National Library of Energy BETA

Sample records for including vessels operated

  1. Augmented Vessels for Pre-operative Preparation in Endovascular Treatments

    E-Print Network [OSTI]

    Chung, Albert C. S.

    Augmented Vessels for Pre-operative Preparation in Endovascular Treatments Wilbur C.K. Wong1 to construct imaginary disease-free vessel lumens, namely augmented vessels, and demarcate the abnormalities;Augmented Vessels for Pre-operative Preparation 603 Several researchers have suggested to detach a saccular

  2. Dye laser amplifier including a dye cell contained within a support vessel

    DOE Patents [OSTI]

    Davin, James (Gilroy, CA)

    1992-01-01

    A large (high flow rate) dye laser amplifier in which a continous replenished supply of dye is excited by a first light beam, specifically a copper vapor laser beam, in order to amplify the intensity of a second different light beam, specifically a dye beam, passing through the dye is disclosed herein. This amplifier includes a dye cell defining a dye chamber through which a continuous stream of dye is caused to pass at a flow rate of greater than 30 gallons/minute at a static pressure greater than 150 pounds/square inch and a specifically designed support vessel for containing the dye cell.

  3. Lined sampling vessel including a filter to separate solids from liquids on exit

    DOE Patents [OSTI]

    Shurtliff, Rodney M. (Idaho Falls, ID); Klingler, Kerry M. (Idaho Falls, ID); Turner, Terry D. (Ammon, ID)

    2001-01-01

    A filtering apparatus has an open canister with an inlet port. A canister lid is provided which includes an outlet port for the passage of fluids from the canister. Liners are also provided which are shaped to fit the interiors of the canister and the lid, with at least the canister liner preferably being flexible. The sample to be filtered is positioned inside the canister liner, with the lid and lid liner being put in place thereafter. A filter element is located between the sample and the outlet port. Seals are formed between the canister liner and lid liner, and around the outlet port to prevent fluid leakage. A pressure differential is created between the canister and the canister liner so that the fluid in the sample is ejected from the outlet port and the canister liner collapses around the retained solids.

  4. USING A CONTAINMENT VESSEL LIFTING APPARATUS FOR REMOTE OPERATIONS OF SHIPPING PACKAGES

    SciTech Connect (OSTI)

    Loftin, Bradley; Koenig, Richard

    2013-08-08

    The 9977 and the 9975 shipping packages are used in various nuclear facilities within the Department of Energy. These shipping packages are often loaded in designated areas with designs using overhead cranes or A-frames with lifting winches. However, there are cases where loading operations must be performed in remote locations where these facility infrastructures do not exist. For these locations, a lifting apparatus has been designed to lift the containment vessels partially out of the package for unloading operations to take place. Additionally, the apparatus allows for loading and closure of the containment vessel and subsequent pre-shipment testing. This paper will address the design of the apparatus and the challenges associated with the design, and it will describe the use of the apparatus.

  5. In-vessel Retention Strategy for High Power Reactors - K-INERI Final Report (includes SBLB Test Results for Task 3 on External Reactor Vessel Cooling (ERVC) Boiling Data and CHF Enhancement Correlations)

    SciTech Connect (OSTI)

    F. B. Cheung; J. Yang; M. B. Dizon; J. Rempe

    2005-01-01

    In-vessel retention (IVR) of core melt is a key severe accident management strategy adopted by some operating nuclear power plants and proposed for some advanced light water reactors (ALWRs). If there were inadequate cooling during a reactor accident, a significant amount of core material could become molten and relocate to the lower head of the reactor vessel, as happened in the Three Mile Island Unit 2 (TMI-2) accident. If it is possible to ensure that the vessel head remains intact so that relocated core materials are retained within the vessel, the enhanced safety associated with these plants can reduce concerns about containment failure and associated risk. For example, the enhanced safety of the Westinghouse Advanced 600 MWe PWR (AP600), which relied upon External Reactor Vessel Cooling (ERVC) for IVR, resulted in the U.S. Nuclear Regulatory Commission (US NRC) approving the design without requiring certain conventional features common to existing LWRs. However, it is not clear that currently proposed external reactor vessel cooling (ERVC) without additional enhancements could provide sufficient heat removal for higher-power reactors (up to 1500 MWe). Hence, a collaborative, three-year, U.S. - Korean International Nuclear Energy Research Initiative (INERI) project was completed in which the Idaho National Engineering and Environmental Laboratory (INEEL), Seoul National University (SNU), Pennsylvania State University (PSU), and the Korea Atomic Energy Research Institute (KAERI) investigated the performance of ERVC and an in-vessel core catcher (IVCC) to determine if IVR is feasible for reactors up to 1500 MWe.

  6. Theory, design, and operation of liquid metal fast breeder reactors, including operational health physics

    SciTech Connect (OSTI)

    Adams, S.R.

    1985-10-01

    A comprehensive evaluation was conducted of the radiation protection practices and programs at prototype LMFBRs with long operational experience. Installations evaluated were the Fast Flux Test Facility (FFTF), Richland, Washington; Experimental Breeder Reactor II (EBR-II), Idaho Falls, Idaho; Prototype Fast Reactor (PFR) Dounreay, Scotland; Phenix, Marcoule, France; and Kompakte Natriumgekuhlte Kernreak Toranlange (KNK II), Karlsruhe, Federal Republic of Germany. The evaluation included external and internal exposure control, respiratory protection procedures, radiation surveillance practices, radioactive waste management, and engineering controls for confining radiation contamination. The theory, design, and operating experience at LMFBRs is described. Aspects of LMFBR health physics different from the LWR experience in the United States are identified. Suggestions are made for modifications to the NRC Standard Review Plan based on the differences.

  7. OPTIMAL OPERATION OF AN INTEGRATED ENERGY PARK INCLUDING FOSSIL FUEL POWER GENERATION,

    E-Print Network [OSTI]

    Stanford University

    OPTIMAL OPERATION OF AN INTEGRATED ENERGY PARK INCLUDING FOSSIL FUEL POWER GENERATION, CO2 CAPTURE combustion turbine, and wind generation. Energy park com- ponents are modeled using energy and mass balances. A formal optimization proce- dure is used to determine the optimal hourly dispatch of energy park

  8. Hydraulically actuated fuel injector including a pilot operated spool valve assembly and hydraulic system using same

    DOE Patents [OSTI]

    Shafer, Scott F. (Morton, IL)

    2002-01-01

    The present invention relates to hydraulic systems including hydraulically actuated fuel injectors that have a pilot operated spool valve assembly. One class of hydraulically actuated fuel injectors includes a solenoid driven pilot valve that controls the initiation of the injection event. However, during cold start conditions, hydraulic fluid, typically engine lubricating oil, is particularly viscous and is often difficult to displace through the relatively small drain path that is defined past the pilot valve member. Because the spool valve typically responds slower than expected during cold start due to the difficulty in displacing the relatively viscous oil, accurate start of injection timing can be difficult to achieve. There also exists a greater difficulty in reaching the higher end of the cold operating speed range. Therefore, the present invention utilizes a fluid evacuation valve to aid in displacement of the relatively viscous oil during cold start conditions.

  9. Microwave-emitting rotor, separator apparatus including same, methods of operation and design thereof

    DOE Patents [OSTI]

    Meikrantz, David H.

    2006-12-19

    An apparatus for use in separating, at least in part, a mixture, including at least one chamber and at least one microwave generation device configured for communicating microwave energy into the at least one chamber is disclosed. The rotor assembly may comprise an electric generator for generating electricity for operating the microwave generation device. At least one microwave generation device may be positioned within a tubular interior shaft extending within the rotor assembly. At least a portion of the tubular interior shaft may be substantially transparent to microwave energy. Microwave energy may be emitted in an outward radial direction or toward an anticipated boundary surface defined between a mixture and a separated constituent thereof. A method including flowing a mixture through at least one chamber and communicating microwave energy into the at least one chamber while rotating same is disclosed. Methods of operating a centrifugal separator and design thereof are disclosed.

  10. Level indicator for pressure vessels

    DOE Patents [OSTI]

    Not Available

    1982-04-28

    A liquid-level monitor for tracking the level of a coal slurry in a high-pressure vessel including a toroidal-shaped float with magnetically permeable bands thereon disposed within the vessel, two pairs of magnetic-field generators and detectors disposed outside the vessel adjacent the top and bottom thereof and magnetically coupled to the magnetically permeable bands on the float, and signal-processing circuitry for combining signals from the top and bottom detectors for generating a monotonically increasing analog control signal which is a function of liquid level. The control signal may be utilized to operate high-pressure control valves associated with processes in which the high-pressure vessel is used.

  11. IEEE TRANSACTIONS ON BIOMEDICAL ENGINEERING, VOL. 58, NO. 7, JULY 2011 1985 Tracking of Vessels in Intra-Operative

    E-Print Network [OSTI]

    Miga, Michael I.

    IEEE TRANSACTIONS ON BIOMEDICAL ENGINEERING, VOL. 58, NO. 7, JULY 2011 1985 Tracking of Vessels, Fellow, IEEE Abstract--This article presents a method designed to automat- ically track cortical vessels. First, models of vessels selected in the first frame of the sequence are built. These models

  12. CATCHER VESSEL DFL MANAGEMENT PROGRAM

    E-Print Network [OSTI]

    CATCHER VESSEL DFL GROUNDFISH TRAWL GEAR MANAGEMENT PROGRAM (Check if applicable and enter number) CDQ Exempted Research AIP No. VESSEL NAME OPERATOR NAME AND SIGNATURE Date (M - D - Y) ADF&G Vessel No Control No. 0648-0213 Expiration Date: 03/31/2018Revised: 05/12/2015 COPY DISTRIBUTION: WHITE Vessel Copy

  13. Fluid-solid contact vessel having fluid distributors therein

    DOE Patents [OSTI]

    Jones, Jr., John B. (Rifle, CO)

    1980-09-09

    Rectangularly-shaped fluid distributors for large diameter, vertical vessels include reinforcers for high heat operation, vertical sides with gas distributing orifices and overhanging, sloped roofs. Devices are provided for cleaning the orifices from a buildup of solid deposits resulting from the reactions in the vessel.

  14. On a theory of vessels and the inverse scattering

    E-Print Network [OSTI]

    A. Melnikov

    2011-08-23

    In this paper we present a theory of vessels and its application to the classical inverse scattering of the Sturm-Liouville differential equation. The classical inverse scattering theory, including all its ingredients: Jost solutions, the Gelfand-Levitan equation, the tau function, corresponds to regular vessels, defined by bounded operators. A contribution of this work is the construction of models of vessels corresponding to unbounded operators, which is a first step for the inverse scattering for a wider class of potentials. A detailed research of Jost solutions and the corresponding vessel is presented for the unbounded Sturm-Liouville case. Models of vessels on curves, corresponding to unbounded operators are presented as a tool to study Linear Differential equations of finite order with a spectral parameter and as examples, we show how the family of Non Linear Schrodinger equations and Canonical Systems arise.

  15. Processing and analysis techniques involving in-vessel material generation

    DOE Patents [OSTI]

    Schabron, John F. (Laramie, WY); Rovani, Jr., Joseph F. (Laramie, WY)

    2012-09-25

    In at least one embodiment, the inventive technology relates to in-vessel generation of a material from a solution of interest as part of a processing and/or analysis operation. Preferred embodiments of the in-vessel material generation (e.g., in-vessel solid material generation) include precipitation; in certain embodiments, analysis and/or processing of the solution of interest may include dissolution of the material, perhaps as part of a successive dissolution protocol using solvents of increasing ability to dissolve. Applications include, but are by no means limited to estimation of a coking onset and solution (e.g., oil) fractionating.

  16. Processing and analysis techniques involving in-vessel material generation

    DOE Patents [OSTI]

    Schabron, John F. (Laramie, WY); Rovani, Jr., Joseph F. (Laramie, WY)

    2011-01-25

    In at least one embodiment, the inventive technology relates to in-vessel generation of a material from a solution of interest as part of a processing and/or analysis operation. Preferred embodiments of the in-vessel material generation (e.g., in-vessel solid material generation) include precipitation; in certain embodiments, analysis and/or processing of the solution of interest may include dissolution of the material, perhaps as part of a successive dissolution protocol using solvents of increasing ability to dissolve. Applications include, but are by no means limited to estimation of a coking onset and solution (e.g., oil) fractionating.

  17. Reactor vessel support system

    DOE Patents [OSTI]

    Golden, Martin P. (Trafford, PA); Holley, John C. (McKeesport, PA)

    1982-01-01

    A reactor vessel support system includes a support ring at the reactor top supported through a box ring on a ledge of the reactor containment. The box ring includes an annular space in the center of its cross-section to reduce heat flow and is keyed to the support ledge to transmit seismic forces from the reactor vessel to the containment structure. A coolant channel is provided at the outside circumference of the support ring to supply coolant gas through the keyways to channels between the reactor vessel and support ledge into the containment space.

  18. A power system includes an engine, a motor/generator operatively connected to the engine, and a starter operatively connected to at least one of the engine and the motor/generator.

    DOE Patents [OSTI]

    Hoff, Brian D. (East Peoria, IL); Algrain, Marcelo C. (Peoria, IL)

    2008-12-09

    A power system includes an engine, a motor/generator operatively connected to the engine, and a starter operatively connected to at least one of the engine and the motor/generator.

  19. Start-up control system and vessel for LMFBR

    DOE Patents [OSTI]

    Durrant, Oliver W. (Akron, OH); Kakarala, Chandrasekhara R. (Clinton, OH); Mandel, Sheldon W. (Galesburg, IL)

    1987-01-01

    A reflux condensing start-up system includes a steam generator, a start-up vessel connected parallel to the steam generator, a main steam line connecting steam outlets of the steam generator and start-up vessel to a steam turbine, a condenser connected to an outlet of the turbine and a feedwater return line connected between the condenser and inlets of the steam generator and start-up vessel. The start-up vessel has one or more heaters at the bottom thereof for heating feedwater which is supplied over a start-up line to the start-up vessel. Steam is thus generated to pressurize the steam generator before the steam generator is supplied with a heat transfer medium, for example liquid sodium, in the case of a liquid metal fast breeder reactor. The start-up vessel includes upper and lower bulbs with a smaller diameter mid-section to act as water and steam reservoirs. The start-up vessel can thus be used not only in a start-up operation but as a mixing tank, a water storage tank and a level control at low loads for controlling feedwater flow.

