles of open and closed ,,5,5... carbon simulations of field emission from bundles of metallic 5,5 carbon nanotubes, which are either ideally open.35.Kt, 03.65.Nk I. INTRODUCTION Carbon nanotubes show interesting field-emission proper- ties

  3. Hydrothermal synthesis of flowerlike SnO{sub 2} nanorod bundles and their application for lithium ion battery

    SciTech Connect (OSTI)

    Wen, Zhigang, E-mail: xh168688@126.com [School of Materials Science and Engineering, Central South University, Changsha 410083 (China); State Key Laboratory of Powder Metallurgy, Central South University, Changsha 410083 (China); Department of Chemistry and Chemical Engineering, Qiannan Normal College for Nationalities, Duyun 558000 (China); Zheng, Feng, E-mail: fzheng@mail.csu.edu.cn [School of Materials Science and Engineering, Central South University, Changsha 410083 (China); State Key Laboratory of Powder Metallurgy, Central South University, Changsha 410083 (China); Yu, Hongchun; Jiang, Ziran [School of Materials Science and Engineering, Central South University, Changsha 410083 (China); Liu, Kanglian [Department of Chemistry and Chemical Engineering, Qiannan Normal College for Nationalities, Duyun 558000 (China)

    2013-02-15T23:59:59.000Z

    SnO{sub 2} nanorod bundles were synthesized by hydrothermal method. Field-emission scanning electron microscopy and transmission electron microscopy images showed that the as-prepared flowerlike SnO{sub 2} nanorod bundles consist of tetragonal nanorods with size readily tunable. Their electrochemical properties and application as anode for lithium-ion battery were evaluated by galvanostatic discharge–charge testing and cycle voltammetry. SnO{sub 2} nanorod flowers possess improved discharge capacity of 694 mA h g{sup ?1} up to 40th cycle at 0.1 C. - Highlights: ? The flowerlike SnO{sub 2} nanorod bundles were synthesized by hydrothermal method. ? SnO{sub 2} nanorod bundles with tunable size by controlling concentration of SnCl{sub 4}. ? A probable formation mechanism of SnO{sub 2} nanorod bundles has been proposed.

  4. Protective laser beam viewing device

    DOE Patents [OSTI]

    Neil, George R.; Jordan, Kevin Carl

    2012-12-18T23:59:59.000Z

    A protective laser beam viewing system or device including a camera selectively sensitive to laser light wavelengths and a viewing screen receiving images from the laser sensitive camera. According to a preferred embodiment of the invention, the camera is worn on the head of the user or incorporated into a goggle-type viewing display so that it is always aimed at the area of viewing interest to the user and the viewing screen is incorporated into a video display worn as goggles over the eyes of the user.

  5. Universality Class of the Fiber Bundle Model on Complex Networks Dong-Hee Kim,1

    E-Print Network [OSTI]

    Jeong, Hawoong

    is broken if the load v is larger than the threshold value th v assigned to the fiber following a given is shared among intact fibers following a load sharing rule. The two most frequently studied rules networks within the framework of the fiber bundle model subject to the local load sharing rule in which

  6. Limit linear series in positive characteristic and Frobenius-unstable vector bundles on curves

    E-Print Network [OSTI]

    Osserman, Brian, 1977-

    2004-01-01T23:59:59.000Z

    (cont.) yield a new proof of a result of Mochizuki yield a new proof of a result of Mochizuki Frobenius-unstable bundles for C general, and hence obtaining a self-contained proof of the resulting formula for the degree of V?.

  7. Load capacity and rupture displacement in viscoelastic fiber bundles Theocharis Baxevanis1,

    E-Print Network [OSTI]

    Katsaounis, Theodoros D.

    for this critical load is given. For stress levels below the critical value, the system suffers only partial failureLoad capacity and rupture displacement in viscoelastic fiber bundles Theocharis Baxevanis1 loading, assuming global load sharing GLS for the redistribution of load following fiber failure. We

  8. Thermal-hydraulic and structural considerations on the gap variation between fuel bundle and hexcan

    SciTech Connect (OSTI)

    Chang, L.K.; Lee, M.J.; Ku, J.Y.

    1992-05-01T23:59:59.000Z

    One of the safety concerns in reactor operation is the temperature of the fuel elements, which are contained in a hexagonal duct, referred to as the hexcan. There are gaps between the fuel bundle and the hexcan, and the gaps somewhat affect thermal-hydraulic behavior of the fuel element. This paper investigates the impact of gap variations on the thermal-hydraulic responses of the fuel element as well as the possibility of fuel bundle and hexcan interaction. The gap variation between hex duct and fuel bundle is caused by differential thermal expansion, creep strain, and irradiation-induced swelling of fuel-cladding and hex duct, and it is a function of fuel burnup. The effects of gap variations on the thermal-hydraulic responses of typical driver subassemblies in the Experimental Breeder Reactor (EBR-II) are investigated. A structural analysis was performed to predict the in-reactor deformation behavior of fuel bundle and hex duct, and followed by a thermal-hydraulic analysis to determine the flow and temperature response due to gap changes. The effects of geometry variation on the thermal-hydraulic response are discussed. The study indicates that the effect of gap variation should not be ignored for subassembly designs.

  9. Input parameters to codes which analyze LMFBR wire-wrapped bundles

    SciTech Connect (OSTI)

    Hawley, J.T.; Chan, Y.N.; Todreas, N.E.

    1980-12-01T23:59:59.000Z

    This report provides a current summary of recommended values of key input parameters required by ENERGY code analysis of LMFBR wire wrapped bundles. This data is based on the interpretation of experimental results from the MIT and other available laboratory programs.

  10. Thermal-hydraulic and structural considerations on the gap variation between fuel bundle and hexcan

    SciTech Connect (OSTI)

    Chang, L.K.; Lee, M.J.; Ku, J.Y.

    1992-01-01T23:59:59.000Z

    One of the safety concerns in reactor operation is the temperature of the fuel elements, which are contained in a hexagonal duct, referred to as the hexcan. There are gaps between the fuel bundle and the hexcan, and the gaps somewhat affect thermal-hydraulic behavior of the fuel element. This paper investigates the impact of gap variations on the thermal-hydraulic responses of the fuel element as well as the possibility of fuel bundle and hexcan interaction. The gap variation between hex duct and fuel bundle is caused by differential thermal expansion, creep strain, and irradiation-induced swelling of fuel-cladding and hex duct, and it is a function of fuel burnup. The effects of gap variations on the thermal-hydraulic responses of typical driver subassemblies in the Experimental Breeder Reactor (EBR-II) are investigated. A structural analysis was performed to predict the in-reactor deformation behavior of fuel bundle and hex duct, and followed by a thermal-hydraulic analysis to determine the flow and temperature response due to gap changes. The effects of geometry variation on the thermal-hydraulic response are discussed. The study indicates that the effect of gap variation should not be ignored for subassembly designs.

  11. An inverse correlation between loop length and stability in a four-helix-bundle protein

    E-Print Network [OSTI]

    Mochrie, Simon

    their intrinsic func- tionality upon their new environmental context: the calcium-binding activity of a loop has the molten globule behavior of apo- - lactalbumin in the absence of calcium [18]. Conversely, loops have beenAn inverse correlation between loop length and stability in a four-helix-bundle protein Athena D

  12. Compressive nonlinearity in the hair bundle's active response to mechanical stimulation

    E-Print Network [OSTI]

    Hudspeth, A. James

    as the one-third power of the stimulus amplitude; the bundle's sensitivity declines accordingly in proportion to the negative two-thirds power of the excitation. This scaling behavior, also found in the response to thermal energy (1). At the other extreme, the ear endures urban, industrial, and military noise

  13. SOLVING GENERATION EXPANSION PLANNING PROBLEMS WITH ENVIRONMENTAL CONSTRAINTS BY A BUNDLE METHOD

    E-Print Network [OSTI]

    Solodov, Mikhail V.

    for the construction of new power plants, while ensuring economic and reliable supply to the future electricity demandSOLVING GENERATION EXPANSION PLANNING PROBLEMS WITH ENVIRONMENTAL CONSTRAINTS BY A BUNDLE METHOD discuss the energy generation expansion planning with environmental constraints, formulated as a nonsmooth

  14. DOI: 10.1002/cphc.200900615 From Branched Networks of Actin Filaments to Bundles

    E-Print Network [OSTI]

    Ben-Shaul, Avinoam

    DOI: 10.1002/cphc.200900615 From Branched Networks of Actin Filaments to Bundles Yifat Brill- ses. Cell movement is driven by the dynamic growth of polar actin networks of various structures,[1 containing the lamellipodium, but lacking the nucleus, micro- tubules and other organels can perform movement

  15. Packages in the `graphics' bundle D. P. Carlisle The LATEX3 Project

    E-Print Network [OSTI]

    Mays, Michael

    Packages in the `graphics' bundle D. P. Carlisle The LATEX3 Project 2005/11/14 Contents 1 . . . . . . . . . . . . . . . . . . . . . . . . . . 7 4 The Graphics packages 7 4.1 Package Options . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9 4.4 Including Graphics Files . . . . . . . . . . . . . . . . . . . . . . . 9 4.5 Other commands

  16. Active hair-bundle movements can amplify a hair cell's response to oscillatory mechanical stimuli

    E-Print Network [OSTI]

    Hudspeth, A. James

    Active hair-bundle movements can amplify a hair cell's response to oscillatory mechanical stimuli, 1999 To enhance their mechanical sensitivity and frequency selectivity, hair cells amplify the mechanical stimuli to which they respond. Although cell-body contractions of outer hair cells are thought

  17. Survival of Bundleless Hair Cells and Subsequent Bundle Replacement in the Bullfrog's Saccule

    E-Print Network [OSTI]

    Survival of Bundleless Hair Cells and Subsequent Bundle Replacement in the Bullfrog's Saccule and balance depend upon hair cells, the sensory receptors of the inner ear. Millions of people suffer from hearing and balance deficits caused by damage to hair cells as a result of exposure to noise

  18. Single-Walled Carbon Nanotubes of Controlled Diameter and Bundle Size and Their Field Emission Properties

    E-Print Network [OSTI]

    Resasco, Daniel

    Single-Walled Carbon Nanotubes of Controlled Diameter and Bundle Size and Their Field Emission: June 8, 2005 Field emission studies were conducted on as-produced CoMoCAT single-walled carbon nanotube electron emitter. By adjusting the catalytic synthesis conditions, single-walled carbon nanotubes (SWNT

  19. Test plan for K-Basin fuel handling tools

    SciTech Connect (OSTI)

    Bridges, A.E.

    1995-02-08T23:59:59.000Z

    The purpose of this document is to provide the test plan and procedures for the acceptance testing of the handling tools enveloped for the removal of an N-Reactor fuel element from its storage canister in the K-Basins storage pool and insertion into the Single fuel Element Can for subsequent shipment to a Hot Cell for examination. Examination of these N-Reactor fuel elements is part of the overall characterization effort. New hand tools were required since previous fuel movement has involved grasping the fuel in a horizontal position. The 305 Building Cold Test Facility will be used to conduct the acceptance testing of the Fuel Handling Tools. Upon completion of this acceptance testing and any subsequent training of operators, the tools will be transferred to the 105 KW Basin for installation and use.

  20. False color viewing device

    DOE Patents [OSTI]

    Kronberg, J.W.

    1991-05-08T23:59:59.000Z

    This invention consists of a viewing device for observing objects in near-infrared false-color comprising a pair of goggles with one or more filters in the apertures, and pads that engage the face for blocking stray light from the sides so that all light reaching, the user`s eyes come through the filters. The filters attenuate most visible light and pass near-infrared (having wavelengths longer than approximately 700 nm) and a small amount of blue-green and blue-violet (having wavelengths in the 500 to 520 nm and shorter than 435 nm, respectively). The goggles are useful for looking at vegetation to identify different species and for determining the health of the vegetation, and to detect some forms of camouflage.

  1. False color viewing device

    DOE Patents [OSTI]

    Kronberg, James W. (108 Independent Blvd., Aiken, SC 29801)

    1992-01-01T23:59:59.000Z

    A viewing device for observing objects in near-infrared false-color comprising a pair of goggles with one or more filters in the apertures, and pads that engage the face for blocking stray light from the sides so that all light reaching the user's eyes come through the filters. The filters attenuate most visible light and pass near-infrared (having wavelengths longer than approximately 700 nm) and a small amount of blue-green and blue-violet (having wavelengths in the 500 to 520 nm and shorter than 435 nm, respectively). The goggles are useful for looking at vegetation to identify different species and for determining the health of the vegetation, and to detect some forms of camouflage.

  2. False color viewing device

    DOE Patents [OSTI]

    Kronberg, J.W.

    1992-10-20T23:59:59.000Z

    A viewing device for observing objects in near-infrared false-color comprising a pair of goggles with one or more filters in the apertures, and pads that engage the face for blocking stray light from the sides so that all light reaching the user's eyes come through the filters. The filters attenuate most visible light and pass near-infrared (having wavelengths longer than approximately 700 nm) and a small amount of blue-green and blue-violet (having wavelengths in the 500 to 520 nm and shorter than 435 nm, respectively). The goggles are useful for looking at vegetation to identify different species and for determining the health of the vegetation, and to detect some forms of camouflage. 7 figs.

  3. Health physics considerations in UF{sub 6} handling

    SciTech Connect (OSTI)

    Bailey, J.C. [Norway Assoicates, Inc., Oak Ridge, TN (United States)

    1991-12-31T23:59:59.000Z

    Uranium is a radioactive substance that emits alpha particles and very small amounts of gamma radiation. Its daughter products emit beta and gamma radiation. In uranium handling operations these are the radiations one must consider. This presentation will review the characteristics of the radiations, the isotopes from which they originate, the growth and decay of the uranium daughter products, and some specific health physics practices dictated by these factors.

  4. Implementation of the Laboratory Air Handling Unit Systems (LAHU)

    E-Print Network [OSTI]

    Cui, Y.; Liu, M.; Conger, K.

    2003-01-01T23:59:59.000Z

    Implementation of the Laboratory Air Handling Unit Systems (LAHU) Y. Cui Graduate Student Energy Systems Laboratory University of Nebraska-Lincoln Omaha, NE, USA M. Liu, Ph.D., P.E. Associate Professor Energy Systems Laboratory...-around coils [18, 19], the variable air volume (VAV) fume hoods [8-16] and the usage-based control devices (UBC) [17]. These measures have effectively reduced the cooling energy, preheat energy and fan power consumption, and sometime, improved indoor...

  5. Ross Hazardous and Toxic Materials Handling Facility: Environmental Assessment.

    SciTech Connect (OSTI)

    URS Consultants, Inc.

    1992-06-01T23:59:59.000Z

    The Bonneville Power Administration (BPA) owns a 200-acre facility in Washington State known as the Ross Complex. Activities at the Ross Complex routinely involve handling toxic substances such as oil-filled electrical equipment containing polychlorinated biphenyls (PCBs), organic and inorganic compounds for preserving wood transmission poles, and paints, solvents, waste oils, and pesticides and herbicides. Hazardous waste management is a common activity on-site, and hazardous and toxic substances are often generated from these and off-site activities. The subject of this environmental assessment (EA) concerns the consolidation of hazardous and toxic substances handling at the Complex. This environmental assessment has been developed to identify the potential environmental impacts of the construction and operation of the proposal. It has been prepared to meet the requirements of the National Environmental Policy Act (NEPA) to determine if the proposed action is likely to have a significant impact on the environment. In addition to the design elements included within the project, mitigation measures have been identified within various sections that are now incorporated within the project. This facility would be designed to improve the current waste handling practices and to assist BPA in meeting Federal and state regulations.

  6. West Valley facility spent fuel handling, storage, and shipping experience

    SciTech Connect (OSTI)

    Bailey, W.J.

    1990-11-01T23:59:59.000Z

    The result of a study on handling and shipping experience with spent fuel are described in this report. The study was performed by Pacific Northwest Laboratory (PNL) and was jointly sponsored by the US Department of Energy (DOE) and the Electric Power Research Institute (EPRI). The purpose of the study was to document the experience with handling and shipping of relatively old light-water reactor (LWR) fuel that has been in pool storage at the West Valley facility, which is at the Western New York Nuclear Service Center at West Valley, New York and operated by DOE. A subject of particular interest in the study was the behavior of corrosion product deposits (i.e., crud) deposits on spent LWR fuel after long-term pool storage; some evidence of crud loosening has been observed with fuel that was stored for extended periods at the West Valley facility and at other sites. Conclusions associated with the experience to date with old spent fuel that has been stored at the West Valley facility are presented. The conclusions are drawn from these subject areas: a general overview of the West Valley experience, handling of spent fuel, storing of spent fuel, rod consolidation, shipping of spent fuel, crud loosening, and visual inspection. A list of recommendations is provided. 61 refs., 4 figs., 5 tabs.

  7. An analysis of repository waste-handling operations

    SciTech Connect (OSTI)

    Dennis, A.W.

    1990-09-01T23:59:59.000Z

    This report has been prepared to document the operational analysis of waste-handling facilities at a geologic repository for high-level nuclear waste. The site currently under investigation for the geologic repository is located at Yucca Mountain, Nye County, Nevada. The repository waste-handling operations have been identified and analyzed for the year 2011, a steady-state year during which the repository receives spent nuclear fuel containing the equivalent of 3000 metric tons of uranium (MTU) and defense high-level waste containing the equivalent of 400 MTU. As a result of this analysis, it has been determined that the waste-handling facilities are adequate to receive, prepare, store, and emplace the projected quantity of waste on an annual basis. In addition, several areas have been identified where additional work is required. The recommendations for future work have been divided into three categories: items that affect the total waste management system, operations within the repository boundary, and the methodology used to perform operational analyses for repository designs. 7 refs., 48 figs., 11 tabs.

  8. Oxygen Handling and Cooling Options in High Temperature Electrolysis Plants

    SciTech Connect (OSTI)

    Manohar S. Sohal; J. Stephen Herring

    2008-07-01T23:59:59.000Z

    Idaho National Laboratory is working on a project to generate hydrogen by high temperature electrolysis (HTE). In such an HTE system, safety precautions need to be taken to handle high temperature oxygen at ~830°C. This report is aimed at addressing oxygen handling in a HTE plant.. Though oxygen itself is not flammable, most engineering material, including many gases and liquids, will burn in the presence of oxygen under some favorable physicochemical conditions. At present, an absolute set of rules does not exist that can cover all aspects of oxygen system design, material selection, and operating practices to avoid subtle hazards related to oxygen. Because most materials, including metals, will burn in an oxygen-enriched environment, hazards are always present when using oxygen. Most materials will ignite in an oxygen-enriched environment at a temperature lower than that in air, and once ignited, combustion rates are greater in the oxygen-enriched environment. Even many metals, if ignited, burn violently in an oxygen-enriched environment. However, these hazards do not preclude the operations and systems involving oxygen. Oxygen can be safely handled and used if all the materials in a system are not flammable in the end-use environment or if ignition sources are identified and controlled. In fact, the incidence of oxygen system fires is reported to be low with a probability of about one in a million. This report is a practical guideline and tutorial for the safe operation and handling of gaseous oxygen in high temperature electrolysis system. The intent is to provide safe, practical guidance that permits the accomplishment of experimental operations at INL, while being restrictive enough to prevent personnel endangerment and to provide reasonable facility protection. Adequate guidelines are provided to govern various aspects of oxygen handling associated with high temperature electrolysis system to generate hydrogen. The intent here is to present acceptable oxygen standards and practices for minimum safety requirements. A summary of operational hazards, along with oxygen safety and emergency procedures, are provided.

  9. The WARRP Core: Optoelectronic Implementation of Network Router Deadlock Handling Mechanisms

    E-Print Network [OSTI]

    Pinkston, Timothy M.

    1 The WARRP Core: Optoelectronic Implementation of Network Router Deadlock Handling Mechanisms. Keywords: adaptive routing, deadlock handling, multiprocessor network router, optoelectronic smart pixel. #12;2 1. Introduction Emerging optoelectronic smart-pixel technology is of increasing interest

  10. NFS File Handle Security Avishay Traeger, Abhishek Rai, Charles P. Wright, and Erez Zadok

    E-Print Network [OSTI]

    Zadok, Erez

    a file han- dle. When an NFS client performs an operation, it passes the file handle to the server, which decodes the file han- dle to determine what object the file handle refers to. Since NFS is a stateless

  11. Department of Industrial & Manufacturing Engineering Fall 2011 Mining Media Handling Project

    E-Print Network [OSTI]

    Demirel, Melik C.

    Project Overview Metso wants to develop a media handling solution (machinery and/or process) to enhance that optimizes media discharge, recharge and liner maintenance procedures in accordance with the handling system

  12. Fuel channel analysis for a large-break loss-of-coolant accident in a Canada deuterium uranium reactor loaded with CANFLEX fuel bundles

    SciTech Connect (OSTI)

    Oh, D.J.; Lim, H.S.; Ohn, M.Y.; Lee, K.M.; Suk, H.C. [Korea Atomic Energy Research Inst., Taejon (Korea, Republic of)

    1996-06-01T23:59:59.000Z

    The CATHENA ``slave`` channel model is used for fuel channel analysis of a 30% reactor inlet header break in a Canada deuterium uranium (CANDU)-6 reactor loaded with 43-element bundles of advanced CANDU [CANDU flexible fueling (CANFLEX)] fuel. The predicted results are compared with those for the reactor loaded with standard 37-element bundles. The maximum fuel centerline and sheath temperatures for the CANFLEX bundle are lower by 388 and 128C, respectively, than those for the standard bundle because of the lower maximum linear power of the CANFLEX bundle. The pressure tube (PT)/calandria tube (CT) contact for the CANFLEX bundle occurs 2 s later than that for the standard bundle. The PT/CT contact temperature for the CANFLEX bundle is 7C lower than that for the standard bundle. These provide the CANFLEX bundle with a slightly enhanced safety margin for fuel channel integrity in the CANDU-6 reactor, compared with the standard bundle. The effect of bearing pad (BP)/PT contact on the PT temperature predictions is assessed. A BP/PT contact conductance of 3 kW/m{sup 2} {center_dot} K after PT ballooning does not create any hot spot because it gives the contacted PT sector approximately the same heat transfer as convective heating by the hot coolant for the adjacent sector. The assumed BP/PT contact conductance does not threaten the fuel channel integrity.

  13. Viability of Existing INL Facilities for Dry Storage Cask Handling

    SciTech Connect (OSTI)

    Randy Bohachek; Charles Park; Bruce Wallace; Phil Winston; Steve Marschman

    2013-04-01T23:59:59.000Z

    This report evaluates existing capabilities at the INL to determine if a practical and cost effective method could be developed for opening and handling full-sized dry storage casks. The Idaho Nuclear Technology and Engineering Center (INTEC) CPP-603, Irradiated Spent Fuel Storage Facility, provides the infrastructure to support handling and examining casks and their contents. Based on a reasonable set of assumptions, it is possible to receive, open, inspect, remove samples, close, and reseal large bolted-lid dry storage casks at the INL. The capability can also be used to open and inspect casks that were last examined at the TAN Hot Shop over ten years ago. The Castor V/21 and REA-2023 casks can provide additional confirmatory information regarding the extended performance of low-burnup (<45 GWD/MTU) used nuclear fuel. Once a dry storage cask is opened inside CPP-603, used fuel retrieved from the cask can be packaged in a shipping cask, and sent to a laboratory for testing. Testing at the INL’s Materials and Fuels Complex (MFC) can occur starting with shipment of samples from CPP-603 over an on-site road, avoiding the need to use public highways. This reduces cost and reduces the risk to the public. The full suite of characterization methods needed to establish the condition of the fuel exists and MFC. Many other testing capabilities also exist at MFC, but when those capabilities are not adequate, samples can be prepared and shipped to other laboratories for testing. This report discusses how the casks would be handled, what work needs to be done to ready the facilities/capabilities, and what the work will cost.

  14. Remote-handled transuranic system assessment. Volume 1

    SciTech Connect (OSTI)

    NONE

    1995-11-01T23:59:59.000Z

    This document identifies the necessary actions for addressing current questions concerning the safe and efficient disposal of remote-handled transuranic wastes that have been generated through Department of Energy activities. In addition, this document presents summaries of existing information and analyses regarding the potential alternatives for disposing of remote-handled (RH) transuranic (TRU) waste at the Department of Energy (DOE) Waste Isolation Pilot Plant (WIPP). A further discussion of DOE`s approach for addressing RH-TRU issues is contained in the document, Waste Isolation Pilot Plant Remote-Handled Transuranic Waste Disposal Strategy, DOE/WIPP-95-1090 (DOE, 1995a). Of this stored and projected inventory, approximately 30% can be characterized with current technology and subsequently certified to meet the waste acceptance criteria for disposal at WIPP; characterization of the remaining 70% will require the use of alternative techniques. At most of the generator sites, characterization equipment and facilities need to be procured in order for the sites to certify waste for shipment either to WIPP or to an interim site. If surface dose rates are too high, the use of non-invasive techniques such as non-destructive examination (NDE) and non-destructive assay (NDA) may be precluded. Characterization methods using NDA can be effectively used on RH-TRU wastes with surface dose rates of less than 1.0 rem/hr (neutron); NDE methods are effective on waste with surface dose rates of less than 10 rem/hr (gamma). The ability to use current NDE technology on waste with surface dose rates above 10 rem/hr will need to be demonstrated. Alternate characterization techniques, such as examination within a hot cell, could be used for the remaining waste; however, such techniques are labor intensive and would require additional effort to gather assay data. Improvements in characterization capabilities are being pursued through future technology development initiatives.

  15. Fusion Potentials for G_k and Handle Squashing

    E-Print Network [OSTI]

    Michael Crescimanno

    1991-10-22T23:59:59.000Z

    Using Chern-Simons gauge theory, we show that the fusion ring of the conformal field theory G_k is isomorphic to P(u)/(\\del V), where V is a polynomial in u and (\\del V) is the ideal generated by the conditions \\del V=0. We also derive a residue-like formula for the correlation functions in the Chern-Simons theory thus providing a RCFT version of the residue formula for the TLG models. An operator that acts like the measure in the residue formula has the ionterpretation of a handle squashing operator and an explicit formula for this operator is given.

  16. Uranium hexafluoride: Safe handling, processing, and transporting: Conference proceedings

    SciTech Connect (OSTI)

    Strunk, W.D.; Thornton, S.G. (eds.)

    1988-01-01T23:59:59.000Z

    This conference seeks to provide a forum for the exchange of information and ideas of the safety aspects and technical issue related to the handling of uranium hexafluoride. By allowing operators, engineers, scientists, managers, educators, and others to meet and share experiences of mutual concern, the conference is also intended to provide the participants with a more complete knowledge of technical and operational issues. The topics for the papers in the proceedings are widely varied and include the results of chemical, metallurgical, mechanical, thermal, and analytical investigations, as well as the developed philosophies of operational, managerial, and regulatory guidelines. Papers have been entered individually into EDB and ERA. (LTN)

  17. CARRIER PREPARATION BUILDING MATERIALS HANDLING SYSTEM DESCRIPTION DOCUMENT

    SciTech Connect (OSTI)

    E.F. Loros

    2000-06-28T23:59:59.000Z

    The Carrier Preparation Building Materials Handling System receives rail and truck shipping casks from the Carrier/Cask Transport System, and inspects and prepares the shipping casks for return to the Carrier/Cask Transport System. Carrier preparation operations for carriers/casks received at the surface repository include performing a radiation survey of the carrier and cask, removing/retracting the personnel barrier, measuring the cask temperature, removing/retracting the impact limiters, removing the cask tie-downs (if any), and installing the cask trunnions (if any). The shipping operations for carriers/casks leaving the surface repository include removing the cask trunnions (if any), installing the cask tie-downs (if any), installing the impact limiters, performing a radiation survey of the cask, and installing the personnel barrier. There are four parallel carrier/cask preparation lines installed in the Carrier Preparation Building with two preparation bays in each line, each of which can accommodate carrier/cask shipping and receiving. The lines are operated concurrently to handle the waste shipping throughputs and to allow system maintenance operations. One remotely operated overhead bridge crane and one remotely operated manipulator is provided for each pair of carrier/cask preparation lines servicing four preparation bays. Remotely operated support equipment includes a manipulator and tooling and fixtures for removing and installing personnel barriers, impact limiters, cask trunnions, and cask tie-downs. Remote handling equipment is designed to facilitate maintenance, dose reduction, and replacement of interchangeable components where appropriate. Semi-automatic, manual, and backup control methods support normal, abnormal, and recovery operations. Laydown areas and equipment are included as required for transportation system components (e.g., personnel barriers and impact limiters), fixtures, and tooling to support abnormal and recovery operations. The Carrier Preparation Building Materials Handling System interfaces with the Cask/Carrier Transport System to move the carriers to and from the system. The Carrier Preparation Building System houses the equipment and provides the facility, utility, safety, communications, and auxiliary systems supporting operations and protecting personnel.

  18. Plutonium stabilization and handling quality assurance program plan

    SciTech Connect (OSTI)

    Weiss, E.V.

    1998-04-22T23:59:59.000Z

    This Quality Assurance Program Plan (QAPP) identifies project quality assurance requirements for all contractors involved in the planning and execution of Hanford Site activities for design, procurement, construction, testing and inspection for Project W-460, Plutonium Stabilization and Handling. The project encompasses procurement and installation of a Stabilization and Packaging System (SPS) to oxidize and package for long term storage remaining plutonium-bearing special nuclear materials currently in inventory at the Plutonium Finishing Plant (PFP), and modification of vault equipment to allow storage of resulting packages of stabilized SNM.

  19. Methods and Cost of Handling Texas Citrus, 1946-51.

    E-Print Network [OSTI]

    Sorensen, H. B.; Baker, C. K.

    1953-01-01T23:59:59.000Z

    Methods and Costs of Handling Texas Citrus TEXAS AGRICULTURAL EXPERIMENT STAT10 R. D. LEWIS. DIRECTOR, COLLEGE STATION. TEXAS DIGEST The citrus industry in Texas underwent considerable change during the 1946-51 period. 7 of production dropped... changes during this period although trends in the use of containers for fresh citrus showed the rise in popularity of consumer-size mesh bags. The increase in proportion of these bags was from 2 percent of the total to 13 percent for grapefruit and from...

  20. Fluid-mixing studies in a hexagonal 217-pin wire-wrapped rod bundle. [LMFBR

    SciTech Connect (OSTI)

    Symolon, P.D.; Todreas, N.E.

    1981-02-01T23:59:59.000Z

    Mixing, pressure drop, and flow split experiments were performed on a 217 pin LMFBR fuel bundle with a pitch to diameter ratio of 1.25 and a lead length of 12 inches. It was found that the turbulent flow data could best be characterized by the energy parameter C/sub 1L/=.106, which is 9% higher than the value from the correlation of Chiu et al. Chiu's correlation was developed on a data base of 61 and 91 pins. The spread of existing data about the correlation is +- 25%, but the error band on our data is expected to be less (approx. +- 10% since injection depth effects were not previously considered). This result is consistent with the concept of increased swirl flow in larger bundles (more pins).