  20. Amendment 80 vessel replacement 1 Implementation and of Amendment 80 Vessel Replacement Provisions

    E-Print Network [OSTI]

    Amendment 80 vessel replacement 1 Implementation and of Amendment 80 Vessel Replacement Provisions identified and limited the vessels that could be used to fish for certain species of BSAI groundfish in a particular sector of the groundfish fishery. The final rule included this vessel restriction based on NMFS

  1. Reactor vessel annealing system

    DOE Patents [OSTI]

    Miller, Phillip E. (Greensburg, PA); Katz, Leonoard R. (Pittsburgh, PA); Nath, Raymond J. (Murrysville, PA); Blaushild, Ronald M. (Export, PA); Tatch, Michael D. (Randolph, NJ); Kordalski, Frank J. (White Oak, PA); Wykstra, Donald T. (Pittsburgh, PA); Kavalkovich, William M. (Monroeville, PA)

    1991-01-01

    A system for annealing a vessel (14) in situ by heating the vessel (14) to a defined temperature, composed of: an electrically operated heater assembly (10) insertable into the vessel (14) for heating the vessel (14) to the defined temperature; temperature monitoring components positioned relative to the heater assembly (10) for monitoring the temperature of the vessel (14); a controllable electric power supply unit (32-60) for supplying electric power required by the heater assembly (10); a control unit (80-86) for controlling the power supplied by the power supply unit (32-60); a first vehicle (2) containing the power supply unit (32-60); a second vehicle (4) containing the control unit (80-86); power conductors (18,22) connectable between the power supply unit (32-60) and the heater unit (10) for delivering the power supplied by the power supply unit (32-60) to the heater assembly (10); signal conductors (20,24) connectable between the temperature monitoring components and the control unit (80-86) for delivering temperature indicating signals from the temperature monitoring components to the control unit (80-86); and control conductors (8) connectable between the control unit (80-86) and the power supply unit (32-60) for delivering to the power supply unit (32-60) control signals for controlling the level of power supplied by the power supply unit (32-60) to the heater assembly (10).

  2. Middle Bronze Age Ceramic Vessels from Kamid el-Loz

    E-Print Network [OSTI]

    Cantazariti, Antonietta

    2014-01-01

    and reconstruction of the ceramic vessel economic systemsis to investigate the ceramic economy of the site of Kamidstudied included mainly complete ceramic vessels and, more

  3. Start-up control system and vessel for LMFBR

    DOE Patents [OSTI]

    Durrant, Oliver W. (Akron, OH); Kakarala, Chandrasekhara R. (Clinton, OH); Mandel, Sheldon W. (Galesburg, IL)

    1987-01-01

    A reflux condensing start-up system comprises a steam generator, a start-up vessel connected parallel to the steam generator, a main steam line connecting steam outlets of the steam generator and start-up vessel to a steam turbine, a condenser connected to an outlet of the turbine and a feedwater return line connected between the condenser and inlets of the steam generator and start-up vessel. The start-up vessel has one or more heaters at the bottom thereof for heating feedwater which is supplied over a start-up line to the start-up vessel. Steam is thus generated to pressurize the steam generator before the steam generator is supplied with a heat transfer medium, for example liquid sodium, in the case of a liquid metal fast breeder reactor. The start-up vessel includes upper and lower bulbs with a smaller diameter mid-section to act as water and steam reservoirs. The start-up vessel can thus be used not only in a start-up operation but as a mixing tank, a water storage tank and a level control at low loads for controlling feedwater flow.

  4. Sapphire tube pressure vessel

    DOE Patents [OSTI]

    Outwater, John O. (Cambridge, MA)

    2000-01-01

    A pressure vessel is provided for observing corrosive fluids at high temperatures and pressures. A transparent Teflon bag contains the corrosive fluid and provides an inert barrier. The Teflon bag is placed within a sapphire tube, which forms a pressure boundary. The tube is received within a pipe including a viewing window. The combination of the Teflon bag, sapphire tube and pipe provides a strong and inert pressure vessel. In an alternative embodiment, tie rods connect together compression fittings at opposite ends of the sapphire tube.

  5. Chapter 12 -Painting Operations Safety 1. Do not perform work in a heavily populated area, including building air intake

    E-Print Network [OSTI]

    Tullos, Desiree

    51 Chapter 12 - Painting Operations Safety Rules General 1. Do not perform work in a heavily is required whenever rust or loose paint is removed from surfaces with a wire brush. A hard hat is required the manufacturer's instructions for handling all epoxy materials, thinners, catalysts, paint removers, etc. Gloves

  6. Reactor vessel support system. [LMFBR

    DOE Patents [OSTI]

    Golden, M.P.; Holley, J.C.

    1980-05-09

    A reactor vessel support system includes a support ring at the reactor top supported through a box ring on a ledge of the reactor containment. The box ring includes an annular space in the center of its cross-section to reduce heat flow and is keyed to the support ledge to transmit seismic forces from the reactor vessel to the containment structure. A coolant channel is provided at the outside circumference of the support ring to supply coolant gas through the keyways to channels between the reactor vessel and support ledge into the containment space.

  7. Neutrino Factory Mercury Vessel

    E-Print Network [OSTI]

    McDonald, Kirk

    Neutrino Factory Mercury Vessel: Initial Cooling Calculations V. Graves Target Studies Nov 15, 2012 vessel assumed to be cooled with Helium ­ Shielding vessel filled with tungsten beads ­ Mercury vessel;7 Managed by UT-Battelle for the U.S. Department of Energy Cooling Calculations 15 Nov 2012 Mercury Vessel

  8. Reactor pressure vessel nozzle

    DOE Patents [OSTI]

    Challberg, Roy C. (Livermore, CA); Upton, Hubert A. (Morgan Hill, CA)

    1994-01-01

    A nozzle for joining a pool of water to a nuclear reactor pressure vessel includes a tubular body having a proximal end joinable to the pressure vessel and a distal end joinable in flow communication with the pool. The body includes a flow passage therethrough having in serial flow communication a first port at the distal end, a throat spaced axially from the first port, a conical channel extending axially from the throat, and a second port at the proximal end which is joinable in flow communication with the pressure vessel. The inner diameter of the flow passage decreases from the first port to the throat and then increases along the conical channel to the second port. In this way, the conical channel acts as a diverging channel or diffuser in the forward flow direction from the first port to the second port for recovering pressure due to the flow restriction provided by the throat. In the backflow direction from the second port to the first port, the conical channel is a converging channel and with the abrupt increase in flow area from the throat to the first port collectively increase resistance to flow therethrough.

  9. Reactor pressure vessel nozzle

    DOE Patents [OSTI]

    Challberg, R.C.; Upton, H.A.

    1994-10-04

    A nozzle for joining a pool of water to a nuclear reactor pressure vessel includes a tubular body having a proximal end joinable to the pressure vessel and a distal end joinable in flow communication with the pool. The body includes a flow passage therethrough having in serial flow communication a first port at the distal end, a throat spaced axially from the first port, a conical channel extending axially from the throat, and a second port at the proximal end which is joinable in flow communication with the pressure vessel. The inner diameter of the flow passage decreases from the first port to the throat and then increases along the conical channel to the second port. In this way, the conical channel acts as a diverging channel or diffuser in the forward flow direction from the first port to the second port for recovering pressure due to the flow restriction provided by the throat. In the backflow direction from the second port to the first port, the conical channel is a converging channel and with the abrupt increase in flow area from the throat to the first port collectively increase resistance to flow therethrough. 2 figs.

  10. CHF Enhancement by Vessel Coating for External Reactor Vessel Cooling

    SciTech Connect (OSTI)

    Yang, J.; Dizon, M.B.; Cheung, F.B. [Department of Mechanical and Nuclear Engineering, Pennsylvania State University, University Park, PA 16802 (United States); Rempe, J.L. [Idaho National Engineering and Environmental Laboratory, P.O. Box 1625, Idaho Falls, ID (United States); Suh, K.Y. [Department of Nuclear Engineering, Seoul National University, Seoul (Korea, Republic of); Kim, S.B. [Korea Atomic Energy Research Institute, P.O. Box 105, Yuseoung, Taejon (Korea, Republic of)

    2004-07-01

    In-vessel retention (IVR) is a key severe accident management (SAM) strategy that has been adopted by some operating nuclear power plants and advanced light water reactors (ALWRs). One viable means for IVR is the method of external reactor vessel cooling (ERVC) by flooding of the reactor cavity during a severe accident. As part of a joint Korean - United States International Nuclear Energy Research Initiative (K-INERI), an experimental study has been conducted to investigate the viability of using an appropriate vessel coating to enhance the critical heat flux (CHF) limits during ERVC. Toward this end, transient quenching and steady-state boiling experiments were performed in the SBLB (Sub-scale Boundary Layer Boiling) facility at Penn State using test vessels with micro-porous aluminum coatings. Local boiling curves and CHF limits were obtained in these experiments. When compared to the corresponding data without coatings, substantial enhancement in the local CHF limits for the case with surface coatings was observed. Results of the steady state boiling experiments showed that micro-porous aluminum coatings were very durable. Even after many cycles of steady state boiling, the vessel coatings remained rather intact, with no apparent changes in color or structure. Moreover, the heat transfer performance of the coatings was found to be highly desirable with an appreciable CHF enhancement in all locations on the vessel outer surface but with very little effect of aging. (authors)

  11. CHF Enhancement by Vessel Coating for External Reactor Vessel Cooling

    SciTech Connect (OSTI)

    Fan-Bill Cheung; Joy L. Rempe

    2004-06-01

    In-vessel retention (IVR) is a key severe accident management (SAM) strategy that has been adopted by some operating nuclear power plants and advanced light water reactors (ALWRs). One viable means for IVR is the method of external reactor vessel cooling (ERVC) by flooding of the reactor cavity during a severe accident. As part of a joint Korean – United States International Nuclear Energy Research Initiative (K-INERI), an experimental study has been conducted to investigate the viability of using an appropriate vessel coating to enhance the critical heat flux (CHF) limits during ERVC. Toward this end, transient quenching and steady-state boiling experiments were performed in the SBLB (Subscale Boundary Layer Boiling) facility at Penn State using test vessels with micro-porous aluminum coatings. Local boiling curves and CHF limits were obtained in these experiments. When compared to the corresponding data without coatings, substantial enhancement in the local CHF limits for the case with surface coatings was observed. Results of the steady state boiling experiments showed that micro-porous aluminum coatings were very durable. Even after many cycles of steady state boiling, the vessel coatings remained rather intact, with no apparent changes in color or structure. Moreover, the heat transfer performance of the coatings was found to be highly desirable with an appreciable CHF enhancement in all locations on the vessel outer surface but with very little effect of aging.

  12. Neutrino Factory Target Vessel

    E-Print Network [OSTI]

    McDonald, Kirk

    Neutrino Factory Target Vessel Concept V. Graves Target Studies EVO April 11, 2012 #12;2 Managed by UT-Battelle for the U.S. Department of Energy Target Vessel Concept 11 Apr 2012 Target Vessel;3 Managed by UT-Battelle for the U.S. Department of Energy Target Vessel Concept 11 Apr 2012 Starting Point

  13. Thermal insulating barrier and neutron shield providing integrated protection for a nuclear reactor vessel

    DOE Patents [OSTI]

    Schreiber, Roger B. (Penn Twp., PA); Fero, Arnold H. (New Kensington, PA); Sejvar, James (Murrysville, PA)

    1997-01-01

    The reactor vessel of a nuclear reactor installation which is suspended from the cold leg nozzles in a reactor cavity is provided with a lower thermal insulating barrier spaced from the reactor vessel to form a chamber which can be flooded with cooling water through passive valving to directly cool the reactor vessel in the event of a severe accident. The passive valving also includes bistable vents at the upper end of the thermal insulating barrier for releasing steam. A removable, modular neutron shield extending around the upper end of the reactor cavity below the nozzles forms with the upwardly and outwardly tapered transition on the outer surface of the reactor vessel, a labyrinthine channel which reduces neutron streaming while providing a passage for the escape of steam during a severe accident, and for the cooling air which is circulated along the reactor cavity walls outside the thermal insulating barrier during normal operation of the reactor.

  14. Thermal insulating barrier and neutron shield providing integrated protection for a nuclear reactor vessel

    DOE Patents [OSTI]

    Schreiber, R.B.; Fero, A.H.; Sejvar, J.

    1997-12-16

    The reactor vessel of a nuclear reactor installation which is suspended from the cold leg nozzles in a reactor cavity is provided with a lower thermal insulating barrier spaced from the reactor vessel to form a chamber which can be flooded with cooling water through passive valving to directly cool the reactor vessel in the event of a severe accident. The passive valving also includes bistable vents at the upper end of the thermal insulating barrier for releasing steam. A removable, modular neutron shield extending around the upper end of the reactor cavity below the nozzles forms with the upwardly and outwardly tapered transition on the outer surface of the reactor vessel, a labyrinthine channel which reduces neutron streaming while providing a passage for the escape of steam during a severe accident, and for the cooling air which is circulated along the reactor cavity walls outside the thermal insulating barrier during normal operation of the reactor. 8 figs.

  15. Additional or Lost Gillnet Tag Order Form All NE multispecies Category A, E, and F Day gillnet vessels fishing for NE multispecies and/or vessels fishing

    E-Print Network [OSTI]

    vessels fishing for NE multispecies and/or vessels fishing under a monkfish DAS using gillnet gear must tag their gillnets with BLUE gillnet tags. Vessel owners are required to account for the total number of tags issued. Should tags be lost, missing, or destroyed, vessel owners/operators must report

  16. Neutrino Factory Target Vessel

    E-Print Network [OSTI]

    McDonald, Kirk

    Neutrino Factory Target Vessel Concept V. Graves Target Studies EVO May 1, 2012 #12;2 Managed by UT-Battelle for the U.S. Department of Energy Target Vessel Concept 1 May 2012 Review ­ Two Target Vessel Ideas · Solid-Battelle for the U.S. Department of Energy Target Vessel Concept 1 May 2012 #12;4 Managed by UT-Battelle for the U

  17. Neutrino Factory Target Vessel

    E-Print Network [OSTI]

    McDonald, Kirk

    Neutrino Factory Target Vessel Concept Update V. Graves T. Lessard Target Studies EVO June 26, 2012 #12;2 Managed by UT-Battelle for the U.S. Department of Energy Target Vessel Update 26 June 2012 of Energy Target Vessel Update 26 June 2012 Review - Mercury Module Extraction #12;4 Managed by UT

  18. Vacuum Vessel Remote Handling

    E-Print Network [OSTI]

    FIRE Vacuum Vessel and Remote Handling Overview B. Nelson, T. Burgess, T. Brown, H-M Fan, G. Jones #12;13 July 2002 Snowmass Review: FIRE Vacuum Vessel and Remote Handling 2 Presentation Outline · Vacuum Vessel - Design requirements - Design concept and features - Analysis to date - Status and summary

  19. Neutrino Factory Target Vessel

    E-Print Network [OSTI]

    McDonald, Kirk

    Neutrino Factory Target Vessel Concept Update V. Graves Target Studies EVO June 12, 2012 #12;2 Managed by UT-Battelle for the U.S. Department of Energy Target Vessel Update 12 June 2012 Review ­ IPAC #12;3 Managed by UT-Battelle for the U.S. Department of Energy Target Vessel Update 12 June 2012 Inner

  20. Neutrino Factory Target Vessel

    E-Print Network [OSTI]

    McDonald, Kirk

    Neutrino Factory Target Vessel Concepts Updated 4/16/12 V. Graves Target Studies EVO April 11, 2012 #12;2 Managed by UT-Battelle for the U.S. Department of Energy Target Vessel Concept 16 Apr 2012 Target Vessel Requirements · Accurate jet placement · Jet/beam dump pool · Double containment of mercury

  1. NO FISHING REPORTING FORM Vessel ID. NO. Vessel Name

    E-Print Network [OSTI]

    NO FISHING REPORTING FORM Vessel ID. NO. Vessel Name: During the entire month of , year this vessel fishery if your vessel does not have a permit for it > Use Black Ink NMFS Use Only: Opened: Atlantic King Mackerel Spanish Mackerel Schedule # NO FISHING REPORTING FORM Vessel ID. NO. Vessel Name: During

  2. Report of the terawatt laser pressure vessel committee

    SciTech Connect (OSTI)

    Woodle, M.H.; Beauman, R.; Czajkowski, C.; Dickinson, T.; Lynch, D.; Pogorelsky, I.; Skjaritka, J.

    2000-09-25

    In 1995 the ATF project sent out an RFP for a CO2 Laser System having a TeraWatt output. Eight foreign and US firms responded. The Proposal Evaluation Panel on the second round selected Optoel, a Russian firm based in St. Petersburg, on the basis of the technical criteria and cost. Prior to the award, BNL representatives including the principal scientist, cognizant engineer and a QA representative visited the Optoel facilities to assess the company's capability to do the job. The contract required Optoel to provide a x-ray preionized high pressure amplifier that included: a high pressure cell, x-ray tube, internal optics and a HV pulse forming network for the main discharge and preionizer. The high-pressure cell consists of a stainless steel pressure vessel with various ports and windows that is filled with a gas mixture operating at 10 atmospheres. In accordance with BNL Standard ESH 1.4.1 ''Pressurized Systems For Experimental Use'', the pressure vessel design criteria is required to comply with the ASME Boiler and Pressure Vessel Code In 1996 a Preliminary Design Review was held at BNL. The vendor was requested to furnish drawings so that we could confirm that the design met the above criteria. The vendor furnished drawings did not have all dimensions necessary to completely analyze the cell. Never the less, we performed an analysis on as much of the vessel as we could with the available information. The calculations concluded that there were twelve areas of concern that had to be addressed to assure that the pressure vessel complied with the requirements of the ASME code. This information was forwarded to the vendor with the understanding that they would resolve these concerns as they continued with the vessel design and fabrication. The assembled amplifier pressure vessel was later hydro tested to 220 psi (15 Atm) as well as pneumatically to 181 psi (12.5 Atm) at the fabricator's Russian facility and was witnessed by a BNL engineer. The unit was shipped to the US and installed at the ATF. As part of the commissioning of the device the amplifier pressure vessel was disassembled several times at which time it became apparent that the vendor had not addressed 7 of the 12 issues previously identified. Closer examination of the vessel revealed some additional concerns including quality of workmanship. Although not required by the contract, the vendor furnished radiographs of a number of pressure vessel welds. A review of the Russian X-rays revealed radiographs of both poor and unreadable quality. However, a number of internal weld imperfections could be observed. All welds in question were excavated and then visually and dye penetrant inspected. These additional inspections confirmed that the weld techniques used to make some of these original welds were substandard. The applicable BNL standard, ESH 1.4.1, addresses the problem of pressure vessel non-compliance by having a committee appointed by the Department Chairman review the design and provide engineering solutions to assure equivalent safety. On January 24, 2000 Dr. M. Hart, the NSLS Chairman, appointed this committee with this charge. This report details the engineering investigations, deliberations, solutions and calculations which were developed by members of this committee to determine that with repairs, new components, appropriate NDE, and lowering the design pressure, the vessel can be considered safe to use.

  3. Cross Section of Coils & Shielding Vessels; Stresses & Deformations Preliminary Results

    E-Print Network [OSTI]

    McDonald, Kirk

    Cross Section of Coils & Shielding Vessels; Stresses & Deformations Preliminary Results Bob Weggel 7/5--7/26/2011 The inner radius of the bore tube of the inner shielding vessel (longitudinal axis compressed) of inner and outer shielding vessels of design "Shields50mm.mph", including

  4. Catcher Vessel Trawl DFL Page 1 of 5 Updated August 30, 2011

    E-Print Network [OSTI]

    Catcher Vessel Trawl DFL Page 1 of 5 Updated August 30, 2011 Instructions for GROUNDFISH DAILY FISHING LOGBOOK (DFL) CATCHER VESSEL TRAWL GEAR RESPONSIBILITY Unless using a NMFS-approved catcher vessel trawl gear electronic logbook (ELB), the owner or operator of a catcher vessel 60 feet or greater length

  5. Catcher Vessel Longline or Pot Gear DFL Page 1 of 8 Updated August 30, 2011

    E-Print Network [OSTI]

    Catcher Vessel Longline or Pot Gear DFL Page 1 of 8 Updated August 30, 2011 Instructions for GROUNDFISH DAILY FISHING LOGBOOK (DFL) CATCHER VESSEL LONGLINE & POT GEAR RESPONSIBILITY Unless using a NMFS-approved catcher vessel longline or pot gear electronic logbook (ELB), the owner or operator of a catcher vessel 60

  6. Reactor vessel using metal oxide ceramic membranes

    DOE Patents [OSTI]

    Anderson, Marc A. (Madison, WI); Zeltner, Walter A. (Oregon, WI)

    1992-08-11

    A reaction vessel for use in photoelectrochemical reactions includes as its reactive surface a metal oxide porous ceramic membrane of a catalytic metal such as titanium. The reaction vessel includes a light source and a counter electrode. A provision for applying an electrical bias between the membrane and the counter electrode permits the Fermi levels of potential reaction to be favored so that certain reactions may be favored in the vessel. The electrical biasing is also useful for the cleaning of the catalytic membrane.

  7. Nuclear reactor vessel fuel thermal insulating barrier

    DOE Patents [OSTI]

    Keegan, C. Patrick; Scobel, James H.; Wright, Richard F.

    2013-03-19

    The reactor vessel of a nuclear reactor installation which is suspended from the cold leg nozzles in a reactor cavity is provided with a lower thermal insulating barrier spaced from the reactor vessel that has a hemispherical lower section that increases in volume from the center line of the reactor to the outer extent of the diameter of the thermal insulating barrier and smoothly transitions up the side walls of the vessel. The space between the thermal insulating harrier and the reactor vessel forms a chamber which can be flooded with cooling water through passive valving to directly cool the reactor vessel in the event of a severe accident. The passive inlet valve for the cooling water includes a buoyant door that is normally maintained sealed under its own weight and floats open when the cavity is Hooded. Passively opening steam vents are also provided.

  8. Solution of the Boussinesq equation using evolutionary vessels

    E-Print Network [OSTI]

    Andrey Melnikov

    2013-01-11

    In this work we present a solution of the Boussinesq equation. The derived formulas include solitons, Schwartz class solutions and solutions, possessing singularities on a closed set Z of the (x,t) domain, obtained from the zeros of the tau function. The idea for solving the Boussinesq equation is identical to the (unified) idea of solving the KdV and the evolutionary NLS equations: we use a theory of evolutionary vessels. But a more powerful theory of non-symmetric evolutionary vessels is presented, inserting flexibility into the construction and allowing to deal with complex-valued solutions. A powerful scattering theory of Deift-Tomei-Trubowitz for a three dimensional operator, which is used to solve the Boussinesq equation, fits into our setting only in a particular case. On the other hand, we create a much wider class of solutions of the Boussinesq equation with singularities on a closed set $Z$.

  9. Thermal Analysis to Calculate the Vessel Temperature and Stress in Alcator C-Mod Due to the Divertor Upgrade

    SciTech Connect (OSTI)

    Han Zhang, Peter H. Titus, Robert Ellis, Soren Harrison and Rui Vieira

    2012-08-29

    Alcator C-Mod is planning an upgrade to its outer divertor. The upgrade is intended to correct the existing outer divertor alignment with the plasma, and to operate at elevated temperatures. Higher temperature operation will allow study of edge physics behavior at reactor relevant temperatures. The outer divertor and tiles will be capable of operating at 600oC. Longer pulse length, together with the plasma and RF heat of 9MW, and the inclusion of heater elements within the outer divertor produces radiative energy which makes the sustained operation much more difficult than before. An ANSYS model based on ref. 1 was built for the global thermal analysis of C-Mod. It models the radiative surfaces inside the vessel and between the components, and also includes plasma energy deposition. Different geometries have been simulated and compared. Results show that steady state operation with the divertor at 600oC is possible with no damage to major vessel internal components. The differential temperature between inner divertor structure, or "girdle" and inner vessel wall is ~70oC. This differential temperature is limited by the capacity of the studs that hold the inner divertor backing plates to the vessel wall. At a 70oC temperature differential the stress on the studs is within allowable limits. The thermal model was then used for a stress pass to quantify vessel shell stresses where thermal gradients are significant.

  10. Dual shell pressure balanced vessel

    DOE Patents [OSTI]

    Fassbender, Alexander G. (West Richland, WA)

    1992-01-01

    A dual-wall pressure balanced vessel for processing high viscosity slurries at high temperatures and pressures having an outer pressure vessel and an inner vessel with an annular space between the vessels pressurized at a pressure slightly less than or equivalent to the pressure within the inner vessel.

  11. Reactor Vessel and Reactor Vessel Internals Segmentation at Zion Nuclear Power Station - 13230

    SciTech Connect (OSTI)

    Cooke, Conrad; Spann, Holger

    2013-07-01

    Zion Nuclear Power Station (ZNPS) is a dual-unit Pressurized Water Reactor (PWR) nuclear power plant located on the Lake Michigan shoreline, in the city of Zion, Illinois approximately 64 km (40 miles) north of Chicago, Illinois and 67 km (42 miles) south of Milwaukee, Wisconsin. Each PWR is of the Westinghouse design and had a generation capacity of 1040 MW. Exelon Corporation operated both reactors with the first unit starting production of power in 1973 and the second unit coming on line in 1974. The operation of both reactors ceased in 1996/1997. In 2010 the Nuclear Regulatory Commission approved the transfer of Exelon Corporation's license to ZionSolutions, the Long Term Stewardship subsidiary of EnergySolutions responsible for the decommissioning of ZNPS. In October 2010, ZionSolutions awarded Siempelkamp Nuclear Services, Inc. (SNS) the contract to plan, segment, remove, and package both reactor vessels and their respective internals. This presentation discusses the tools employed by SNS to remove and segment the Reactor Vessel Internals (RVI) and Reactor Vessels (RV) and conveys the recent progress. SNS's mechanical segmentation tooling includes the C-HORCE (Circumferential Hydraulically Operated Cutting Equipment), BMT (Bolt Milling Tool), FaST (Former Attachment Severing Tool) and the VRS (Volume Reduction Station). Thermal segmentation of the reactor vessels will be accomplished using an Oxygen- Propane cutting system. The tools for internals segmentation were designed by SNS using their experience from other successful reactor and large component decommissioning and demolition (D and D) projects in the US. All of the designs allow for the mechanical segmentation of the internals remotely in the water-filled reactor cavities. The C-HORCE is designed to saw seven circumferential cuts through the Core Barrel and Thermal Shield walls with individual thicknesses up to 100 mm (4 inches). The BMT is designed to remove the bolts that fasten the Baffle Plates to the Baffle Former Plates. The FaST is designed to remove the Baffle Former Plates from the Core Barrel. The VRS further volume reduces segmented components using multiple configurations of the 38i and horizontal reciprocating saws. After the successful removal and volume reduction of the Internals, the RV will be segmented using a 'First in the US' thermal cutting process through a co-operative effort with Siempelkamp NIS Ingenieurgesellschaft mbH using their experience at the Stade NPP and Karlsruhe in Germany. SNS mobilized in the fall of 2011 to commence execution of the project in order to complete the RVI segmentation, removal and packaging activities for the first unit (Unit 2) by end of the 2012/beginning 2013 and then mobilize to the second unit, Unit 1. Parallel to the completion of the segmentation of the reactor vessel internals at Unit 1, SNS will segment the Unit 2 pressure vessel and at completion move to Unit 1. (authors)

  12. Thermal wake/vessel detection technique

    DOE Patents [OSTI]

    Roskovensky, John K. (Albuquerque, NM); Nandy, Prabal (Albuquerque, NM); Post, Brian N (Albuquerque, NM)

    2012-01-10

    A computer-automated method for detecting a vessel in water based on an image of a portion of Earth includes generating a thermal anomaly mask. The thermal anomaly mask flags each pixel of the image initially deemed to be a wake pixel based on a comparison of a thermal value of each pixel against other thermal values of other pixels localized about each pixel. Contiguous pixels flagged by the thermal anomaly mask are grouped into pixel clusters. A shape of each of the pixel clusters is analyzed to determine whether each of the pixel clusters represents a possible vessel detection event. The possible vessel detection events are represented visually within the image.

  13. Photoacoustic spectroscopy sample array vessel and photoacoustic spectroscopy method for using the same

    DOE Patents [OSTI]

    Amonette, James E.; Autrey, S. Thomas; Foster-Mills, Nancy S.; Green, David

    2005-03-29

    Methods and apparatus for analysis of multiple samples by photoacoustic spectroscopy are disclosed. Particularly, a photoacoustic spectroscopy sample array vessel including a vessel body having multiple sample cells connected thereto is disclosed. At least one acoustic detector is acoustically coupled with the vessel body. Methods for analyzing the multiple samples in the sample array vessels using photoacoustic spectroscopy are provided.

  14. ASSESSMENT OF THE POTENTIAL FOR HYDROGEN GENERATION DURING DEACTIVATION AND DECOMMISSIONING OF REACTOR VESSELS AT THE SAVANNAH RIVER SITE

    SciTech Connect (OSTI)

    Wiersma, B.; Serrato, M.; Langton, C.