  1. Two-dimensional modeling of sodium boiling transients in simulated LMFBR fuel bundles

    SciTech Connect (OSTI)

    Rose, S.D.; Dearing, J.F; Carbajo, J.J.; Levin, A.E.; Montgomery, B.H.; Wantland, J.L.

    1982-01-01T23:59:59.000Z

    A two-dimensional code for analysis of sodium boiling in LMFBR fuel assemblies has been developed at ORNL. This code, THORAX, has been used to analyze tests in 19- and 61-pin electrically-heated, simulated LMFBR fuel assemblies in the THORS facility. THORAX has simulated well the transient growth of the two-dimensional boiling region and the resulting static flow instability leading to dryout. Extrapolation of results to a full size fuel pin bundle shows that two-dimensional effects are reduced but still significant. The code will be extended to include a loop model in support of forthcoming tests in the THORS-SHRS Assembly 1 loop, which will include two parallel 19-pin simulated driver bundles.

  2. Numerical study on the turbulence structures in closely spaced rod bundle subchannels

    SciTech Connect (OSTI)

    Wu, X. (Univ. of Manitoba, Winnipeg (Canada). Dept. of Mechanical Engineering)

    1994-06-01T23:59:59.000Z

    Fully developed turbulent flow through simulated rod bundle subchannels formed by a rod-trapezoidal duct was numerically studied. With a simple coordinate system transformation from an orthogonal cylindrical system to a nonorthogonal curvilinear system, the highly irregular flow passage of a rod-trapezoidal duct was converted to that of a regular rectangle. An empirical anisotropic eddy viscosity distribution based on existing experimental data was used in conjunction with the algebraic stress model to address the influence of coherent large-scale cross-gap eddy motion, whose existence in closely spaced rod bundle subchannels has bene substantiated by extensive hot-wire measurements. Results of the calculation are compared with experimental data, with emphasis on secondary flow and turbulence kinetic energy. The credibility of this numerical scheme was establishment through a series of numerical tests on simple geometry flows.

  3. FOLIATIONS WITH TRIVIAL CANONICAL BUNDLE ON FANO FRANK LORAY1, JORGE VITORIO PEREIRA2 AND FREDERIC TOUZET1

    E-Print Network [OSTI]

    Pereira, Jorge Vitório

    FOLIATIONS WITH TRIVIAL CANONICAL BUNDLE ON FANO 3-FOLDS FRANK LORAY1, JORGE VIT´ORIO PEREIRA2 Poisson structure. 1 #12;2 F. LORAY, J.V. PEREIRA AND F. TOUZET classification of foliations of degree two

  4. Spray evaporation heat transfer performance in R-123 in tube bundles

    SciTech Connect (OSTI)

    Moeykens, S. [Trane Co., LaCrosse, WI (United States); Kelly, J.E. [Kansas State Univ., Manhattan, KS (United States). Dept. of Mechanical Engineering; Pate, M.B. [Iowa State Univ., Ames, IA (United States). Mechanical Engineering Dept.

    1996-12-31T23:59:59.000Z

    This study focuses on evaluating the heat transfer performance of refrigerant R-123 in the spray evaporation environment for pure refrigerant and for the case of lubricant addition. Tests were conducted with triangular-pitch tube bundles made from enhanced boiling tubes, enhanced condensation tubes, and plain-surface tubes. A second enhanced boiling surface tube bundle, made with a square-pitch tube alignment, was also tested so a comparison could be made between the square- and triangular-pitch geometries. In addition to pure refrigerant work, experiments were performed with small concentrations of a 305 SUS naphthenic mineral oil to evaluate its effect on falling-film heat transfer performance. Two different refrigerant supply rates were used in this work so the effects of film-feed supply rate could be interpreted from the data. Refrigerant was introduced to the test section via low-pressure-drop, wide-angle nozzles located directly over the tube bundle. Data were taken over a heat flux range of 40 kW/m{sup 2} (12,688 Btu/[h{center_dot}ft{sup 2}]) to 19 kW/m{sup 2} (6,027 Btu/[h{center_dot}ft{sup 2}]), while the refrigerant supply rate remained fixed. Collector tests were performed in parallel with the heat transfer experiments so the amount of refrigerant bypassing the tube bundle could be determined. It was found that the heat transfer coefficients were dependent upon film-feed supply rate, oil concentration, and heat flux. The enhanced boiling surface yielded higher heat transfer coefficients than either the enhanced condensation surface or the plain surface.

  5. Evaluation of the magnitude and effects of bundle duct interaction in fuel assemblies at developmental plant conditions

    SciTech Connect (OSTI)

    Serell, D.C.; Kaplan, S.

    1980-09-01T23:59:59.000Z

    Purpose of this evaluation is to estimate the magnitude and effects of irradiation and creep induced fuel bundle deformations in the developmental plant. This report focuses on the trends of the results and the ability of present models to evaluate the assembly temperatures in the presence of bundle deformation. Although this analysis focuses on the developmental plant, the conclusions are applicable to LMFBR fuel assemblies in general if they have wire spacers.

  6. Molecular Dynamic Simulation of Sodium in 7-Pin LMFBR Bundle Under Hypothetical Accident Conditions

    SciTech Connect (OSTI)

    Bottoni, Maurizio [University of Ferrara, Physics Department, Via Paradiso 12, I-44100 Ferrara (Italy); Bottoni, Claudio; Scanu, John [University of Pisa, Lungarno Pacinotti, 43 - 56126 Pisa (Italy)

    2006-07-01T23:59:59.000Z

    In the frame of safety analysis of liquid metal fast breeder reactors (LMFBRs) under hypothetical Unprotected Loss of Flow (ULOF) conditions two-phase flow of sodium is simulated in a 7-pin bundle, with hexagonal lattice. Molecular dynamics, with the application of the Direct Simulation Monte Carlo (DSMC) method, and a macroscopic model describing rewetting sequences due to the flow of a sodium liquid film along the pin surfaces, are applied to simulate the coolant in the bundle. The pin surfaces and the inner surface of the hexagonal canning are treated in the Monte Carlo simulation as diffusively reflecting surfaces. Collisions of sodium molecules are computed with the 'hard-sphere' model. With respect to previous work the following improvements of the computational code were made: i) The full bundle is simulated, thus allowing for asymmetries, like a skewed power distribution, to be accounted for; ii) A pin model calculates detailed temperature distributions in the pins, so that temperature boundary conditions are computed and not imposed; iii) Post processing visualisation of computed results was developed. An out of pile sodium boiling experiment run at the Nuclear Research Center of Karlsruhe, Germany, is simulated and conclusions are drawn about the applicability of the methodology in computer codes dedicated to breeder reactors safety analysis. (authors)

  7. Process development for remote-handled mixed-waste treatment

    SciTech Connect (OSTI)

    Berry, J.B.; Campbell, D.O.; Lee, D.D.; White, T.L.

    1990-01-01T23:59:59.000Z

    The Oak Ridge National Laboratory (ORNL) is developing a treatment process for remote-handled (RH) liquid transuranic mixed waste governed by the concept of minimizing the volume of waste requiring disposal. This task is to be accomplished by decontaminating the bulk components so the process effluent can be disposed with less risk and expense. Practical processes have been demonstrated on the laboratory scale for removing cesium 137 and strontium 90 isotopes from the waste, generating a concentrated waste volume, and rendering the bulk of the waste nearly radiation free for downstream processing. The process is projected to give decontamination factors of 10{sup 4} for cesium and 10{sup 3} for strontium. Because of the extent of decontamination, downstream processing will be contact handled. The transuranic, radioactive fraction of the mixed waste stream will be solidified using a thin-film evaporator and/or microwave solidification system. Resultant solidified waste will be disposed at the Waste Isolation Pilot Plant (WIPP). 8 refs., 2 figs., 3 tabs.

  8. Safer Transportation and Disposal of Remote Handled Transuranic Waste - 12033

    SciTech Connect (OSTI)

    Rojas, Vicente; Timm, Christopher M.; Fox, Jerry V. [PECOS Management Services, Inc., Albuquerque, NM (United States)

    2012-07-01T23:59:59.000Z

    Since disposal of remote handled (RH) transuranic (TRU) waste at the Waste Isolation Pilot Plant (WIPP) began in 2007, the Department of Energy (DOE) has had difficulty meeting the plans and schedule for disposing this waste. PECOS Management Services, Inc. (PECOS) assessed the feasibility of proposed alternate RH-TRU mixed waste containerisation concepts that would enhance the transportation rate of RH-TRU waste to WIPP and increase the utilization of available WIPP space capacity for RH-TRU waste disposal by either replacing or augmenting current and proposed disposal methods. In addition engineering and operational analyses were conducted that addressed concerns regarding criticality, heat release, and worker exposure to radiation. The results of the analyses showed that the concept, development, and use of a concrete pipe based design for an RH-TRU waste shipping and disposal container could be potentially advantageous for disposing a substantial quantity of RHTRU waste at WIPP in the same manner as contact-handled RH waste. Additionally, this new disposal method would eliminate the hazard associated with repackaging this waste in other containers without the requirement for NRC approval for a new shipping container. (authors)

  9. Resolutions of C^n/Z_n Orbifolds, their U(1) Bundles, and Applications to String Model Building

    E-Print Network [OSTI]

    S. Groot Nibbelink; M. Trapletti; M. G. A. Walter

    2007-03-06T23:59:59.000Z

    We describe blowups of C^n/Z_n orbifolds as complex line bundles over CP^{n-1}. We construct some gauge bundles on these resolutions. Apart from the standard embedding, we describe U(1) bundles and an SU(n-1) bundle. Both blowups and their gauge bundles are given explicitly. We investigate ten dimensional SO(32) super Yang-Mills theory coupled to supergravity on these backgrounds. The integrated Bianchi identity implies that there are only a finite number of U(1) bundle models. We describe how the orbifold gauge shift vector can be read off from the gauge background. In this way we can assert that in the blow down limit these models correspond to heterotic C^2/Z_2 and C^3/Z_3 orbifold models. (Only the Z_3 model with unbroken gauge group SO(32) cannot be reconstructed in blowup without torsion.) This is confirmed by computing the charged chiral spectra on the resolutions. The construction of these blowup models implies that the mismatch between type-I and heterotic models on T^6/Z_3 does not signal a complication of S-duality, but rather a problem of type-I model building itself: The standard type-I orbifold model building only allows for a single model on this orbifold, while the blowup models give five different models in blow down.

  10. DESIGN OF WIRE-WRAPPED ROD BUNDLE MATCHED INDEX-OF-REFRACTION EXPERIMENTS

    SciTech Connect (OSTI)

    Hugh McIlroy; Hongbin Zhang; Kurt Hamman

    2008-05-01T23:59:59.000Z

    Experiments will be conducted in the Idaho National Laboratory (INL) Matched Index-of-Refraction (MIR) Flow Facility [1] to characterize the three-dimensional velocity and turbulence fields in a wire-wrapped rod bundle typically employed in liquid-metal cooled fast reactors and to provide benchmark data for computer code validation. Sodium cooled fast reactors are under consideration for use in the U.S. Department of Energy (DOE) Global Nuclear Energy Partnership (GNEP) program. The experiment model will be constructed of quartz components and the working fluid will be mineral oil. Accurate temperature control (to within 0.05 oC) matches the index-of-refraction of mineral oil with that of quartz and renders the model transparent to the wavelength of laser light employed for optical measurements. The model will be a scaled 7-pin rod bundle enclosed in a hexagonal canister. Flow field measurements will be obtained with a LaVision 3-D particle image velocimeter (PIV) and complimented by near-wall velocity measurements obtained from a 2-D laser Doppler velocimeter (LDV). These measurements will be used as benchmark data for computational fluid dynamics (CFD) validation. The rod bundle model dimensions will be scaled up from the typical dimensions of a fast reactor fuel assembly to provide the maximum Reynolds number achievable in the MIR flow loop. A range of flows from laminar to fully-turbulent will be available with a maximum Reynolds number, based on bundle hydraulic diameter, of approximately 22,000. The fuel pins will be simulated by 85 mm diameter quartz tubes (closed on the inlet ends) and the wire-wrap will be simulated by 25 mm diameter quartz rods. The canister walls will be constructed from quartz plates. The model will be approximately 2.13 m in length. Bundle pressure losses will also be measured and the data recorded for code comparisons. The experiment design and preliminary CFD calculations, which will be used to provide qualitative hydrodynamic information, are presented in this paper.

  11. A Regulator's View of Cogeneration

    E-Print Network [OSTI]

    Shanaman, S. M.

    1982-01-01T23:59:59.000Z

    of the total national electric generation. In view of the energy requirements of Pennsylvania's industry and the impact of increasing energy costs on employment the Commission directed its technical staff to investigate the potential for industrial cogeneration...

  12. Test reports for K Basins vertical fuel handling tools

    SciTech Connect (OSTI)

    Meling, T.A.

    1995-02-01T23:59:59.000Z

    The vertical fuel handling tools, for moving N Reactor fuel elements, were tested in the 305 Building Cold Test Facility (CTF) in the 300 Area. After fabrication was complete, the tools were functionally tested in the CTF using simulated N Reactor fuel rods (inner and outer elements). The tools were successful in picking up the simulated N Reactor fuel rods. These tools were also load tested using a 62 pound dummy to test the structural integrity of each assembly. The tools passed each of these tests, based on the performance objectives. Finally, the tools were subjected to an operations acceptance test where K Basins Operations personnel operated the tool to determine its durability and usefulness. Operations personnel were satisfied with the tools. Identified open items included the absence of a float during testing, and documentation required prior to actual use of the tools in the 100 K fuel storage basin.

  13. The combustion and handling properties of several heavy bitumen emulsions

    SciTech Connect (OSTI)

    Whaley, H.; Wong, J.K.L.; Banks, G.N.; Lee, S.W.

    1995-12-31T23:59:59.000Z

    A research program was undertaken by ACT/CANMET to compare the combustion and heat transfer characteristics of a number of bitumen-based water emulsions with those of heavy fuel oil. The addition of water gives some advantage in the areas of fuel handling, atomization and emissions. These studies showed that the emulsions burn and transfer heat in a manner similar to commercial heavy fuel oils and make excellent fuels for boiler and process combustors. However, if the heavy bitumen is partially upgraded, the emulsion made from these residues can sometimes give rise to combustion and emissions related concerns. Particular attention must be paid to the burner/atomization system in order to avoid combustion problems resulting in unacceptably high levels of soot deposition and emissions.

  14. Automated cassette-to-cassette substrate handling system

    DOE Patents [OSTI]

    Kraus, Joseph Arthur; Boyer, Jeremy James; Mack, Joseph; DeChellis, Michael; Koo, Michael

    2014-03-18T23:59:59.000Z

    An automated cassette-to-cassette substrate handling system includes a cassette storage module for storing a plurality of substrates in cassettes before and after processing. A substrate carrier storage module stores a plurality of substrate carriers. A substrate carrier loading/unloading module loads substrates from the cassette storage module onto the plurality of substrate carriers and unloads substrates from the plurality of substrate carriers to the cassette storage module. A transport mechanism transports the plurality of substrates between the cassette storage module and the plurality of substrate carriers and transports the plurality of substrate carriers between the substrate carrier loading/unloading module and a processing chamber. A vision system recognizes recesses in the plurality of substrate carriers corresponding to empty substrate positions in the substrate carrier. A processor receives data from the vision system and instructs the transport mechanism to transport substrates to positions on the substrate carrier in response to the received data.

  15. Viewing device for electron-beam equipment

    SciTech Connect (OSTI)

    Nasyrov, R.S.

    1985-06-01T23:59:59.000Z

    Viewing devices are used to observe melting, welding, and so on in vacuum systems, an it is necessary to protect the windows from droplets and vapor. A viewing device for electron-beam equipment is described in which the viewing tube and mounting flange are made as a tubular ball joint enclosed in a steel bellows, which render the viewing device flexible. Bending the viewing tube in the intervals between observations protects the viewing window from sputtering and from drops of molten metal.

  16. U-226: Linux Kernel SFC Driver TCP MSS Option Handling Denial...

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

    The vulnerability is caused due to an error in the Solarflare network driver (driversnetethernetsfctx.c) when handling TCP segments and can be exploited via a...

  17. Remote-Handled Low-Level Waste (RHLLW) Disposal Project Code of Record

    SciTech Connect (OSTI)

    S.L. Austad, P.E.; L.E. Guillen, P.E.; C. W. McKnight, P.E.; D. S. Ferguson, P.E.

    2010-10-01T23:59:59.000Z

    The Remote-Handled Low-Level Waste Disposal Project addresses an anticipated shortfall in remote-handled LLW disposal capability following cessation of operations at the existing facility, which will continue until it is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of fiscal year 2015). Development of a new onsite disposal facility, the highest ranked alternative, will provide necessary remote handled LLW disposal capability and will ensure continuity of operations that generate remote-handled LLW. This report documents the Code of Record for design of a new LLW disposal capability.

  18. Wide field of view telescope

    DOE Patents [OSTI]

    Ackermann, Mark R. (Albuquerque, NM); McGraw, John T. (Placitas, NM); Zimmer, Peter C. (Albuquerque, NM)

    2008-01-15T23:59:59.000Z

    A wide field of view telescope having two concave and two convex reflective surfaces, each with an aspheric surface contour, has a flat focal plane array. Each of the primary, secondary, tertiary, and quaternary reflective surfaces are rotationally symmetric about the optical axis. The combination of the reflective surfaces results in a wide field of view in the range of approximately 3.8.degree. to approximately 6.5.degree.. The length of the telescope along the optical axis is approximately equal to or less than the diameter of the largest of the reflective surfaces.

  19. Urenco`s experience of UF{sub 6} handling

    SciTech Connect (OSTI)

    Saelmans, F. [Urenco Almelo (Netherlands); Scane, C. [Urenco Capenhurst (United Kingdom); Christofzik, J. [Urenco Gronau (Germany)

    1991-12-31T23:59:59.000Z

    Urenco operates enrichment plants at three sites, Almelo (Netherlands), Capenhurst (United Kingdom) and Gronau (Germany). Current installed separative work capacity is 2,500 tSWpa. Since 1971, when the first pilot plants were built, enrichment production has totalled 18,000 tSW. During this last 20 years over 3,500 48 containers of UF{sub 6} have been fed to the plants, over 3,700 30 containers have been filled with product and delivered successfully to Urenco`s customers worldwide and over 3,000 48 containers of depleted tails have been filled and have either been returned to customers or retained for long term storage on site. The paper gives a brief outline of Urenco`s experience in handling UF{sub 6}: the equipment and methods used in receiving, feeding, filling, blending, liquid sampling, storing, moving on site and despatching of UF{sub 6} containers. Some of the difficulties experienced with UF{sub 6} containers are appended.

  20. B cell remote-handled waste shipment cask alternatives study

    SciTech Connect (OSTI)

    RIDDELLE, J.G.

    1999-05-26T23:59:59.000Z

    The decommissioning of the 324 Facility B Cell includes the onsite transport of grouted remote-handled radioactive waste from the 324 Facility to the 200 Areas for disposal. The grouted waste has been transported in the leased ATG Nuclear Services 3-82B Radioactive Waste Shipping Cask (3-82B cask). Because the 3-82B cask is a U.S. Nuclear Regulatory Commission (NRC)-certified Type B shipping cask, the lease cost is high, and the cask operations in the onsite environment may not be optimal. An alternatives study has been performed to develop cost and schedule information on alternative waste transportation systems to assist in determining which system should be used in the future. Five alternatives were identified for evaluation. These included continued lease of the 3-82B cask, fabrication of a new 3-82B cask, development and fabrication of an onsite cask, modification of the existing U.S. Department of Energy-owned cask (OH-142), and the lease of a different commercially available cask. Each alternative was compared to acceptance criteria for use in the B Cell as an initial screening. Only continued leasing of the 3-82B cask, fabrication of a new 3-82B cask, and the development and fabrication of an onsite cask were found to meet all of the B Cell acceptance criteria.

  1. Removable pellicle for lithographic mask protection and handling

    DOE Patents [OSTI]

    Klebanoff, Leonard E. (Dublin, CA); Rader, Daniel J. (Albuquerque, NM); Hector, Scott D. (Oakland, CA); Nguyen, Khanh B. (Sunnyvale, CA); Stulen, Richard H. (Livermore, CA)

    2002-01-01T23:59:59.000Z

    A removable pellicle for a lithographic mask that provides active and robust particle protection, and which utilizes a traditional pellicle and two deployments of thermophoretic protection to keep particles off the mask. The removable pellicle is removably attached via a retaining structure to the mask substrate by magnetic attraction with either contacting or non-contacting magnetic capture mechanisms. The pellicle retaining structural is composed of an anchor piece secured to the mask substrate and a frame member containing a pellicle. The anchor piece and the frame member are in removable contact or non-contact by the magnetic capture or latching mechanism. In one embodiment, the frame member is retained in a floating (non-contact) relation to the anchor piece by magnetic levitation. The frame member and the anchor piece are provided with thermophoretic fins which are interdigitated to prevent particles from reaching the patterned area of the mask. Also, the anchor piece and mask are maintained at a higher temperature than the frame member and pellicle which also prevents particles from reaching the patterned mask area by thermophoresis. The pellicle can be positioned over the mask to provide particle protection during mask handling, inspection, and pumpdown, but which can be removed manually or robotically for lithographic use of the mask.

  2. Limited View Angle Iterative CT Reconstruction

    E-Print Network [OSTI]

    ;Some Prior Literature in Limited View Tomography CT with limited-angle data and few views IRR algorithm Iterative Reconstruction-Reprojection (IRR) : An Algorithm for Limited Data Cardiac- Computed-views and limited-angle data in divergent-beam CT by E. Y. Sidky, CM Kao, and X. Pan (2006) Few-View Projection

  3. Project Execution Plan for the Remote Handled Low-Level Waste Disposal Project

    SciTech Connect (OSTI)

    Danny Anderson

    2014-07-01T23:59:59.000Z

    As part of ongoing cleanup activities at the Idaho National Laboratory (INL), closure of the Radioactive Waste Management Complex (RWMC) is proceeding under the Comprehensive Environmental Response, Compensation, and Liability Act (42 USC 9601 et seq. 1980). INL-generated radioactive waste has been disposed of at RWMC since 1952. The Subsurface Disposal Area (SDA) at RWMC accepted the bulk of INL’s contact and remote-handled low-level waste (LLW) for disposal. Disposal of contact-handled LLW and remote-handled LLW ion-exchange resins from the Advanced Test Reactor in the open pit of the SDA ceased September 30, 2008. Disposal of remote-handled LLW in concrete disposal vaults at RWMC will continue until the facility is full or until it must be closed in preparation for final remediation of the SDA (approximately at the end of fiscal year FY 2017). The continuing nuclear mission of INL, associated ongoing and planned operations, and Naval spent fuel activities at the Naval Reactors Facility (NRF) require continued capability to appropriately dispose of contact and remote handled LLW. A programmatic analysis of disposal alternatives for contact and remote-handled LLW generated at INL was conducted by the INL contractor in Fiscal Year 2006; subsequent evaluations were completed in Fiscal Year 2007. The result of these analyses was a recommendation to the Department of Energy (DOE) that all contact-handled LLW generated after September 30, 2008, be disposed offsite, and that DOE proceed with a capital project to establish replacement remote-handled LLW disposal capability. An analysis of the alternatives for providing replacement remote-handled LLW disposal capability has been performed to support Critical Decision-1. The highest ranked alternative to provide this required capability has been determined to be the development of a new onsite remote-handled LLW disposal facility to replace the existing remote-handled LLW disposal vaults at the SDA. Several offsite DOE and commercial disposal options exist for contact-handled LLW; however, offsite disposal options are either not currently available (i.e., commercial disposal facilities), practical, or cost-effective for all remote-handled LLW streams generated at INL. Offsite disposal of all INL and tenant-generated remote-handled waste is further complicated by issues associated with transporting highly radioactive waste in commerce; and infrastructure and processing changes at the generating facilities, specifically NRF, that would be required to support offsite disposal. The INL Remote-Handled LLW Disposal Project will develop a new remote handled LLW disposal facility to meet mission-critical, remote-handled LLW disposal needs. A formal DOE decision to proceed with the project has been made in accordance with the requirements of National Environmental Policy Act (42 USC§ 4321 et seq.). Remote-handled LLW is generated from nuclear programs conducted at INL, including spent nuclear fuel handling and operations at NRF and operations at the Advanced Test Reactor. Remote-handled LLW also will be generated by new INL programs and from segregation and treatment (as necessary) of remote handled scrap and waste currently stored in the Radioactive Scrap and Waste Facility at the Materials and Fuels Complex.

  4. View

    E-Print Network [OSTI]

    2010-08-12T23:59:59.000Z

    all real solutions of a given system of polynomial equations. ... A crucial ingredient is a semidefinite characterization of the real radical ideal ...... The options.

  5. View

    E-Print Network [OSTI]

    2003-07-16T23:59:59.000Z

    flow equation is discretized in space using a control volume finite-element technique .... The control volume finite-element method is selected .... parallel plates.

  6. View

    E-Print Network [OSTI]

    2013-10-14T23:59:59.000Z

    based on median finding, variable fixing, and secant techniques. Keywords: ..... arithmetic operations, the overall complexity is O(n2). D. The worst case bound in ..... always work on its rated clock speed, we turned force the Linux system to use the ..... dimensionally equidistributed uniform pseudo-random number generator.

  7. View

    E-Print Network [OSTI]

    2011-01-28T23:59:59.000Z

    obtained by using different uncertainty sets estimated using simulated and ... Given a fixed mix of electric power plants (nuclear, thermal, hydroelectric, and ...

  8. View

    E-Print Network [OSTI]

    2010-03-14T23:59:59.000Z

    Aug 19, 2009 ... linear-algebraic and graph theoretic properties of this matrix class. The con- ..... The MatLab solvers linprog and quadprog were used.

  9. View

    E-Print Network [OSTI]

    1910-31-00T23:59:59.000Z

    Sep 3, 2003 ... Landau (TDGL) equation, the Maxwell equations, and an energy equation ... varying currents and magnetic fields generate thermal energy, ...

  10. View

    E-Print Network [OSTI]

    2004-12-25T23:59:59.000Z

    Let fbe a meromorphic function satisfying condition (1.2), and let rj be a sequence with property (2.5). Then the set S is finite and for some subsequence of ...

  11. View

    E-Print Network [OSTI]

    2010-07-30T23:59:59.000Z

    project of the classification of (simple) nuclear separable C*-algebras [E]. Let C? denote the category of separable C*-algebras and ?-homomorphisms.

  12. View

    E-Print Network [OSTI]

    2006-07-11T23:59:59.000Z

    the classification results of Kirchberg and Phillips using the notion of nuclear absorbing ... A simple purely infinite nuclear separable C*-algebra is called.

  13. View

    E-Print Network [OSTI]

    2008-07-07T23:59:59.000Z

    a battery of benchmark instances of up to 200 nodes are reported. These seem to be the largest instances that have been solved exactly for this problem.

  14. View

    E-Print Network [OSTI]

    2009-05-07T23:59:59.000Z

    author would also like to acknowledge the Center for High Performance Computing at VCU for providing computational infrastructure and support. 1 ...

  15. View

    E-Print Network [OSTI]

    2008-02-01T23:59:59.000Z

    the results of [8] to obtain, for each natural number n, a simple nuclear C?- algebra An whose ordered K0-group is order isomorphic to Zn. This result was further ...

  16. View

    E-Print Network [OSTI]

    2006-02-28T23:59:59.000Z

    Feb 28, 2006 ... Abstract. The major focus of this work is to compare several methods for computing the proximal point of a nonconvex function via numerical ...

  17. View

    E-Print Network [OSTI]

    andrea,,,

    In order to increase the search capability of MBH, a population framework has been proposed ... The key idea is to avoid new individuals to enter the population if someone similar (in a ..... We measure the efficiency in terms of number of (two-.

  18. View

    E-Print Network [OSTI]

    2005-05-30T23:59:59.000Z

    May 31, 2005 ... Robert M. Freund: MIT Sloan School of Management, 50 Memorial Drive, Cambridge, Massachusetts 02139-4307, ...... the transition kernel.

  19. View

    E-Print Network [OSTI]

    2005-05-12T23:59:59.000Z

    May 12, 2005 ... We propose in this paper to study the problem of estimating the cost-to- ... and have been proposed in the context of econometry in [Chen and White, 1998]. .... Rearranging terms, we see that the last relation can be written as.

  20. View

    E-Print Network [OSTI]

    2011-06-21T23:59:59.000Z

    May 14, 2010 ... Generally, even testing whether a matrix is in C? is co-NP-complete [23]. ...... One concrete example is the following: ?. ?. ?. ?. ?. ?. 1 1/3 1/3 ...

  1. A New Aerodynamic Traction Principle for Handling Products on an Air Cushion

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    1 A New Aerodynamic Traction Principle for Handling Products on an Air Cushion Guillaume J. Laurent. The product is carried on a thin air cushion and transported along the system by induced air flows principle for handling delicate and clean products, such as silicon wafers, glass sheets or flat foodstuff

  2. Extending a Deductive ObjectOriented Database System with Spatial Data Handling Facilities

    E-Print Network [OSTI]

    Fernandes, Alvaro A. A.

    Extending a Deductive Object­Oriented Database System with Spatial Data Handling Facilities Alvaro, 1998 Abstract This paper describes the integration of a spatial data handling component with the ROCK collection of spatial data types as primitive types whose operations have state­of­the­art computational

  3. Safety First Safety Last Safety Always Inspect rigging equipment for material handling before use

    E-Print Network [OSTI]

    Minnesota, University of

    Safety First Safety Last Safety Always Inspect rigging equipment for material handling before use. Rigging Equipment for Material Handling Safety Tip #19 At your job or at the plate, you can't get home on the reverse side of this safety tip sheet. Please refrain from reading the information verbatim

  4. Preliminary Hazard Analysis for the Remote-Handled Low-Level Waste Disposal Facility

    SciTech Connect (OSTI)

    Lisa Harvego; Mike Lehto

    2010-05-01T23:59:59.000Z

    The need for remote handled low level waste (LLW) disposal capability has been identified. A new onsite, remote-handled LLW disposal facility has been identified as the highest ranked alternative for providing continued, uninterrupted remote-handled LLW disposal capability for remote-handled LLW that is generated as part of the nuclear mission of the Idaho National Laboratory and from spent nuclear fuel processing activities at the Naval Reactors Facility. Historically, this type of waste has been disposed of at the Radioactive Waste Management Complex. Disposal of remote-handled LLW in concrete disposal vaults at the Radioactive Waste Management Complex will continue until the facility is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). This document supports the conceptual design for the proposed remote-handled LLW disposal facility by providing an initial nuclear facility hazard categorization and by identifying potential hazards for processes associated with onsite handling and disposal of remote-handled LLW.