    2010-11-10

    The R- and P-reactor vessels at the Savannah River Site (SRS) are being prepared for deactivation and decommissioning (D&D). D&D activities will consist primarily of physically isolating and stabilizing the reactor vessel by filling it with a grout material. The reactor vessels contain aluminum alloy materials, which pose a concern in that aluminum corrodes rapidly when it comes in contact with the alkaline grout. A product of the corrosion reaction is hydrogen gas and therefore potential flammability issues were assessed. A model was developed to calculate the hydrogen generation rate as the reactor is being filled with the grout material. Three options existed for the type of grout material for D&D of the reactor vessels. The grout formulation options included ceramicrete (pH 6-8), a calcium aluminate sulfate (CAS) based cement (pH 10), or Portland cement grout (pH 12.4). Corrosion data for aluminum in concrete were utilized as input for the model. The calculations considered such factors as the surface area of the aluminum components, the open cross-sectional area of the reactor vessel, the rate at which the grout is added to the reactor vessel, and temperature. Given the hydrogen generation rate, the hydrogen concentration in the vapor space of the reactor vessel above the grout was calculated. This concentration was compared to the lower flammability limit for hydrogen. The assessment concluded that either ceramicrete or the CAS grout may be used to safely grout the P-reactor vessel. The risk of accumulation of a flammable mixture of hydrogen between the grout-air interface and the top of the reactor is very low. Portland cement grout, on the other hand, for the same range of process parameters did not provide a margin of safety against the accumulation of flammable gas in the reactor vessel during grouting operations in the P-reactor vessel. Therefore, it was recommended that this grout not be utilized for this task. On the other hand, the R-reactor vessel contained significantly less aluminum surface area that the P-reactor vessel based on current facility process knowledge, surface observations, and drawings. Therefore, a Portland cement grout may be considered for grouting operations as well as the other grout formulations.

  15. A Xenon Condenser with a Remote Liquid Storage Vessel

    E-Print Network [OSTI]

    S. Slutsky; Y. -R. Yen; H. Breuer; A. Dobi; C. Hall; T. Langford; D. S. Leonard; L. J. Kaufman; V. Strickland; N. Voskanian

    2009-07-25

    We describe the design and operation of a system for xenon liquefaction in which the condenser is separated from the liquid storage vessel. The condenser is cooled by a pulse tube cryocooler, while the vessel is cooled only by the liquid xenon itself. This arrangement facilitates liquid particle detector research by allowing easy access to the upper and lower flanges of the vessel. We find that an external xenon gas pump is useful for increasing the rate at which cooling power is delivered to the vessel, and we present measurements of the power and efficiency of the apparatus.

  16. Zone separator for multiple zone vessels

    DOE Patents [OSTI]

    Jones, John B. (Grand Junction, CO)

    1983-02-01

    A solids-gas contact vessel, having two vertically disposed distinct reaction zones, includes a dynamic seal passing solids from an upper to a lower zone and maintaining a gas seal against the transfer of the separate treating gases from one zone to the other, and including a stream of sealing fluid at the seal.

  17. Reactor pressure vessel vented head

    DOE Patents [OSTI]

    Sawabe, J.K.

    1994-01-11

    A head for closing a nuclear reactor pressure vessel shell includes an arcuate dome having an integral head flange which includes a mating surface for sealingly mating with the shell upon assembly therewith. The head flange includes an internal passage extending therethrough with a first port being disposed on the head mating surface. A vent line includes a proximal end disposed in flow communication with the head internal passage, and a distal end disposed in flow communication with the inside of the dome for channeling a fluid therethrough. The vent line is fixedly joined to the dome and is carried therewith when the head is assembled to and disassembled from the shell. 6 figures.

  18. Vessel with filter and method of use

    DOE Patents [OSTI]

    Morrell, Jonathan S.; Ripley, Edward B.; Cecala, David M.

    2008-01-29

    Chemical processing apparatuses which incorporate a process vessel, such as a crucible or retort, and which include a gas separation or filtration system. Various embodiments incorporate such features as loose filtration material, semi-rigid filtration material, and structured filtration material. The vessel may include material that is a microwave susceptor. Filtration media may be selected so that if it inadvertently mixes with the chemical process or the reaction products of such process, it would not adversely affect the results of the chemical process.

  19. Scaled Testing to Evaluate Pulse Jet Mixer Performance in Waste Treatment Plant Mixing Vessels

    SciTech Connect (OSTI)

    Fort, James A.; Meyer, Perry A.; Bamberger, Judith A.; Enderlin, Carl W.; Scott, Paul A.; Minette, Michael J.; Gauglitz, Phillip A.

    2010-03-07

    The Waste Treatment and Immobilization Plant (WTP) at Hanford is being designed and built to pre-treat and vitrify the waste in Hanford’s 177 underground waste storage tanks. Numerous process vessels will hold waste at various stages in the WTP. These vessels have pulse jet mixer (PJM) systems. A test program was developed to evaluate the adequacy of mixing system designs in the solids-containing vessels in the WTP. The program focused mainly on non-cohesive solids behavior. Specifically, the program addressed the effectiveness of the mixing systems to suspend settled solids off the vessel bottom, and distribute the solids vertically. Experiments were conducted at three scales using various particulate simulants. A range of solids loadings and operational parameters were evaluated, including jet velocity, pulse volume, and duty cycle. In place of actual PJMs, the tests used direct injection from tubes with suction at the top of the tank fluid. This gave better control over the discharge duration and duty cycle and simplified the facility requirements. The mixing system configurations represented in testing varied from 4 to 12 PJMs with various jet nozzle sizes. In this way the results collected could be applied to the broad range of WTP vessels with varying geometrical configurations and planned operating conditions. Data for “just-suspended velocity”, solids cloud height, and solids concentration vertical profile were collected, analyzed, and correlated. The correlations were successfully benchmarked against previous large-scale test results, then applied to the WTP vessels using reasonable assumptions of anticipated waste properties to evaluate adequacy of the existing mixing system designs.

  20. Tone signal generator for producing multioperator tone signals using an operator circuit including a waveform generator, a selector and an enveloper

    DOE Patents [OSTI]

    Dong, Q.; Jenkins, M.V.; Bernadas, S.R.

    1997-09-09

    A frequency modulation (FM) tone signal generator for generating a FM tone signal is disclosed. The tone signal generator includes a waveform generator having a plurality of wave tables, a selector and an enveloper. The waveform generator furnishes a waveform signal in response to a phase angle address signal. Each wave table stores a different waveform. The selector selects one of the wave tables in response to a plurality of selection signals such that the selected wave table largely provides the waveform signal upon being addressed largely by the phase angle address signal. Selection of the selected wave table varies with each selection signal. The enveloper impresses an envelope signal on the waveform signal. The envelope signal is used as a carrier or modulator for generating the FM tone signal. 17 figs.

  1. Scaling Theory for Pulsed Jet Mixed Vessels, Sparging, and Cyclic Feed Transport Systems for Slurries

    SciTech Connect (OSTI)

    Kuhn, William L.; Rector, David R.; Rassat, Scot D.; Enderlin, Carl W.; Minette, Michael J.; Bamberger, Judith A.; Josephson, Gary B.; Wells, Beric E.; Berglin, Eric J.

    2013-09-27

    This document is a previously unpublished work based on a draft report prepared by Pacific Northwest National Laboratory (PNNL) for the Hanford Waste Treatment and Immobilization Plant (WTP) in 2012. Work on the report stopped when WTP’s approach to testing changed. PNNL is issuing a modified version of the document a year later to preserve and disseminate the valuable technical work that was completed. This document establishes technical bases for evaluating the mixing performance of Waste Treatment Plant (WTP) pretreatment process tanks based on data from less-than-full-scale testing, relative to specified mixing requirements. The technical bases include the fluid mechanics affecting mixing for specified vessel configurations, operating parameters, and simulant properties. They address scaling vessel physical performance, simulant physical performance, and “scaling down” the operating conditions at full scale to define test conditions at reduced scale and “scaling up” the test results at reduced scale to predict the performance at full scale. Essentially, this document addresses the following questions: • Why and how can the mixing behaviors in a smaller vessel represent those in a larger vessel? • What information is needed to address the first question? • How should the information be used to predict mixing performance in WTP? The design of Large Scale Integrated Testing (LSIT) is being addressed in other, complementary documents.

  2. Method and device for supporting blood vessels during anastomosis

    DOE Patents [OSTI]

    Doss, J.D.

    1985-05-20

    A device and method for preventing first and second severed blood vessels from collapsing during attachment to each other. The device comprises a dissolvable non-toxic stent that is sufficiently rigid to prevent the blood vessels from collapsing during anastomosis. The stent can be hollow or have passages to permit blood flow before it dissolves. A single stent can be inserted with an end in each of the two blood vessels or separate stents can be inserted into each blood vessel. The stent may include a therapeutically effective amount of a drug which is slowly released into the blood stream as the stent dissolves. 12 figs.

  3. LQG Dynamic Positioning for a Supply Vessel

    E-Print Network [OSTI]

    Hansen, Scott Ron

    8  2.1.   Vessel9  2.1.2.   3 DOF Marine Vessel Equations ofPositioning for a Supply Vessel A Thesis submitted in

  4. Radiant vessel auxiliary cooling system

    DOE Patents [OSTI]

    Germer, John H. (San Jose, CA)

    1987-01-01

    In a modular liquid-metal pool breeder reactor, a radiant vessel auxiliary cooling system is disclosed for removing the residual heat resulting from the shutdown of a reactor by a completely passive heat transfer system. A shell surrounds the reactor and containment vessel, separated from the containment vessel by an air passage. Natural circulation of air is provided by air vents at the lower and upper ends of the shell. Longitudinal, radial and inwardly extending fins extend from the shell into the air passage. The fins are heated by radiation from the containment vessel and convect the heat to the circulating air. Residual heat from the primary reactor vessel is transmitted from the reactor vessel through an inert gas plenum to a guard or containment vessel designed to contain any leaking coolant. The containment vessel is conventional and is surrounded by the shell.

  5. nAture methods | VOL.7 NO.8 | august2010 | 655 not all tumor vessels are equal. tumor-associated vasculature

    E-Print Network [OSTI]

    Cai, Long

    Articles nAture methods | VOL.7 NO.8 | august2010 | 655 not all tumor vessels are equal. tumor-associated vasculature includes immature vessels, regressing vessels, transport vessels undergoing arteriogenesis and peritumor vessels influenced by tumor growth factors. current techniques for analyzing tumor blood flow do

  6. Fish Bulletin. Fishing Party Vessels

    E-Print Network [OSTI]

    State of California, Department of Fish and Game

    1990-01-01

    FISH BULLETIN: Fishing Party Vessels In the Text and Excelby the passenger carrying fishing industry (party boat). The

  7. Original Investigation Vessel Specific Coronary Artery

    E-Print Network [OSTI]

    van Vliet, Lucas J.

    Original Investigation Vessel Specific Coronary Artery Calcium Scoring: An Automatic System Rahil heart as well as per coronary artery on non-contrast-enhanced cardiac computed tomographic images and tested on 157 data sets. Statistical testing included determining Pearson's correlation coefficients

  8. Original Investigations Vessel Specific Coronary Artery

    E-Print Network [OSTI]

    van Vliet, Lucas J.

    Original Investigations Vessel Specific Coronary Artery Calcium Scoring: An Automatic System Rahil heart as well as per coronary artery on non-contrast-enhanced cardiac computed tomographic images and tested on 157 data sets. Statistical testing included determining Pearson's correlation coefficients

  9. High pressure storage vessel

    DOE Patents [OSTI]

    Liu, Qiang

    2013-08-27

    Disclosed herein is a composite pressure vessel with a liner having a polar boss and a blind boss a shell is formed around the liner via one or more filament wrappings continuously disposed around at least a substantial portion of the liner assembly combined the liner and filament wrapping have a support profile. To reduce susceptible to rupture a locally disposed filament fiber is added.

  10. Casting Apparatus Including A Gas Driven Molten Metal Injector And Method

    DOE Patents [OSTI]

    Meyer, Thomas N. (Murrysville, PA)

    2004-06-01

    The casting apparatus (50) includes a holding vessel (10) for containing a supply of molten metal (12) and a casting mold (52) located above the holding vessel (10) and having a casting cavity (54). A molten metal injector (14) extends into the holding vessel (10) and is at least partially immersed in the molten metal (12) in the holding vessel (10). The molten metal injector (14) is in fluid communication with the casting cavity (54). The molten metal injector (14) has an injector body (16) defining an inlet opening (24) for receiving molten metal into the injector body (16). A gas pressurization source (38) is in fluid communication with the injector body (16) for cyclically pressurizing the injector body (16) and inducing molten metal to flow from the injector body (16) to the casting cavity (54). An inlet valve (42) is located in the inlet opening (24) in the injector body (16) for filling molten metal into the injector body (16). The inlet valve (42) is configured to prevent outflow of molten metal from the injector body (16) during pressurization and permit inflow of molten metal into the injector body (16) after pressurization. The inlet valve (42) has an inlet valve actuator (44) located above the surface of the supply of molten metal (12) and is operatively connected to the inlet valve (42) for operating the inlet valve (42) between open and closed positions.

  11. Investigation of Cracked Lithium Hydride Reactor Vessels

    SciTech Connect (OSTI)

    bird, e.l.; mustaleski, t.m.

    1999-06-01

    Visual examination of lithium hydride reactor vessels revealed cracks that were adjacent to welds, most of which were circumferentially located in the bottom portion of the vessels. Sections were cut from the vessels containing these cracks and examined by use of the metallograph, scanning electron microscope, and microprobe to determine the cause of cracking. Most of the cracks originated on the outer surface just outside the weld fusion line in the base material and propagated along grain boundaries. Crack depths of those examined sections ranged from {approximately}300 to 500 {micro}m. Other cracks were reported to have reached a maximum depth of 1/8 in. The primary cause of cracking was the creation of high tensile stresses associated with the differences in the coefficients of thermal expansion between the filler metal and the base metal during operation of the vessel in a thermally cyclic environment. This failure mechanism could be described as creep-type fatigue, whereby crack propagation may have been aided by the presence of brittle chromium carbides along the grain boundaries, which indicates a slightly sensitized microstructure.

  12. Photoacoustic spectroscopy sample array vessels and photoacoustic spectroscopy methods for using the same

    DOE Patents [OSTI]

    Amonette, James E.; Autrey, S. Thomas; Foster-Mills, Nancy S.

    2006-02-14

    Methods and apparatus for simultaneous or sequential, rapid analysis of multiple samples by photoacoustic spectroscopy are disclosed. Particularly, a photoacoustic spectroscopy sample array vessel including a vessel body having multiple sample cells connected thereto is disclosed. At least one acoustic detector is acoustically positioned near the sample cells. Methods for analyzing the multiple samples in the sample array vessels using photoacoustic spectroscopy are provided.

  13. Effect of soluble epoxide hydrolase inhibition on epoxyeicosatrienoic acid metabolism in human blood vessels

    E-Print Network [OSTI]

    Hammock, Bruce D.

    blood vessels Xiang Fang,1 Neal L. Weintraub,2,3,4 Ryan B. McCaw,1 Shanming Hu,1 Shawn D. Harmon,1 James on epoxyeicosatrienoic acid metabolism in human blood vessels. Am J Physiol Heart Circ Physiol 287: H2412­H2420, 2004 vessels, including the human saphenous vein (HSV), coronary artery (HCA), and aorta (HA). When HSV

  14. Using SA508/533 for the HTGR Vessel Material

    SciTech Connect (OSTI)

    Larry Demick

    2012-06-01

    This paper examines the influence of High Temperature Gas-cooled Reactor (HTGR) module power rating and normal operating temperatures on the use of SA508/533 material for the HTGR vessel system with emphasis on the calculated times at elevated temperatures approaching or exceeding ASME Code Service Limits (Levels B&C) to which the reactor pressure vessel could be exposed during postulated pressurized and depressurized conduction cooldown events over its design lifetime.

  15. Dual shell pressure balanced reactor vessel. Final project report

    SciTech Connect (OSTI)

    Robertus, R.J.; Fassbender, A.G.

    1994-10-01

    The Department of Energy`s Office of Energy Research (OER) has previously provided support for the development of several chemical processes, including supercritical water oxidation, liquefaction, and aqueous hazardous waste destruction, where chemical and phase transformations are conducted at high pressure and temperature. These and many other commercial processes require a pressure vessel capable of operating in a corrosive environment where safety and economy are important requirements. Pacific Northwest Laboratory (PNL) engineers have recently developed and patented (U.S. patent 5,167,930 December 1, 1992) a concept for a novel Dual Shell Pressure Balanced Vessel (DSPBV) which could solve a number of these problems. The technology could be immediately useful in continuing commercialization of an R&D 100 award-winning technology, Sludge-to-oil Reactor System (STORS), originally developed through funding by OER. Innotek Corporation is a small business that would be one logical end-user of the DSPBV reactor technology. Innotek is working with several major U.S. engineering firms to evaluate the potential of this technology in the disposal of wastes from sewage treatment plants. PNL entered into a CRADA with Innotek to build a bench-scale demonstration reactor and test the system to advance the economic feasibility of a variety of high pressure chemical processes. Hydrothermal processing of corrosive substances on a large scale can now be made significantly safer and more economical through use of the DSPBV. Hydrothermal chemical reactions such as wet-air oxidation and supercritical water oxidation occur in a highly corrosive environment inside a pressure vessel. Average corrosion rates from 23 to 80 miles per year have been reported by Rice (1994) and Latanision (1993).

  16. Iranian Long Spouted Vessels of the Third and Second Millennium BCE: Contextualizing an Enigmatic Vessel 

    E-Print Network [OSTI]

    Cromartie, Amy

    2014-01-01

    Long Spouted Vessels of the Third and SecondContextualizing an Enigmatic Vessel Reflective Essay By Amylong spouted Iranian bronze vessel from the third millennium

  17. A wall-crawling robot for reactor vessel inspection in advanced reactors

    SciTech Connect (OSTI)

    Spelt, P.F.; Crane, C.; Feng, L.; Abidi, M.; Tosunoglu, S.

    1994-06-01

    A consortium of four universities and the Center for Engineering Systems Advanced Research of the Oak Ridge National Laboratory has designed a prototype wall-crawling robot to perform weld inspection in advanced nuclear reactors. Design efforts for the reactor vessel inspection robot (RVIR) concentrated on the Advanced Liquid Metal Reactor because it presents the most demanding environment in which such a robot must operate. The RVIR consists of a chassis containing two sets of suction cups that can alternately grasp the side of the vessel being inspected, providing both locomotion and steering functions. Sensors include three CCD cameras and a weld inspection device based on new shear-wave technology. The restrictions of the inspection environment presented major challenges to the team. These challenges were met in the prototype, which has been tested in a non-radiation, room-temperature mockup of the robot work environment and shown to perform as expected.

  18. Photoacoustic removal of occlusions from blood vessels

    DOE Patents [OSTI]

    Visuri, Steven R. (Livermore, CA); Da Silva, Luiz B. (Danville, CA); Celliers, Peter M. (Berkeley, CA); London, Richard A. (Orinda, CA); Maitland, IV, Duncan J. (Lafayette, CA); Esch, Victor C. (San Francisco, CA)

    2002-01-01

    Partial or total occlusions of fluid passages within the human body are removed by positioning an array of optical fibers in the passage and directing treatment radiation pulses along the fibers, one at a time, to generate a shock wave and hydrodynamics flows that strike and emulsify the occlusions. A preferred application is the removal of blood clots (thrombin and embolic) from small cerebral vessels to reverse the effects of an ischemic stroke. The operating parameters and techniques are chosen to minimize the amount of heating of the fragile cerebral vessel walls occurring during this photo acoustic treatment. One such technique is the optical monitoring of the existence of hydrodynamics flow generating vapor bubbles when they are expected to occur and stopping the heat generating pulses propagated along an optical fiber that is not generating such bubbles.

  19. Coal gasification vessel

    DOE Patents [OSTI]

    Loo, Billy W. (Oakland, CA)

    1982-01-01

    A vessel system (10) comprises an outer shell (14) of carbon fibers held in a binder, a coolant circulation mechanism (16) and control mechanism (42) and an inner shell (46) comprised of a refractory material and is of light weight and capable of withstanding the extreme temperature and pressure environment of, for example, a coal gasification process. The control mechanism (42) can be computer controlled and can be used to monitor and modulate the coolant which is provided through the circulation mechanism (16) for cooling and protecting the carbon fiber and outer shell (14). The control mechanism (42) is also used to locate any isolated hot spots which may occur through the local disintegration of the inner refractory shell (46).

  20. Confinement Vessel Assay System: Design and Implementation Report

    SciTech Connect (OSTI)

    Frame, Katherine C. [Los Alamos National Laboratory; Bourne, Mark M. [Los Alamos National Laboratory; Crooks, William J. [Los Alamos National Laboratory; Evans, Louise [Los Alamos National Laboratory; Mayo, Douglas R. [Los Alamos National Laboratory; Gomez, Cipriano D. [Retired CMR-OPS: OPERATIONS; Miko, David K. [Los Alamos National Laboratory; Salazar, William R. [Los Alamos National Laboratory; Stange, Sy [Los Alamos National Laboratory; Vigil, Georgiana M. [Los Alamos National Laboratory

    2012-07-18

    Los Alamos National Laboratory has a number of spherical confinement vessels remaining from tests involving nuclear materials. These vessels have an inner diameter of 6 feet with 1- to 2-inch thick steel walls. The goal of the Confinement Vessel Disposition (CVD) project is to remove debris and reduce contamination inside the vessels. We have developed a neutron assay system for the purposes of Materials Control and Accountability (MC&A) measurements of the vessel prior to and after cleanout. We present our approach to confronting the challenges in designing, building, and testing such a system. The system was designed to meet a set of functional and operational requirements. A Monte Carlo model was developed to aid in optimizing the detector design as well as to predict the systematic uncertainty associated with confinement vessel measurements. Initial testing was performed to optimize and determine various measurement parameters, and then the system was characterized using {sup 252}Cf placed a various locations throughout the measurement system. Measurements were also performed with a {sup 252}Cf source placed inside of small steel and HDPE shells to study the effect of moderation. These measurements compare favorably with their MCNPX model equivalent, making us confident that we can rely on the Monte Carlo simulation to predict the systematic uncertainty due to variations in response to material that may be localized at different points within a vessel.

  1. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Vessel Time Exposure Escort for all Focus Vessels on Haro Routes Draft #12;11/21/2013 2 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 DEFINITION OF ASSUMED LOCATIONS FOR ADDED ESCORT VESSEL FOR HARO-BOUNDARY ROUTES (GREEN

  2. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Vessel Time Exposure-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 DEFINITION OF ASSUMED LOCATIONS FOR ADDED ESCORT VESSEL All FV - Vessel Time Exposure: 125% of Base Case VTE 23-24 22-23 21-22 20-21 19-20 18-19 17-18 16

  3. A Survey of Pressure Vessel Code Compliance for Superconducting RF Cryomodules

    SciTech Connect (OSTI)

    Peterson, Thomas; Klebaner, Arkadiy; Nicol, Tom; Theilacker, Jay; /Fermilab; Hayano, Hitoshi; Kako, Eiji; Nakai, Hirotaka; Yamamoto, Akira; /KEK, Tsukuba; Jensch, Kay; Matheisen, Axel; /DESY; Mammosser, John; /Jefferson Lab

    2011-06-07

    Superconducting radio frequency (SRF) cavities made from niobium and cooled with liquid helium are becoming key components of many particle accelerators. The helium vessels surrounding the RF cavities, portions of the niobium cavities themselves, and also possibly the vacuum vessels containing these assemblies, generally fall under the scope of local and national pressure vessel codes. In the U.S., Department of Energy rules require national laboratories to follow national consensus pressure vessel standards or to show ''a level of safety greater than or equal to'' that of the applicable standard. Thus, while used for its superconducting properties, niobium ends up being treated as a low-temperature pressure vessel material. Niobium material is not a code listed material and therefore requires the designer to understand the mechanical properties for material used in each pressure vessel fabrication; compliance with pressure vessel codes therefore becomes a problem. This report summarizes the approaches that various institutions have taken in order to bring superconducting RF cryomodules into compliance with pressure vessel codes. In Japan, Germany, and the U.S., institutions building superconducting RF cavities integrated in helium vessels or procuring them from vendors have had to deal with pressure vessel requirements being applied to SRF vessels, including the niobium and niobium-titanium components of the vessels. While niobium is not an approved pressure vessel material, data from tests of material samples provide information to set allowable stresses. By means of procedures which include adherence to code welding procedures, maintaining material and fabrication records, and detailed analyses of peak stresses in the vessels, or treatment of the vacuum vessel as the pressure boundary, research laboratories around the world have found methods to demonstrate and document a level of safety equivalent to the applicable pressure vessel codes.

  4. Impacts of reducing shipboard NOx? and SOx? emissions on vessel performance

    E-Print Network [OSTI]

    Caputo, Ronald J., Jr. (Ronald Joseph)

    2010-01-01

    The international maritime community has been experiencing tremendous pressures from environmental organizations to reduce the emissions footprint of their vessels. In the last decade, air emissions, including nitrogen ...

  5. Nuclear reactor construction with bottom supported reactor vessel

    DOE Patents [OSTI]

    Sharbaugh, John E. (Bullskin Township, Fayette County, PA)

    1987-01-01

    An improved liquid metal nuclear reactor construction has a reactor core and a generally cylindrical reactor vessel for holding a large pool of low pressure liquid metal coolant and housing the core within the pool. The reactor vessel has an open top end, a closed flat bottom end wall and a continuous cylindrical closed side wall interconnecting the top end and bottom end wall. The reactor also has a generally cylindrical concrete containment structure surrounding the reactor vessel and being formed by a cylindrical side wall spaced outwardly from the reactor vessel side wall and a flat base mat spaced below the reactor vessel bottom end wall. A central support pedestal is anchored to the containment structure base mat and extends upwardly therefrom to the reactor vessel and upwardly therefrom to the reactor core so as to support the bottom end wall of the reactor vessel and the lower end of the reactor core in spaced apart relationship above the containment structure base mat. Also, an annular reinforced support structure is disposed in the reactor vessel on the bottom end wall thereof and extends about the lower end of the core so as to support the periphery thereof. In addition, an annular support ring having a plurality of inward radially extending linear members is disposed between the containment structure base mat and the bottom end of the reactor vessel wall and is connected to and supports the reactor vessel at its bottom end on the containment structure base mat so as to allow the reactor vessel to expand radially but substantially prevent any lateral motions that might be imposed by the occurrence of a seismic event. The reactor construction also includes a bed of insulating material in sand-like granular form, preferably being high density magnesium oxide particles, disposed between the containment structure base mat and the bottom end wall of the reactor vessel and uniformly supporting the reactor vessel at its bottom end wall on the containment structure base mat so as to insulate the reactor vessel bottom end wall from the containment structure base mat and allow the reactor vessel bottom end wall to freely expand as it heats up while providing continuous support thereof. Further, a deck is supported upon the side wall of the containment structure above the top open end of the reactor vessel, and a plurality of serially connected extendible and retractable annular bellows extend between the deck and the top open end of the reactor vessel and flexibly and sealably interconnect the reactor vessel at its top end to the deck. An annular guide ring is disposed on the containment structure and extends between its side wall and the top open end of the reactor vessel for providing lateral support of the reactor vessel top open end by limiting imposition of lateral loads on the annular bellows by the occurrence of a lateral seismic event.

  6. Regional Class Research VesselsThe next generation of ships for coastal science

    E-Print Network [OSTI]

    Kurapov, Alexander

    research vessels as depicted in the image. OSU will operate the West Coast's RCRV and create new economies aim to strategically revitalize the U.S. fleet via the introduction of new vessels in the various algal blooms · Underwater earthquakes and tsunamis · Engineering & robotics · Wave & tidal energy

  7. FFTF thermal-hydraulic testing results affecting piping and vessel component design in LMFBR's

    SciTech Connect (OSTI)

    Stover, R.L.; Beaver, T.R.; Chang, S.C.

    1983-01-01

    The Fast Flux Test Facility completed four years of pre-operational testing in April 1982. This paper describes thermal-hydraulic testing results from this period which impact piping and vessel component design in LMFBRs. Data discussed are piping flow oscillations, piping thermal stratification and vessel upper plenum stratification. Results from testing verified that plant design limits were met.

  8. The bunkering industry and its effect on shipping tanker operations

    E-Print Network [OSTI]

    Boutsikas, Angelos

    2004-01-01

    The bunkering industry provides the shipping industry with the fuel oil that the vessels consume. The quality of the fuel oil provided will ensure the safe operation of vessels. Shipping companies under their fuel oil ...