  5. Preliminary Hazard Analysis for the Remote-Handled Low-Level Waste Disposal Project

    SciTech Connect (OSTI)

    Lisa Harvego; Mike Lehto

    2010-10-01T23:59:59.000Z

    The need for remote handled low level waste (LLW) disposal capability has been identified. A new onsite, remote-handled LLW disposal facility has been identified as the highest ranked alternative for providing continued, uninterrupted remote-handled LLW disposal capability for remote-handled LLW that is generated as part of the nuclear mission of the Idaho National Laboratory and from spent nuclear fuel processing activities at the Naval Reactors Facility. Historically, this type of waste has been disposed of at the Radioactive Waste Management Complex. Disposal of remote-handled LLW in concrete disposal vaults at the Radioactive Waste Management Complex will continue until the facility is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). This document supports the conceptual design for the proposed remote-handled LLW disposal facility by providing an initial nuclear facility hazard categorization and by identifying potential hazards for processes associated with onsite handling and disposal of remote-handled LLW.

  6. GUIDELINES FOR DESIGN AND SAFE HANDLING OF CURVED I-SHAPED STEEL GIRDERS

    E-Print Network [OSTI]

    Texas at Austin, University of

    0-5574-P1 GUIDELINES FOR DESIGN AND SAFE HANDLING OF CURVED I-SHAPED STEEL GIRDERS Authors: Jason FOR DESIGN AND SAFE HANDLING OF CURVED I-SHAPED STEEL GIRDERS PURPOSE: The purpose of this set of guidelines-sixth #12;2 (Eq. 6.10.2.2-2). However, TxDOT's Preferred Practices for Steel Bridge Design, Fabrication

  7. SPE SPE 160638 A Novel Approach to Handle Continuous Wettability Alteration during

    E-Print Network [OSTI]

    Hossain, M. Enamul

    SPE SPE 160638 A Novel Approach to Handle Continuous Wettability Alteration during Immiscible CO2 to investigate wettability alteration during CO2 flooding process. However, limited research on numerical and, a novel approach was developed to handle wettability alteration on continuous basis during immiscible CO2

  8. Preliminary Hazard Analysis for the Remote-Handled Low-Level Waste Disposal Facility

    SciTech Connect (OSTI)

    Lisa Harvego; Mike Lehto

    2010-02-01T23:59:59.000Z

    The need for remote handled low level waste (LLW) disposal capability has been identified. A new onsite, remote-handled LLW disposal facility has been identified as the highest ranked alternative for providing continued, uninterrupted remote-handled LLW disposal capability for remote-handled LLW that is generated as part of the nuclear mission of the Idaho National Laboratory and from spent nuclear fuel processing activities at the Naval Reactors Facility. Historically, this type of waste has been disposed of at the Radioactive Waste Management Complex. Disposal of remote-handled LLW in concrete disposal vaults at the Radioactive Waste Management Complex will continue until the facility is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). This document supports the conceptual design for the proposed remote-handled LLW disposal facility by providing an initial nuclear facility hazard categorization and by identifying potential hazards for processes associated with onsite handling and disposal of remote-handled LLW.

  9. From Modelica Models to Fault Diagnosis in Air Handling Units Raymond Sterling1

    E-Print Network [OSTI]

    Cengarle, María Victoria

    From Modelica Models to Fault Diagnosis in Air Handling Units Raymond Sterling1 , Peter Struss2 Handling Unit (AHU). This solution is derived from a general first-principle Modelica model and exploits 4 presents the modelica models and its calibration. In section 5 an example of the complete tool

  10. MODELING OF PLANE-WAVE INCIDENCE ON A TWISTED-WIRE PAIR BUNDLE FOR RF INGRESS ESTIMATION IN DIGITAL SUBSCRIBER LINE SYSTEMS

    E-Print Network [OSTI]

    is electromagnetic interference (EMI) caused by external radio sources that operate in the same frequency band) system consisting of a bundle of twisted-wire pairs (TWPs) in the presence of electromagnetic interference (EMI) is presented. The objective of such a model is to analyze the susceptibility of TWP bundles

  11. A correlation for local coefficients of heat transfer in boiling of R12 and R22 refrigerants on multirow bundles of smooth tubes

    SciTech Connect (OSTI)

    Rebrov, P.N.; Bukin, V.G.; Danilova, G.N.

    1989-07-01T23:59:59.000Z

    Experimental results on the boiling of R12 and R22 on bundles of 30 to 50 vertically stacked rows of smooth tubes are presented and correlated. Engineering equations for determining the coefficients of heat transfer in the pool boiling of freons on such multirow bundles are derived.

  12. Safe handling of potential peroxide forming compounds and their corresponding peroxide yielded derivatives.

    SciTech Connect (OSTI)

    Sears, Jeremiah Matthew; Boyle, Timothy J.; Dean, Christopher J.

    2013-06-01T23:59:59.000Z

    This report addresses recent developments concerning the identification and handling of potential peroxide forming (PPF) and peroxide yielded derivative (PYD) chemicals. PPF chemicals are described in terms of labeling, shelf lives, and safe handling requirements as required at SNL. The general peroxide chemistry concerning formation, prevention, and identification is cursorily presented to give some perspective to the generation of peroxides. The procedure for determining peroxide concentrations and the proper disposal methods established by the Hazardous Waste Handling Facility are also provided. Techniques such as neutralization and dilution are provided for the safe handling of any PYD chemicals to allow for safe handling. The appendices are a collection of all available SNL documentation pertaining to PPF/PYD chemicals to serve as a single reference.

  13. Qualitative human reliability analysis for spent fuel handling

    SciTech Connect (OSTI)

    Brewer, J. D. [Sandia National Laboratories, P.O. Box 5800, Albuquerque, NM 87185-0748 (United States); Amico, P. [Science Applications International Corporation (United States); Cooper, S. E. [United Stated Nuclear Regulatory Commission (United States)

    2006-07-01T23:59:59.000Z

    Human reliability analysis (HRA) methods have been developed primarily to provide information for use in probabilistic risk assessments (PRAs) that analyze nuclear power plant (NPP) operations. Given the original emphasis of these methods, it is understandable that many HRAs have not ventured far from NPP control room applications. Despite this historical focus on the control room, there has been growing interest and discussion regarding the application of HRA methods to other NPP activities such as spent fuel handling (SFH) or operations in different types of facilities. One recently developed HRA method, 'A Technique for Human Event Analysis' (ATHEANA) has been proposed as a promising candidate for diverse applications due to its particular approach for systematically uncovering the dynamic, contextual conditions influencing human performance. This paper describes one successful test of this proposition by presenting portions of a recently completed project in which a scoping study was performed to accomplish the following goals: (1) investigate what should be included in a qualitative HRA for spent fuel and cask handling operations; and (2) demonstrate that the ATHEANA HRA technique can be usefully applied to these operations. The preliminary, scoping qualitative HRA examined, in a generic manner, how human performance of SFH and dry cask storage operations (DCSOs) can plausibly lead to radiological consequences that impact the public and the environment. The study involved the performance of typical, qualitative HRA tasks such as collecting relevant information and the preliminary identification of human failure events or unsafe actions, relevant influences (e.g., performance shaping factors, other contextual factors), event scenario development and categorization of human failure event (HFE) scenario groupings. Information from relevant literature sources was augmented with subject matter expert interviews and analysis of an edited video of selected operations. Elements of NUREG-1792, Good Practices for Implementing Human Reliability Analyses (HRA) and NUREG-1624, Rev. 1, Technical Basis and Implementation Guidelines for A Technique for Human Event Analysis (ATHEANA) formed critical parts of the technical basis for the preliminary analysis. Mis-loading of spent fuel into a cask and dropping of a loaded cask were the two human failure event groupings of primary interest, although all human performance aspects of DCSOs were considered to some extent. Of important note is that HRA is typically performed in the context of a plant-specific PRA study. This analysis was performed without the benefit of the context provided by a larger PRA study, nor was it plant specific, and so it investigated only generic HRA issues relevant to SFH. However, the improved understanding of human performance issues provided by the study will likely enhance the ability to carry out a detailed qualitative HRA for a specific NPP at some point in the future. Furthermore, support was obtained regarding the potential for applying ATHEANA beyond NPP settings. This paper provides a description of the process followed during the analysis, a description of the HFE scenario groupings, discussion regarding general human performance vulnerabilities, and a detailed examination of one HFE scenario developed in the study. (authors)

  14. Views of the solar system

    SciTech Connect (OSTI)

    Hamilton, C.

    1995-02-01T23:59:59.000Z

    Views of the Solar System has been created as an educational tour of the solar system. It contains images and information about the Sun, planets, moons, asteroids and comets found within the solar system. The image processing for many of the images was done by the author. This tour uses hypertext to allow space travel by simply clicking on a desired planet. This causes information and images about the planet to appear on screen. While on a planet page, hyperlinks travel to pages about the moons and other relevant available resources. Unusual terms are linked to and defined in the Glossary page. Statistical information of the planets and satellites can be browsed through lists sorted by name, radius and distance. History of Space Exploration contains information about rocket history, early astronauts, space missions, spacecraft and detailed chronology tables of space exploration. The Table of Contents page has links to all of the various pages within Views Of the Solar System.

  15. Chisolm View | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Office of InspectorConcentrating SolarElectricEnergyCTBarreisVolcanic National Park |Chile:CooperationChisolm View Jump

  16. For current viewing resistor loads

    DOE Patents [OSTI]

    Lyons, Gregory R. (Tijeras, NM); Hass, Jay B. (Lee's Summit, MO)

    2011-04-19T23:59:59.000Z

    The invention comprises a terminal unit for a flat cable comprising a BNC-PCB connector having a pin for electrically contacting one or more conducting elements of a flat cable, and a current viewing resistor having an opening through which the pin extends and having a resistor face that abuts a connector face of the BNC-PCB connector, wherein the device is a terminal unit for the flat cable.

  17. A classification theorem on Fano bundles Roberto Mu~noz, Gianluca Occhetta, and Luis E. Sola Conde

    E-Print Network [OSTI]

    Occhetta, Gianluca

    A classification theorem on Fano bundles Roberto Mu~noz, Gianluca Occhetta, and Luis E. Sol´a Conde;2 ROBERTO MU~NOZ, GIANLUCA OCCHETTA, AND LUIS E. SOL´A CONDE (P2) Q3 = LG(1, 3) G(1, 3), (P3) P3 = G(1, 4)Q

  18. Non-Intrusive Experiemental Investigation of Multi-Scale Flow Behavior in Rod Bundle with Spacer-Grids

    E-Print Network [OSTI]

    Dominguez Ontiveros, Elvis Efren

    2011-08-08T23:59:59.000Z

    5 x 5 rod bundle with spacer-grids. Measurements were performed using two different grid designs. One typical of Boiling Water Reactors (BWR) with swirl type mixing vanes and the other typical of Pressurized Water Reactors (PWR) with split type...

  19. Conceptual Safety Design Report for the Remote Handled Low-Level Waste Disposal Facility

    SciTech Connect (OSTI)

    Boyd D. Christensen

    2010-02-01T23:59:59.000Z

    A new onsite, remote-handled LLW disposal facility has been identified as the highest ranked alternative for providing continued, uninterrupted remote-handled LLW disposal for remote-handled LLW from the Idaho National Laboratory and for spent nuclear fuel processing activities at the Naval Reactors Facility. Historically, this type of waste has been disposed of at the Radioactive Waste Management Complex. Disposal of remote-handled LLW in concrete disposal vaults at the Radioactive Waste Management Complex will continue until the facility is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). This conceptual safety design report supports the design of a proposed onsite remote-handled LLW disposal facility by providing an initial nuclear facility hazard categorization, by identifying potential hazards for processes associated with onsite handling and disposal of remote-handled LLW, by evaluating consequences of postulated accidents, and by discussing the need for safety features that will become part of the facility design.

  20. Conceptual Safety Design Report for the Remote Handled Low-Level Waste Disposal Facility

    SciTech Connect (OSTI)

    Boyd D. Christensen

    2010-05-01T23:59:59.000Z

    A new onsite, remote-handled LLW disposal facility has been identified as the highest ranked alternative for providing continued, uninterrupted remote-handled LLW disposal for remote-handled LLW from the Idaho National Laboratory and for spent nuclear fuel processing activities at the Naval Reactors Facility. Historically, this type of waste has been disposed of at the Radioactive Waste Management Complex. Disposal of remote-handled LLW in concrete disposal vaults at the Radioactive Waste Management Complex will continue until the facility is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). This conceptual safety design report supports the design of a proposed onsite remote-handled LLW disposal facility by providing an initial nuclear facility hazard categorization, by identifying potential hazards for processes associated with onsite handling and disposal of remote-handled LLW, by evaluating consequences of postulated accidents, and by discussing the need for safety features that will become part of the facility design.

  1. Preliminary Safety Design Report for Remote Handled Low-Level Waste Disposal Facility

    SciTech Connect (OSTI)

    Timothy Solack; Carol Mason

    2012-03-01T23:59:59.000Z

    A new onsite, remote-handled low-level waste disposal facility has been identified as the highest ranked alternative for providing continued, uninterrupted remote-handled low-level waste disposal for remote-handled low-level waste from the Idaho National Laboratory and for nuclear fuel processing activities at the Naval Reactors Facility. Historically, this type of waste has been disposed of at the Radioactive Waste Management Complex. Disposal of remote-handled low-level waste in concrete disposal vaults at the Radioactive Waste Management Complex will continue until the facility is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). This preliminary safety design report supports the design of a proposed onsite remote-handled low-level waste disposal facility by providing an initial nuclear facility hazard categorization, by discussing site characteristics that impact accident analysis, by providing the facility and process information necessary to support the hazard analysis, by identifying and evaluating potential hazards for processes associated with onsite handling and disposal of remote-handled low-level waste, and by discussing the need for safety features that will become part of the facility design.

  2. The geometry of the tangent bundle and the relativistic kinetic theory of gases

    E-Print Network [OSTI]

    Olivier Sarbach; Thomas Zannias

    2014-04-03T23:59:59.000Z

    This article discusses the relativistic kinetic theory for a simple collisionless gas from a geometric perspective. We start by reviewing the rich geometrical structure of the tangent bundle TM of a given spacetime manifold, including the splitting of the tangent spaces of TM into horizontal and vertical subspaces and the natural metric and symplectic structure it induces on TM. Based on these structures we introduce the Liouville vector field L and a suitable Hamiltonian function H on TM. The Liouville vector field turns out to be the Hamiltonian vector field associated to H. On the other hand, H also defines the mass shells as Lorentzian submanifolds of the tangent bundle. A simple collisionless gas is described by a distribution function on a particular mass shell, satisfying the Liouville equation. Together with the Liouville vector field the distribution function can be thought of as defining a fictitious incompressible fluid on the mass shells, with associated conserved current density. Flux integrals of this current density provide the averaged properties of the gas, while suitable fibre integrals of the distribution function define divergence-free tensor fields on the spacetime manifold such as the current density and stress-energy tensor. Finally, we discuss the relationship between symmetries of the spacetime manifold and symmetries of the distribution function. As a first application of our formalism we derive the most general spherically symmetric distribution function on any spherically symmetric spacetime and write the Einstein-Liouville equations as effective field equations on the two-dimensional radial manifold. As a second application we derive the most general collisionless distribution function on a Kerr black hole spacetime background.

  3. Power Handling of the Bulk Tungsten Divertor Row at JET: First Measurements and Comparison to the GTM Thermal Model

    E-Print Network [OSTI]

    Power Handling of the Bulk Tungsten Divertor Row at JET: First Measurements and Comparison to the GTM Thermal Model

  4. Development of an Outdoor Concentrating Photovoltaic Module Testbed, Module Handling and Testing Procedures, and Initial Energy Production Results

    SciTech Connect (OSTI)

    Muller, M.

    2009-09-01T23:59:59.000Z

    This report addresses the various aspects of setting up a CPV testbed and procedures for handling and testing CPV modules.

  5. ParaView at NERSC

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLas Conchas recoveryLaboratorySpeedingOptimizingToolsto control intensePageveterans4 - ParaView

  6. ARRA Material Handling Equipment Composite Data Products: Data Through Quarter 4 of 2013

    SciTech Connect (OSTI)

    Kurtz, J.; Sprik, S.; Peters, M.

    2014-06-01T23:59:59.000Z

    This report includes 47 composite data products (CDPs) produced for American Recovery and Reinvestment Act (ARRA) fuel cell material handling equipment, with data through the fourth quarter of 2013.

  7. Remote-Handled Low-Level Waste Disposal Project Code of Record

    SciTech Connect (OSTI)

    S.L. Austad, P.E.; L.E. Guillen, P.E.; C. W. McKnight, P.E.; D. S. Ferguson, P.E.

    2014-06-01T23:59:59.000Z

    The Remote-Handled Low-Level Waste (LLW) Disposal Project addresses an anticipated shortfall in remote-handled LLW disposal capability following cessation of operations at the existing facility, which will continue until it is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). Development of a new onsite disposal facility will provide necessary remote-handled LLW disposal capability and will ensure continuity of operations that generate remote-handled LLW. This report documents the Code of Record for design of a new LLW disposal capability. The report is owned by the Design Authority, who can authorize revisions and exceptions. This report will be retained for the lifetime of the facility.

  8. A MICROFLUIDIC MAGNETIC HYBRID ACTUATOR FOR ADVANCED HANDLING FUNCTIONS AT CELL RESOLUTION

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    A MICROFLUIDIC MAGNETIC HYBRID ACTUATOR FOR ADVANCED HANDLING FUNCTIONS-CNRS, Toulouse, FRANCE 2 Université de Toulouse, Toulouse, FRANCE *email : mfouet@laas.fr In microfluidics are usually integrated. Coils were thus integrated to microfluidic chips

  9. Remote-Handled Low-Level Waste Disposal Project Code of Record

    SciTech Connect (OSTI)

    S.L. Austad, P.E.; L.E. Guillen, P.E.; C. W. McKnight, P.E.; D. S. Ferguson, P.E.

    2011-04-01T23:59:59.000Z

    The Remote-Handled Low-Level Waste (LLW) Disposal Project addresses an anticipated shortfall in remote-handled LLW disposal capability following cessation of operations at the existing facility, which will continue until it is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). Development of a new onsite disposal facility, the highest ranked alternative, will provide necessary remote-handled LLW disposal capability and will ensure continuity of operations that generate remote-handled LLW. This report documents the Code of Record for design of a new LLW disposal capability. The report is owned by the Design Authority, who can authorize revisions and exceptions. This report will be retained for the lifetime of the facility.

  10. Remote-Handled Low-Level Waste Disposal Project Code of Record

    SciTech Connect (OSTI)

    S.L. Austad, P.E.; L.E. Guillen, P.E.; C. W. McKnight, P.E.; D. S. Ferguson, P.E.

    2011-01-01T23:59:59.000Z

    The Remote-Handled Low-Level Waste (LLW) Disposal Project addresses an anticipated shortfall in remote-handled LLW disposal capability following cessation of operations at the existing facility, which will continue until it is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). Development of a new onsite disposal facility, the highest ranked alternative, will provide necessary remote-handled LLW disposal capability and will ensure continuity of operations that generate remote-handled LLW. This report documents the Code of Record for design of a new LLW disposal capability. The report is owned by the Design Authority, who can authorize revisions and exceptions. This report will be retained for the lifetime of the facility.

  11. Using Product Specific Simulation Models in a Tool for Manual Commissioning of Air Handling Units

    E-Print Network [OSTI]

    Eriksson, J.

    2003-01-01T23:59:59.000Z

    This short paper describes an outline of a tool for manual commissioning of air handling units. The prototype tool is implemented EES professional version that can generate standalone programs. The idea is to use the benefit of simulation models...

  12. Construction and operation of replacement hazardous waste handling facility at Lawrence Berkeley Laboratory. Environmental Assessment

    SciTech Connect (OSTI)

    Not Available

    1992-09-01T23:59:59.000Z

    The US Department of Energy (DOE) has prepared an environmental assessment (EA), DOE/EA-0423, for the construction and operation of a replacement hazardous waste handling facility (HWHF) and decontamination of the existing HWHF at Lawrence Berkeley Laboratory (LBL), Berkeley, California. The proposed facility would replace several older buildings and cargo containers currently being used for waste handling activities and consolidate the LBL`s existing waste handling activities in one location. The nature of the waste handling activities and the waste volume and characteristics would not change as a result of construction of the new facility. Based on the analysis in the EA, DOE has determined that the proposed action would not constitute a major Federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act (NEPA) of 1969, 42 USC. 4321 et seq. Therefore, an environmental impact statement is not required.

  13. Webinar February 17: Material Handling Fuel Cells for Building Electric Peak Shaving Applications

    Broader source: Energy.gov [DOE]

    The Fuel Cell Technologies Office will present a live webinar entitled "Material Handling Fuel Cells for Building Electric Peak Shaving Applications" on Tuesday, February 17, from 12 to 1 p.m. Eastern Standard Time.

  14. ARRA Material Handling Equipment Composite Data Products: Data through Quarter 2 of 2012

    SciTech Connect (OSTI)

    Kurtz, J.; Sprik, S.; Ramsden, T.; Ainscough, C.; Saur, G.

    2012-10-01T23:59:59.000Z

    This presentation from the U.S. Department of Energy's National Renewable Energy Laboratory includes American Recovery and Reinvestment Act (ARRA) fuel cell material handling equipment composite data products for data through the second quarter of 2012.

  15. Criticality Safety Evaluation Report for the Cold Vacuum Drying (CVD) Facilities Process Water Handling System

    SciTech Connect (OSTI)

    KESSLER, S.F.

    2000-08-10T23:59:59.000Z

    This report addresses the criticality concerns associated with process water handling in the Cold Vacuum Drying Facility. The controls and limitations on equipment design and operations to control potential criticality occurrences are identified.

  16. ARRA Material Handling Equipment Composite Data Products: Data Through Quarter 4 of 2012

    SciTech Connect (OSTI)

    Kurtz, J.; Sprik, S.; Ainscough, C.; Saur, G.; Post, M.; Peters, M.; Ramsden, T.

    2013-05-01T23:59:59.000Z

    This presentation from the U.S. Department of Energy's National Renewable Energy Laboratory includes American Recovery and Reinvestment Act (ARRA) fuel cell material handling equipment composite data products for data through the fourth quarter of 2012.

  17. ARRA Material Handling Equipment Composite Data Products: Data through Quarter 2 of 2013

    SciTech Connect (OSTI)

    Kurtz, J.; Sprik, S.; Ainscough, C.; Saur, G.; Post, M.; Peters, M.

    2013-11-01T23:59:59.000Z

    This report includes 47 composite data products (CDPs) produced for American Recovery and Reinvestment Act (ARRA) fuel cell material handling equipment, with data through the second quarter of 2013.

  18. Handling Coordination in a Tree Adjoining Anoop Sarkar and Aravind Joshi

    E-Print Network [OSTI]

    Sarkar, Anoop

    Handling Coordination in a Tree Adjoining Grammar Anoop Sarkar and Aravind Joshi Department,joshig@linc.cis.upenn.edu Draft of August 19, 1997 Longer version of (Sarkar and Joshi, 1996) Abstract In this paper we show

  19. Remote-Handled Low-Level Waste Disposal Project Code of Record

    SciTech Connect (OSTI)

    S.L. Austad, P.E.; L.E. Guillen, P.E.; C. W. McKnight, P.E.; D. S. Ferguson, P.E.

    2012-04-01T23:59:59.000Z

    The Remote-Handled Low-Level Waste (LLW) Disposal Project addresses an anticipated shortfall in remote-handled LLW disposal capability following cessation of operations at the existing facility, which will continue until it is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). Development of a new onsite disposal facility will provide necessary remote-handled LLW disposal capability and will ensure continuity of operations that generate remote-handled LLW. This report documents the Code of Record for design of a new LLW disposal capability. The report is owned by the Design Authority, who can authorize revisions and exceptions. This report will be retained for the lifetime of the facility.

  20. Remote-Handled Low-Level Waste Disposal Project Code of Record

    SciTech Connect (OSTI)

    S.L. Austad, P.E.; L.E. Guillen, P.E.; C. W. McKnight, P.E.; D. S. Ferguson, P.E.

    2012-06-01T23:59:59.000Z

    The Remote-Handled Low-Level Waste (LLW) Disposal Project addresses an anticipated shortfall in remote-handled LLW disposal capability following cessation of operations at the existing facility, which will continue until it is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). Development of a new onsite disposal facility will provide necessary remote-handled LLW disposal capability and will ensure continuity of operations that generate remote-handled LLW. This report documents the Code of Record for design of a new LLW disposal capability. The report is owned by the Design Authority, who can authorize revisions and exceptions. This report will be retained for the lifetime of the facility.

  1. Better Buildings Network View | November 2014 | Department of...

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

    November 2014 More Documents & Publications Better Buildings Network View | July-August 2014 Better Buildings Network View | December 2014 Better Buildings Network View | January...

  2. The Better Buildings Neighborhood View - August 2012 | Department...

    Energy Savers [EERE]

    The Better Buildings Neighborhood View - August 2012 The Better Buildings Neighborhood View - August 2012 The Better Buildings Neighborhood View monthly newsletter from the U.S....

  3. Cosmology: a bird's eye view

    E-Print Network [OSTI]

    Alan A. Coley; Sigbjorn Hervik; Woei Chet Lim

    2006-05-15T23:59:59.000Z

    In this essay we discuss the difference in views of the Universe as seen by two different observers. While one of the observers follows a geodesic congruence defined by the geometry of the cosmological model, the other observer follows the fluid flow lines of a perfect fluid with a linear equation of state. We point out that the information these observers collect regarding the state of the Universe can be radically different; while one observes a non-inflating ever-expanding ever-lasting universe, the other observer can experience a dynamical behaviour reminiscent to that of quintessence or even that of a phantom cosmology leading to a 'big rip' singularity within finite time (but without the need for exotic forms of matter).

  4. On the calculation of flow and heat transfer characteristics for CANDU-type 19-rod fuel bundles

    SciTech Connect (OSTI)

    Yuh-Shan Yueh; Ching-Chang Chieng

    1987-08-01T23:59:59.000Z

    A numerical study is reported of flow and heat transfer in a CANDU-type 19 rod fuel bundle. The flow domain of interest includes combinations of trangular, square, and peripheral subchannels. The basic equations of momentum and energy are solved with the standard k--epsilon model of turbulence. Isotropic turbulent viscosity is assumed and no secondary flow is considered for this steady-state, fully developed flow. Detailed velocity and temperature distributions with wall shear stress and Nusselt number distributions are obtained for turbulent flow of Re = 4.35 x 10/sup 4/, 10/sup 5/, 2 x 10/sup 5/, and for laminar flow of Re--2400. Friction factor and heat transfer ceofficients of various subchannels inside the full bundle are compared with those of infinite rod arrays of triangular or square arrangements. The calculated velocity contours of peripheral subchannel agreed reasonably with measured data.

  5. Subchannel Thermal-Hydraulic Experimental Program (STEP). Volume 1. Mixing in a pressurized water reactor (PWR) rod bundle. Final report

    SciTech Connect (OSTI)

    Barber, A.R.; Zielke, L.A.

    1980-08-01T23:59:59.000Z

    This volume describes an experiment that was performed to determine the mixing characteristics of a pressurized water reactor (PWR) rod bundle. The objective of this project was to improve the subchannel computer code models of the reactor core. The experimental technique was isokinetic subchannel withdrawal of the entire flow from two sample subchannels. Once withdrawn, the sample fluid was condensed and its enthalpy was measured by regenerative heat exchange calorimetry. The test bundle was a 4 x 6 electrically heated array with a 50% power upset. The COBRA IIIC code was used to model the experiment and to determine the value of the thermal mixing coefficient, ..beta.., that was necessary to predict the measured results. Both single- and two-phase data were obtained over a range of PWR operating conditions. The results indicate that both single- and two-phase mixing is small. The COBRA model predicts the enthalpy data using a turbulent mixing coefficient, ..beta.. approx. = 0.002.

  6. Mixed convection and high-pressure low-flow steam cooling data from a 64-rod bundle

    SciTech Connect (OSTI)

    Sozer, A.

    1984-01-01T23:59:59.000Z

    Heat transfer data were obtained from low flow steam cooling experiments in a partially uncovered 64-rod bundle. These tests indicated that free convection effects were superimposed on the laminar and turbulent forced convection heat transfer. This paper describes the influence of buoyancy on laminar and turbulent forced convection heat transfer coefficients. Mechanisms due to buoyancy which alter the local heat transfer are summarized. Criteria indicating the importance of buoyancy on laminar and turbulent upflow in a vertical pipe were developed and compared to other criteria found in the literature. These criteria were used to determine the steam cooling data with significant buoyancy influence. Data with buoyancy influence were compared to mixed convection correlations and to a numerical study for rod bundles.

  7. THORAX pretest prediction of a sodium-boiling transient in a 19-pin simulated LMFBR driver bundle

    SciTech Connect (OSTI)

    Rose, S.D.

    1982-01-01T23:59:59.000Z

    Experiments will be conducted in the Thermal-Hydraulic Out-of-Reactor Safety-Shutdown Heat Removal System (THORS-SHRS) Assembly 1 loop at Oak Ridge National Laboratory (ORNL) to model the behavior of a reactor during degraded decay heat removal conditions. The test section is to consist of two parallel 19-pin electrically-heated driver bundles, typical of U.S. Large Developmental Plant (LDP) Liquid Metal Fast Breeder Reactor (LMFBR) design. Analysis of these experiments will include using THORAX, a two-dimensional boiling model which assumes an equilibrium mixture two-phase flow (with slip). A THORAX prediction is presented for a single-bundle forced convection boiling-to-dryout transient at 15.8 kW/pin.

  8. On the calculation of flow and heat transfer characteristics for CANDU-type 19-rod fuel bundles

    SciTech Connect (OSTI)

    Yueh, Yuhshan; Chieng, Chingchang (National Tsing Hua Univ., Hsinchu (Taiwan))

    1987-08-01T23:59:59.000Z

    A numerical study is reported of flow and heat transfer in a CANDU-type 19 rod fuel bundle. The flow domain of interest includes combinations of triangular, square, and peripheral subchannels. The basic equations of momentum and energy are solved with the standard k-{epsilon} model of turbulence. Isotropic turbulent viscosity is assumed and no secondary flow is considered for this steady-state, fully developed flow. Detailed velocity and temperature distributions with wall shear stress and Nusselt number distributions are obtained for turbulent flow of Re = 4.35 {times} 10{sup 4}, 10{sup 5}, 2 {times} 10{sup 5}, and for laminar flow of Re {approximately} 2,400. Friction factor and heat transfer coefficients of various subchannels inside the full bundle are compared with those of infinite rod arrays of triangular or square arrangements. The calculated velocity contours of peripheral subchannel agreed reasonably with measured data.

  9. Cobra-IE Evaluation by Simulation of the NUPEC BWR Full-Size Fine-Mesh Bundle Test (BFBT)

    SciTech Connect (OSTI)

    Burns, C. J. and Aumiler, D. L.