  9. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Vessel Time Exposure GW-VCU Draft #12;11/21/2013 2 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 RMM 1: Max. Speed of Container Vessels at 17 knots. RMM 2: Reduce Human Error incident on Oil Barges by 50% RMM 3: No Bunkering

  10. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Vessel Time Exposure Escort Cape Size Draft #12;11/21/2013 2 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 DEFINITION OF ASSUMED LOCATIONS FOR ADDED ESCORT VESSEL FOR HARO-BOUNDARY ROUTES (GREEN) AND FOR ROSARIO ROUTES (ORANGE

  11. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Oil Time Exposure Dr & 6 RMM's Draft #12;11/21/2013 2 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 RMM 1: Max. Speed-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 DEFINITION OF ASSUMED LOCATIONS FOR ADDED ESCORT VESSEL

  12. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Potential Grounding/23/2013 2 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 Draft #12;T : GW - KM - DP & +VAR FV 3D Risk-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 Draft #12;12/23/2013 4 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT

  13. MFR PAPER 1075 Soviet vessels " constitute more than

    E-Print Network [OSTI]

    to develop new fishing techniques and methods in order to extend its operations into every ocean in the world into nontraditional fishing areas and to seek new species in order to meet the catch targets set by the centralMFR PAPER 1075 Soviet vessels " constitute more than a quarter of the world's fishing fleet

  14. A mathematical model for batch and continuous thickening of flocculated suspensions in vessels with varying cross-section

    E-Print Network [OSTI]

    Karlsen, Kenneth Hvistendahl

    A mathematical model for batch and continuous thickening of flocculated suspensions in vessels of continuous thickening of flocculated suspensions in an ideal cylindrical thickener is extended to vessels having varying cross-section, including divergent or convergent conical vessels. The purpose

  15. print_grid() add_vessel()

    E-Print Network [OSTI]

    Sharlin, Ehud

    grid.py print_grid() add_vessel() has_overlap() GRID_WIDTH GRID_HEIGHT NUM_VESSELS B VESSEL_NAMES[] VESSEL_SIZES[] human.py get_location() get_choice() grid_defend[] grid_attack[] import grid ai.py get, return false · add_vessel(grid, row, column, size, direction) ­ Check direction ­ Single for loop (size

  16. Late-Phase Melt Conditions Affecting the Potential for In-Vessel Retention in High Power Reactors

    SciTech Connect (OSTI)

    D. L. Knudson; J. L. Rempe; K. G. Condie; K. Y. Suh; F. B.Cheung; S. B. Kim

    2004-05-01

    If cooling is inadequate during a reactor accident, a significant amount of core material could become molten and relocate to the lower head of the reactor vessel, as happened in the Three Mile Island Unit 2 accident. In such a case, concerns about containment failure and associated risks can be eliminated if it is possible to ensure that the lower head remains intact so that relocated core materials are retained within the vessel. Accordingly, in-vessel retention (IVR) of core melt as a key severe accident management strategy has been adopted by some operating nuclear power plants and planned for some advanced light water reactors. However, it is not clear that currently proposed external reactor vessel cooling (ERVC) without additional enhancements can provide sufficient heat removal to assure IVR for high power reactors (i.e., reactors with power levels up to 1500 MWe). Consequently, a joint United States/Korean International Nuclear Energy Research Initiative (I-NERI) has been launched to develop recommendations to improve the margin of success for in-vessel retention in high power reactors. This program is initially focussed on the Korean Advanced Power Reactor—1400 MWe (APR1400) design. However, recommendations will be developed that can be applied to a wide range of existing and advanced reactor designs. The recommendations will focus on modifications to enhance ERVC and modifications to enhance in-vessel debris coolability. In this paper, late-phase melt conditions affecting the potential for IVR of core melt in the APR1400 were established as a basis for developing the I-NERI recommendations. The selection of ‘bounding’ reactor accidents, simulation of those accidents using the SCDAP/RELAP5-3D© code, and resulting late-phase melt conditions are presented. Results from this effort indicate that bounding late-phase melt conditions could include large melt masses (>120,000 kg) relocating at high temperatures (3400 K). Estimated lower head heat fluxes associated with this melt could exceed the maximum critical heat flux, indicating additional measures such as the use of a core catcher and/or modifications to enhance external reactor vessel cooling may be necessary to ensure in-vessel retention of core melt.

  17. Rigorous Simulation of Accidental Leaks from High-Pressure Storage Vessels 

    E-Print Network [OSTI]

    Alisha, -

    2014-07-07

    Several major industrial disasters involve accidental releases of hazardous chemicals from ruptured vessels or pipelines as consequence of equipment failures, maintenance errors, operational errors, cracks, corrosion, ruptures, or also by acts...

  18. The Borobudur Vessels in Context 

    E-Print Network [OSTI]

    Inglis, Douglas Andrew

    2014-07-28

    ). .................................................. 102 Fig. 39. Peterson’s reconstruction of I.b.86 (from Peterson 2006, 54, fig. 8.8). ............ 104 Fig. 40. Van Erp’s Photograph of I.b.86 (after Van Erp 1923, 18, afb. 6). .................... 104 Fig. 41: Sarimanok, built and sailed by Rob..., 28, afb. 10). ................................................... 113 Fig. 48. Vessel I.b.82 is a schematic view of a beached ship’s boat. The vessel is distinctly disproportionate to the figures (photograph after Anandajoti 2009d...

  19. In-Vessel Retention - Recent Efforts and Future Needs

    SciTech Connect (OSTI)

    J. L. Rempe

    2004-10-01

    In-vessel retention (IVR) of core melt is a key severe accident management strategy adopted by some operating nuclear power plants and proposed for some advanced light water reactors (ALWRs). If there were inadequate cooling during a reactor accident, a significant amount of core material could become molten and relocate to the lower head of the reactor vessel, as happened in the Three Mile Island Unit 2 (TMI-2) accident. If it is possible to ensure that the vessel head remains intact so that relocated core materials are retained within the vessel, the enhanced safety associated with these plants can reduce concerns about containment failure and associated risk. However, it is not clear that the external reactor vessel cooling (ERVC) proposed for existing and some advanced reactors would provide sufficient heat removal for higher-power reactors (up to 1400 MWe) without additional enhancements. This paper summarizes recent efforts to enhance IVR and identifies additional needs to demonstrate that there is sufficient margin for successful IVR in high power reactors.

  20. CATCHER VESSEL INTERCOOPERATIVE FINAL REPORT

    E-Print Network [OSTI]

    2001 CATCHER VESSEL INTERCOOPERATIVE FINAL REPORT TO THE NORTH PACIFIC FISHERY MANAGEMENT COUNCIL. The Race for Fish 8 Graph 2.2a 1999 & 2001 Mothership Pollock Harvest 9 Graph 2.2b 1999 & 2001 Inshore - Coop Sideboard Caps, Transfers, and Directed Fishing Appendix IX - BBRKC Management Plan #12;3 Section

  1. COMMERCIAL FISHING VESSELS AND GEAR

    E-Print Network [OSTI]

    COMMERCIAL FISHING VESSELS AND GEAR I Mafine Biological Laboratory SEP 2 01957 WOODS HOLE, MASS. UNITED STATES DEPARTMENT OF THE INTERIOR FISH AND WILDLIFE SERVICE CIRCULAR 48 #12;CONTENTS Page Tuna Clipper 3 Tuna Bait Fishing 4 Two-Pole Tuna Fishing 4 Halibut Schooner 5 Halibut Long- Line 6 Steel Cable

  2. Seismic Vessel Problem Gregory Gutin

    E-Print Network [OSTI]

    Gutin, Gregory

    Seismic Vessel Problem Gregory Gutin , Helmut Jakubowicz , Shuki Ronen and Alexei Zverovitch§ November 14, 2003 Abstract We introduce and study a new combinatorial optimization prob- lem, the Seismic computational experience with solving SVP instances drawn from industrial practice (geophysical seismic acquisi

  3. Corium Retention for High Power Reactors by An In-Vessel Core Catcher in Combination with External Reactor Vessel Cooling

    SciTech Connect (OSTI)

    Joy L. Rempe; D. L. Knudson; K. G. Condie; K. Y. Suh; F. -B. Cheung; S. -B. Kim

    2004-05-01

    If there were inadequate cooling during a reactor accident, a significant amount of core material could become molten and relocate to the lower head of the reactor vessel, as happened in the Three Mile Island Unit 2 (TMI-2) accident. If it is possible to ensure that the vessel lower head remains intact so that relocated core materials are retained within the vessel, the enhanced safety associated with these plants can reduce concerns about containment failure and associated risk. For example, the enhanced safety of the Westinghouse Advanced 600 MWe Pressurized Water Reactor (AP600), which relied upon External Reactor Vessel Cooling (ERVC) for in-vessel retention (IVR), resulted in the United States Nuclear Regulatory Commission (US NRC) approving the design without requiring certain conventional features common to existing Light Water Reactors (LWRs). Accordingly, IVR of core melt is a key severe accident management strategy adopted by some operating nuclear power plants and proposed for some advanced light water reactors. However, it is not clear that currently-proposed methods to achieve ERVC will provide sufficient heat removal for higher power reactors. A US–Korean International Nuclear Energy Research Initiative (INERI) project has been initiated in which the Idaho National Engineering and Environmental Laboratory (INEEL), Seoul National University (SNU), Pennsylvania State University (PSU), and the Korea Atomic Energy Research Institute (KAERI) will determine if IVR is feasible for reactors up to 1500 MWe. This paper summarizes results from the first year of this 3-year project.

  4. Middle Bronze Age Ceramic Vessels from Kamid el-Loz

    E-Print Network [OSTI]

    Cantazariti, Antonietta

    2014-01-01

    and reconstruction of the ceramic vessel economic systemsmainly complete ceramic vessels and, more specifically,chemical composition of the vessel. This was particularly

  5. Vessel network detection using contour evolution and color components

    E-Print Network [OSTI]

    Ushizima, Daniela

    2013-01-01

    segmentation of retinal blood vessels and identification ofnormalization and local vessel detection. IEEE Trans MedLea. A review of 3d vessel lumen segmentation techniques:

  6. Identification of reactor vessel failures using spatiotemporal neural networks

    SciTech Connect (OSTI)

    Roh, C.H.; Chang, H.S.; Kim, H.G.; Chang, S.H. [Korea Advanced Inst. of Science and Technology, Taejon (Korea, Republic of). Dept. of Nuclear Engineering

    1996-12-01

    Identification of vessel failures provides operators and technical support center personnel with important information to manage severe accidents in a nuclear power plant. It may be very difficult, however, for operators to identify a reactor vessel failure simply by watching temporal trends of some parameters because they have not experienced severe accidents. Therefore, the authors propose a methodology on the identification of pressurized water reactor (PWR) vessel failure for severe accident management using spatiotemporal neural network (STN). STN can deal directly with the spatial and temporal aspects of input signals and can well identify a time-varying problem. Target patterns of seven parameter signals were generated for training the network from the modular accident in nuclear power plants. They integrated MAAP code with STN in on-line system to mimic real accident situation in nuclear power plants. Using new pattern of signals that had never been used for training, the identification capability of STN was tested in a real-time manner. At the tests, STN developed in this study demonstrated acceptable performance in identifying the occurrence of a vessel failure. It is found that STN techniques can be extended to the identification of other key events such as onset of core uncovery, coremelt initiation, containment failure, etc.

  7. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Vessel Time Exposure & No Bunkering Draft #12;Q: GW 487 3D Risk Profile All FV - Vessel Time Exposure: 113% of Base Case VTE 23-24 22-4 2-3 1-2 0-1 11/17/2013 2 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 Draft #12;Q: GW 487 & NB

  8. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Vessel Time Exposure + Bunkering Draft #12;P: Base Case 3D Risk Profile All FV - Vessel Time Exposure: 100% of Base Case VTE 23-5 3-4 2-3 1-2 0-1 11/17/2013 2 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 Draft #12;S: DP 415 3

  9. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Vessel Time Exposure & No Bunkering & Only Haro Draft #12;Q: GW 487 & NB 3D Risk Profile All FV - Vessel Time Exposure: 108% of Base-8 6-7 5-6 4-5 3-4 2-3 1-2 0-1 11/17/2013 2 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 Draft #12

  10. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Vessel Time Exposure & Additional Variability of Case T What-If Focus Vessel Arrivals Draft #12;T: GW - KM - DP 3D Risk Profile All FV - Vessel Time Exposure: 125% of Base Case VTE 23-24 22-23 21-22 20-21 19-20 18-19 17-18 16-17 15

  11. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Vessel Time Exposure + Cargo FV set at High December 2013 Draft #12;T: GW - KM - DP 3D Risk Profile All FV - Vessel Time-12 10-11 9-10 8-9 7-8 6-7 5-6 4-5 3-4 2-3 1-2 0-1 12/13/2013 2 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT

  12. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Vessel Time Exposure + Bunkering Draft #12;P: Base Case 3D Risk Profile All FV - Vessel Time Exposure: 100% of Base Case VTE 23-5 3-4 2-3 1-2 0-1 11/17/2013 2 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 Draft #12;R: KM 348 3

  13. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Vessel Time Exposure ­ DP & Tankers set Low #12;T: GW - KM - DP 3D Risk Profile All FV - Vessel Time Exposure: 125% of Base-8 6-7 5-6 4-5 3-4 2-3 1-2 0-1 12/23/2013 2 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 #12;T

  14. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Vessel Time Exposure GW-VCU Draft #12;P: Base Case 3D Risk Profile All FV - Vessel Time Exposure: 100% of Base Case VTE 23-5 3-4 2-3 1-2 0-1 11/17/2013 2 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 Draft #12;T: GW - KM

  15. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Vessel Time Exposure + Bunkering Draft #12;P: Base Case 3D Risk Profile All FV - Vessel Time Exposure: 100% of Base Case VTE 23-5 3-4 2-3 1-2 0-1 11/17/2013 2 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 Draft #12;Q: GW 487 3

  16. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Vessel Time Exposure + Cargo FV set Low December 2013 Draft #12;T: GW - KM - DP 3D Risk Profile All FV - Vessel Time Exposure-11 9-10 8-9 7-8 6-7 5-6 4-5 3-4 2-3 1-2 0-1 12/23/2013 2 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA

  17. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Vessel Time Exposure set at High December 2013 Draft #12;T: GW - KM - DP 3D Risk Profile All FV - Vessel Time Exposure: 125-10 8-9 7-8 6-7 5-6 4-5 3-4 2-3 1-2 0-1 12/13/2013 2 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

  18. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Vessel Time Exposure and Cargo FV set at High Draft #12;P: Base Case 3D Risk Profile All FV - Vessel Time Exposure: 100% of Base-8 6-7 5-6 4-5 3-4 2-3 1-2 0-1 12/12/2013 2 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 Draft #12

  19. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Vessel Time Exposure Way ATB's Rosario #12;T: GW - KM - DP 3D Risk Profile All FV - Vessel Time Exposure: 125% of Base Case-7 5-6 4-5 3-4 2-3 1-2 0-1 11/20/2013 2 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 #12;T: GW

  20. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Oil Time Exposure Dr-5 3-4 2-3 1-2 0-1 12/12/2013 2 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 Draft #12;P: BC/12/2013 3 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 Draft #12;12/12/2013 4 GW-VCU VESSEL TRAFFIC

  1. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Oil Time Exposure Dr-5 3-4 2-3 1-2 0-1 11/17/2013 2 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 Draft #12;T: GW - KM GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 Draft #12;11/17/2013 4 GW-VCU VESSEL TRAFFIC RISK

  2. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Vessel Time Exposure TRAFFIC RISK ASSESSMENT (VTRA) 2010 Draft #12;U : GW - KM - DP & VAR 3D Risk Profile All FV - Vessel Time-12 10-11 9-10 8-9 7-8 6-7 5-6 4-5 3-4 2-3 1-2 0-1 11/21/2013 3 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT

  3. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Oil Time Exposure Dr-4 2-3 1-2 0-1 11/17/2013 2 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 Draft #12;R: KM 348 3D-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 Draft #12;11/17/2013 4 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT

  4. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Oil Time Exposure Dr-4 2-3 1-2 0-1 11/17/2013 2 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 Draft #12;S: DP 415 3D-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 Draft #12;11/17/2013 4 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT

  5. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Oil Time Exposure Dr-4 2-3 1-2 0-1 11/17/2013 2 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 Draft #12;Q: GW 487 3D-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 Draft #12;11/17/2013 4 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT

  6. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Oil Time Exposure Dr-4 2-3 1-2 0-1 11/17/2013 2 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 Draft #12;Q: GW 487 & NB GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 Draft #12;11/17/2013 4 GW-VCU VESSEL TRAFFIC RISK

  7. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Oil Time Exposure Dr-5 3-4 2-3 1-2 0-1 11/21/2013 3 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 Draft #12;T: GW - KM/21/2013 4 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 Draft #12;11/21/2013 5 GW-VCU VESSEL TRAFFIC

  8. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Oil Time Exposure Dr-5 3-4 2-3 1-2 0-1 12/19/2013 2 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 Draft #12;P: BC & LOW GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 Draft #12;12/19/2013 4 GW-VCU VESSEL TRAFFIC RISK

  9. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    ;12/19/2013 4 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 POTENTIAL COLLISION OIL LOSS - PCO Draft #12;12/19/2013 5 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 POTENTIAL COLLISION OIL LOSS - PCO Draft #12VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Potential Collision

  10. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    -VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 POTENTIAL COLLISION OIL LOSS - PCO Draft #12;11/17/2013 5 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 POTENTIAL COLLISION OIL LOSS - PCO Draft #12;Q: GW 487 3D RiskVESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Potential Collision

  11. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    ;11/17/2013 4 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 POTENTIAL GROUNDING OIL LOSS - PGO Draft #12;11/17/2013 5 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 POTENTIAL GROUNDING OIL LOSS - PGO Draft #12VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Potential Grounding

  12. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    ;12/19/2013 4 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 POTENTIAL GROUNDING OIL LOSS - PGO Draft #12;12/19/2013 5 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 POTENTIAL GROUNDING OIL LOSS - PGO Draft #12VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Potential Grounding

  13. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Oil Time Exposure Dr-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 OIL TIME EXPOSURE- OTE #12;12/23/2013 5 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 OIL TIME EXPOSURE- OTE #12;T: GW - KM - DP 3D Risk Profile What-If FV - Oil

  14. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    ;11/17/2013 4 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 POTENTIAL COLLISION OIL LOSS - PCO Draft #12;11/17/2013 5 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 POTENTIAL COLLISION OIL LOSS - PCO Draft #12VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Potential Collision

  15. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Oil Time Exposure Dr;11/18/2013 4 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 OIL TIME EXPOSURE- OTE Draft #12;11/18/2013 5 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 OIL TIME EXPOSURE- OTE Draft #12;DEFINITION OF 15 WATERWAY

  16. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    ;12/23/2013 4 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 POTENTIAL GROUNDING OIL LOSS - PGO #12;12/23/2013 5 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 POTENTIAL GROUNDING OIL LOSS - PGO #12;T: GW) 2010 POTENTIAL GROUNDING OIL LOSS - PGO #12;12/23/2013 9 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA

  17. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    Draft #12;11/17/2013 4 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 POTENTIAL COLLISION OIL LOSS - PCO Draft #12;11/17/2013 5 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 POTENTIAL COLLISION OIL-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 POTENTIAL COLLISION OIL LOSS - PCO Draft #12;11/17/2013 9 GW

  18. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    #12;12/23/2013 4 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 POTENTIAL COLLISION OIL LOSS - PCO #12;12/23/2013 5 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 POTENTIAL COLLISION OIL LOSS - PCO TRAFFIC RISK ASSESSMENT (VTRA) 2010 POTENTIAL COLLISION OIL LOSS - PCO #12;12/23/2013 9 GW-VCU VESSEL

  19. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    ;12/12/2013 4 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 POTENTIAL GROUNDING OIL LOSS - PGO Draft #12;12/12/2013 5 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 POTENTIAL GROUNDING OIL LOSS - PGO Draft #12;P-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 POTENTIAL GROUNDING OIL LOSS - PGO Draft #12;DEFINITION OF 15

  20. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    -VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 POTENTIAL GROUNDING OIL LOSS - PGO Draft #12;12/19/2013 5 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 POTENTIAL GROUNDING OIL LOSS - PGO Draft #12;DEFINITION OF 15VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Potential Grounding

  1. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    -VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 POTENTIAL COLLISION OIL LOSS - PCO Draft #12;12/19/2013 5 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 POTENTIAL COLLISION OIL LOSS - PCO Draft #12;DEFINITION OF 15VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Potential Collision

  2. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    ;11/21/2013 5 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 POTENTIAL COLLISION OIL LOSS - PCO Draft #12;11/21/2013 6 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 POTENTIAL COLLISION OIL LOSS - PCO Draft #12;T ASSESSMENT (VTRA) 2010 POTENTIAL COLLISION OIL LOSS - PCO Draft #12;11/21/2013 10 GW-VCU VESSEL TRAFFIC RISK

  3. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    Draft #12;12/13/2013 4 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 POTENTIAL COLLISION OIL LOSS - PCO Draft #12;12/13/2013 5 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 POTENTIAL COLLISION OIL;12/13/2013 8 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 POTENTIAL COLLISION OIL LOSS - PCO Draft #12

  4. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    ;11/17/2013 4 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 POTENTIAL COLLISION OIL LOSS - PCO Draft #12;11/17/2013 5 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 POTENTIAL COLLISION OIL LOSS - PCO Draft #12;T-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 POTENTIAL COLLISION OIL LOSS - PCO Draft #12;DEFINITION OF 15

  5. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    #12;12/23/2013 4 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 POTENTIAL GROUNDING OIL LOSS - PGO #12;12/23/2013 5 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 POTENTIAL GROUNDING OIL LOSS - PGO TRAFFIC RISK ASSESSMENT (VTRA) 2010 POTENTIAL GROUNDING OIL LOSS - PGO #12;12/23/2013 9 GW-VCU VESSEL

  6. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    -VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 POTENTIAL COLLISION OIL LOSS - PCO Draft #12;11/17/2013 5 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 POTENTIAL COLLISION OIL LOSS - PCO Draft #12;R: KM 348 3D RiskVESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Potential Collision

  7. Nonlinear Tracking Control of Underactuated Surface Vessel

    E-Print Network [OSTI]

    Guo, Yi

    Nonlinear Tracking Control of Underactuated Surface Vessel Wenjie Dong and Yi Guo Abstract-- We consider in this paper the tracking control problem of an underactuated surface vessel. Based that the proposed control laws are effective. I. INTRODUCTION Control of underactuated surface vessels has attracted

  8. Vessel segmentation for angiographic enhancement and analysis

    E-Print Network [OSTI]

    Lübeck, Universität zu

    Vessel segmentation for angiographic enhancement and analysis Alexandru Condurache1 , Til Aach1@isip.uni-luebeck.de Abstract. Angiography is a widely used method of vessel imaging for the diagnosis and treatment of pathological manifestations as well as for medical research. Vessel segmentation in angiograms is useful

  9. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Potential Collision ASSESSMENT (VTRA) 2010 Draft #12;12/13/2013 4 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 POTENTIAL COLLISION OIL LOSS - PCO Draft #12;12/13/2013 5 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 POTENTIAL

  10. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Potential Collision ­ KM ­ DP & 6 RMM's Draft #12;11/21/2013 2 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 RMM 1: Max;11/21/2013 3 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 DEFINITION OF ASSUMED LOCATIONS FOR ADDED ESCORT

  11. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Potential Collision;11/22/2013 2 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 DEFINITION OF ASSUMED LOCATIONS FOR ADDED ESCORT GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 Draft #12;T: GW - KM - DP & ER 3D Risk Profile All

  12. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Potential Collision GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 Draft #12;T : GW - KM - DP & +VAR FV 3D Risk RISK ASSESSMENT (VTRA) 2010 12/23/2013 3 GW-VCU Draft #12;12/23/2013 4 GW-VCU VESSEL TRAFFIC RISK

  13. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Potential Grounding ­ KM ­ DP & 6 RMM's Draft #12;11/21/2013 2 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 RMM 1: Max;11/21/2013 3 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 DEFINITION OF ASSUMED LOCATIONS FOR ADDED ESCORT

  14. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Potential Grounding GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 Draft #12;T : GW - KM - DP & +VAR FV 3D Risk ASSESSMENT (VTRA) 2010 12/23/2013 3 GW-VCU Draft #12;12/23/2013 4 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA

  15. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Potential Collision T ­ GW ­ KM ­ DP & 6 RMM's Draft #12;11/21/2013 2 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 RMM 1) Draft #12;11/21/2013 3 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 DEFINITION OF ASSUMED LOCATIONS

  16. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Potential Collision ASSESSMENT (VTRA) 2010 Draft #12;12/13/2013 4 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 POTENTIAL COLLISION FREQUENCY - PCF Draft #12;12/13/2013 5 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 POTENTIAL

  17. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Oil Time Exposure Dr-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 DEFINITION OF ASSUMED LOCATIONS FOR ADDED ESCORT VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 Draft #12;T: GW - KM - DP & ER 3D Risk Profile All FV - Oil Time

  18. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Potential Collision TRAFFIC RISK ASSESSMENT (VTRA) 2010 Draft #12;T : GW - KM - DP & High Tan + CFV 3D Risk Profile All FV-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 Draft #12;12/13/2013 4 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT

  19. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Potential Grounding T ­ GW ­ KM ­ DP & 6 RMM's Draft #12;11/21/2013 2 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 RMM 1) Draft #12;11/21/2013 3 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 DEFINITION OF ASSUMED LOCATIONS

  20. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Potential Collision GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 Draft #12;U : GW - KM - DP & VAR 3D Risk Profile ASSESSMENT (VTRA) 2010 11/21/2013 3 GW-VCU Draft #12;11/21/2013 4 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA

  1. Design Considerations For Blast Loads In Pressure Vessels.

    SciTech Connect (OSTI)

    Rodriguez, E. A. (Edward A.); Nickell, Robert E.; Pepin, J. E. (Jason E.)

    2007-01-01

    Los Alamos National Laboratory (LANL), under the auspices of the U.S. Department of Energy (DOE) and the National Nuclear Security Administration (NNSA), conducts confined detonation experiments utilizing large, spherical, steel pressure vessels to contain the reaction products and hazardous materials from high-explosive (HE) events. Structural design and analysis considerations include: (a) Blast loading phase (i.e., impulsive loading); (b) Dynamic structural response; (c) Fragment (i.e., shrapnel) generation and penetration; (d) Ductile and non-ductile fracture; and (e) Design Criteria to ASME Code Sec. VIII, Div. 3, Impulsively Loaded Vessels. These vessels are designed for one-time-use only, efficiently utilizing the significant plastic energy absorption capability of ductile vessel materials. Alternatively, vessels may be designed for multiple-detonation events, in which case the material response is restricted to elastic or near-elastic range. Code of Federal Regulations, Title 10 Part 50 provides requirements for commercial nuclear reactor licensing; specifically dealing with accidental combustible gases in containment structures that might cause extreme loadings. The design philosophy contained herein may be applied to extreme loading events postulated to occur in nuclear reactor and non-nuclear systems or containments.

  2. Pump apparatus including deconsolidator

    DOE Patents [OSTI]

    Sonwane, Chandrashekhar; Saunders, Timothy; Fitzsimmons, Mark Andrew

    2014-10-07

    A pump apparatus includes a particulate pump that defines a passage that extends from an inlet to an outlet. A duct is in flow communication with the outlet. The duct includes a deconsolidator configured to fragment particle agglomerates received from the passage.

  3. Effect of CTE on Fatigue Cracking of Stainless Steel Vessels

    SciTech Connect (OSTI)

    Bird, E. L.; Mustaleski, T. M.

    2002-01-31

    Visual examination of lithium hydride reactor vessels revealed cracks that were adjacent to welds. Most cracks were parallel to the weld in the bottom portion of the vessel. Sections were cut out of the vessel containing these cracks and examined using the metallograph, scanning electron microscope, and microprobe to determine the cause of cracking. most of the cracks originated on the outer surface just outside the weld fusion line in the heat affected zone and propagated along grain boundaries. Crack depth of those sections examined ranged from about 300 to 500 {micro}m. Other cracks were reported to have reached a maximum depth of 0.32-cm (0.125-inch). The primary cause of cracking was the creation of high tensile stresses associated with the CTE differences between the filler metal and the base metal during operation of the vessel in a thermally cyclic environment. This failure mechanism could be described as creep-type fatigue whereby crack propagation might have been aided by the presence of brittle chromium carbides along the grain boundaries, which is indicative of a slightly sensitized microstructure.

  4. An Enhanced In-Vessel Core Catcher for Improving In-Vessel Retention Margins

    SciTech Connect (OSTI)

    Joy L. Rempe

    2005-11-01

    In-vessel retention (IVR) of core melt that may relocate to the lower head of a reactor vessel is a key severe accident management strategy adopted by some operating nuclear power plants and proposed for several advanced light water reactors. A U.S.-Korean International Nuclear Energy Research Initiative project has been initiated to explore design enhancements that could increase the margin for IVR for advanced reactors with higher power levels [up to 1500 MW(electric)]. As part of this effort, an enhanced in-vessel core catcher is being designed and evaluated. To reduce cost and simplify manufacture and installation, this new core catcher design consists of several interlocking sections that are machined to fit together when inserted into the lower head. If needed, the core catcher can be manufactured with holes to accommodate lower head penetrations. Each section of the core catcher consists of two material layers with an option to add a third layer (if deemed necessary). The first is a base material that has the capability to support and contain the mass of core materials that may relocate during a severe accident; the second is an oxide coating on top of the base material, which resists interactions with high-temperature core materials; and the third is an optional coating on the bottom side of the base material to protect it from oxidation during the lifetime of the reactor. This paper summarizes results from the invessel core catcher design and evaluation efforts, focusing on recently obtained results from materials interaction tests and prototypic testing activities.