    2006-04-26T23:59:59.000Z

    The COBRA-IE computer code is a thermal-hydraulic subchannel analysis program capable of simulating phenomena present in both PWRs and BWRs. As part of ongoing COBRA-IE assessment efforts, the code has been evaluated against experimental data from the NUPEC BWR Full-Size Fine-Mesh Bundle Tests (BFBT). The BFBT experiments utilized an 8 x 8 rod bundle to simulate BWR operating conditions and power profiles, providing an excellent database for investigation of the capabilities of the code. Benchmarks performed included steady-state and transient void distribution, single-phase and two-phase pressure drop, and steady-state and transient critical power measurements. COBRA-IE effectively captured the trends seen in the experimental data with acceptable prediction error. Future sensitivity studies are planned to investigate the effects of enabling and/or modifying optional code models dealing with void drift, turbulent mixing, rewetting, and CHF.

  10. Electrolytic/fuel cell bundles and systems including a current collector in communication with an electrode thereof

    DOE Patents [OSTI]

    Hawkes, Grant L.; Herring, James S.; Stoots, Carl M.; O'Brien, James E.

    2013-03-05T23:59:59.000Z

    Electrolytic/fuel cell bundles and systems including such bundles include an electrically conductive current collector in communication with an anode or a cathode of each of a plurality of cells. A cross-sectional area of the current collector may vary in a direction generally parallel to a general direction of current flow through the current collector. The current collector may include a porous monolithic structure. At least one cell of the plurality of cells may include a current collector that surrounds an outer electrode of the cell and has at least six substantially planar exterior surfaces. The planar surfaces may extend along a length of the cell, and may abut against a substantially planar surface of a current collector of an adjacent cell. Methods for generating electricity and for performing electrolysis include flowing current through a conductive current collector having a varying cross-sectional area.

  11. COBRA-PI: an extension of the COBRA-3M code dynamically dimensioned to accept pin bundles of any size. [LMFBR

    SciTech Connect (OSTI)

    Froehle, P.H.; Bauer, T.H.

    1983-03-28T23:59:59.000Z

    COBRA, in general, performs a thermal-hydraulic analysis of an actual pin bundle by subdividing the bundle cross-section into coolant subchannels, pin sectors, duct wall sectors. Its calculation includes heat convected axially upward through coolant mass flow, heat flow between pin sectors and adjoining subchannels, and heat and mass flow between coolant subchannels. COBRA-3M is a version of COBRA built for LMFBR applications, that includes a sophisticated thermal model of fuel pins and duct wall. COBRA-3M that can explicitly model a wider variety of pin bundle configurations than 3M would allow and includes significant improvements to its thermal modeling. COBRA-PI is currently being used for thermal-hydraulic analysis of hypothetical LMFBR accident transients in both power and flow. Pin bundles currently being analyzed explicitly range from 7 to 37 pins of axial lengths ranging from approx. 0.3-2.0 meters.

  12. Algebraic stress model for axial flow in a bare rod-bundle

    SciTech Connect (OSTI)

    de Lemos, M.J.S.

    1987-01-01T23:59:59.000Z

    The problem of predicting transport properties for momentum and heat across the boundaries of interconnected channels has been the subject of many investigations. In the particular case of axial flow through rod-bundles, transport coefficients for channel faces aligned with rod centers are known to be considerably higher than those calculated by simple isotropic theories. And yet, it was been found that secondary flows play only a minor role in this overall transport, being turbulence highly enhanced across that hypothetical surface. In order to numerically predict the correct amount of the quantity being transported, the approach taken by many investigators was then to artificially increase the diffusion coefficient obtained via a simple isopropic theory (usually the standard k-epsilon model) and numerically match the correct experimentally observed mixing rates. The present paper reports an attempt to describe the turbulent stresses by means of an Algebraic Stress Model for turbulence. Relative turbulent kinetic energy distribution in all three directions are presented and compared with experiments in a square lattice. The strong directional dependence of transport terms are then obtained via a model for the Reynolds stresses. The results identify a need for a better representation of the mean-flow field part of the pressure-strain correlation term.

  13. Ensemble phase averaging equations for multiphase flows in porous media, part I: the bundle-of-tubes model

    SciTech Connect (OSTI)

    Yang, Dali [Los Alamos National Laboratory; Zhang, Duan [Los Alamos National Laboratory; Currier, Robert [Los Alamos National Laboratory

    2008-01-01T23:59:59.000Z

    A bundle-of-tubes construct is used as a model system to study ensemble averaged equations for multiphase flow in a porous material. Momentum equations for the fluid phases obtained from the method are similar to Darcy's law, but with additional terms. We study properties of the additional terms, and the conditions under which the averaged equations can be approximated by the diffusion model or the extended Darcy's law as often used in models for multiphase flows in porous media. Although the bundle-of-tubes model is perhaps the simplest model for a porous material, the ensemble averaged equation technique developed in this paper assumes the very same form in more general treatments described in Part 2 of the present work (Zhang 2009). Any model equation system intended for the more general cases must be understood and tested first using simple models. The concept of ensemble phase averaging is dissected here in physical terms, without involved mathematics through its application to the idealized bundle-of-tubes model for multiphase flow in porous media.

  14. Investigation of the relative abundance of heavy versus light nuclei in primary cosmic rays using underground muon bundles

    SciTech Connect (OSTI)

    Sundaralingam, N.

    1993-06-08T23:59:59.000Z

    We study multiple muon events (muon bundles) recorded underground at a depth of 2090 mwe. To penetrate to this depth, the muons must have energies above 0.8 TeV at the Earth`s surface; the primary cosmic ray nuclei which give rise to the observed muon bundles have energies at incidence upon the upper atmosphere of 10 to 10{sup 5}TeV. The events are detected using the Soudan 2 experiment`s fine grained tracking calorimeter which is surrounded by a 14 m {times}10 m {times} 31 m proportional tube array (the ``active shield``). Muon bundles which have at least one muon traversing the calorimeter, are reconstructed using tracks in the calorimeter together with hit patterns in the proportional tube shield. All ionization pulses are required to be coincident within 3 microseconds. A goal of this study is to investigate the relative nuclear abundances in the primary cosmic radiation around the ``knee`` region (10{sup 3} {minus} 10{sup 4} TeV) of the incident energy spectrum. Four models for the nuclear composition of cosmic rays are considered: The Linsley model, the Constant Mass Composition model (CMC), the Maryland model and the Proton-poor model. A Monte Carlo which incorporates one model at a time is used to simulate events which are then reconstructed using the same computer algorithms that are used for the data. Identical cuts and selections are applied to the data and to the simulated events.

  15. Fibrations and universal view updatability Michael Johnson

    E-Print Network [OSTI]

    Johnson, Michael

    Fibrations and universal view updatability Michael Johnson Computing Department, Macquarie methods to manage the complexity. Dampney and Johnson [25] first showed how data models based on entity

  16. Fibrations and universal view updatability Michael Johnson

    E-Print Network [OSTI]

    Rosebrugh, Robert

    Fibrations and universal view updatability Michael Johnson Computing Department, Macquarie and Johnson [25] first showed how data models based on entity-relationship (ER) diagrams [10] are enhanced

  17. Better Buildings Network View | May 2014 | Department of Energy

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

    May 2014 More Documents & Publications Better Buildings Network View | July-August 2014 Better Buildings Network View | June...

  18. Interplay between structural and electronic properties of bundled Mo x nanowires

    E-Print Network [OSTI]

    apply. View the table of contents for this issue, or go to the journal homepage for more Home Search explore the structural stability, elastic behavior and electronic structure at all these minima for eachIx , which are air- stable, exhibit a very unusual ability to stretch irreversibly by 30% at very low energy

  19. 18 years experience on UF{sub 6} handling at Japanese nuclear fuel manufacturer

    SciTech Connect (OSTI)

    Fujinaga, H.; Yamazaki, N.; Takebe, N. [Japan Nucelar Fuel Conversion Co., Ltd., Ibaraki (Japan)

    1991-12-31T23:59:59.000Z

    In the spring of 1991, a leading nuclear fuel manufacturing company in Japan, celebrated its 18th anniversary. Since 1973, the company has produced over 5000 metric ton of ceramic grade UO{sub 2} powder to supply to Japanese fabricators, without major accident/incident and especially with a successful safety record on UF{sub 6} handling. The company`s 18 years experience on nuclear fuel manufacturing reveals that key factors for the safe handling of UF{sub 6} are (1) installing adequate facilities, equipped with safety devices, (2) providing UF{sub 6} handling manuals and executing them strictly, and (3) repeating on and off the job training for operators. In this paper, equipment and the operation mode for UF{sub 6} processing at their facility are discussed.

  20. Remote-Handled Low-Level Waste Disposal Project Alternatives Analysis

    SciTech Connect (OSTI)

    David Duncan

    2009-10-01T23:59:59.000Z

    This report identifies, evaluates, and compares alternatives for meeting the U.S. Department of Energy’s mission need for management of remote-handled low-level waste generated by the Idaho National Laboratory and its tenants. Each alternative identified in the Mission Need Statement for the Remote-Handled Low-Level Waste Treatment Project is described and evaluated for capability to fulfill the mission need. Alternatives that could meet the mission need are further evaluated and compared using criteria of cost, risk, complexity, stakeholder values, and regulatory compliance. The alternative for disposal of remote-handled low-level waste that has the highest confidence of meeting the mission need and represents best value to the government is to build a new disposal facility at the Idaho National Laboratory Site.

  1. Remote-Handled Low-Level Waste Disposal Project Alternatives Analysis

    SciTech Connect (OSTI)

    David Duncan

    2010-06-01T23:59:59.000Z

    This report identifies, evaluates, and compares alternatives for meeting the U.S. Department of Energy’s mission need for management of remote-handled low-level waste generated by the Idaho National Laboratory and its tenants. Each alternative identified in the Mission Need Statement for the Remote-Handled Low-Level Waste Treatment Project is described and evaluated for capability to fulfill the mission need. Alternatives that could meet the mission need are further evaluated and compared using criteria of cost, risk, complexity, stakeholder values, and regulatory compliance. The alternative for disposal of remote-handled low-level waste that has the highest confidence of meeting the mission need and represents best value to the government is to build a new disposal facility at the Idaho National Laboratory Site.

  2. Remote-Handled Low-Level Waste Disposal Project Alternatives Analysis

    SciTech Connect (OSTI)

    David Duncan

    2011-03-01T23:59:59.000Z

    This report identifies, evaluates, and compares alternatives for meeting the U.S. Department of Energy’s mission need for management of remote-handled low-level waste generated by the Idaho National Laboratory and its tenants. Each alternative identified in the Mission Need Statement for the Remote-Handled Low-Level Waste Treatment Project is described and evaluated for capability to fulfill the mission need. Alternatives that could meet the mission need are further evaluated and compared using criteria of cost, risk, complexity, stakeholder values, and regulatory compliance. The alternative for disposal of remote-handled low-level waste that has the highest confidence of meeting the mission need and represents best value to the government is to build a new disposal facility at the Idaho National Laboratory Site.

  3. Remote-Handled Low-Level Waste Disposal Project Alternatives Analysis

    SciTech Connect (OSTI)

    David Duncan

    2011-04-01T23:59:59.000Z

    This report identifies, evaluates, and compares alternatives for meeting the U.S. Department of Energy’s mission need for management of remote-handled low-level waste generated by the Idaho National Laboratory and its tenants. Each alternative identified in the Mission Need Statement for the Remote-Handled Low-Level Waste Treatment Project is described and evaluated for capability to fulfill the mission need. Alternatives that could meet the mission need are further evaluated and compared using criteria of cost, risk, complexity, stakeholder values, and regulatory compliance. The alternative for disposal of remote-handled low-level waste that has the highest confidence of meeting the mission need and represents best value to the government is to build a new disposal facility at the Idaho National Laboratory Site.

  4. Alternative configurations for the waste-handling building at the Yucca Mountain Repository

    SciTech Connect (OSTI)

    NONE

    1990-08-01T23:59:59.000Z

    Two alternative configurations of the waste-handling building have been developed for the proposed nuclear waste repository in tuff at Yucca Mountain, Nevada. One configuration is based on criteria and assumptions used in Case 2 (no monitored retrievable storage facility, no consolidation), and the other configuration is based on criteria and assumptions used in Case 5 (consolidation at the monitored retrievable storage facility) of the Monitored Retrievable Storage System Study for the Repository. Desirable waste-handling design concepts have been selected and are included in these configurations. For each configuration, general arrangement drawings, plot plans, block flow diagrams, and timeline diagrams are prepared.

  5. Training in Health Care: The Benefits of Context and Emergency Simulation on Patient Handling

    E-Print Network [OSTI]

    Marc L. Resnick; Roderick Sanchez

    In the United States, there is no standardized method for training nurses in manual patient handling, despite the high incidence of injury. The objective of this research was to evaluate several training protocols, including the use of simulated emergency situations and the use of realistic context during course delivery, to evaluate their impact on nurses ’ postures and compliance with trained procedures during post-training tests. The results show that training on body mechanics and proper use of equipment can significantly reduce the amount of torso flexion and rotation during patient handling and compliance with safe practices. Implications for health care training are provided.

  6. Prediction of heat transfer for a supercritical water test with a four pin fuel bundle

    SciTech Connect (OSTI)

    Behnke, L. [RWE Power AG, Essen (Germany); Himmel, S.; Waata, C.; Schulenberg, T. [Forschungszentrum Karlsruhe GmbH, Institute for Nuclear and Energy Technologies, PO Box 3640, D-76021 Karlsruhe (Germany); Laurien, E. [University of Stuttgart (Germany)

    2006-07-01T23:59:59.000Z

    As a next step to validate prediction methods for core design of a Supercritical Water Cooled Reactor, a small, electrically heated fuel bundle with 4 pins is planned to be tested. This paper summarizes first heat transfer predictions for such a test, which were performed based on supercritical and subcritical sub-channel analyses. For heat transfer under supercritical pressure conditions, the sub-channel code STAFAS has been applied, which had been tested successfully already for a supercritical water reactor design. Design studies with different assembly box sizes at a given pin diameter and pitch have been performed to optimize the coolant temperature distribution. With a fuel pin outer diameter of 10 mm and a pitch to diameter ratio of 1.15, an optimum inner width of the assembly box was determined to be 24 mm. Coolant and cladding surface temperatures to be expected at subcritical pressure conditions have been predicted with the sub-channel code MATRA. As, different from typical PWR or BWR conditions, a dryout has been foreseen for the tests, this code had to be extended to include suitable dryout criteria as well as post dryout heat transfer correlations at higher enthalpies and pressures. Different from PWR or BWR design, the cladding surface temperature of fuel pins in supercritical water reactors can vary significantly around the circumference of each pin, causing bending towards its hotter side which, in turn, can cause additional sub-channel heat-up and thus additional thermal bending of the pin. To avoid a thermal instability by this effect, a sensitivity study with respect to thermal bending of fuel pins has been performed, which determines the minimum number of grid spacers needed for this test. (authors)

  7. Handbook for Handling, Storing, and Dispensing E85, July 2010, Energy Efficiency and Renewable Energy (EERE), Clean Cities (Brochure)

    SciTech Connect (OSTI)

    Not Available

    2010-07-01T23:59:59.000Z

    Guidebook contains information about EPAct alternative fuels regulations for fleets, flexible fuel vehicles, E85 properties and specifications, and E85 handling and storage guidelines.

  8. Hydrogen Fuel Cell Performance in the Key Early Markets of Material Handling Equipment and Backup Power (Presentation)

    SciTech Connect (OSTI)

    Kurtz, J.; Sprik, S.; Ramsden, T.; Saur, G.; Ainscough, C.; Post, M.; Peters, M.

    2013-10-01T23:59:59.000Z

    This presentation summarizes the results of NREL's analysis of hydrogen fuel cell performance in the key early markets of material handling equipment (MHE) and backup power.

  9. A plug and play framework for an HVAC air handling unit and temperature sensor auto recognition technique.

    E-Print Network [OSTI]

    Zhou, Xiaohui

    2010-01-01T23:59:59.000Z

    ??A plug and play framework for an HVAC air handling unit control system is proposed in this study. This is the foundation and the first… (more)

  10. Missing Data Handling for Meter Data Management System Ru-Sen Jeng1

    E-Print Network [OSTI]

    Chen, Ling-Jyh

    Missing Data Handling for Meter Data Management System Ru-Sen Jeng1 , Chien-Yu Kuo1 , Yao-hua Ho1, Academia Sinica ABSTRACT We study the meter data management systems (MDMS) with a fo- cus on missing data meter data manage- ment systems. Categories and Subject Descriptors H.4.2 [Information Systems

  11. A New Contactless Conveyor System for Handling Clean and Delicate Products Using Induced Air Flows

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    A New Contactless Conveyor System for Handling Clean and Delicate Products Using Induced Air Flows thanks to an air cushion and induced air flows. A model of the system is established or in semiconductor production processes. Furthermore, dry fric- tion forces are canceled, which enables accurate

  12. November 28, 2006 Seismologists get handle on heat flow deep in earth

    E-Print Network [OSTI]

    Garnero, Ed

    November 28, 2006 Seismologists get handle on heat flow deep in earth Earth's interior placid inner Earth as a dynamic environment filled with exotic materials and substances roiling under that has an impact on what happens on our planet's surface. The latest evidence of this dynamic inner Earth

  13. Automated control for coal handling operations at Bethlehem Steel, Burns Harbor Division

    SciTech Connect (OSTI)

    Zendzian, T.N. [Bethlehem Steel Corp., Chesterton, IN (United States). Burns Harbor Div.

    1997-12-31T23:59:59.000Z

    The Burns Harbor coal handling operation processes 7,200 tons of coal per day to supply two 82 oven, six meter batteries. The operations in coal handling are subdivided into three separate sections: the coal field and stacker reclaimer operation, the crushing and storage of coal, and the coal blending operation. In 1996 a supervisory system was developed and installed to fully automate all the operations and equipment in the coal handling unit, add additional instrumentation and logic controls to prevent coal contamination, and improve data collection and logging. The supervisory system is operated from a computer based workstation and is based on a distributed control philosophy utilizing programmable logic controllers, set point controllers, and man-machine interface displays. The previous control system for the coal handling operation consisted of a switchboard from which an operator controller the set up and running of the conveyor systems and equipment to stack, reclaim, and blend coal. The new supervisory system was installed in parallel with the original control system to safeguard continued operation during the system installation and commissioning. The original system still exists and can be operated in even of failure of the supervisory system.

  14. Plasma Power Handling Parameters and Issues May 1-3, 2000

    E-Print Network [OSTI]

    Distribution · Divertor Heat Loads · Divertor Conceptual Design Outline #12;Power Distribution · Heating Power power distribution ­ Inner - 7 MW (3.4 each) ­ Outer - 27 MW (14 each) #12;Divertor Heat LoadsPlasma Power Handling Parameters and Issues May 1-3, 2000 M. Ulrickson Presented at the FIRE

  15. LLaannggeerrhhaannss LLaabb PPrroottooccoollss Handling of Dead Fish at Yates Mill Facility

    E-Print Network [OSTI]

    Langerhans, Brian

    LLaannggeerrhhaannss LLaabb PPrroottooccoollss Handling of Dead Fish at Yates Mill Facility If a study fish is found dead, preserve it and return it to the lab for DRILL recording. If you are going to DCL shortly after finding the fish: 1. Put it in a plastic bag and bring it to DCL. 2. Put

  16. IS THIS A SUB-RECIPIENT OR A VENDOR RELATIONSHIP AND WHICH OFFICE HANDLES EACH?

    E-Print Network [OSTI]

    IS THIS A SUB-RECIPIENT OR A VENDOR RELATIONSHIP AND WHICH OFFICE HANDLES EACH? (For agreements AND CONTRACTING SERVICES Vendors/Consultants (If an entity fulfills the criteria for Vendor/Consultant below provider. Purchased Services (or PO): · Vendor is not providing substantive programmatic work

  17. 3.1.1.2 Feed Processing and Handling DL2 Final Report

    SciTech Connect (OSTI)

    Elliott, Douglas C.; Magnuson, Jon K.; Wend, Christopher F.

    2006-09-30T23:59:59.000Z

    This milestone report is the deliverable for our Feed Processing and Handling project. It includes results of wet biomass feedstock analysis, slurry pumping information, fungal processing to produce a lignin-rich biorefinery residue and two subcontracted efforts to quantify the amount of wet biomass feedstocks currently available within the corn processing and paper processing industries.

  18. RIS0-M-2294 HANDLING OF DEUTERIUM PELLETS FOR PLASMA REFUELLING

    E-Print Network [OSTI]

    RIS0-M-2294 HANDLING OF DEUTERIUM PELLETS FOR PLASMA REFUELLING P.s. Jensen and V. Andersen Association Euratom - Ris0 National Laboratory Abstract. The use of a guide tube technique to inject pellets in pellet-plasma experiments guide tube on the mass and (v ~ 150 m/s) is negligible. jectories

  19. LPV/H controller for vehicle handling and stability enhancement M. DOUMIATI 1

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    LPV/H controller for vehicle handling and stability enhancement M. DOUMIATI 1 , O. SENAME 1 , J Laboratory, Computer and Automation Research Institute, Budapest, HUNGARY, e-mail: {gaspar, szabo, bokor with steering/braking coordination task, for automotive vehicle yaw control scheme. Because of the tire

  20. Harvesting and StorageHarvesting and Storage Importance of safe food handling during harvest and storage

    E-Print Network [OSTI]

    Liskiewicz, Maciej

    Harvesting and StorageHarvesting and Storage Importance of safe food handling during harvest illness. Steps to take prior to harvest When washing and sanitizing surfaces, use the appropriate. Pressure washing is a good way to clean. Clean and sanitize harvesting tools such as knives, pruners

  1. HANDLING WHITE-MATTER ANISOTROPY IN BEM FOR THE EEG FORWARD PROBLEM

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    HANDLING WHITE-MATTER ANISOTROPY IN BEM FOR THE EEG FORWARD PROBLEM Emmanuel Olivi Th and EEG for- ward fields. Those tissues include white matter, whose con- ductivity is anisotropic because of its fiber structure. While white matter anisotropy can be measured thanks to Diffusion- Weighted MRI

  2. DIMENSIONS: Why do we need a new Data Handling architecture for Sensor Networks?

    E-Print Network [OSTI]

    Ganesan, Deepak

    DIMENSIONS: Why do we need a new Data Handling architecture for Sensor Networks? Deepak Ganesan incorporate their ex- treme resource constraints - energy, storage and processing - and spatio-temporal interpretation of the physical world in the design, cost model, and metrics of evaluation. We describe DIMENSIONS

  3. Handles Revisited: Optimising Performance and Memory Costs in a Real-Time Collector

    E-Print Network [OSTI]

    Kent, University of

    Handles Revisited: Optimising Performance and Memory Costs in a Real-Time Collector Tomas Kalibera garbage collectors must update all references to ob- jects they move. Updating is a lengthy operation references have been updated which, in a real-time collector, must be done incrementally. One solution

  4. Animal carcasses must be handled properly to prevent harm to people, herds, flocks,

    E-Print Network [OSTI]

    Mukhtar, Saqib

    Animal carcasses must be handled properly to prevent harm to people, herds, flocks, water (Fig. 1): · Diseases can be spread to people and animals. · Carcass fluids can leach into and pollute, or rivers). · Obnoxious gases and odors can be emitted to the atmosphere. · The carcasses can attract

  5. COS/HST FUV Grating Shipping Container Handling Procedure Date: November 30, 1999

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    COS/HST FUV Grating Shipping Container Handling Procedure Date: November 30, 1999 Document Number University of Colorado Campus Box 593 Boulder, Colorado 80309 #12;REVISIONS Letter ECO No. Description Check. Wilkinson 11-30-99 The Center for Astrophysics and Space Astronomy Reviewed: COS/HST FUV Grating Shipping

  6. Feasibility Study of Developing a Virtual Chilled Water Flow Meter at Air Handling Unit Level

    E-Print Network [OSTI]

    Song, L.; Swamy, A.; Shim, G.

    2011-01-01T23:59:59.000Z

    In this paper, a virtual Air handling unit (AHU) level water flow meter is explored by using a control valve as a measurement device. The flow through the valve is indirectly calculated using differential pressure over both the valve and its...

  7. Siting Study for the Remote-Handled Low-Level Waste Disposal Project

    SciTech Connect (OSTI)

    Lisa Harvego; Joan Connolly; Lance Peterson; Brennon Orr; Bob Starr

    2010-10-01T23:59:59.000Z

    The U.S. Department of Energy has identified a mission need for continued disposal capacity for remote-handled low-level waste (LLW) generated at the Idaho National Laboratory (INL). An alternatives analysis that was conducted to evaluate strategies to achieve this mission need identified two broad options for disposal of INL generated remote-handled LLW: (1) offsite disposal and (2) onsite disposal. The purpose of this study is to identify candidate sites or locations within INL boundaries for the alternative of an onsite remote handled LLW disposal facility and recommend the highest-ranked locations for consideration in the National Environmental Policy Act process. The study implements an evaluation based on consideration of five key elements: (1) regulations, (2) key assumptions, (3) conceptual design, (4) facility performance, and (5) previous INL siting study criteria, and uses a five-step process to identify, screen, evaluate, score, and rank 34 separate sites located across INL. The result of the evaluation is identification of two recommended alternative locations for siting an onsite remote-handled LLW disposal facility. The two alternative locations that best meet the evaluation criteria are (1) near the Advanced Test Reactor Complex and (2) west of the Idaho Comprehensive Environmental Response, Compensation, and Liability Act Disposal Facility.

  8. DESIGN OF THE MERCURY HANDLING SYSTEM FOR A MUON COLLIDER/NEUTRINO FACTORY TARGET

    E-Print Network [OSTI]

    McDonald, Kirk

    DESIGN OF THE MERCURY HANDLING SYSTEM FOR A MUON COLLIDER/NEUTRINO FACTORY TARGET V.B. Graves , Oak is a free mercury jet within a 20-T magnetic field being impacted by an 8-GeV proton beam. A pool of mercury serves as a receiving reservoir for the mercury and a dump for the unexpended proton beam. Modifications

  9. DESIGN OF THE MERCURY HANDLING SYSTEM FOR A MUON COLLIDER/NEUTRINO FACTORY TARGET

    E-Print Network [OSTI]

    McDonald, Kirk

    DESIGN OF THE MERCURY HANDLING SYSTEM FOR A MUON COLLIDER/NEUTRINO FACTORY TARGET (IPAC13, THPFI092) The baseline target concept for a Muon Collider or Neutrino Factory is a free mercury jet within a 20-T magnetic field being impacted by an 8-GeV proton beam. A pool of mercury serves as a receiving reservoir

  10. Cooling output optimization of an air handling unit Andrew Kusiak *, Mingyang Li

    E-Print Network [OSTI]

    Kusiak, Andrew

    supply temperature and supply air temperature in response to the dynamic cooling load and changingCooling output optimization of an air handling unit Andrew Kusiak *, Mingyang Li Department mining Neural network Multi-objective optimization Evolutionary computation Dynamic modeling Cooling

  11. An internship in postharvest handling of vegetables and fruits at Valley Onions, McAllen, Texas: and an analysis of the postharvest handling system of onions

    E-Print Network [OSTI]

    Sanchez-Ramos, Jose Ignacio

    1984-01-01T23:59:59.000Z

    , McALLW, TEXAS ~ AN ANALYSIS OF THE POSTHARVEST HANDLING SYSTEM OF ONIONS A Professional Paper by Jose Ignacio Sanchez-Eamon Approved as to style and content by: Leonard M. Pike (Hort) Chairman, Advisory Committee James Benton Storey (Hort.... Am. Econ. Rev. 50:908-17. 19. Zusman, P. and A. Amiad. 1965. Simulation: A tool for farm planing under conditions of uncertainty. J. Farm. Econ. 47:574-95. 31 VITA NAME PERMANENT ADDRESS TELEPHONE Jose Ignacio Sanchez~os. Callejon de la Rosa...

  12. Design, Feasibility, and Testing of Instrumented Rod Bundles to Improve Heat Transfer Knowledge in PWR Fuel Assemblies

    SciTech Connect (OSTI)

    Bergeron, A. [CEA, Saclay (France); Chataing, T.; Garnier, J. [CEA, Genoble (France); Decossin, E.; Peturaud, P. [EDF/R and D, Chatou (France); Yagnik, S.K. [Electric Power Research Institute - EPRI (United States)

    2007-07-01T23:59:59.000Z

    Two 5 x 5 test rod bundles mimicking the PWR fuel assembly have been adapted into two suitable test loop facilities, respectively, to carry out sufficiently detailed hydraulic and thermal measurements in identical geometric configuration. The objective is to investigate heat transfer phenomena in single-phase as well as with onset of nucleate boiling (ONB). The accuracy and reproducibility of the temperature measurements using the sliding-traversing thermocouple device under typical PWR conditions has been demonstrated in the thermal test facility. In the hydraulic loop, a Laser Doppler Velocimetry (LDV) system to precisely scan the local axial velocity component in each sub-channel has been implemented. The approach is to utilize mean sub-channel axial velocity distributions and pressure drop data from the hydraulic loop and the global boundary conditions (Pressure, Temperature, flow rate) from the thermal loop to simulate sub-channels in appropriate T/H codes. This permits computation of sub-channel averaged fluid temperatures (as well as mass velocity) in various subchannels within the test bundle. Subsequently, in conjunction with the wall temperatures and applied heat flux values from the thermal loop, it is possible to develop a complete map of heat transfer coefficients along the 9 instrumented central heater rods. Locations downstream of spacer grids would be of special interest. Depending on pressure, mass velocity and heat flux conditions of a given test, the inlet temperature will be a parameter to be varied so that the ONB boundary can be observed within the bundle. Detailed designs of the test section, required loop modifications, and adaptation of specialized instrumentation and data acquisition systems have been accomplished in both test loops. Further we have established that based on such detailed rod surface temperature and sub-channel axial velocity measurements, it is possible to achieve sufficient accuracy in the temperature measurements to meet the objective of improving the heat transfer correlations applicable to PWR cores. (authors)

  13. x.0 Handling of White SVT Cables (SVT Excess Cables) before and during Withdrawing of Endcap In general we (UC Santa Cruz) prefer to do all handling of the white SVT cables necessary to withdraw and reinsert

    E-Print Network [OSTI]

    California at Santa Cruz, University of

    13 x.0 Handling of White SVT Cables (SVT Excess Cables) before and during Withdrawing of Endcap In general we (UC Santa Cruz) prefer to do all handling of the white SVT cables necessary to withdraw@scipp.ucsc.edu, office in SC: (831) 459­3337 , extn. at SLAC: 8561. The white SVT cables consist of two parts

  14. Assessment of CCFL model of RELAP5/MOD3 against simple vertical tubes and rod bundle tests. International Agreement Report

    SciTech Connect (OSTI)

    Cho, S.; Arne, N. [Korea Electric Power Corp., Taejon (KR). Research Center; Chung, B.D.; Kim, H.J. [Korea Inst. of Nuclear Safety, Taejon (KR)

    1993-06-01T23:59:59.000Z

    The CCFL model used in RELAP5/MOD3 version 5m5 has been assessed against simple vertical tubes and bundle tests performed at a facility of Korea Atomic Energy Research Institute. The effect of changes in tube diameter and nodalization of tube section were investigated. The roles of interfacial drags on the flooding characteristics are discussed. Differences between the calculation and the experiment are also discussed. A comparison between model assessment results and the test data showed that the calculated value lay well on the experimental flooding curve specified by user, but the pressure jump before onset of flooding was not calculated.

  15. Physical modeling and numerical simulation of subcooled boiling in one- and three-dimensional representation of bundle geometry

    SciTech Connect (OSTI)

    Bottoni, M.; Lyczkowski, R.; Ahuja, S.

    1995-07-01T23:59:59.000Z

    Numerical simulation of subcooled boiling in one-dimensional geometry with the Homogeneous Equilibrium Model (HEM) may yield difficulties related to the very low sonic velocity associated with the HEM. These difficulties do not arise with subcritical flow. Possible solutions of the problem include introducing a relaxation of the vapor production rate. Three-dimensional simulations of subcooled boiling in bundle geometry typical of fast reactors can be performed by using two systems of conservation equations, one for the HEM and the other for a Separated Phases Model (SPM), with a smooth transition between the two models.

  16. Investigation of combined free and forced convection in a 2 x 6 rod bundle during controlled flow transients

    SciTech Connect (OSTI)

    Bates, J.M.; Khan, E.U.

    1980-10-01T23:59:59.000Z

    An experimental study was performed to obtain local fluid velocity and temperature measurements in the mixed (combined free and forced) convection regime for specific flow coastdown transients. A brief investigation of steady-state flows for the purely free-convection regime was also completed. The study was performed using an electrically heated 2 x 6 rod bundle contained in a flow housing. In addition a transient data base was obtained for evaluating the COBRA-WC thermal-hydraulic computer program (a modified version of the COBRA-IV code).

  17. JOBAID-VIEWING AN EMPLOYEE MATRIX (SUPERVISOR)

    Broader source: Energy.gov [DOE]

    The purpose of this job aid is to guide supervisor users through the step-by-step process of viewing an employee matrix within SuccessFactors Learning.

  18. The new option view of investment

    E-Print Network [OSTI]

    Dixit, Avinash K.

    1995-01-01T23:59:59.000Z

    This paper provides a simple introduction to the new option view of investment. We explain the shortcomings of the orthodox theory, and then outline the basic ideas behind the option framework. Several industry examples ...

  19. Incorporating video into Google Mobile Street View

    E-Print Network [OSTI]

    Wright, Christina (Christina E.)

    2010-01-01T23:59:59.000Z

    Mobile Street View is a compelling application but suffers from significant latency problems, especially in limited bandwidth circumstances. Currently, the application uses static images to display street level information. ...

  20. Jefferson and Hamilton as viewed by historians

    E-Print Network [OSTI]

    Jungmeyer, Paul Edward

    1970-01-01T23:59:59.000Z

    JEFFERSON AND HAMILTON AS VIEHED BY HISTORIANS A Thesis Paul Edward Jungmeyer Submitted to the Graduate College of Texas A&M University in ' partial fulfillment of the requirement for the degree of MASTER OF ARTS August, 1970 Major Subject...: History JEFFERSON AND HAMILTON AS VIEWED BY HISTORIANS A Thesis by Paul Edward Jungmeyer Approved as to style and content by: (Chairman of Committee d i~) (Member) (M er) August, 1970 ABSTRACT JEFFERSON AND HAMILTON AS VIEWED BY HISTORIANS...

  1. Fuel cell integral bundle assembly including ceramic open end seal and vertical and horizontal thermal expansion control

    DOE Patents [OSTI]

    Zafred, Paolo R. (Murrysville, PA); Gillett, James E. (Greensburg, PA)

    2012-04-24T23:59:59.000Z

    A plurality of integral bundle assemblies contain a top portion with an inlet fuel plenum and a bottom portion containing a base support, the base supports a dense, ceramic air exhaust manifold having four supporting legs, the manifold is below and connects to air feed tubes located in a recuperator zone, the air feed tubes passing into the center of inverted, tubular, elongated, hollow electrically connected solid oxide fuel cells having an open end above a combustion zone into which the air feed tubes pass and a closed end near the inlet fuel plenum, where the open end of the fuel cells rest upon and within a separate combination ceramic seal and bundle support contained in a ceramic support casting, where at least one flexible cushion ceramic band seal located between the recuperator and fuel cells protects and controls horizontal thermal expansion, and where the fuel cells operate in the fuel cell mode and where the base support and bottom ceramic air exhaust manifolds carry from 85% to all of the weight of the generator.

  2. Simulation of steady-state and transient sodium boiling experiments in a seven-pin bundle under flow rundown conditions by using BODYFIT-1FE code

    SciTech Connect (OSTI)

    Chen, B.C.J.; Sha, W.T.

    1981-01-01T23:59:59.000Z

    A seven-pin rod bundle under flow rundown conditions was simulated by using the computer code BODYFIT-1FE (BOunDarY-FITted Coordinate System - 1 phase, Fully-Elliptic). In this code, the complicated rod bundle configuration is first transformed into rectangular geometry with uniform meshes. The transformed governing equations for all the thermal-hydraulic variables are then solved. The results of the simulation are presented here. All the predicted values agree favorably with the measured data. 7 refs., 20 figs.

  3. Dispersed-flow film boiling in rod-bundle geometry: steady-state heat-transfer data and correlation comparisons. [PWR; BWR

    SciTech Connect (OSTI)

    Yoder, G. L.; Morris, D. G.; Mullins, C. B.; Ott, L. J.; Reed, D. A.

    1982-03-01T23:59:59.000Z

    Assessment of six film boiling correlations and one single-phase vapor correlation has been made using data from 22 steady state upflow rod bundle tests (series 3.07.9). Bundle fluid conditions were calculated using energy and mass conservation considerations. Results of the steady state film boiling tests support the conclusions reached in the analysis of prior transient tests 3.03.6AR, 3.06.6B, and 3.08.6C. Comparisons between experimentally determined and correlation-predicted heat transfer coefficients, are presented.

  4. PWR FLECHT SEASET 163-Rod Bundle Flow Blockage Task data report. NRC/EPRI/Westinghouse report No. 13, August-October 1982

    SciTech Connect (OSTI)

    Loftus, M J; Hochreiter, L E; McGuire, M F; Valkovic, M M

    1983-10-01T23:59:59.000Z

    This report presents data from the 163-Rod Bundle Blow Blockage Task of the Full-Length Emergency Cooling Heat Transfer Systems Effects and Separate Effects Test Program (FLECHT SEASET). The task consisted of forced and gravity reflooding tests utilizing electrical heater rods with a cosine axial power profile to simulate PWR nuclear core fuel rod arrays. These tests were designed to determine effects of flow blockage and flow bypass on reflooding behavior and to aid in the assessment of computational models in predicting the reflooding behavior of flow blockage in rod bundle arrays.

  5. Handling and archiving of magnetic fusion data at DIII-D

    SciTech Connect (OSTI)

    VanderLaan, J.F.; Miller, S.; McHarg, B.B. Jr.; Henline, P.A.

    1995-10-01T23:59:59.000Z

    Recent modifications to the computer network at DIII-D enhance the collection and distribution of newly acquired and archived experimental data. Linked clients and servers route new data from diagnostic computers to centralized mass storage and distribute data on demand to local and remote workstations and computers. Capacity for data handling exceeds the upper limit of DIII-D Tokamak data production of about 4 GBytes per day. Network users have fast access to new data stored on line. An interactive program handles requests for restoration of data archived off line. Disk management procedures retain selected data on line in preference to other data. Redundancy of all components on the archiving path from the network to magnetic media has prevented loss of data. Older data are rearchived as dictated by limited media life.

  6. A probabilistic safety analysis of UF{sub 6} handling at the Portsmouth Gaseous Diffusion Plant

    SciTech Connect (OSTI)

    Boyd, G.J.; Lewis, S.R.; Summitt, R.L. [Safety and Reliability Optimization Services (SAROS), Inc., Knoxville, TN (United States)

    1991-12-31T23:59:59.000Z

    A probabilistic safety study of UF{sub 6} handling activities at the Portsmouth Gaseous Diffusion Plant has recently been completed. The analysis provides a unique perspective on the safety of UF{sub 6} handling activities. The estimated release frequencies provide an understanding of current risks, and the examination of individual contributors yields a ranking of important plant features and operations. Aside from the probabilistic results, however, there is an even more important benefit derived from a systematic modeling of all operations. The integrated approach employed in the analysis allows the interrelationships among the equipment and the required operations to be explored in depth. This paper summarizes the methods used in the study and provides an overview of some of the technical insights that were obtained. Specific areas of possible improvement in operations are described.

  7. Conceptual Design Report for the Remote-Handled Low-Level Waste Disposal Project

    SciTech Connect (OSTI)

    David Duncan

    2011-05-01T23:59:59.000Z

    This conceptual design report addresses development of replacement remote-handled low-level waste disposal capability for the Idaho National Laboratory. Current disposal capability at the Radioactive Waste Management Complex is planned until the facility is full or until it must be closed in preparation for final remediation (approximately at the end of Fiscal Year 2017). This conceptual design report includes key project assumptions; design options considered in development of the proposed onsite disposal facility (the highest ranked alternative for providing continued uninterrupted remote-handled low level waste disposal capability); process and facility descriptions; safety and environmental requirements that would apply to the proposed facility; and the proposed cost and schedule for funding, design, construction, and operation of the proposed onsite disposal facility.

  8. Conceptual Design Report for Remote-Handled Low-Level Waste Disposal Facility

    SciTech Connect (OSTI)

    Lisa Harvego; David Duncan; Joan Connolly; Margaret Hinman; Charles Marcinkiewicz; Gary Mecham

    2010-10-01T23:59:59.000Z

    This conceptual design report addresses development of replacement remote-handled low-level waste disposal capability for the Idaho National Laboratory. Current disposal capability at the Radioactive Waste Management Complex is planned until the facility is full or until it must be closed in preparation for final remediation (approximately at the end of Fiscal Year 2017). This conceptual design report includes key project assumptions; design options considered in development of the proposed onsite disposal facility (the highest ranked alternative for providing continued uninterrupted remote-handled low level waste disposal capability); process and facility descriptions; safety and environmental requirements that would apply to the proposed facility; and the proposed cost and schedule for funding, design, construction, and operation of the proposed onsite disposal facility.

  9. Conceptual Design Report for the Remote-Handled Low-Level Waste Disposal Project

    SciTech Connect (OSTI)

    Lisa Harvego; David Duncan; Joan Connolly; Margaret Hinman; Charles Marcinkiewicz; Gary Mecham

    2011-03-01T23:59:59.000Z

    This conceptual design report addresses development of replacement remote-handled low-level waste disposal capability for the Idaho National Laboratory. Current disposal capability at the Radioactive Waste Management Complex is planned until the facility is full or until it must be closed in preparation for final remediation (approximately at the end of Fiscal Year 2017). This conceptual design report includes key project assumptions; design options considered in development of the proposed onsite disposal facility (the highest ranked alternative for providing continued uninterrupted remote-handled low level waste disposal capability); process and facility descriptions; safety and environmental requirements that would apply to the proposed facility; and the proposed cost and schedule for funding, design, construction, and operation of the proposed onsite disposal facility.

  10. TITLE III EVALUATION REPORT FOR THE MATERIAL AND PERSONNEL HANDLING SYSTEM

    SciTech Connect (OSTI)

    T. A. Misiak

    1998-05-21T23:59:59.000Z

    This Title III Evaluation Report (TER) provides the results of an evaluation that was conducted on the Material and Personnel Handling System. This TER has been written in accordance with the ''Technical Document Preparation Plan for the Mined Geologic Disposal System Title III Evaluation Reports'' (BA0000000-01717-4600-00005 REV 03). The objective of this evaluation is to provide recommendations to ensure consistency between the technical baseline requirements, baseline design, and the as-constructed Material and Personnel Handling System. Recommendations for resolving discrepancies between the as-constructed system, the technical baseline requirements, and the baseline design are included in this report. Cost and Schedule estimates are provided for all recommended modifications.

  11. Fault detection in an air-handling unit using residual and recursive parameter identification methods

    SciTech Connect (OSTI)

    Lee, W.Y. [Korea Inst. of Energy Research, Taejon (Korea, Republic of); Park, C.; Kelly, G.E. [National Inst. of Standards and Technology, Gaithersburg, MD (United States)

    1996-11-01T23:59:59.000Z

    A scheme for detecting faults in an air-handling unit using residual and parameter identification methods is presented. Faults can be detected by comparing the normal or expected operating condition data with the abnormal, measured data using residuals. Faults can also be detected by examining unmeasurable parameter changes in a model of a controlled system using a system parameter identification technique. In this study, autoregressive moving average with exogenous input (ARMAX) and autoregressive with exogenous input (ARX) models with both single-input/single-output (SISO) and multi-input/single-output (MISO) structures are examined. Model parameters are determined using the Kalman filter recursive identification method. This approach is tested using experimental data from a laboratory`s variable-air-volume (VAV) air-handling unit operated with and without faults.

  12. Evaluation of the Total Cost of Ownership of Fuel Cell-Powered Material Handling Equipment

    SciTech Connect (OSTI)

    Ramsden, T.

    2013-04-01T23:59:59.000Z

    This report discusses an analysis of the total cost of ownership of fuel cell-powered and traditional battery-powered material handling equipment (MHE, or more typically 'forklifts'). A number of fuel cell MHE deployments have received funding support from the federal government. Using data from these government co-funded deployments, DOE's National Renewable Energy Laboratory (NREL) has been evaluating the performance of fuel cells in material handling applications. NREL has assessed the total cost of ownership of fuel cell MHE and compared it to the cost of ownership of traditional battery-powered MHE. As part of its cost of ownership assessment, NREL looked at a range of costs associated with MHE operation, including the capital costs of battery and fuel cell systems, the cost of supporting infrastructure, maintenance costs, warehouse space costs, and labor costs. Considering all these costs, NREL found that fuel cell MHE can have a lower overall cost of ownership than comparable battery-powered MHE.

  13. Elimination of ``memory`` from sample handling and inlet system of a mass spectrometer

    DOE Patents [OSTI]

    Chastgner, P.

    1991-05-08T23:59:59.000Z

    This paper describes a method for preparing the sample handling and inlet system of a mass spectrometer for analysis of a subsequent sample following analysis of a previous sample comprising the flushing of the system interior with supercritical CO{sub 2} and venting the interior. The method eliminates the effect of system ``memory`` on the subsequent analysis, especially following persistent samples such as xenon and krypton.

  14. Analysis of postharvest handling and marketing systems for vegetable production in East and Central Texas

    E-Print Network [OSTI]

    Vamosy, Margaret Laurain

    1985-01-01T23:59:59.000Z

    , and southern peas. Crops were harvested and sold an average of 5 months. Most farm operations included the participation of several family members and hired labor, and most used a variety of outlets to market their produce. A wide variety of postharvest... OF FIGURES INTRODUCTION AND REVIEW OF THE LITERATURE vi xiii Objectives of the Study Definition of Farming Systems Research Rationalization for Farming Systems Research Implications for a Study of Harvesting, Handling and Marketing Systems...

  15. Remote Handling Equipment for a High-Level Waste Waste Package Closure System

    SciTech Connect (OSTI)

    Kevin M. Croft; Scott M. Allen; Mark W. Borland

    2006-04-01T23:59:59.000Z

    High-level waste will be placed in sealed waste packages inside a shielded closure cell. The Idaho National Laboratory (INL) has designed a system for closing the waste packages including all cell interior equipment and support systems. This paper discusses the material handling aspects of the equipment used and operations that will take place as part of the waste package closure operations. Prior to construction, the cell and support system will be assembled in a full-scale mockup at INL.

  16. Reducing Building Energy Costs Using Optimized Operation Strategies for Constant Volume Air Handling Systems

    E-Print Network [OSTI]

    Liu, M.; Athar, A.; Reddy, A.; Claridge, D. E.; Haberl, J. S.; White, E.

    1994-01-01T23:59:59.000Z

    SDCVP 67.380 $153.200 $41.800 $195.000 $2.89 measured energy consumption for each building. The horizontal axis is the ambient temperature. The venical axis is the average daily energy consumption in MMBtulhr. Figure 5 compares the predicted...REDUCING BUILDING ENERGY COSTS USING OPTIMIZED OPERATION STRATEGIES FOR CONSTANT VOLUME AIR HANDLING SYSTEMS Mingsheng Liu, her Atha, Agarni Reddy Ed White David Claridge and Jeff Haberl Department of Physical Plant Texas A&M University...

  17. Remote Handled Transuranic Sludge Retrieval Transfer And Storage System At Hanford

    SciTech Connect (OSTI)

    Raymond, Rick E. [CH2M HILL Plateau Remediation Company, Richland, WA (United States); Frederickson, James R. [AREVA, Avignon (France); Criddle, James [AREVA, Avignon (France); Hamilton, Dennis [CH2M HILL Plateau Remediation Company, Richland, WA (United States); Johnson, Mike W. [CH2M HILL Plateau Remediation Company, Richland, WA (United States)

    2012-10-18T23:59:59.000Z

    This paper describes the systems developed for processing and interim storage of the sludge managed as remote-handled transuranic (RH-TRU). An experienced, integrated CH2M HILL/AFS team was formed to design and build systems to retrieve, interim store, and treat for disposal the K West Basin sludge, namely the Sludge Treatment Project (STP). A system has been designed and is being constructed for retrieval and interim storage, namely the Engineered Container Retrieval, Transfer and Storage System (ECRTS).

  18. Algorithms and Automated Material Handling Systems Design for Stacking 3D Irregular Stone Pieces

    E-Print Network [OSTI]

    Ko, Ming-Cheng

    2011-10-21T23:59:59.000Z

    ALGORITHMS AND AUTOMATED MATERIAL HANDLING SYSTEMS DESIGN FOR STACKING 3D IRREGULAR STONE PIECES A Thesis by MING-CHENG KO Submitted to the Office of Graduate Studies of Texas A&M University in partial fulfillment... Submitted to the Office of Graduate Studies of Texas A&M University in partial fulfillment of the requirements for the degree of MASTER OF SCIENCE Approved by: Chair of Committee, Sheng-Jen (?Tony?) Hsieh Committee Members, Sai C...

  19. Better Buildings Network View | April 2014 | Department of Energy

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

    April 2014 More Documents & Publications Better Buildings Network View | December 2014 Better Buildings Residential Network Orientation Better Buildings Network View | November...

  20. Better Buildings Network View | February 2014 | Department of...

    Energy Savers [EERE]

    February 2014 Better Buildings Network View | February 2014 The Better Buildings Network View monthly newsletter from the U.S. Department of Energy's Better Buildings Residential...

  1. Better Buildings Network View | January 2015 | Department of...

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

    5 More Documents & Publications Better Buildings Network View | December 2014 Better Buildings Network View | November 2014 Better Buildings Residential Network Orientation...

  2. Better Buildings Network View | June 2014 | Department of Energy

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

    June 2014 Better Buildings Network View | June 2014 The Better Buildings Network View monthly newsletter from the U.S. Department of Energy's Better Buildings Residential Network....

  3. Better Buildings Network View | March 2014 | Department of Energy

    Energy Savers [EERE]

    March 2014 Better Buildings Network View | March 2014 The Better Buildings Network View monthly newsletter from the U.S. Department of Energy's Better Buildings Residential...

  4. Better Buildings Network View | December 2014 | Department of...

    Energy Savers [EERE]

    December 2014 Better Buildings Network View | December 2014 The Better Buildings Network View monthly newsletter from the U.S. Department of Energy's Better Buildings Residential...

  5. Better Buildings Network View | January 2014 | Department of...

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

    4 Better Buildings Network View | January 2014 The Better Buildings Network View monthly newsletter from the U.S. Department of Energy's Better Buildings Residential Network....

  6. Better Buildings Network View | October 2014 | Department of...

    Energy Savers [EERE]

    October 2014 Better Buildings Network View | October 2014 The Better Buildings Network View monthly newsletter from the U.S. Department of Energy's Better Buildings Residential...

  7. Better Buildings Network View | February 2015 | Department of...

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

    5 More Documents & Publications Better Buildings Network View | November 2014 Better Buildings Network View | September 2014 Better Buildings Residential Network Case Study:...

  8. Residential Windows and Window Coverings: A Detailed View of...

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

    Residential Windows and Window Coverings: A Detailed View of the Installed Base and User Behavior Residential Windows and Window Coverings: A Detailed View of the Installed Base...

  9. Benchmarking the Remote-Handled Waste Facility at the West Valley Demonstration Project

    SciTech Connect (OSTI)

    O. P. Mendiratta; D. K. Ploetz

    2000-02-29T23:59:59.000Z

    ABSTRACT Facility decontamination activities at the West Valley Demonstration Project (WVDP), the site of a former commercial nuclear spent fuel reprocessing facility near Buffalo, New York, have resulted in the removal of radioactive waste. Due to high dose and/or high contamination levels of this waste, it needs to be handled remotely for processing and repackaging into transport/disposal-ready containers. An initial conceptual design for a Remote-Handled Waste Facility (RHWF), completed in June 1998, was estimated to cost $55 million and take 11 years to process the waste. Benchmarking the RHWF with other facilities around the world, completed in November 1998, identified unique facility design features and innovative waste pro-cessing methods. Incorporation of the benchmarking effort has led to a smaller yet fully functional, $31 million facility. To distinguish it from the June 1998 version, the revised design is called the Rescoped Remote-Handled Waste Facility (RRHWF) in this topical report. The conceptual design for the RRHWF was completed in June 1999. A design-build contract was approved by the Department of Energy in September 1999.

  10. METHODS FOR THE SAFE STORAGE, HANDLING, AND DISPOSAL OF PYROPHORIC LIQUIDS AND SOLIDS IN THE LABORATORY

    SciTech Connect (OSTI)

    Simmons, F.; Kuntamukkula, M.; Alnajjar, M.; Quigley, D.; Freshwater, D.; Bigger, S.

    2010-02-02T23:59:59.000Z

    Pyrophoric reagents represent an important class of reactants because they can participate in many different types of reactions. They are very useful in organic synthesis and in industrial applications. The Occupational Safety and Health Administration (OSHA) and the National Fire Protection Association (NFPA) define Pyrophorics as substances that will self-ignite in air at temperatures of 130 F (54.4 C) or less. However, the U.S. Department of Transportation (DOT) uses criteria different from the auto-ignition temperature criterion. The DOT defines a pyrophoric material as a liquid or solid that, even in small quantities and without an external ignition source, can ignite within five minutes after coming in contact with air when tested according to the United Nations Manual of Tests and Criteria. The Environmental Protection Agency has adopted the DOT definition. Regardless of which definition is used, oxidation of the pyrophoric reagents by oxygen or exothermic reactions with moisture in the air (resulting in the generation of a flammable gas such as hydrogen) is so rapid that ignition occurs spontaneously. Due to the inherent nature of pyrophoric substances to ignite spontaneously upon exposure to air, special precautions must be taken to ensure their safe handling and use. Pyrophoric gases (such as diborane, dichloroborane, phosphine, etc.) are typically the easiest class of pyrophoric substances to handle since the gas can be plumbed directly to the application and used remotely. Pyrophoric solids and liquids, however, require the user to physically manipulate them when transferring them from one container to another. Failure to follow proper safety precautions could result in serious injury or unintended consequences to laboratory personnel. Because of this danger, pyrophorics should be handled only by experienced personnel. Users with limited experience must be trained on how to handle pyrophoric reagents and consult with a knowledgeable staff member prior to performing the experimental task. The purpose of this article is three fold: (1) to provide guidelines and general safety precautions to avoid accidents, (2) describe proper techniques on how to successfully handle, store, and dispose of pyrophoric liquids and solids, and (3) illustrate best practices for working with this class of reactants in a laboratory environment.

  11. Mission Need Statement for the Idaho National Laboratory Remote-Handled Low-Level Waste Disposal Project

    SciTech Connect (OSTI)

    Lisa Harvego

    2009-06-01T23:59:59.000Z

    The Idaho National Laboratory proposes to establish replacement remote-handled low-level waste disposal capability to meet Nuclear Energy and Naval Reactors mission-critical, remote-handled low-level waste disposal needs beyond planned cessation of existing disposal capability at the end of Fiscal Year 2015. Remote-handled low-level waste is generated from nuclear programs conducted at the Idaho National Laboratory, including spent nuclear fuel handling and operations at the Naval Reactors Facility and operations at the Advanced Test Reactor. Remote-handled low-level waste also will be generated by new programs and from segregation and treatment (as necessary) of remote-handled scrap and waste currently stored in the Radioactive Scrap and Waste Facility at the Materials and Fuels Complex. Replacement disposal capability must be in place by Fiscal Year 2016 to support uninterrupted Idaho operations. This mission need statement provides the basis for the laboratory’s recommendation to the Department of Energy to proceed with establishing the replacement remote-handled low-level waste disposal capability, project assumptions and constraints, and preliminary cost and schedule information for developing the proposed capability. Without continued remote-handled low-level waste disposal capability, Department of Energy missions at the Idaho National Laboratory would be jeopardized, including operations at the Naval Reactors Facility that are critical to effective execution of the Naval Nuclear Propulsion Program and national security. Remote-handled low-level waste disposal capability is also critical to the Department of Energy’s ability to meet obligations with the State of Idaho.

  12. Figure 1. Elevation View of TPX Core including IR TV locations and view of plasma

    E-Print Network [OSTI]

    stabilizer plates PPPL-3130 - Preprint Date: August 1995 TPX Diagnostics for Tokamak Operation, Plasma. First plasma is scheduled for mid-2001. Diagnostics are required for real time plasma control, physicsFigure 1. Elevation View of TPX Core including IR TV locations and view of plasma through

  13. Assessment of Biasi and Columbia University CHF correlations with GE 3x3 rod bundle experiment. [PWR; BWR

    SciTech Connect (OSTI)

    Chen, B.C.J.; Chien, T.H.; Sha, W.T.; Kim, J.H.

    1984-01-01T23:59:59.000Z

    The critical heat flux (CHF), at which a sudden degradation of heat transfer occurs without corresponding decrease in heat generation, is one of the limiting parameters for safe operation of nuclear reactors. Reactor operation beyond the CHF causes a rapid rise in fuel cladding temperature and thus should be avoided to maintain the fuel element integrity. Reactor power limits are therefore set so that a prescribed safety margin below the CHF is maintained. Two CHF correlations are evaluated for reactor core thermal hydraulic analysis: the Biasi correlation and the Columbia University correlation. The BODYFIT-2PE computer code is used for this assessment. The CHF predicted by the BODYFIT-2PE using the two correlations is compared with GE 3x3 rod bundle CHF experiment.

  14. Air/water subchannel measurements of the equilibrium quality and mass-flux distribution in a rod bundle. [BWR

    SciTech Connect (OSTI)

    Sterner, R.W.; Lahey, R.T. Jr.

    1983-07-01T23:59:59.000Z

    Subchannel measurements were performed in order to determine the equilibrium quality and mass flux distribution in a four rod bundle, using air/water flow. An isokinetic technique was used to sample the flow in the center, side and corner subchannels of this test section. Flow rates of the air and water in each sampled subchannel were measured. Experiments were performed for two test-section-average mass fluxes (0.333x10/sup 6/ and 0.666x10/sup 6/ lb/sub m//h-ft/sup 2/), and the test-section-average quality was varied from 0% to 0.54% for each mass flux. Single-phase liquid, bubbly, slug and churn-turbulent two-phase flow regimes were achieved. The observed data trends agreed with previous diabatic measurements in which the center subchannel had the highest quality and mass flux, while the corner subchannel had the lowest.

  15. BLUE VIEW VISION INSIGHT! Good news--your vision plan

    E-Print Network [OSTI]

    California at Santa Cruz, University of

    WELCOME TO BLUE VIEW VISION INSIGHT! Good news--your vision plan is flexible and easy to use, your discounts, and much more! Blue View Vision InsightSM University of California Student Health Insurance Plan (UC SHIP) 2013/14 Your Blue View Vision Insight Network Blue View Vision Insight offers you

  16. BLUE VIEW VISION INSIGHT! Good news--your vision plan

    E-Print Network [OSTI]

    Barrett, Jeffrey A.

    WELCOME TO BLUE VIEW VISION INSIGHT! Good news--your vision plan is flexible and easy to use, your discounts, and much more! Blue View Vision InsightSM University of California Student Health Insurance Plan (UC SHIP) 2012/13 Your Blue View Vision Insight Network Blue View Vision Insight offers you

  17. NEWS & VIEWS Radiation SouRCES

    E-Print Network [OSTI]

    Loss, Daniel

    NEWS & VIEWS Radiation SouRCES Electrons and lasers sing THz tune gwyn P. Williams is in the Free Bielawski and colleagues describe the ability to coherently control the radiative behaviour of the electrons a bright, tunable source of radiation in the difficult-to-reach terahertz region of the electromagnetic

  18. Friction in full view A. P. Merklea

    E-Print Network [OSTI]

    Marks, Laurence D.

    Friction in full view A. P. Merklea and L. D. Marksb Materials Science and Engineering proposed friction mechanisms explaining the unique tribological properties of graphite. Wear of graphite chemical or struc- tural information from the interface during a friction experi- ment. Examples

  19. INVESTIGATION Retrospective View of North American Potato

    E-Print Network [OSTI]

    Douches, David S.

    INVESTIGATION Retrospective View of North American Potato (Solanum tuberosum L.) Breeding in the 20, Madison, Wisconsin, 53706 ABSTRACT Cultivated potato (Solanum tuberosum L.), a vegetatively propagated explore the effects of potato breeding at the genome level, we used 8303 single-nucleotide polymorphism

  20. Project Title: Older People's View of

    E-Print Network [OSTI]

    Hickman, Mark

    /AGECONCERN/10/NP Age Concern Canterbury provides support for older people, many of whom face loneliness, lowProject Title: Older People's View of Community Support Bachelor of Arts Internship Company information, support and advocacy, to enable older people in Canterbury to have real choices". (http

  1. Year in Review 2007 GoddardView

    E-Print Network [OSTI]

    Christian, Eric

    Year in Review 2007 GoddardView National Aeronautics and Space Administration www.nasa.gov Volume 4, to stunning images from the highest-resolution satellite data products ever realized, to a visit from Security staff did a marvelous job in planning and coordinating the efforts of at least six different

  2. Global Food Security Programme Exploring public views

    E-Print Network [OSTI]

    Global Food Security Programme ­ Exploring public views #12;©TNS June 2012 -1- Executive Summary significant public policy issues of this century. This scoping study for the Global Food Security programme. The project involved a total of 44 people in a two stage workshop process in London, Edinburgh and Aberystwyth

  3. Evolution of self-incompatibility: Early Views

    E-Print Network [OSTI]

    Bhattacharyya, Madan Kumar

    Evolution of self-incompatibility: Early Views: Whitehouse (1950): 1. Sudden rise of angiosperms by Whitehouse (1950). Isolation of components of the self-incompatibilities paved the way to study the evolution of SIs Matton et al. (1994): Molecular data supports Bateman. Three self-incompatibility systems

  4. Oak Ridge National Laboratory contact-handled Transuranic Waste Certification Program plan

    SciTech Connect (OSTI)

    Smith, J.H.; Smith, M.A.

    1990-08-01T23:59:59.000Z

    The Oak Ridge National Laboratory (ORNL) is required by Department of Energy (DOE) Order 5820.2A to package its transuranic (TRU) waste to comply with waste acceptance criteria (WAC) for the Waste Isolation Pilot Plant (WIPP). TRU wastes are defined in DOE Order 5820.A as those radioactive wastes that are contaminated with alpha-emitting transuranium radionuclides having half-lives greater than 20 years and concentrations greater than 100 nCi/g at the time of the assay. In addition, ORNL handles U{sup 233}, Cm{sup 244}, and Cf{sup 252} as TRU waste radionuclides. The ORNL Transuranic Waste Certification Program was established to ensure that all TRU waste at ORNL is packaged to meet the required transportation and storage criteria for shipping to and storage at the WIPP. The objective of this document is to describe the methods that will be used at ORNL to package contact handled-transuranic (CH-TRU) waste to meet the criteria set forth in the WIPP certification requirements documents. This document addresses newly generated (NG) CH-TRU waste. Stored CH-TRU will be repackaged. This document is organized to provide a brief overview of waste generation operations at ORNL, along with details on data management for CH-TRU waste. The methods used to implement this plan are discussed briefly along with the responsibilities and authorities of applicable organizations. Techniques used for waste data collection, records control, and data archiving are defined. Procedures for the procurement and handling of waste containers are also described along with related quality control methods. 11 refs., 3 figs.

  5. Joint Working Group-39, Manufacturing Technology Subworking Group-F, remote handling and automation

    SciTech Connect (OSTI)

    Merrill, R.D.

    1995-02-01T23:59:59.000Z

    The terms of reference were reviewed and continue to encompass the scope of activities of the SUBWOG. No revisions to the terms of reference were proposed. The list of site contacts who should receive copies of SUBWOG correspondence and meeting minutes was reviewed and updated. Documents exchanged related to the meeting include: Minutes of the sixth SUBOG 39F meeting; transactions of the fifth topical meeting on robotics and remote handling; data on manipulators was forwarded to LLNL from the robotics group at AEA Harwell; and the specifications of the duct remediation robot from the Rocky Flats Plant.

  6. Overview of Remote Handling Equipment Used for the NPP A1 Decommissioning - 12141

    SciTech Connect (OSTI)

    Kravarik, K.; Medved, J.; Pekar, A.; Stubna, M. [VUJE, Inc., Okruzna 5, 918 64 Trnava (Slovakia); Michal, V. [IAEA, Wagramer Strasse 5, P.O.Box 100, A-1400 Vienna (Austria); Vargovcik, L. [ZTS VVU Kosice, Inc., Juzna Trieda 95, 041 24 Kosice (Slovakia)

    2012-07-01T23:59:59.000Z

    The first Czechoslovak NPP A1 was in operation from 1972 to 1977 and it was finally shutdown due to an accident (level 4 according to the INES). The presence of radioactive, toxic or hazardous materials limits personnel access to facilities and therefore it is necessary to use remote handling technologies for some most difficult characterization, retrieval, decontamination and dismantling tasks. The history of remote handling technologies utilization started in nineties when the spent nuclear fuel, including those fuel assemblies damaged during the accident, was prepared for the transport to Russia. Subsequent significant development of remote handling equipment continued during implementation of the NPP A1 decommissioning project - Stage I and ongoing Stage II. Company VUJE, Inc. is the general contractor for both mentioned stages of the decommissioning project. Various remote handling manipulators and robotics arms were developed and used. It includes remotely controlled vehicle manipulator MT-15 used for characterisation tasks in hostile and radioactive environment, special robust manipulator DENAR-41 used for the decontamination of underground storage tanks and multi-purposes robotics arms MT-80 and MT-80A developed for variety of decontamination and dismantling tasks. The heavy water evaporator facility dismantling is the current task performed remotely by robotics arm MT-80. The heavy water evaporator is located inside the main production building in the room No. 220 where loose surface contamination varies from 10 Bq/cm{sup 2} to 1x10{sup 3} Bq/cm{sup 2}, dose rate is up to 1.5 mGy/h and the feeding pipeline contained liquid RAW with high tritium content. Presented manipulators have been designed for broad range of decommissioning tasks. They are used for recognition, sampling, waste retrieval from large underground tanks, decontamination and dismantling of technological equipments. Each of the mentioned fields claims specific requirements on design of manipulator, their operation and control systems as well as tools of manipulators. Precise planning of decontamination and dismantling tasks is necessary for its successful performance by remotely controlled manipulator. The example of the heavy water evaporator demonstrates typical procedure for decommissioning of contaminated technological equipment by remotely controlled manipulators - planning of decommissioning tasks, preparatory tasks, modification of applied tools and design of specific supporting constructions for manipulator and finally decontamination and dismantling themselves. Due to the particularly demanding conditions in highly contaminated A1 NPP, a team of experts with special know-how in the field of decommissioning has grown up, and unique technological equipment enabling effective and safe work in environment with a high radiation level has been developed. (authors)

  7. Preliminary Project Execution Plan for the Remote-Handled Low-Level Waste Disposal Project

    SciTech Connect (OSTI)

    David Duncan

    2011-05-01T23:59:59.000Z

    This preliminary project execution plan (PEP) defines U.S. Department of Energy (DOE) project objectives, roles and responsibilities of project participants, project organization, and controls to effectively manage acquisition of capital funds for construction of a proposed remote-handled low-level waste (LLW) disposal facility at the Idaho National Laboratory (INL). The plan addresses the policies, requirements, and critical decision (CD) responsibilities identified in DOE Order 413.3B, 'Program and Project Management for the Acquisition of Capital Assets.' This plan is intended to be a 'living document' that will be periodically updated as the project progresses through the CD process to construction and turnover for operation.

  8. Conceptual design report, plutonium stabilization and handling,project W-460

    SciTech Connect (OSTI)

    Weiss, E.V.

    1997-03-06T23:59:59.000Z

    Project W-460, Plutonium Stabilization and Handling, encompasses procurement and installation of a Stabilization and Packaging System (SPS) to oxidize and package for long term storage remaining plutonium-bearing special nuclear materials currently in inventory at the Plutonium Finishing Plant (PFP), and modification of vault equipment to allow storage of resulting packages of stabilized SNM for up to fifty years. This Conceptual Design Report (CDR) provides conceptual design details for the vault modification, site preparation and site interface with the purchased SPS. Two concepts are described for vault configuration; acceleration of this phase of the project did not allow completion of analysis which would clearly identify a preferred approach.

  9. HANDLING MISSING ATTRIBUTE VALUES IN DECISION TABLES USING VALUED TOLERANCE APPROACH

    E-Print Network [OSTI]

    Vasudevan, Supriya

    2008-01-01T23:59:59.000Z

    using the lower and upper approximations. The set that separates the lower and the upper approximation is the boundary region for the rough set. The main advantage of rough set theory is that it does not require any additional information about data... by the algorithm (MLEM2 or valued tolerance) and computes the error rate. Two rule checkers are used namely, ?srch? and ?chkrul?. The rule checker ?srch? is used to convert the rules according to the LERS format since it does not handle missing attribute values...

  10. Under-sodium viewing technology for improvement of fast-reactor safeguards

    SciTech Connect (OSTI)

    Beddingfield, David H [Los Alamos National Laboratory; Gerhart, Jeremy J [Los Alamos National Laboratory; Kawakubo, Yoko [JAEA

    2009-01-01T23:59:59.000Z

    The current safeguards approach for fast reactors relies exclusively on maintenance of continuity of knowledge to track the movement of fuel assemblies through these facilities. The remote handling of fuel assemblies, the visual opacity of the liquid metal coolant. and the chemical reactivity of sodium all combine and result in significant limitations on the available options to verify fuel assembly identification numbers or the integrity of these assemblies. These limitations also serve to frustrate attempts to restore the continuity-of-knowledge in instances where the information is under a variety of scenarios. The technology of ultrasonic under-sodium viewing offers new options to the safeguards community for recovering continuity-of-knowledge and applying more traditional item accountancy to fast reactor facilities. We have performed a literature review to investigate the development of under-sodium viewing technologies. In this paper we will summarize our findings and report the state of development of this technology and we will present possible applications to the fast reactor system to improve the existing safeguards approach at these reactors and in future fast reactors.

  11. Preliminary Dynamic Siol-Structure-Interaction Analysis for the Waste Handling Building

    SciTech Connect (OSTI)

    G. Wagenblast

    2000-05-01T23:59:59.000Z

    The objective of this analysis package is to document a preliminary dynamic seismic evaluation of a simplified design concept of the Wade Handling Building (WHB). Preliminary seismic ground motions and soil data will be used. Loading criteria of the WHB System Design Description will be used. Detail design of structural members will not be performed.. The results of the analysis will be used to determine preliminary sizes of structural concrete and steel members and to determine whether the seismic response of the structure is within an acceptable level for future License Application design of safety related facilities. In order to complete this preliminary dynamic evaluation to meet the Site Recommendation (SR) schedule, the building configuration was ''frozen in time'' as the conceptual design existed in October 1999. Modular design features and dry or wet waste storage features were intentionally excluded from this preliminary dynamic seismic evaluation. The document was prepared in accordance with the Development Plan for the ''Preliminary/Dynamic Soil Structure Interaction Analysis for the Waste Handling Building'' (CRWMS M&O 2000b), which was completed, in accordance with AP-2.13Q, ''Technical Product Development Planning''.

  12. Safety Design Strategy for the Remote Handled Low-Level Waste Disposal Project

    SciTech Connect (OSTI)

    Gary Mecham

    2010-05-01T23:59:59.000Z

    In accordance with the requirements of U.S. Department of Energy (DOE) Order 413.3A, “Program and Project Management for the Acquisition of Capital Assets,” safety must be integrated into the design process for new or major modifications to DOE Hazard Category 1, 2, and 3 nuclear facilities. The intended purpose of this requirement involves the handling of hazardous materials, both radiological and chemical, in a way that provides adequate protection to the public, workers, and the environment. Requirements provided in DOE Order 413.3A and DOE Order 420.1B, “Facility Safety,” and the expectations of DOE-STD-1189-2008, “Integration of Safety into the Design Process,” provide for identification of hazards early in the project and use of an integrated team approach to design safety into the facility. This safety design strategy provides the basic safety-in-design principles and concepts that will be used for the Remote-Handled Low-Level Waste Disposal Project.

  13. Safety Design Strategy for the Remote Handled Low-Level Waste Disposal Project

    SciTech Connect (OSTI)

    Boyd D. Chirstensen

    2012-08-01T23:59:59.000Z

    In accordance with the requirements of U.S. Department of Energy (DOE) Order 413.3A, “Program and Project Management for the Acquisition of Capital Assets,” safety must be integrated into the design process for new or major modifications to DOE Hazard Category 1, 2, and 3 nuclear facilities. The intended purpose of this requirement involves the handling of hazardous materials, both radiological and chemical, in a way that provides adequate protection to the public, workers, and the environment. Requirements provided in DOE Order 413.3A and DOE Order 420.1B, “Facility Safety,” and the expectations of DOE-STD-1189-2008, “Integration of Safety into the Design Process,” provide for identification of hazards early in the project and use of an integrated team approach to design safety into the facility. This safety design strategy provides the basic safety-in-design principles and concepts that will be used for the Remote-Handled Low-Level Waste Disposal Project.

  14. Safety Design Strategy for the Remote Handled Low-Level Waste Disposal Project

    SciTech Connect (OSTI)

    Gary Mecham

    2010-10-01T23:59:59.000Z

    In accordance with the requirements of U.S. Department of Energy (DOE) Order 413.3A, “Program and Project Management for the Acquisition of Capital Assets,” safety must be integrated into the design process for new or major modifications to DOE Hazard Category 1, 2, and 3 nuclear facilities. The intended purpose of this requirement involves the handling of hazardous materials, both radiological and chemical, in a way that provides adequate protection to the public, workers, and the environment. Requirements provided in DOE Order 413.3A and DOE Order 420.1B, “Facility Safety,” and the expectations of DOE-STD-1189-2008, “Integration of Safety into the Design Process,” provide for identification of hazards early in the project and use of an integrated team approach to design safety into the facility. This safety design strategy provides the basic safety-in-design principles and concepts that will be used for the Remote-Handled Low-Level Waste Disposal Project.

  15. Safety Design Strategy for the Remote Handled Low-Level Waste Disposal Project

    SciTech Connect (OSTI)

    Boyd D. Chirstensen

    2012-04-01T23:59:59.000Z

    In accordance with the requirements of U.S. Department of Energy (DOE) Order 413.3A, “Program and Project Management for the Acquisition of Capital Assets,” safety must be integrated into the design process for new or major modifications to DOE Hazard Category 1, 2, and 3 nuclear facilities. The intended purpose of this requirement involves the handling of hazardous materials, both radiological and chemical, in a way that provides adequate protection to the public, workers, and the environment. Requirements provided in DOE Order 413.3A and DOE Order 420.1B, “Facility Safety,” and the expectations of DOE-STD-1189-2008, “Integration of Safety into the Design Process,” provide for identification of hazards early in the project and use of an integrated team approach to design safety into the facility. This safety design strategy provides the basic safety-in-design principles and concepts that will be used for the Remote-Handled Low-Level Waste Disposal Project.

  16. Safety Design Strategy for the Remote Handled Low-Level Waste Disposal Project

    SciTech Connect (OSTI)

    Gary Mecham

    2009-10-01T23:59:59.000Z

    In accordance with the requirements of U.S. Department of Energy (DOE) Order 413.3A, “Program and Project Management for the Acquisition of Capital Assets,” safety must be integrated into the design process for new or major modifications to DOE Hazard Category 1, 2, and 3 nuclear facilities. The intended purpose of this requirement involves the handling of hazardous materials, both radiological and chemical, in a way that provides adequate protection to the public, workers, and the environment. Requirements provided in DOE Order 413.3A and DOE Order 420.1B, “Facility Safety,” and the expectations of DOE-STD-1189-2008, “Integration of Safety into the Design Process,” provide for identification of hazards early in the project and use of an integrated team approach to design safety into the facility. This safety design strategy provides the basic safety-in-design principles and concepts that will be used for the Remote-Handled Low-Level Waste Disposal Project.

  17. A Globally Distributed System for Job, Data, and Information Handling for High Energy Physics

    SciTech Connect (OSTI)

    Garzoglio, Gabriele; /DePaul U.; ,

    2005-12-01T23:59:59.000Z

    The computing infrastructures of the modern high energy physics experiments need to address an unprecedented set of requirements. The collaborations consist of hundreds of members from dozens of institutions around the world and the computing power necessary to analyze the data produced surpasses already the capabilities of any single computing center. A software infrastructure capable of seamlessly integrating dozens of computing centers around the world, enabling computing for a large and dynamical group of users, is of fundamental importance for the production of scientific results. Such a computing infrastructure is called a computational grid. The SAM-Grid offers a solution to these problems for CDF and DZero, two of the largest high energy physics experiments in the world, running at Fermilab. The SAM-Grid integrates standard grid middleware, such as Condor-G and the Globus Toolkit, with software developed at Fermilab, organizing the system in three major components: data handling, job handling, and information management. This dissertation presents the challenges and the solutions provided in such a computing infrastructure.

  18. Update on intrusive characterization of mixed contact-handled transuranic waste at Argonne-West

    SciTech Connect (OSTI)

    Dwight, C.C.; Jensen, B.A.; Bryngelson, C.D.; Duncan, D.S.

    1997-02-03T23:59:59.000Z

    Argonne National Laboratory and Lockheed Martin Idaho Technologies Company have jointly participated in the Department of Energy`s (DOE) Waste Isolation Pilot Plant (WIPP) Transuranic Waste Characterization Program since 1990. Intrusive examinations have been conducted in the Waste Characterization Area, located at Argonne-West in Idaho Falls, Idaho, on over 200 drums of mixed contact-handled transuranic waste. This is double the number of drums characterized since the last update at the 1995 Waste Management Conference. These examinations have provided waste characterization information that supports performance assessment of WIPP and that supports Lockheed`s compliance with the Resource Conservation and Recovery Act. Operating philosophies and corresponding regulatory permits have been broadened to provide greater flexibility and capability for waste characterization, such as the provision for minor treatments like absorption, neutralization, stabilization, and amalgamation. This paper provides an update on Argonne`s intrusive characterization permits, procedures, results, and lessons learned. Other DOE sites that must deal with mixed contact-handled transuranic waste have initiated detailed planning for characterization of their own waste. The information presented herein could aid these other storage and generator sites in further development of their characterization efforts.

  19. A review of polymer-based water conditioners for reduction of handling-related injury

    SciTech Connect (OSTI)

    Harnish, Ryan A.; Colotelo, Alison HA; Brown, Richard S.

    2011-01-01T23:59:59.000Z

    Fish are coated with an external layer of protective mucus. This layer serves as the primary barrier against infection or injury, reduces friction, and plays a role in ionic and osmotic regulation. However, the mucus layer is easily disturbed when fish are netted, handled, transported, stressed, or subjected to adverse water conditions. Water additives containing polyvinylpyrrolidone (PVP) or proprietary polymers have been used to prevent the deleterious effects of mucus layer disturbances in the commercial tropical fish industry, aquaculture, and for other fisheries management purposes. This paper reviews research on the effectiveness of water conditioners, and examines the contents and uses of a wide variety of commercially available water conditioners. Water conditioners containing polymers may reduce external damage to fish held in containers during scientific experimentation, including surgical implantation of electronic tags. However, there is a need to empirically test the effectiveness of water conditioners at preventing damage to and promoting healing of the mucus layer. A research agenda is provided to advance the science related to the use of water conditions to improve the condition of fish during handling and tagging.

  20. An Alternative to Performing Remote-Handled Transuranic Waste Container Headspace Gas Sampling and Analysis

    SciTech Connect (OSTI)

    Spangler, L. R.; Djordjevic, S. M.; Kehrman, R. F.; Most, W. A.

    2002-02-26T23:59:59.000Z

    The Waste Isolation Pilot Plant (WIPP) is operating under a Resource Conservation and Recovery Act (RCRA) Hazardous Waste Facility Permit (HWFP) for contact-handled (CH) transuranic (TRU) waste. The HWFP contains limitations on allowable emissions from waste disposed in the underground. This environmental performance standard imposed on the WIPP consists of limiting volatile organic compound (VOC) emissions from emplaced waste to ensure protection of human health and the environment. The standard is currently met by tracking individual waste container headspace gas concentrations, which are determined by headspace gas sampling and analysis of CH TRU waste containers. The WIPP is seeking a HWFP modification to allow the disposal of remote-handled (RH) TRU waste. Because RH TRU waste is limited to approximately 5% of the waste volume and is emplaced in the disposal room walls, it is possible to bound the potential RH TRU waste contribution to VOC emissions using conservative upper bounds. These conservative upper bounds were developed as an alternative to RH TRU waste canister headspace gas sampling and analysis. The methodology used to perform the calculations used to evaluate VOC emissions from emplaced RH TRU waste canisters applied the same equations as those used to evaluate VOC emissions in the original HWFP application.

  1. Nuclear reactor fuel assembly duct-tube-to-handling-socket attachment system

    DOE Patents [OSTI]

    Christiansen, David W. (Kennewick, WA); Smith, Bob G. (Kennewick, WA)

    1982-01-01T23:59:59.000Z

    A reusable system for removably attaching the upper end 10of a nuclear reactor duct tube to the lower end 30 of a nuclear reactor fuel assembly handling socket. A transition ring 20, fixed to the duct tube's upper end 10, has an interior-threaded section 22 with a first locking hole segment 24. An adaptor ring 40, fixed to the handling socket's lower end 30 has an outside-threaded section 42 with a second locking hole segment 44. The inside 22 and outside 42 threaded sections match and can be joined so that the first 24 and second 44 locking hole segments can be aligned to form a locking hole. A locking ring 50, with a locking pin 52, slides over the adaptor ring 40 so that the locking pin 52 fits in the locking hole. A swage lock 60 or a cantilever finger lock 70 is formed from the locking cup collar 26 to fit in a matching groove 54 or 56 in the locking ring 50 to prevent the locking ring's locking pin 52 from backing out of the locking hole.

  2. Remote Handled TRU Waste Status and Activities and Challenges at the Hanford Site

    SciTech Connect (OSTI)

    MCKENNEY, D.E.

    2000-02-01T23:59:59.000Z

    A significant portion of the Department of Energy's forecast volume of remote-handled (RH) transuranic (TRU) waste will originate from the Hanford Site. The forecasted Hanford RH-TRU waste volume of over 2000 cubic meters may constitute over one-third of the forecast inventory of RH-TRU destined for disposal at the Waste Isolation Pilot Plant (WIPP). To date, the Hanford TRU waste program has focused on the retrieval, treatment and certification of the contact-handled transuranic (CH-TRU) wastes. This near-term focus on CH-TRU is consistent with the National TRU Program plans and capabilities. The first shipment of CH-TRU waste from Hanford to the WIPP is scheduled early in Calendar Year 2000. Shipments of RH-TRU from Hanford to the WIPP are scheduled to begin in Fiscal Year 2006 per the National TRU Waste Management Plan. This schedule has been incorporated into milestones within the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement). These Tri-Party milestones (designated the ''M-91'' series of milestones) relate to development of project management plans, completion of design efforts, construction and contracting schedules, and initiation of process operations. The milestone allows for modification of an existing facility, construction of a new facility, and/or commercial contracting to provide the capabilities for processing and certification of RH-TRU wastes for disposal at the WIPP. The development of a Project Management Plan (PMP) for TRU waste is the first significant step in the development of a program for disposal of Hanford's RH-TRU waste. This PMP will address the path forward for disposition of waste streams that cannot be prepared for disposal in the Hanford Waste Receiving and Processing facility (a contact-handled, small container facility) or other Site facilities. The PMP development effort has been initiated, and the PMP will be provided to the regulators for their approval by June 30, 2000. This plan will detail the path forward for the Hanford RH-TRU program.

  3. Evaluation of a New Remote Handling Design for High Throughput Annular Centrifugal Contactors

    SciTech Connect (OSTI)

    David H. Meikrantz; Troy G. Garn; Jack D. Law; Lawrence L. Macaluso

    2009-09-01T23:59:59.000Z

    Advanced designs of nuclear fuel recycling plants are expected to include more ambitious goals for aqueous based separations including; higher separations efficiency, high-level waste minimization, and a greater focus on continuous processes to minimize cost and footprint. Therefore, Annular Centrifugal Contactors (ACCs) are destined to play a more important role for such future processing schemes. Previous efforts defined and characterized the performance of commercial 5 cm and 12.5 cm single-stage ACCs in a “cold” environment. The next logical step, the design and evaluation of remote capable pilot scale ACCs in a “hot” or radioactive environment was reported earlier. This report includes the development of remote designs for ACCs that can process the large throughput rates needed in future nuclear fuel recycling plants. Novel designs were developed for the remote interconnection of contactor units, clean-in-place and drain connections, and a new solids removal collection chamber. A three stage, 12.5 cm diameter rotor module has been constructed and evaluated for operational function and remote handling in highly radioactive environments. This design is scalable to commercial CINC ACC models from V-05 to V-20 with total throughput rates ranging from 20 to 650 liters per minute. The V-05R three stage prototype was manufactured by the commercial vendor for ACCs in the U.S., CINC mfg. It employs three standard V-05 clean-in-place (CIP) units modified for remote service and replacement via new methods of connection for solution inlets, outlets, drain and CIP. Hydraulic testing and functional checks were successfully conducted and then the prototype was evaluated for remote handling and maintenance suitability. Removal and replacement of the center position V-05R ACC unit in the three stage prototype was demonstrated using an overhead rail mounted PaR manipulator. This evaluation confirmed the efficacy of this innovative design for interconnecting and cleaning individual stages while retaining the benefits of commercially reliable ACC equipment for remote applications in the nuclear industry. Minor modifications and suggestions for improved manual remote servicing by the remote handling specialists were provided but successful removal and replacement was demonstrated in the first prototype.

  4. ENVIRONMENTAL SAMPLING USING LOCATION SPECIFIC AIR MONITORING IN BULK HANDLING FACILITIES

    SciTech Connect (OSTI)

    Sexton, L.; Hanks, D.; Degange, J.; Brant, H.; Hall, G.; Cable-Dunlap, P.; Anderson, B.

    2011-06-07T23:59:59.000Z

    Since the introduction of safeguards strengthening measures approved by the International Atomic Energy Agency (IAEA) Board of Governors (1992-1997), international nuclear safeguards inspectors have been able to utilize environmental sampling (ES) (e.g. deposited particulates, air, water, vegetation, sediments, soil and biota) in their safeguarding approaches at bulk uranium/plutonium handling facilities. Enhancements of environmental sampling techniques used by the IAEA in drawing conclusions concerning the absence of undeclared nuclear materials or activities will soon be able to take advantage of a recent step change improvement in the gathering and analysis of air samples at these facilities. Location specific air monitoring feasibility tests have been performed with excellent results in determining attribute and isotopic composition of chemical elements present in an actual test-bed sample. Isotopic analysis of collected particles from an Aerosol Contaminant Extractor (ACE) collection, was performed with the standard bulk sampling protocol used throughout the IAEA network of analytical laboratories (NWAL). The results yielded bulk isotopic values expected for the operations. Advanced designs of air monitoring instruments such as the ACE may be used in gas centrifuge enrichment plants (GCEP) to detect the production of highly enriched uranium (HEU) or enrichments not declared by a State. Researchers at Savannah River National Laboratory in collaboration with Oak Ridge National Laboratory are developing the next generation of ES equipment for air grab and constant samples that could become an important addition to the international nuclear safeguards inspector's toolkit. Location specific air monitoring to be used to establish a baseline environmental signature of a particular facility employed for comparison of consistencies in declared operations will be described in this paper. Implementation of air monitoring will be contrasted against the use of smear ES when used during unannounced inspections, design information verification, limited frequency unannounced access, and complementary access visits at bulk handling facilities. Analysis of technical features required for tamper indication and resistance will demonstrate the viability of successful application of the system in taking ES within a bulk handling location. Further exploration of putting this technology into practice is planned to include mapping uranium enrichment facilities for the identification of optimal for installation of air monitoring devices.

  5. Part 1: Participatory Ergonomics Approach to Waste Container Handling Utilizing a Multidisciplinary Team

    SciTech Connect (OSTI)

    Zalk, D.M.; Tittiranonda, P.; Burastero, S.; Biggs, T.W.; Perry, C.M.; Tageson, R.; Barsnick, L.

    2000-02-07T23:59:59.000Z

    This multidisciplinary team approach to waste container handling, developed within the Grassroots Ergonomics process, presents participatory ergonomic interpretations of quantitative and qualitative aspects of this process resulting in a peer developed training. The lower back, shoulders, and wrists were identified as frequently injured areas, so these working postures were a primary focus for the creation of the workers' training. Handling procedures were analyzed by the team to identify common cycles involving one 5 gallon (60 pounds), two 5 gallons (60 and 54 pounds), 30 gallon (216 pounds), and 55 gallon (482 pounds) containers: lowering from transporting to/from transport vehicles, loading/unloading on transport vehicles, and loading onto pallet. Eleven experienced waste container handlers participated in this field analysis. Ergonomic exposure assessment tools measuring these field activities included posture analysis, posture targeting, Lumbar Motion Monitor{trademark} (LMM), and surface electromyography (sEMG) for the erector spinae, infraspinatus, and upper trapezius muscles. Posture analysis indicates that waste container handlers maintained non-neutral lower back postures (flexion, lateral bending, and rotation) for a mean of 51.7% of the time across all activities. The right wrist was in non-neutral postures (radial, ulnar, extension, and flexion) a mean of 30.5% of the time and the left wrist 31.4%. Non-neutral shoulder postures (elevation) were the least common, occurring 17.6% and 14.0% of the time in the right and left shoulders respectively. For training applications, each cycle had its own synchronized posture analysis and posture target diagram. Visual interpretations relating to the peak force modifications of the posture target diagrams proved to be invaluable for the workers' understanding of LMM and sEMG results (refer to Part II). Results were reviewed by the team's field technicians and their interpretations were developed into ergonomic training that address the issues originally raised. This training includes intervention methods, ergonomic tools used, dam acquired, and effects of waste container handling techniques on lower back, shoulder, and wrists and methods to help proactively reduce injuries associated with this profession.

  6. Three-Dimensional Characteristics of Post-CHF Behaviour Within a Rod Bundle for Loss-of-Flow Simulation: Experimental and Three-Fluid Porous Media Numerical Analyses

    SciTech Connect (OSTI)

    Stosic, Zoran V. [Framatome ANP GmbH, PO Box 3220, Erlangen, 91050 (Germany); Stevanovic, Vladimir D. [University of Belgrade, Kraljice Marije 16, 11000 Belgrade, Serbia and Montenegro (Yugoslavia); Tadashi Iguchi [Japan Atomic Energy Research Institute, Tokai-mura 319-1195 (Japan)

    2002-07-01T23:59:59.000Z

    The investigation of three-dimensional transient propagations of dry-out fronts within a nuclear fuel rod bundle is performed, based on experimental and numerical simulations. The spreading of Critical Heat Flux (CHF) fronts across a bundle, caused by sudden decrease of coolant mass flow rate followed by delayed gradual decrease of power generation is predicted, and the locus of dry patches is shown. Simultaneous occurrence of CHF and re-wet multi-fronts in here-analysed flow transient has not been detected so obvious as in power transient, previously analysed. Due to a possible building of a vapour zone, the CHF front spatial propagation has to be carefully analysed in transient conditions. (authors)

  7. PWR FLECHT SEASET 21-rod bundle flow blockage task data and analysis report. NRC/EPRI/Westinghouse Report No. 11. Appendices K-P

    SciTech Connect (OSTI)

    Loftus, M.J.; Hochreiter, L.E.; Lee, N.; McGuire, M.F.; Wenzel, A.H.; Valkovic, M.M.

    1982-09-01T23:59:59.000Z

    This report presents data and limited analysis from the 21-Rod Bundle Flow Blockage Task of the Full-Length Emergency Cooling Heat Transfer Separate Effects and Systems Effects Test Program (FLECHT SEASET). The tests consisted of forced and gravity reflooding tests utilizing electrical heater rods with a cosine axial power profile to simulate PWR nuclear core fuel rod arrays. Steam cooling and hydraulic characteristics tests were also conducted. These tests were utilized to determine effects of various flow blockage configurations (shapes and distributions) on reflooding behavior, to aid in development/assessment of computational models in predicting reflooding behavior of flow blockage configurations, and to screen flow blockage configurations for future 163-rod flow blockage bundle tests.

  8. Enhancement of Raman Light Scattering in Dye-Labeled Rat Glioma Cells by Langmuir-Blodgett CNT-Bundles Arranged on Metal-Containing Conducting Polymer Film

    E-Print Network [OSTI]

    Egorov, A S; Grushevskaya, H V; Krot, V I; Krylova, N G; Lipnevich, I V; Orekhovskaya, T I; Shulitsky, B G

    2015-01-01T23:59:59.000Z

    We have fabricated layered nanocomposite consisting of a nanoporous anodic alumina sublayer (AOA), an ultrathin metal-containing polymer Langmuir-Blodgett (LB) film coating AOA, and multi-walled carbon nanotube (MCNT) - bundles which are arranged on the LB-film. MCNTs were preliminarily chemically modified by carboxyl groups and functionalized by stearic acid. We have experimentally observed an enhancement of Raman light scattering on surface plasmons in the LB-monolayers. This enhancement is due to charge and energy transfer. We demonstrate that propidium iodide (PI) fluorescence is quenched by the MCNT-bundles. A method of two-dimensional system imaging based on the MCNT-enhanced Raman spectroscopy has been proposed. This method has been applied to visualize focal adhesion sites on membranes of living PI-labeled rat glioma cells.

  9. Cellulosic Biofuels: Expert Views on Prospects for Advancement: Supplementary Material

    E-Print Network [OSTI]

    Massachusetts at Amherst, University of

    Cellulosic Biofuels: Expert Views on Prospects for Advancement: Supplementary Material Erin Baker Keywords: Biofuels; Technology R&D; Uncertainty; Environmental policy 2 #12;1 Introduction This paper contains supplementary material for "Cellulosic Biofuels: Expert Views on Prospects for Advancement

  10. Better Buildings Network View | July-August 2014 | Department...

    Energy Savers [EERE]

    July-August 2014 Better Buildings Network View | July-August 2014 The Better Buildings Network View monthly newsletter from the U.S. Department of Energy's Better Buildings...

  11. Process Knowledge Summary Report for Materials and Fuels Complex Contact-Handled Transuranic Debris Waste

    SciTech Connect (OSTI)

    R. P. Grant; P. J. Crane; S. Butler; M. A. Henry

    2010-02-01T23:59:59.000Z

    This Process Knowledge Summary Report summarizes the information collected to satisfy the transportation and waste acceptance requirements for the transfer of transuranic (TRU) waste between the Materials and Fuels Complex (MFC) and the Advanced Mixed Waste Treatment Project (AMWTP). The information collected includes documentation that addresses the requirements for AMWTP and the applicable portion of their Resource Conservation and Recovery Act permits for receipt and treatment of TRU debris waste in AMWTP. This report has been prepared for contact-handled TRU debris waste generated by the Idaho National Laboratory at MFC. The TRU debris waste will be shipped to AMWTP for purposes of supercompaction. This Process Knowledge Summary Report includes information regarding, but not limited to, the generation process, the physical form, radiological characteristics, and chemical contaminants of the TRU debris waste, prohibited items, and packaging configuration. This report, along with the referenced supporting documents, will create a defensible and auditable record for waste originating from MFC.

  12. Temporally propagated optical pulses, and what they reveal about dispersion handling

    E-Print Network [OSTI]

    Kinsler, Paul

    2015-01-01T23:59:59.000Z

    I derive a temporally propagated uni-directional optical pulse equation valid in the few cycle limit. Temporal propagation is advantageous because it naturally preserves causality, unlike the competing spatially propagated models. The approach generates exact coupled bi-directional equations, which can be efficiently approximated down to a uni-directional form in cases where an optical pulse changes little over one optical cycle. It also also allows a direct term-to-term comparison of an exact bi-directional theory with an approximate uni-directional theory. Notably, temporal propagation handles dispersion in a different way, and this difference serves to highlight existing approximations inherent in spatially propagated treatments of dispersion. Accordingly, I emphasise the need for future work in clarifying the limitations of the dispersion conversion required by these types of approaches; since the only alternative in the few cycle limit may be to resort to the much more computationally intensive full Maxw...

  13. Safety Evaluation Report of the Waste Isolation Pilot Plant Contact Handled (CH) Waste Documented Safety Analysis

    SciTech Connect (OSTI)

    Washington TRU Solutions LLC

    2005-09-01T23:59:59.000Z

    This Safety Evaluation Report (SER) documents the Department of Energy’s (DOE's) review of Revision 9 of the Waste Isolation Pilot Plant Contact Handled (CH) Waste Documented Safety Analysis, DOE/WIPP-95-2065 (WIPP CH DSA), and provides the DOE Approval Authority with the basis for approving the document. It concludes that the safety basis documented in the WIPP CH DSA is comprehensive, correct, and commensurate with hazards associated with CH waste disposal operations. The WIPP CH DSA and associated technical safety requirements (TSRs) were developed in accordance with 10 CFR 830, Nuclear Safety Management, and DOE-STD-3009-94, Preparation Guide for U. S. Department of Energy Nonreactor Nuclear Safety Analysis Reports.

  14. Evaluation and improvement on external-hazard proof of JSFR fuel handling system

    SciTech Connect (OSTI)

    Katoh, A.; Chikazawa, Y. [Japan Atomic Energy Agency, 4002 Narita, O-arai-machi, Ibaraki-ken, 311-1393 (Japan); Uzawa, M. [Mitsubishi FBR Systems Inc. MFBR, 34-17, Jingumae 2-chome, Shibuya-ku, Tokyo 150-0001 (Japan)

    2012-07-01T23:59:59.000Z

    Responding to the the Fukushima Dai-ichi nuclear power plant (1F-NPP) accident, the earthquake and the tsunami proof of the fuel handling system (FHS) in Japan sodium-cooled fast reactor (JSFR) is studied. In the earthquake proof estimation, the margin of seismic resistance against the earthquake of the 1F-envelop condition and the sloshing behavior in the EVST is estimated. In terms of the tsunami proof, the scenario to lead fuel subassemblies into the stable cooling state and the potential of the cooling system is introduced in case of loss of the emergency power supply. As a result, it is clear that JSFR FHS originally could already be prepared to have the potential to prevent the release of radioactive material. (authors)

  15. Alternative Views on Knowledge: Presentation of Open Learner Models

    E-Print Network [OSTI]

    Bull, Susan

    a learner with a graphical view of their Bayesian learner model. STyLE-OLM [2] works with the learner

  16. Hanford`s remote-handled transuranic and transuranic mixed waste volume assessment

    SciTech Connect (OSTI)

    Templeton, K.J.; DeForest, T.J.; Hladek, K.L.

    1996-03-01T23:59:59.000Z

    This study documents the results of an assessment of each Hanford program`s potential RH-TRU(M) waste forecast volumes. Of this 3,470 m{sup 3} of remote-handled transuranic and transuranic mixed (RH-TRU[M]) forecast waste, the Environmental Restoration program is the only program generating waste (360 m{sup 3}) after the closure of the WIPP in FY 2033. Previous forecast assessments have estimated Hanford`s RH-TRU(M) waste volumes to range from 4,000 m{sup 3} to 45,000 m{sup 3}. In FY 1995, the RH-TRU(M) waste forecast was approximately 22,200 m{sup 3} (BIR), which exceeds the WIPP remote-handled capacity. The FY-1996 Solid Waste Integrated Life-Cycle Forecast Volume Summary (WHC-EP-0900) published in February 1996 stated that the baseline RH-TRU(M) waste volume was 13,350 m{sup 3}. The primary reason for the three different estimates results from two programmatic baseline revisions: Tank Waste Remediation Systems (TWRS) and Environmental Restoration (EM-40). The difference in the TWRS programmatic baseline is due to a revised programmatic baseline for the disposition of the long-length equipment currently present in the tanks. The difference in the Environmental Restoration programmatic baseline is due to an assessment based on recent experience that many of the facilities at Hanford will not contain RH-TRU(M) waste during decontamination and decommissioning and that for many other facilities, the RH-TRU(M) waste volumes will not be as great as previously estimated.

  17. View Payments to Vendors and Non-Employees

    E-Print Network [OSTI]

    Shull, Kenneth R.

    View Payments to Vendors and Non-Employees NUFinancials Purchasing Job Aid ViewPaymentsVendors to vendors for Purchase Orders, Direct Payment Requests, Visitor Expense Reports, and Contracted Services information via Accounts Payable · Method 6: View vendor payments by Dept ID via Accounts Payable · Helpful

  18. Steady-state film-boiling data in rod-bundle geometry and non-equilibrium correlation assessment

    SciTech Connect (OSTI)

    Yoder, G.L.; Morris, D.G.; Mullins, C.B.; Ott, L.J.; Reed, D.A.

    1982-01-01T23:59:59.000Z

    A series of 22 steady-state, rod bundle, dispersed flow film boiling experiments has been performed in the Thermal-Hydraulic Test Facility (THTF), a pressurized-water loop containing 64 full-length electrically heated rods. Test parameters in the upflow experiments cover a wide range of conditions typical of those which might be encountered during a nuclear reactor loss-of-coolant accident. Local equilibrium fluid conditions were calculated using mass and energy conservation considerations. Experimentally determined heat transfer coefficients were compared to several available film boiling heat transfer correlations: Dougall-Rohsenow, Groeneveld 5.7, Groeneveld-Delorme, Chen, Jones-Zuber, and Yoder-Rohsenow. The Groeneveld 5.7 correlation tended to predict the data better than any other correlation tested. The Dougall-Rohsenow correlation tends to overpredict the data while the Yoder-Rohsenow correlation predicted the data better than the other nonequilibrium correlations examined. However, all of the nonequilibrium correlations generally underpredict the heat transfer.

  19. A New View of the Cosmic Landscape

    E-Print Network [OSTI]

    S. -H. Henry Tye

    2007-04-16T23:59:59.000Z

    In this scenario, a generic meta-stable deSitter vacuum site in the cosmic landscape in string theory has a very short lifetime. Typically, the smaller is the vacuum energy of a meta-stable site, the longer is its lifetime. This view of the landscape can provide a qualitative dynamical explanation why the dark energy of our universe is so small. The argument for this scenario is based on resonance tunneling, a well-known quantum mechanical phenomenon, the topography of the landscape, and the vastness of the cosmic landscape. Mapping the topography of the landscape, even if only in a small region, will test the validity of this scenario.

  20. Energy Efficiency in Buildings- the Utilities View

    E-Print Network [OSTI]

    Konig, U.

    PAGE 1 Energy Efficiency in Buildings - the Utilities View U. K?nig RWE Energy AG The energy to lead ESL-IC-08-10-27 Proceedings of the Eighth International Conference for Enhanced Building Operations, Berlin, Germany, October 20-22, 2008 RWE... International Conference for Enhanced Building Operations, Berlin, Germany, October 20-22, 2008 RWE Energy / Energieeffizienz bei Immobilien / U. K?nig / ICEBO '08 SEITE 3 RWE ? One of the five leading Energy Companies in Europe > Nr 1 producer of electricity...

  1. Valley View Wind Farm | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home5b9fcbce19 NoPublic Utilities Address: 160 East 300 South Place: Salt Lake City, Utah Zip:Scale Solar IncVairexVallesValley View

  2. View from the Bridge | Department of Energy

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious RankCombustion |Energy Usage »of| Department of Energy Ventilation SystemNovember 1,View from the Bridge

  3. Better Buildings Network View, March 2015

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:YearRound-Up fromDepartmentTie Ltd: ScopeDepartment1, 2011 Better Buildings0,28,AugustNetwork View

  4. Lake View Geothermal Facility | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home5b9fcbce19 No revision hasInformation Earth's Heat JumpInc Place:Keystone Clean Airjoin <Nacimiento,View Geothermal

  5. Experimental investigations of uncovered-bundle heat transfer and two-phase mixture-level swell under high-pressure low heat-flux conditions. [PWR

    SciTech Connect (OSTI)

    Anklam, T. M.; Miller, R. J.; White, M. D.

    1982-03-01T23:59:59.000Z

    Results are reported from a series of uncovered-bundle heat transfer and mixture-level swell tests. Experimental testing was performed at Oak Ridge National Laboratory in the Thermal Hydraulic Test Facility (THTF). The THTF is an electrically heated bundle test loop configured to produce conditions similar to those in a small-break loss-of-coolant accident. The objective of heat transfer testing was to acquire heat transfer coefficients and fluid conditions in a partially uncovered bundle. Testing was performed in a quasi-steady-state mode with the heated core 30 to 40% uncovered. Linear heat rates varied from 0.32 to 2.22 kW/m.rod (0.1 to 0.68 kW/ft.rod). Under these conditions peak clad temperatures in excess of 1050 K (1430/sup 0/F) were observed, and total heat transfer coefficients ranged from 0.0045 to 0.037 W/cm/sup 2/.K (8 to 65 Btu/h.ft/sup 2/./sup 0/F). Spacer grids were observed to enhance heat transfer at, and downstream of, the grid. Radiation heat transfer was calculated to account for as much as 65% of total heat transfer in low-flow tests.

  6. Collective cargo hauling by a bundle of parallel microtubules: bi-directional motion caused by load-dependent polymerization and depolymerization

    E-Print Network [OSTI]

    Dipanwita Ghanti; Debashish Chowdhury

    2015-01-09T23:59:59.000Z

    A microtubule (MT) is a hollow tube of approximately 25 nm diameter. The two ends of the tube are dissimilar and are designated as `plus' and `minus' ends. Motivated by the collective push and pull exerted by a bundle of MTs during chromosome segregation in a living cell, we have developed here a much simplified theoretical model of a bundle of parallel dynamic MTs. The plus-end of all the MTs in the bundle are permanently attached to a movable `wall' by a device whose detailed structure is not treated explicitly in our model. The only requirement is that the device allows polymerization and depolymerization of each MT at the plus-end. In spite of the absence of external force and direct lateral interactions between the MTs, the group of polymerizing MTs attached to the wall create a load force against the group of depolymerizing MTs and vice-versa; the load against a group is shared equally by the members of that group. Such indirect interactions among the MTs gives rise to the rich variety of possible states of collective dynamics that we have identified by computer simulations of the model in different parameter regimes. The bi-directional motion of the cargo, caused by the load-dependence of the polymerization kinetics, is a "proof-of-principle" that the bi-directional motion of chromosomes before cell division does not necessarily need active participation of motor proteins.

  7. Heating, Ventilating, and Air-Conditioning: Recent Advances in Diagnostics and Controls to Improve Air-Handling System Performance

    SciTech Connect (OSTI)

    Wray, Craig; Wray, Craig P.; Sherman, Max H.; Walker, I.S.; Dickerhoff, D.J.; Federspiel, C.C.

    2008-02-01T23:59:59.000Z

    The performance of air-handling systems in buildings needs to be improved. Many of the deficiencies result from myths and lore and a lack of understanding about the non-linear physical principles embedded in the associated technologies. By incorporating these principles, a few important efforts related to diagnostics and controls have already begun to solve some of the problems. This paper illustrates three novel solutions: one rapidly assesses duct leakage, the second configures ad hoc duct-static-pressure reset strategies, and the third identifies useful intermittent ventilation strategies. By highlighting these efforts, this paper seeks to stimulate new research and technology developments that could further improve air-handling systems.

  8. Low-level waste certification plan for the Lawrence Berkeley Laboratory Hazardous Waste Handling Facility. Revision 1

    SciTech Connect (OSTI)

    NONE

    1995-01-10T23:59:59.000Z

    The purpose of this plan is to describe the organization and methodology for the certification of low-level radioactive waste (LLW) handled in the Hazardous Waste Handling Facility (HWHF) at Lawrence Berkeley Laboratory (LBL). This plan is composed to meet the requirements found in the Westinghouse Hanford Company (WHC) Solid Waste Acceptance Criteria (WAC) and follows the suggested outline provided by WHC in the letter of April 26, 1990, to Dr. R.H. Thomas, Occupational Health Division, LBL. LLW is to be transferred to the WHC Hanford Site Central Waste Complex and Burial Grounds in Hanford, Washington.

  9. A Bulk Tungsten Tile for JET: Derivation of Power-Handling Performance and Validation of the Thermal Model, in the MARION Facility

    E-Print Network [OSTI]

    A Bulk Tungsten Tile for JET: Derivation of Power-Handling Performance and Validation of the Thermal Model, in the MARION Facility

  10. Analysis of core samples from the BPXA-DOE-USGS Mount Elbert gas hydrate stratigraphic test well: Insights into core disturbance and handling

    E-Print Network [OSTI]

    Kneafsey, Timothy J.

    2010-01-01T23:59:59.000Z

    and handling of natural gas hydrate. GSC Bulletin, 544: 263-naturally occurring gas hydrates: the structures of methaneDOE-USGS Mount Elbert gas hydrate stratigraphic test well:

  11. National Environmental Policy Act Compliance Strategy for the Remote-Handled Low-level Waste Disposal Facility

    SciTech Connect (OSTI)

    Peggy Hinman

    2010-10-01T23:59:59.000Z

    The U.S. Department of Energy (DOE) needs to have disposal capability for remote-handled low level waste (LLW) generated at the Idaho National Laboratory (INL) at the time the existing disposal facility is full or must be closed in preparation for final remediation of the INL Subsurface Disposal Area in approximately the year 2017.

  12. U.S. Department of Energy-Funded Performance Validation of Fuel Cell Material Handling Equipment (Presentation)

    SciTech Connect (OSTI)

    Kurtz, J.; Sprik, S.; Ramsden, T.; Saur, G.; Ainscough, C.; Post, M.; Peters, M.

    2013-11-01T23:59:59.000Z

    This webinar presentation to the UK Hydrogen and Fuel Cell Association summarizes how the U.S. Department of Energy is enabling early fuel cell markets; describes objectives of the National Fuel Cell Technology Evaluation Center; and presents performance status of fuel cell material handling equipment.

  13. Estimated energy expenditure during a manual material handling task: the prolonged effect of wearing the Oxylog System

    E-Print Network [OSTI]

    Mudd, Michelle Leigh

    1998-01-01T23:59:59.000Z

    This purpose of this study was to evaluate the prolonged effect of wearing the Oxylog System from Morgan Scientific, Inc. during a series of four manual material handling tests. The lift tests were performed by 12 males (average age of 23 years...

  14. Gas Cylinder Storage and Handling Serious accidents can result from the misuse, abuse, or mishandling of compressed gas

    E-Print Network [OSTI]

    de Lijser, Peter

    Gas Cylinder Storage and Handling Serious accidents can result from the misuse, abuse, or mishandling of compressed gas cylinders. Safe procedures for their use are as follows: · All compressed gas combustible material. · Keep cylinders out of the direct sun and do not allow them to be overheated. · Gas

  15. Farm Fuel Safety Accidents in the handling, use and storage of gasoline, gasohol, diesel fuel, LP-gas and

    E-Print Network [OSTI]

    112 Farm Fuel Safety Accidents in the handling, use and storage of gasoline, gasohol, diesel fuel and by keeping fuel storage facilities in top condition. Flammable Liquids and Gases Gasoline, diesel fuel, LP flammability and safety precautions. Do not keep gasoline inside the home or transport it in the trunks

  16. Exploring Maximum Humidity Control and Energy Conservation Opportunities with Single Duct Single Zone Air-Handling Units

    E-Print Network [OSTI]

    Zhou, J.; Wei, G.; Turner, W. D.; Deng, S.; Claridge, D.

    2006-01-01T23:59:59.000Z

    Humidity control for single-duct single-zone (SDSZ) constant volume air handling units is known to be a challenge. The operation of these systems is governed by space temperature only. Under mild weather conditions, discharge air temperature can get...

  17. Report on the handling of safety information concerning flammable gases and ferrocyanide at the Hanford waste tanks

    SciTech Connect (OSTI)

    Not Available

    1990-07-01T23:59:59.000Z

    This report discusses concerns safety issues, and management at Hanford Tank Farm. Concerns center on the issue of flammable gas generation which could ignite, and on possible exothermic reactions of ferrocyanide compounds which were added to single shell tanks in the 1950's. It is believed that information concerning these issues has been mis-handled and the problems poorly managed. (CBS)

  18. Optimal Control in Three-deck Multi-Zone Air-Handling Units: A Case-Study

    E-Print Network [OSTI]

    Joo, I. S.; Song, L.; Liu, M.; Douglas, B.

    A multi-zone air-handling unit was popular several decades ago due to the convenience of small sized modular units, which were inexpensive to install and easily maintained in a mechanical room. The cost and convenience proved to be of little benefit...

  19. Guidance Document Fume hoods are used when handling toxic or hazardous chemicals. Harmful gases, vapors and fumes

    E-Print Network [OSTI]

    Guidance Document FumeHoods Fume hoods are used when handling toxic or hazardous chemicals. Harmful the maximum safe mark (provided by Facilities Management during annual test) Use secondary containment (a hood without permission from EHS. Call EHS or Facilities Management if a hood is not functioning

  20. Uncertainty Analysis for a Virtual Flow Meter Using an Air-Handling Unit Chilled Water Valve

    SciTech Connect (OSTI)

    Song, Li; Wang, Gang; Brambley, Michael R.

    2013-04-28T23:59:59.000Z

    A virtual water flow meter is developed that uses the chilled water control valve on an air-handling unit as a measurement device. The flow rate of water through the valve is calculated using the differential pressure across the valve and its associated coil, the valve command, and an empirically determined valve characteristic curve. Thus, the probability of error in the measurements is significantly greater than for conventionally manufactured flow meters. In this paper, mathematical models are developed and used to conduct uncertainty analysis for the virtual flow meter, and the results from the virtual meter are compared to measurements made with an ultrasonic flow meter. Theoretical uncertainty analysis shows that the total uncertainty in flow rates from the virtual flow meter is 1.46% with 95% confidence; comparison of virtual flow meter results with measurements from an ultrasonic flow meter yielded anuncertainty of 1.46% with 99% confidence. The comparable results from the theoretical uncertainty analysis and empirical comparison with the ultrasonic flow meter corroborate each other, and tend to validate the approach to computationally estimating uncertainty for virtual sensors introduced in this study.

  1. Dangerous Waste Characteristics of Contact-Handled Transuranic Mixed Wastes from the Hanford Tanks

    SciTech Connect (OSTI)

    Tingey, Joel M.; Bryan, Garry H.; Deschane, Jaquetta R.

    2004-08-31T23:59:59.000Z

    This report summarizes existing analytical data from samples taken from the Hanford tanks designated as potentially containing transuranic mixed process wastes. Process knowledge of the wastes transferred to these tanks has been reviewed to determine whether the dangerous waste characteristics now assigned to all Hanford underground storage tanks are applicable to these particular wastes. Supplemental technologies are being examined to accelerate the Hanford tank waste cleanup mission and accomplish waste treatment safely and efficiently. To date, 11 Hanford waste tanks have been designated as potentially containing contact-handled (CH) transuranic mixed (TRUM) wastes. The CH-TRUM wastes are found in single-shell tanks B-201 through B-204, T-201 through T-204, T-104, T-110, and T-111. Methods and equipment to solidify and package the CH-TRUM wastes are part of the supplemental technologies being evaluated. The resulting packages and wastes must be acceptable for disposal at the Waste Isolation Pilot Plant (WIPP). The dangerous waste characteristics being considered include ignitability, corrosivity, reactivity, and toxicity arising from the presence of 2,4,5-trichlorophenol at levels above the dangerous waste threshold. The analytical data reviewed include concentrations of sulfur, sulfate, cyanide, 2,4,5-trichlorophenol, total organic carbon, and oxalate; the composition of the tank headspace, pH, and mercury. Differential scanning calorimetry results were used to determine the energetics of the wastes as a function of temperature.

  2. DOE assay methods used for characterization of contact-handled transuranic waste

    SciTech Connect (OSTI)

    Schultz, F.J. (Oak Ridge National Lab., TN (United States)); Caldwell, J.T. (Pajarito Scientific Corp., Los Alamos, NM (United States))

    1991-08-01T23:59:59.000Z

    US Department of Energy methods used for characterization of contact-handled transuranic (CH-TRU) waste prior to shipment to the Waste Isolation Pilot Plant (WIPP) are described and listed by contractor site. The methods described are part of the certification process. All CH-TRU waste must be assayed for determination of fissile material content and decay heat values prior to shipment and prior to storage on-site. Both nondestructive assay (NDA) and destructive assay methods are discussed, and new NDA developments such as passive-action neutron (PAN) crate counter improvements and neutron imaging are detailed. Specifically addressed are assay method physics; applicability to CH-TRU wastes; calibration standards and implementation; operator training requirements and practices; assay procedures; assay precision, bias, and limit of detection; and assay limitation. While PAN is a new technique and does not yet have established American Society for Testing and Materials. American National Standards Institute, or Nuclear Regulatory Commission guidelines or methods describing proper calibration procedures, equipment setup, etc., comparisons of PAN data with the more established assay methods (e.g., segmented gamma scanning) have demonstrated its reliability and accuracy. Assay methods employed by DOE have been shown to reliable and accurate in determining fissile, radionuclide, alpha-curie content, and decay heat values of CH-TRU wastes. These parameters are therefore used to characterize packaged waste for use in certification programs such as that used in shipment of CH-TRU waste to the WIPP. 36 refs., 10 figs., 7 tabs.

  3. Advanced Aerodynamic Devices to Improve the Performance, Economics, Handling, and Safety of Heavy Vehicles

    SciTech Connect (OSTI)

    Robert J. Englar

    2001-05-14T23:59:59.000Z

    Research is being conducted at the Georgia Tech Research Institute (GTRI) to develop advanced aerodynamic devices to improve the performance, economics, stability, handling and safety of operation of Heavy Vehicles by using previously-developed and flight-tested pneumatic (blown) aircraft technology. Recent wind-tunnel investigations of a generic Heavy Vehicle model with blowing slots on both the leading and trailing edges of the trailer have been conducted under contract to the DOE Office of Heavy Vehicle Technologies. These experimental results show overall aerodynamic drag reductions on the Pneumatic Heavy Vehicle of 50% using only 1 psig blowing pressure in the plenums, and over 80% drag reductions if additional blowing air were available. Additionally, an increase in drag force for braking was confirmed by blowing different slots. Lift coefficient was increased for rolling resistance reduction by blowing only the top slot, while downforce was produced for traction increase by blowing only the bottom. Also, side force and yawing moment were generated on either side of the vehicle, and directional stability was restored by blowing the appropriate side slot. These experimental results and the predicted full-scale payoffs are presented in this paper, as is a discussion of additional applications to conventional commercial autos, buses, motor homes, and Sport Utility Vehicles.

  4. Performance Assessment for the Idaho National Laboratory Remote-Handled Low-Level Waste Disposal Facility

    SciTech Connect (OSTI)

    Annette L. Schafer; A. Jeffrey Sondrup; Arthur S. Rood

    2012-05-01T23:59:59.000Z

    This performance assessment for the Remote-Handled Low-Level Radioactive Waste Disposal Facility at the Idaho National Laboratory documents the projected radiological dose impacts associated with the disposal of low-level radioactive waste at the facility. This assessment evaluates compliance with the applicable radiological criteria of the U.S. Department of Energy and the U.S. Environmental Protection Agency for protection of the public and the environment. The calculations involve modeling transport of radionuclides from buried waste to surface soil and subsurface media, and eventually to members of the public via air, groundwater, and food chain pathways. Projections of doses are calculated for both offsite receptors and individuals who inadvertently intrude into the waste after site closure. The results of the calculations are used to evaluate the future performance of the low-level radioactive waste disposal facility and to provide input for establishment of waste acceptance criteria. In addition, one-factor-at-a-time, Monte Carlo, and rank correlation analyses are included for sensitivity and uncertainty analysis. The comparison of the performance assessment results to the applicable performance objectives provides reasonable expectation that the performance objectives will be met

  5. SNS Target Test Facility: Prototype Hg Operations and Remote Handling Tests P. T. Spampinato, T. W. Burgess, J. B. Chesser, V. B. Graves, and S.L. Schrock

    E-Print Network [OSTI]

    McDonald, Kirk

    SNS Target Test Facility: Prototype Hg Operations and Remote Handling Tests P. T. Spampinato, T. W remote handling techniques and tools for replacing target system components. During the past year and analytical data. These included a welded-tube heat exchanger, an electromagnetic flow meter, a hydraulically

  6. ALS Technique Gives Novel View of Lithium Battery Dendrite Growth

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

    ALS Technique Gives Novel View of Lithium Battery Dendrite Growth Print Lithium-ion batteries, popular in today's electronic devices and electric vehicles, could gain significant...

  7. July 2013 Most Viewed Documents for Renewable Energy Sources...

    Office of Scientific and Technical Information (OSTI)

    2013 Most Viewed Documents for Renewable Energy Sources Science Subject Feed Chapter 11. Heat Exchangers Rafferty, Kevin D.; Culver, Gene (1998) 484 > Environmental Impacts of...

  8. April 2013 Most Viewed Documents for Renewable Energy Sources...

    Office of Scientific and Technical Information (OSTI)

    2013 Most Viewed Documents for Renewable Energy Sources Science Subject Feed Chapter 11. Heat Exchangers Rafferty, Kevin D.; Culver, Gene (1998) 1252 > Seventh Edition Fuel Cell...

  9. The Better Buildings Neighborhood View - December 2013 | Department...

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

    - July 2013 Focus Series: Philadelphia Energyworks: In the City of Brotherly Love, Sharing Know-How Leads to Sustainability The Better Buildings Neighborhood View - October 2012...

  10. September 2013 Most Viewed Documents for Fission And Nuclear...

    Office of Scientific and Technical Information (OSTI)

    September 2013 Most Viewed Documents for Fission And Nuclear Technologies Science Subject Feed Estimation of gas leak rates through very small orifices and channels. From sealed...

  11. January 2013 Most Viewed Documents for Fission And Nuclear Technologie...

    Office of Scientific and Technical Information (OSTI)

    January 2013 Most Viewed Documents for Fission And Nuclear Technologies Laboratory studies of shearleach processing of zircaloy clad metallic uranium reactor fuel Swanson, J.L.;...

  12. April 2013 Most Viewed Documents for Energy Storage, Conversion...

    Office of Scientific and Technical Information (OSTI)

    April 2013 Most Viewed Documents for Energy Storage, Conversion, And Utilization Science Subject Feed Seventh Edition Fuel Cell Handbook NETL (2004) 628 > Continuously variable...

  13. Better Buildings Network View | September 2014 | Department of...

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

    Financing Program: On-Bill Financing Brings Lenders and Homeowners On Board Better Buildings Network View | December 2014 On-Bill Financing for Energy Efficiency Improvements...

  14. The Better Buildings Neighborhood View - July 2013 | Department...

    Energy Savers [EERE]

    Better Buildings Neighborhood View - October 2012 Better Buildings Neighborhood Program Home Accomplishments History Better Buildings Partners Stories Interviews Videos Contact Us...

  15. Thermal analysis for fuel handling system for sodium cooled reactor considering minor actinide-bearing metal fuel.

    SciTech Connect (OSTI)

    Chikazawa, Y.; Grandy, C.; Nuclear Engineering Division

    2009-03-01T23:59:59.000Z

    The Advanced Burner Reactor (ABR) is one of the components of the Global Nuclear Energy Partnership (GNEP) used to close the fuel cycle. ABR is a sodium-cooled fast reactor that is used to consume transuranic elements resulting from the reprocessing of light water reactor spent nuclear fuel. ABR-1000 [1000 MW(thermal)] is a fast reactor concept created at Argonne National Laboratory to be used as a reference concept for various future trade-offs. ABR-1000 meets the GNEP goals although it uses what is considered base sodium fast reactor technology for its systems and components. One of the considerations of any fast reactor plant concept is the ability to perform fuel-handling operations with new and spent fast reactor fuel. The transmutation fuel proposed as the ABR fuel has a very little experience base, and thus, this paper investigates a fuel-handling concept and potential issues of handling fast reactor fuel containing minor actinides. In this study, two thermal analyses supporting a conceptual design study on the ABR-1000 fuel-handling system were carried out. One analysis investigated passive dry spent fuel storage, and the other analysis investigated a fresh fuel shipping cask. Passive dry storage can be made suitable for the ABR-1000 spent fuel storage with sodium-bonded metal fuel. The thermal analysis shows that spent fast reactor fuel with a decay heat of 2 kW or less can be stored passively in a helium atmosphere. The 2-kW value seems to be a reasonable and practical level, and a combination of reasonably-sized in-sodium storage followed by passive dry storage could be a candidate for spent fuel storage for the next-generation sodium-cooled reactor with sodium-bonded metal fuel. Requirements for the shipping casks for minor actinide-bearing fuel with a high decay heat level are also discussed in this paper. The shipping cask for fresh sodium-cooled-reactor fuel should be a dry type to reduce the reaction between residual moisture on fresh fuel and the sodium coolant. The cladding temperature requirement is maintained below the creep temperature limit to avoid any damage before core installation. The thermal analysis shows that a helium gas-filled cask can accommodate ABR-1000 fresh minor actinide-bearing fuel with 700-W decay heat. The above analysis results revealed the overall requirement for minor actinide-bearing metal fuel handling. The information is thought to be helpful in the design of the ABR-1000 and future sodium-cooled-reactor fuel-handling system.

  16. Contact-Handled Transuranic Waste Acceptance Criteria for the Waste Isolation Pilot Plant

    SciTech Connect (OSTI)

    Washington TRU Solutions LLC

    2005-12-29T23:59:59.000Z

    The purpose of this document is to summarize the waste acceptance criteria applicable to the transportation, storage, and disposal of contact-handled transuranic (CH-TRU) waste at the Waste Isolation Pilot Plant (WIPP). These criteria serve as the U.S. Department of Energy's (DOE) primary directive for ensuring that CH-TRU waste is managed and disposed of in a manner that protects human health and safety and the environment.The authorization basis of WIPP for the disposal of CH-TRU waste includes the U.S.Department of Energy National Security and Military Applications of Nuclear EnergyAuthorization Act of 1980 (reference 1) and the WIPP Land Withdrawal Act (LWA;reference 2). Included in this document are the requirements and associated criteriaimposed by these acts and the Resource Conservation and Recovery Act (RCRA,reference 3), as amended, on the CH-TRU waste destined for disposal at WIPP.|The DOE TRU waste sites must certify CH-TRU waste payload containers to thecontact-handled waste acceptance criteria (CH-WAC) identified in this document. Asshown in figure 1.0, the flow-down of applicable requirements to the CH-WAC istraceable to several higher-tier documents, including the WIPP operational safetyrequirements derived from the WIPP CH Documented Safety Analysis (CH-DSA;reference 4), the transportation requirements for CH-TRU wastes derived from theTransuranic Package Transporter-Model II (TRUPACT-II) and HalfPACT Certificates ofCompliance (references 5 and 5a), the WIPP LWA (reference 2), the WIPP HazardousWaste Facility Permit (reference 6), and the U.S. Environmental Protection Agency(EPA) Compliance Certification Decision and approval for PCB disposal (references 7,34, 35, 36, and 37). The solid arrows shown in figure 1.0 represent the flow-down of allapplicable payload container-based requirements. The two dotted arrows shown infigure 1.0 represent the flow-down of summary level requirements only; i.e., the sitesmust reference the regulatory source documents from the U.S. Nuclear RegulatoryCommission (NRC) and the New Mexico Environment Department (NMED) for acomprehensive and detailed listing of the requirements.This CH-WAC does not address the subject of waste characterization relating to adetermination of whether the waste is hazardous; rather, the sites are referred to theWaste Analysis Plan (WAP) contained in the WIPP Hazardous Waste Facility Permit fordetails of the sampling and analysis protocols to be used in determining compliance withthe required physical and chemical properties of the waste. Requirements andassociated criteria pertaining to a determination of the radiological properties of thewaste, however, are addressed in appendix A of this document. The collectiveinformation obtained from waste characterization records and acceptable knowledge(AK) serves as the basis for sites to certify that their CH-TRU waste satisfies the WIPPwaste acceptance criteria listed herein.

  17. Performance viewing and editing in ASSESS Outsider

    SciTech Connect (OSTI)

    Snell, M.K. [Sandia National Labs., Albuquerque, NM (US); Key, B.; Bingham, B. [Science and Engineering Associates, Inc., Albuquerque, NM (US)

    1993-07-01T23:59:59.000Z

    The Analytic System and Software for Evaluation of Safeguards and Security (ASSESS) Facility module records site information in the path elements and areas of an Adversary Sequence Diagram. The ASSESS Outsider evaluation module takes this information and first calculates performance values describing how much detection and delay is assigned at each path element and then uses the performance values to determine most-vulnerable paths. This paper discusses new Outsider capabilities that allow the user to view how elements are being defeated and to modify some of these values in Outsider. Outsider now displays how different path element segments are defeated and contrasts the probability of detection for alternate methods of defeating a door (e.g., the lock or the door face itself). The user can also override element segment delays and detection probabilities directly during analysis in Outsider. These capabilities allow users to compare element performance and to verify correct path element performance for all elements, not just those on the most-vulnerable path as is the case currently. Improvements or reductions in protection can be easily checked without creating a set of new facility files to accomplish it.

  18. The INTEGRAL View of the Galactic Nucleus

    E-Print Network [OSTI]

    Goldwurm, A; Goldoni, P; Paul, J; Terrier, R; Falanga, M; Ubertini, P; Bazzano, A; Santo, M D; Winkler, C; Parmar, A N; Kuulkers, E; Ebisawa, K; Roques, J P; Skinner, G K; Lund, N; Melia, F; Yusef-Zadeh, F

    2004-01-01T23:59:59.000Z

    We present the preliminary results of the observational campaign performed in 2003 to study the Galactic Nucleus with INTEGRAL. The mosaicked images obtained with the IBIS/ISGRI coded aperture instrument in the energy range above 20 keV, give a yet unseen view of the high-energy sources of this region in hard X and gamma-rays, with an angular resolution of 12'. We report on the discovery of a source, IGR J17456-2901, compatible with the instrument's point spread function and coincident with the Galactic Nucleus Sgr A* to within 0.9'. The source is visible up to 60-80 keV with a 20-100 keV luminosity at 8 kpc of 3 x 10E35 erg/s. Although we cannot unequivocally associate the new INTEGRAL source to the Galactic Nucleus, this is the first report of significant hard X-ray emission from within the inner 10' of the Galaxy and a contribution from the galactic center supermassive black hole itself cannot be excluded. Here we discuss the results obtained and the perspectives for future observations of the Galactic Nuc...

  19. Upgrade plans to handle 30 to 40 Mbytes of data for DIII-D

    SciTech Connect (OSTI)

    Henline, P.

    1989-11-01T23:59:59.000Z

    The Department of Energy funds the DIII-D tokamak program which carries out plasma physics and fusion energy research experiments. The machine began operations in February 1986; at that time, approximately 7 Mbytes of data was collected for each shot. Since that time, the shot size has steadily increased to a maximum of over 30 Mbytes. The average shot size is now about 25 Mbytes and over 1 Gigabyte of data has been collected during some operation day. The computer systems were designed to handle a maximum shot size of 25 Mbytes. In order to meet the increased demands, changes to hardware and software are being made and each experiment reviewed before being added to a shot. The area of data transfer now increasing the most is data transferred from small diagnostic DEC VAX systems to the main VAX cluster. Plans in this area include upgrading the VAX which receives data (possibly to a VAX 6310) to have both more CPU power and a faster interface to the Network Systems Hyperchannel which transfers data to the VAX. The new machine will be more easily upgraded with additional CPU's, communication devices and storage devices. Software changes are being incorporated on diagnostic VAXes so that subsets of data, or calculated results are included with the shot data file, rather than the often large (6 to 20 Mbytes) amount of data collected locally. More careful examination is being given to all experiments added to the tokamak, and only necessary and useful data is being added to the system for permanent storage. 4 refs.

  20. Proposal for Construction/Demonstration/Implementation of A Material Handling System

    SciTech Connect (OSTI)

    Jim Jnatt

    2001-08-24T23:59:59.000Z

    Vortec Corporation, the United States Enrichment Corporation (USEC) and DOE/Paducah propose to complete the technology demonstration and the implementation of the Material Handling System developed under Contract Number DE-AC21-92MC29120. The demonstration testing and operational implementation will be done at the Paducah Gaseous Diffusion Plant. The scope of work, schedule and cost for the activities are included in this proposal. A description of the facility to be constructed and tested is provided in Exhibit 1, attached. The USEC proposal for implementation at Paducah is presented in Exhibit 2, and the commitment letters from the site are included in Exhibit 3. Under our agreements with USEC, Bechtel Jacobs Corporation and DOE/Paducah, Vortec will be responsible for the construction of the demonstration facility as documented in the engineering design package submitted under Phase 4 of this contract on August 9, 2001. USEC will have responsibility for the demonstration testing and commercial implementation of the plant. The demonstration testing and initial commercial implementation of the technology will be achieved by means of a USEC work authorization task with the Bechtel Jacobs Corporation. The initial processing activities will include the processing of approximately 4,250 drums of LLW. Subsequent processing of LLW and TSCA/LLW will be done under a separate contract or work authorization task. To meet the schedule for commercial implementation, it is important that the execution of the Phase 4 project option for construction of the demonstration system be executed as soon as possible. The schedule we have presented herein assumes initiation of the construction phase by the end of September 2001. Vortec proposes to complete construction of the demonstration test system for an estimated cost of $3,254,422. This price is based on the design submitted to DOE/NETL under the Phase 4 engineering design deliverable (9 august 2001). The cost is subject to the assumptions and conditions identified in Section 6 of this proposal.

  1. Multi Canister Overpack (MCO) Handling Machine Independent Review of Seismic Structural Analysis

    SciTech Connect (OSTI)

    SWENSON, C.E.

    2000-09-22T23:59:59.000Z

    The following separate reports and correspondence pertains to the independent review of the seismic analysis. The original analysis was performed by GEC-Alsthom Engineering Systems Limited (GEC-ESL) under subcontract to Foster-Wheeler Environmental Corporation (FWEC) who was the prime integration contractor to the Spent Nuclear Fuel Project for the Multi-Canister Overpack (MCO) Handling Machine (MHM). The original analysis was performed to the Design Basis Earthquake (DBE) response spectra using 5% damping as required in specification, HNF-S-0468 for the 90% Design Report in June 1997. The independent review was performed by Fluor-Daniel (Irvine) under a separate task from their scope as Architect-Engineer of the Canister Storage Building (CSB) in 1997. The comments were issued in April 1998. Later in 1997, the response spectra of the Canister Storage Building (CSB) was revised according to a new soil-structure interaction analysis and accordingly revised the response spectra for the MHM and utilized 7% damping in accordance with American Society of Mechanical Engineers (ASME) NOG-1, ''Rules for Construction of Overhead and Gantry Cranes (Top Running Bridge, Multiple Girder).'' The analysis was re-performed to check critical areas but because manufacturing was underway, designs were not altered unless necessary. FWEC responded to SNF Project correspondence on the review comments in two separate letters enclosed. The dispositions were reviewed and accepted. Attached are supplier source surveillance reports on the procedures and process by the engineering group performing the analysis and structural design. All calculation and analysis results are contained in the MHM Final Design Report which is part of the Vendor Information File 50100. Subsequent to the MHM supplier engineering analysis, there was a separate analyses for nuclear safety accident concerns that used the electronic input data files provided by FWEC/GEC-ESL and are contained in document SNF-6248, ''Evaluation of MHM Uplift Restraint for Seismic Event During Repositioning Operations,'' (EDT-629126 and EDT-629132).

  2. A Gaussian process-based approach for handling uncertainty in vehicle dynamics simulation.

    SciTech Connect (OSTI)

    Schmitt, K.; Madsen, J.; Anitescu, M.; Negrut, D.; Mathematics and Computer Science; Univ. of Wisconsin at Madison

    2009-01-01T23:59:59.000Z

    Advances in vehicle modeling and simulation in recent years have led to designs that are safer, easier to handle, and less sensitive to external factors. Yet, the potential of simulation is adversely impacted by its limited ability to predict vehicle dynamics in the presence of uncertainty. A commonly occurring source of uncertainty in vehicle dynamics is the road-tire friction interaction, typically represented through a spatially distributed stochastic friction coefficient. The importance of its variation becomes apparent on roads with ice patches, where if the stochastic attributes of the friction coefficient are correctly factored into real time dynamics simulation, robust control strategies could be designed to improve transportation safety. This work concentrates on correctly accounting in the nonlinear dynamics of a car model for the inherent uncertainty in friction coefficient distribution at the road/tire interface. The outcome of this effort is the ability to quantify the effect of input uncertainty on a vehicle's trajectory and the associated escalation of risk in driving. By using a space-dependent Gaussian process, the statistical representation of the friction coefficient allows for consistent space dependence of randomness. The approach proposed allows for the incorporation of noise in the observed data and a nonzero mean for inhomogeneous distribution of the friction coefficient. Based on the statistical model considered, consistent friction coefficient sample distributions are generated over large spatial domains of interest. These samples are subsequently used to compute and characterize the statistics associated with the dynamics of a nonlinear vehicle model. The information concerning the state of the road and thus the friction coefficient is assumed available (measured) at a limited number of points by some sensing device that has a relatively homogeneous noise field (satellite picture or ground sensors, for instance). The methodology proposed can be modified to incorporate information that is sensed by each individual car as it advances along its trajectory.

  3. Safe handling of TBP and nitrates in the nuclear process industry

    SciTech Connect (OSTI)

    Hyder, M.L.

    1994-07-01T23:59:59.000Z

    A laboratory and literature study was made of the reactions of tri-n-butyl phosphate (TBP) with nitric acid and nitrates. Its goal was to establish safe conditions for solvent extraction processes involving these chemicals. The damaging explosions at the Tomsk-7 PUREX plant in Russia graphically illustrated the potential hazard involved in such operations. The study has involved a review of prior and contemporary experiments, and new experiments to answer particular questions about these reactions. TBP extracts nitric acid and some metal nitrates from aqueous solutions. The resulting liquid contains both oxidant and reductant, and can react exothermically if heated sufficiently. Safe handling of these potentially reactive materials involves not only limiting the heat generated by the chemical reaction, but also providing adequate heat removal and venting. Specifically, the following recommendations are made to ensure safety: (1) tanks in which TBP-nitrate complexes are or may be present should be adequately vented to avoid pressurization. Data are supplied as a basis for adequacy; (2) chemically degraded TBP, or TBP that has sat a long time in the presence of acids or radiation, should be purified before use in solvent extraction; (3) evaporators in which TBP might be introduced should be operated at a controlled temperature, and their TBP content should be limited; (4) evaporator bottoms that may contain TBP should be cooled under conditions that ensure heat removal. Finally, process design should consider the potential for such reactions, and operators should be made aware of this potential, so that it is considered during training and process operation.

  4. Dynamic Bundle Methods

    E-Print Network [OSTI]

    2007-03-15T23:59:59.000Z

    Claudia Sagastizábal: CEPEL, Electric Energy Research Center. On leave from INRIA ..... set J. In particular, it drives to zero the J-component of s + ˆ?. Because.

  5. DEVELOPMENT OF A TAMPER RESISTANT/INDICATING AEROSOL COLLECTION SYSTEM FOR ENVIRONMENTAL SAMPLING AT BULK HANDLING FACILITIES

    SciTech Connect (OSTI)

    Sexton, L.

    2012-06-06T23:59:59.000Z

    Environmental sampling has become a key component of International Atomic Energy Agency (IAEA) safeguards approaches since its approval for use in 1996. Environmental sampling supports the IAEA's mission of drawing conclusions concerning the absence of undeclared nuclear material or nuclear activities in a Nation State. Swipe sampling is the most commonly used method for the collection of environmental samples from bulk handling facilities. However, augmenting swipe samples with an air monitoring system, which could continuously draw samples from the environment of bulk handling facilities, could improve the possibility of the detection of undeclared activities. Continuous sampling offers the opportunity to collect airborne materials before they settle onto surfaces which can be decontaminated, taken into existing duct work, filtered by plant ventilation, or escape via alternate pathways (i.e. drains, doors). Researchers at the Savannah River National Laboratory and Oak Ridge National Laboratory have been working to further develop an aerosol collection technology that could be installed at IAEA safeguarded bulk handling facilities. The addition of this technology may reduce the number of IAEA inspector visits required to effectively collect samples. The principal sample collection device is a patented Aerosol Contaminant Extractor (ACE) which utilizes electrostatic precipitation principles to deposit particulates onto selected substrates. Recent work has focused on comparing traditional swipe sampling to samples collected via an ACE system, and incorporating tamper resistant and tamper indicating (TRI) technologies into the ACE system. Development of a TRI-ACE system would allow collection of samples at uranium/plutonium bulk handling facilities in a manner that ensures sample integrity and could be an important addition to the international nuclear safeguards inspector's toolkit. This work was supported by the Next Generation Safeguards Initiative (NGSI), Office of Nonproliferation and International Security (NIS), National Nuclear Security Administration (NNSA).

  6. Semantic Web enabled Information Systems: Personalized Views on Web Data

    E-Print Network [OSTI]

    Henze, Nicola

    Semantic Web enabled Information Systems: Personalized Views on Web Data Robert Baumgartner1@math.uni-hannover.de Abstract. In this paper a methodology and a framework for personal- ized views on data available describe the Web data extraction task (Section 2), and an approach for personalized content presentation

  7. 3D Model Retrieval based on Adaptive Views Clustering

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    3D Model Retrieval based on Adaptive Views Clustering Tarik Filali Ansary1 , Mohamed Daoudi2 , Jean.daoudi@univ-tours.fr http://www-rech.enic.fr/miire Abstract. In this paper, we propose a method for 3D model indexing based selection of 2D views from a 3D model, and a probabilistic Bayesian method for 3D model retrieval from

  8. Updatable Process Views for Adapting Large Process Models

    E-Print Network [OSTI]

    Ulm, Universität

    Updatable Process Views for Adapting Large Process Models: The proView Demonstrator Jens Kolb. The increasing adoption of process-aware information sys- tems (PAISs) has resulted in large process model collections. To support users having different perspectives on these processes and related data, a PAIS should

  9. Concentration of remote-handled, transuranic, sodium nitrate-based sludge using agitated thin-film evaporators

    SciTech Connect (OSTI)

    Walker, J.F. Jr.; Youngblood, E.L.; Berry, J.B. (Oak Ridge National Lab., TN (USA)); Pen, Ben-Li (Institute of Nuclear Energy Research, Lung-Tan (Taiwan))

    1991-01-01T23:59:59.000Z

    The Waste Handling and Packaging Plant (WHPP) is being designed at Oak Ridge National Laboratory (ORNL) to prepared transuranic waste for final disposal. Once operational, this facility will process, package, and certify remote-handled transuranic waste for ultimate shipment and disposal at the Waste Isolation Pilot Plant (WIPP) in Carlsbad, New Mexico. One of the wastes that will be handled at WHIPP is the transuranic sludge currently stored at ORNL in eight 50,000-gal underground tanks. The use of an Agitated Thin-Film Evaporator (ATFE) for concentration of this waste is being investigated. Tests have shown that the ATFE can be used to produce a thick slurry, a powder, or a fused salt. A computer model developed at the Savannah River Plant (SRP) to simulate the operation of ATFE's on their waste is being modified for use on the ORNL transuranic sludge. This paper summarizes the results of the test with the ATFEs to date, discusses the changes in the SRP model necessary to use this model with the ORNL waste, and compares the results of the model with the actual data taken from the operation of ATFEs at vendors' test facilities. 8 refs., 1 fig., 3 tabs.

  10. Audit Report on "Waste Processing and Recovery Act Acceleration Efforts for Contact-Handled Transuranic Waste at the Hanford Site"

    SciTech Connect (OSTI)

    None

    2010-05-01T23:59:59.000Z

    The Department of Energy's Office of Environmental Management's (EM), Richland Operations Office (Richland), is responsible for disposing of the Hanford Site's (Hanford) transuranic (TRU) waste, including nearly 12,000 cubic meters of radioactive contact-handled TRU wastes. Prior to disposing of this waste at the Department's Waste Isolation Pilot Plant (WIPP), Richland must certify that it meets WIPP's waste acceptance criteria. To be certified, the waste must be characterized, screened for prohibited items, treated (if necessary) and placed into a satisfactory disposal container. In a February 2008 amendment to an existing Record of Decision (Decision), the Department announced its plan to ship up to 8,764 cubic meters of contact-handled TRU waste from Hanford and other waste generator sites to the Advanced Mixed Waste Treatment Project (AMWTP) at Idaho's National Laboratory (INL) for processing and certification prior to disposal at WIPP. The Department decided to maximize the use of the AMWTP's automated waste processing capabilities to compact and, thereby, reduce the volume of contact-handled TRU waste. Compaction reduces the number of shipments and permits WIPP to more efficiently use its limited TRU waste disposal capacity. The Decision noted that the use of AMWTP would avoid the time and expense of establishing a processing capability at other sites. In May 2009, EM allocated $229 million of American Recovery and Reinvestment Act of 2009 (Recovery Act) funds to support Hanford's Solid Waste Program, including Hanford's contact-handled TRU waste. Besides providing jobs, these funds were intended to accelerate cleanup in the short term. We initiated this audit to determine whether the Department was effectively using Recovery Act funds to accelerate processing of Hanford's contact-handled TRU waste. Relying on the availability of Recovery Act funds, the Department changed course and approved an alternative plan that could increase costs by about $25 million by processing Hanford TRU-waste on-site rather than at AMWTP. Further, under the newly adopted alternative approach, the Department would fail to achieve the previously anticipated reductions in volume associated with the use of existing AMWTP waste compaction capabilities.

  11. Multifunctional Metallic and Refractory Materials for Energy Efficient Handling of Molten Metals

    SciTech Connect (OSTI)

    Xingbo Liu; Ever Barbero; Bruce Kang; Bhaskaran Gopalakrishnan; James Headrick; Carl Irwin

    2009-02-06T23:59:59.000Z

    The goal of the project was to extend the lifetime of hardware submerged in molten metal by an order of magnitude and to improve energy efficiency of molten metal handling process. Assuming broad implementation of project results, energy savings in 2020 were projected to be 10 trillion BTU/year, with cost savings of approximately $100 million/year. The project team was comprised of materials research groups from West Virginia University and the Missouri University of Science and Technology formerly University of Missouri – Rolla, Oak Ridge National Laboratory, International Lead and Zinc Research Organization, Secat and Energy Industries of Ohio. Industry partners included six suppliers to the hot dip galvanizing industry, four end-user steel companies with hot-dip Galvanize and/or Galvalume lines, eight refractory suppliers, and seven refractory end-user companies. The results of the project included the development of: (1) New families of materials more resistant to degradation in hot-dip galvanizing bath conditions were developed; (2) Alloy 2020 weld overlay material and process were developed and applied to GI rolls; (3) New Alloys and dross-cleaning procedures were developed for Galvalume processes; (4) Two new refractory compositions, including new anti-wetting agents, were identified for use with liquid aluminum alloys; (5) A new thermal conductivity measurement technique was developed and validated at ORNL; (6) The Galvanizing Energy Profiler Decision Support System (GEPDSS)at WVU; Newly Developed CCW Laser Cladding Shows Better Resistance to Dross Buildup than 316L Stainless Steel; and (7) A novel method of measuring the corrosion behavior of bath hardware materials. Project in-line trials were conducted at Southwire Kentucky Rod and Cable Mill, Nucor-Crawfordsville, Nucor-Arkansas, Nucor-South Carolina, Wheeling Nisshin, California Steel, Energy Industries of Ohio, and Pennex Aluminum. Cost, energy, and environmental benefits resulting from the project are due to: i) a reduced number of process shutdowns to change hardware or lining material, ii) reduced need to produce new hardware or lining material, iii) improved product quality leads to reduced need to remake product or manufacturing of new product, iv) reduction in contamination of melt from degradation of refractory and metallic components, v) elimination of worn hardware will increase efficiency of process, vi) reduced refractory lining deterioration or formation of a less insulating phase, would result in decreased heat loss through the walls. Projected 2015 benefits for the U.S. aluminum industry, assuming 21% market penetration of improved refractory materials, are energy savings of approximately 0.2 trillion BTU/year, cost savings of $2.3 billion/year and carbon reductions of approximately 1.4 billion tons/year. The carbon reduction benefit of the project for the hot-dip galvanize and aluminum industries combined is projected to be approximately 2.2 billion tons/year in 2015. Pathways from research to commercialization were based on structure of the project’s industrial partnerships. These partnerships included suppliers, industrial associations, and end users. All parties were involved in conducting the project including planning and critiquing the trials. Supplier companies such as Pyrotech Metaullics, Stoody, and Duraloy have commercialized products and processes developed on the project.

  12. Shipping Remote Handled Transuranic Waste to the Waste Isolation Pilot Plant - An Operational Experience

    SciTech Connect (OSTI)

    Anderson, S.; Bradford, J.; Clements, T.; Crisp, D.; Sherick, M. [CH2M-WG Idaho, Idaho Falls, ID (United States); D'Amico, E. [Washington TRU Solutions, Denver, CO (United States); Lattin, W. [United States Department of Energy, Idaho Operations Office, Idaho Falls, ID (United States); Watson, K. [United States Department of Energy, Carlsbad Field Office, Carlsbad, NM (United States)

    2008-07-01T23:59:59.000Z

    On January 18, 2007, the first ever shipment of Remote Handled Transuranic (RH TRU) waste left the gate at the Idaho National Laboratory (INL), headed toward the Waste Isolation Pilot Plant (WIPP) for disposal, thus concluding one of the most stressful, yet rewarding, periods the authors have ever experienced. The race began in earnest on October 16, 2006, with signature of the New Mexico Environment Department Secretary's Final Order, ruling that the '..draft permit as changed is hereby approved in its entirety.' This established the effective date of the approved permit as November 16, 2006. The permit modification was a consolidation of several Class 3 modification requests, one of which included incorporation of RH TRU requirements and another of which incorporated the requirements of Section 311 of Public Law 108-137. The obvious goal was to complete the first shipment by November 17. While many had anticipated its approval, the time had finally come to actually implement, and time seemed to be the main item lacking. At that point, even the most aggressive schedule that could be seriously documented showed a first ship date in March 2007. Even though planning for this eventuality had started in May 2005 with the arrival of the current Idaho Cleanup Project (ICP) contractor (and even before that), there were many facility and system modifications to complete, startup authorizations to fulfill, and many regulatory audits and approvals to obtain before the first drum could be loaded. Through the dedicated efforts of the ICP workers, the partnership with Department of Energy (DOE) - Idaho, the coordinated integration with the Central Characterization Project (CCP), the flexibility and understanding of the regulatory community, and the added encouragement of DOE - Carlsbad Field Office and at Headquarters, the first RH TRU canister was loaded on December 22, 2006. Following final regulatory approval on January 17, 2007, the historic event finally occurred the following day. While some of the success of this endeavor can be attributed to the sheer will and determination of the individuals involved, the fact that it was established and managed as a separate sub-project under the ICP, accounts for a majority of the success. Utilizing a structured project management approach, including development of, and management to, a performance baseline, allowed for timely decision making and the flexibility to adapt to changing conditions as the various aspects of the project matured. This paper provides some insight into how this was achieved, in a relatively short time, and provides an overview of the experience of start-up of a new retrieval, characterization, loading, and transportation operation in the midst of an aggressive cleanup project. Additionally, as one might expect, everything within the project did not go as planned, which provides a great opportunity to discuss some lessons learned. Finally, the first shipment was just the beginning. There are 224 additional shipments scheduled. In keeping with the theme of WM 2008, Phoenix Rising: Moving Forward in Waste Management, this paper will address the future opportunities and challenges of RH TRU waste management at the INL. (authors)

  13. E-Print Network 3.0 - aversive picture viewing Sample Search...

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

    Expected utility theory does a poor job of handling risk aversion. Most people are risk averse Source: Fitelson, Branden - Department of Philosophy, University of California...

  14. Development of an Online Expert Rule Based Automated fault Detection and Diagnostic (AFDD) Tool for Air Handling Units: Beta Test Results

    E-Print Network [OSTI]

    Bruton, K.; Coakley, D.; O'Donovan, P.; Keane, M.; O'Sullivan, D.

    2013-01-01T23:59:59.000Z

    Heating Ventilation and Air Conditioning (HVAC) system energy consumption accounts for an average of 40% of an industrial sites energy consumption. Studies have indicated that 20 - 30% energy savings are achievable by recommissioning Air Handling...

  15. EA-1793: Replacement Capability for Disposal of Remote-handled Low-level Waste Generated at the Department of Energy's Idaho Site

    Broader source: Energy.gov [DOE]

    This EA evaluates the environmental impacts of replacement capability for disposal of remote-handled low-level radioactive waste (LLW) generated at the Idaho National Laboratory (INL) site beginning in October 2017.

  16. Challenges in Applying Formal Methods An SME View

    E-Print Network [OSTI]

    Southampton, University of

    Challenges in Applying Formal Methods An SME View Mathieu Clabaut Systerel, Aix-en-Provence, France classical B and event B to design safety related systems in an SME. 1 Activities Systerel is an SME doing

  17. A Parent's View of a Kid Growing Up in Lawrence

    E-Print Network [OSTI]

    Wright, Beatrice A.

    1991-04-01T23:59:59.000Z

    Alan Sica invited me to speak about Erik at this centennial celebration, stating that "your view of how this famous sociologist developed would only augment his own fascinating remarks." Of course I was delighted to do so. ...

  18. June 2014 Most Viewed Documents for Fission And Nuclear Technologies...

    Office of Scientific and Technical Information (OSTI)

    June 2014 Most Viewed Documents for Fission And Nuclear Technologies Behavior of spent nuclear fuel in water pool storage Johnson, A.B. Jr. (1977) 78 Estimation of gas leak rates...

  19. July 2013 Most Viewed Documents for Fission And Nuclear Technologies...

    Office of Scientific and Technical Information (OSTI)

    July 2013 Most Viewed Documents for Fission And Nuclear Technologies Science Subject Feed Estimation of gas leak rates through very small orifices and channels. From sealed PuO...

  20. A Unified View on Speeded Categorization Hongbin Gu 1

    E-Print Network [OSTI]

    Ji, Chuanshu

    A Unified View on Speeded Categorization Hongbin Gu 1 Chuanshu Ji 2 1 Introduction The research of Psychiatry, School of Medicine, University of North Carolina, Chapel Hill, NC 27599, USA; hongbin