  5. Tow Vessel | 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| Open Energy Information Serbia-EnhancingEt Al., 2013)OpenEnergy Facilities Biomass Facility Jump to:Tow Vessel Jump

  6. Neutron Assay System for Confinement Vessel Disposition

    SciTech Connect (OSTI)

    Frame, Katherine C. [Los Alamos National Laboratory; Bourne, Mark M. [Los Alamos National Laboratory; Crooks, William J. [Los Alamos National Laboratory; Evans, Louise [Los Alamos National Laboratory; Mayo, Douglas R. [Los Alamos National Laboratory; Miko, David K. [Los Alamos National Laboratory; Salazar, William R. [Los Alamos National Laboratory; Stange, Sy [Los Alamos National Laboratory; Valdez, Jose I. [Los Alamos National Laboratory; Vigil, Georgiana M. [Los Alamos National Laboratory

    2012-07-13

    Los Alamos National Laboratory has a number of spherical confinement vessels (CVs) remaining from tests involving nuclear materials. These vessels have an inner diameter of 6 feet with 1-inch thick steel walls. The goal of the Confinement Vessel Disposition (CVD) project is to remove debris and reduce contamination inside the CVs. The Confinement Vessel Assay System (CVAS) was developed to measure the amount of special nuclear material (SNM) in CVs before and after cleanout. Prior to cleanout, the system will be used to perform a verification measurement of each vessel. After cleanout, the system will be used to perform safeguards-quality assays of {le}100-g {sup 239}Pu equivalent in a vessel for safeguards termination. The CVAS has been tested and calibrated in preparation for verification and safeguards measurements.

  7. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    GROUNDING OIL LOSS - PGO Draft #12;11/22/2013 6 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 POTENTIAL GROUNDING OIL LOSS - PGO Draft #12;11/22/2013 7 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 T: GW - KM;11/22/2013 9 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 POTENTIAL GROUNDING OIL LOSS - PGO Draft #12

  8. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Potential Grounding-10 8-9 7-8 6-7 5-6 4-5 3-4 2-3 1-2 0-1 12/12/2013 3 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 Draft #12;12/12/2013 4 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 POTENTIAL GROUNDING FREQUENCY

  9. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Potential Grounding-11 9-10 8-9 7-8 6-7 5-6 4-5 3-4 2-3 1-2 0-1 12/23/2013 3 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 #12;12/23/2013 4 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 POTENTIAL GROUNDING FREQUENCY

  10. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Potential Grounding-12 10-11 9-10 8-9 7-8 6-7 5-6 4-5 3-4 2-3 1-2 0-1 11/17/2013 2 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 Draft #12;11/17/2013 3 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 Q: GW 487 & NB & OH

  11. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Potential Collision: GW ­ KM ­ DP & +1 Escort Cape Size Draft #12;11/21/2013 2 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA-12 10-11 9-10 8-9 7-8 6-7 5-6 4-5 3-4 2-3 1-2 0-1 11/21/2013 3 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT

  12. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Potential Grounding-8 6-7 5-6 4-5 3-4 2-3 1-2 0-1 11/17/2013 2 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 Draft #12-2 0-1 VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 11/17/2013 3 GW-VCU Draft #12;11/17/2013 4 GW

  13. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Potential Collision TRAFFIC RISK ASSESSMENT (VTRA) 2010 DEFINITION OF ASSUMED LOCATIONS FOR ADDED ESCORT VESSEL FOR HARO-11 9-10 8-9 7-8 6-7 5-6 4-5 3-4 2-3 1-2 0-1 11/21/2013 3 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA

  14. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Potential Collision-8 6-7 5-6 4-5 3-4 2-3 1-2 0-1 VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 11/17/2013 2 GW-VCU Draft #12-2 0-1 11/17/2013 3 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 Draft #12;11/17/2013 4 GW

  15. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Potential Grounding TRAFFIC RISK ASSESSMENT (VTRA) 2010 DEFINITION OF ASSUMED LOCATIONS FOR ADDED ESCORT VESSEL FOR HARO-8 6-7 5-6 4-5 3-4 2-3 1-2 0-1 11/21/2013 3 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 Draft #12

  16. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Oil Time Exposure Dr-7 5-6 4-5 3-4 2-3 1-2 0-1 12/19/2013 2 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 Draft #12;P-2 0-1 12/19/2013 3 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 Draft #12;12/19/2013 4 GW

  17. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Potential Collision-2 0-1 12/23/2013 2 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 Draft #12;T : GW - KM - DP & +VAR-2 0-1 12/23/2013 3 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 Draft #12;12/23/2013 4 GW

  18. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Potential Grounding-12 10-11 9-10 8-9 7-8 6-7 5-6 4-5 3-4 2-3 1-2 0-1 12/13/2013 3 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 Draft #12;12/13/2013 4 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 POTENTIAL GROUNDING

  19. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Oil Time Exposure Dr & +1 Escort Cape Size Draft #12;11/21/2013 2 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010-10 8-9 7-8 6-7 5-6 4-5 3-4 2-3 1-2 0-1 11/21/2013 3 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

  20. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Potential Grounding ­ KM ­ DP & +1 Escort Cape Size Draft #12;11/21/2013 2 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA-10 8-9 7-8 6-7 5-6 4-5 3-4 2-3 1-2 0-1 11/21/2013 3 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

  1. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Potential Grounding RISK ASSESSMENT (VTRA) 2010 DEFINITION OF ASSUMED LOCATIONS FOR ADDED ESCORT VESSEL FOR HARO-8 6-7 5-6 4-5 3-4 2-3 1-2 0-1 11/21/2013 3 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 Draft #12

  2. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Potential Collision-8 6-7 5-6 4-5 3-4 2-3 1-2 0-1 11/17/2013 2 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 Draft #12-2 0-1 VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 11/17/2013 3 GW-VCU Draft #12;11/17/2013 4 GW

  3. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Oil Time Exposure Dr-7 5-6 4-5 3-4 2-3 1-2 0-1 11/17/2013 2 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 Draft #12;P-2 0-1 11/17/2013 3 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 Draft #12;11/17/2013 4 GW

  4. U-182: Microsoft Windows Includes Some Invalid Certificates

    Broader source: Energy.gov [DOE]

    The operating system includes some invalid intermediate certificates. The vulnerability is due to the certificate authorities and not the operating system itself.

  5. Cryostat including heater to heat a target

    DOE Patents [OSTI]

    Pehl, R.H.; Madden, N.W.; Malone, D.F.

    1990-09-11

    A cryostat is provided which comprises a vacuum vessel; a target disposed within the vacuum vessel; a heat sink disposed within the vacuum vessel for absorbing heat from the detector; a cooling mechanism for cooling the heat sink; a cryoabsorption mechanism for cryoabsorbing residual gas within the vacuum vessel; and a heater for maintaining the target above a temperature at which the residual gas is cryoabsorbed in the course of cryoabsorption of the residual gas by the cryoabsorption mechanism. 2 figs.

  6. D-Zero Central Calorimeter Pressure Vessel and Vacuum Vessel Safety Notes

    SciTech Connect (OSTI)

    Rucinski, R.; Luther, R.; /Fermilab

    1990-10-25

    The relief valve and relief piping capacity was calculated to be 908 sefm air. This exceeds all relieving conditions. The vessel also has a rupture disc with a 2640 scfm air stamped capacity. In order to significantly decrease the amount of time required to fill the cryostats, it is desired to raise the setpoint of the 'operating' relief valve on the argon storage dewar to 20 psig from its existing 16 psig setting. This additional pressure increases the flow to the cryostats and will overwhelm the relief capacity if the temperature of the modules within these vessels is warm enough. Using some conservative assumptions and simple calculations within this note, the maximum average temperature that the modules within each cryostat can be at prior to filling from the storage dewar with liquid argon is at least 290 K. The average temperature of the module mass for any of the three cryostats can be as high as 290 K prior to filling that particular cryostat. This should not be confused with the average temperature of a single type or location which is useful in protecting the modules-not necessarily the vessel itself. A few modules of each type and at different elevations should be used in an average which would account for the different weights of each module. Note that at 290 K, the actual flow of argon through the relief valve and the rupture disk was under the maximum theoretical flows for each relief device. This means that the bulk temperature could actually have been raised to flow argon through the reliefs at their maximum capacity. Therefore, the temperature of 290 K is a conservative value for the calculated flow rate of 12.3 gpm. Safeguards in addition to and used in conjunction with operating procedures shall be implemented in such a way so that the above temperature limitation is not exceeded and such that it is exclusive of the programmable logic controller (PLC). One suggestion is using a toggle switch for each cryostat mounted in the PLC I/O box which would maintain control of the signals to open the cold fill valves of each cryostat. With the safeguards in place while carefully monitoring the temperatures during a cooldown cycle in each cryostat, the set pressure in the argon storage dewar can safely be increased to 20 psig.

  7. Market characteristics of future oil tanker operations

    E-Print Network [OSTI]

    Willemann, Simmy Dhawan

    2014-01-01

    This work analyzes the market characteristics of future oil tanker operations with a particular emphasis on those aspects which will have a potential impact on the design of future vessels. The market analysis model used ...

  8. Device for inspecting vessel surfaces

    DOE Patents [OSTI]

    Appel, D. Keith (Aiken, SC)

    1995-01-01

    A portable, remotely-controlled inspection crawler for use along the walls of tanks, vessels, piping and the like. The crawler can be configured to use a vacuum chamber for supporting itself on the inspected surface by suction or a plurality of magnetic wheels for moving the crawler along the inspected surface. The crawler is adapted to be equipped with an ultrasonic probe for mapping the structural integrity or other characteristics of the surface being inspected. Navigation of the crawler is achieved by triangulation techniques between a signal transmitter on the crawler and a pair of microphones attached to a fixed, remote location, such as the crawler's deployment unit. The necessary communications are established between the crawler and computers external to the inspection environment for position control and storage and/or monitoring of data acquisition.

  9. FIRE Vacuum Vessel Design and Analysis

    E-Print Network [OSTI]

    quality vacuum - outgassing and leak rate of waste disposal #12;6 June 2001 FIRE Review: Vacuum Vessel Design 8 Vessel shell dimensions #12;6 June - Shielding water + steel with 60% packing factor - Volume of torus interior 35 m^3 - Surface Area of torus

  10. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    TRAFFIC RISK ASSESSMENT (VTRA) 2010 POTENTIAL GROUNDING OIL LOSS - PGO Draft #12;11/17/2013 5 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 POTENTIAL GROUNDING OIL LOSS - PGO Draft #12;Q: GW 487 3D RiskVESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Potential Grounding

  11. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Oil Time Exposure Dr RISK ASSESSMENT (VTRA) 2010 Draft #12;P: BC & DH100 3D Risk Profile All FV - Oil Time Exposure: 100 Draft #12;11/18/2013 4 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 OIL TIME EXPOSURE- OTE Draft

  12. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    TRAFFIC RISK ASSESSMENT (VTRA) 2010 POTENTIAL GROUNDING OIL LOSS - PGO Draft #12;11/17/2013 5 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 POTENTIAL GROUNDING OIL LOSS - PGO Draft #12;R: KM 348 3D RiskVESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Potential Grounding

  13. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Oil Time Exposure Dr TRAFFIC RISK ASSESSMENT (VTRA) 2010 OIL TIME EXPOSURE- OTE #12;12/23/2013 5 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 OIL TIME EXPOSURE- OTE #12;T: GW - KM - DP 3D Risk Profile What-If FV - Oil Time

  14. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    -VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 POTENTIAL GROUNDING OIL LOSS - PGO Draft #12;11/17/2013 5 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 POTENTIAL GROUNDING OIL LOSS - PGO Draft #12;T: GW - KM - DP 3 RISK ASSESSMENT (VTRA) 2010 POTENTIAL GROUNDING OIL LOSS - PGO Draft #12;DEFINITION OF 15 WATERWAY

  15. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Oil Time Exposure Dr TRAFFIC RISK ASSESSMENT (VTRA) 2010 OIL TIME EXPOSURE- OTE #12;11/20/2013 5 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 OIL TIME EXPOSURE- OTE #12;T: GW - KM - DP 3D Risk Profile What-If FV - Oil Time

  16. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    ) 2010 POTENTIAL GROUNDING OIL LOSS - PGO Draft #12;11/21/2013 5 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT GROUNDING OIL LOSS - PGO Draft #12;11/21/2013 9 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 POTENTIALVESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Potential Grounding

  17. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Oil Time Exposure Dr ASSESSMENT (VTRA) 2010 Draft #12;P: BC & OB HE100 3D Risk Profile All FV - Oil Time Exposure: 100% of Base;11/19/2013 4 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 OIL TIME EXPOSURE- OTE Draft #12;11/19/2013 5 GW

  18. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    ;12/12/2013 4 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 POTENTIAL COLLISION OIL LOSS - PCO Draft #12;12/12/2013 5 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 POTENTIAL COLLISION OIL LOSS - PCO Draft #12;P TRAFFIC RISK ASSESSMENT (VTRA) 2010 POTENTIAL COLLISION OIL LOSS - PCO Draft #12;DEFINITION OF 15 WATERWAY

  19. Foam vessel for cryogenic fluid storage

    DOE Patents [OSTI]

    Spear, Jonathan D (San Francisco, CA)

    2011-07-05

    Cryogenic storage and separator vessels made of polyolefin foams are disclosed, as are methods of storing and separating cryogenic fluids and fluid mixtures using these vessels. In one embodiment, the polyolefin foams may be cross-linked, closed-cell polyethylene foams with a density of from about 2 pounds per cubic foot to a density of about 4 pounds per cubic foot.

  20. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Potential Collision;11/22/2013 2 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 DEFINITION OF ASSUMED LOCATIONS FOR ADDED ESCORT RISK ASSESSMENT (VTRA) 2010 11/22/2013 3 GW-VCU Draft #12;T: GW - KM - DP & ER 3D Risk Profile All FV

  1. T-603: Mac OS X Includes Some Invalid Comodo Certificates

    Broader source: Energy.gov [DOE]

    The operating system includes some invalid certificates. The vulnerability is due to the invalid certificates and not the operating system itself. Other browsers, applications, and operating systems are affected.

  2. Analysis of the Three Mile Island submerged demineralizer system vessel burial data

    SciTech Connect (OSTI)

    Jasen, W.G.; Amir, S.J.

    1989-09-01

    The Submerged Demineralizer System (SDS) was used during the Three Mile Island (TMI) nuclear reactor cleanup to remove cesium and strontium from contaminated water. The SDS vessels are 2-ft-in diameter and 4-ft tall stainless steel cylinders containing up to 60 kCi of radioactive cesium and strontium loaded on damp zeolite. The water in the damp zeolite absorbs some of the ionizing radiation and decomposes to hydrogen and oxygen by a process called radiolysis. Gas generation rates approaching 1 L/h (Quinn et al. 1984) have been calculated and measured for some of these loaded vessels. Each of the SDS vessels contains a catalyst bed to recombine the available hydrogen and oxygen back to water. Tests have proven this hydrogen control method to be highly effective, even under very wet (but unsubmerged) conditions. Nineteen SDS vessels, packaged one at a time in a shielded and licensed shipping cask, were shipped to Rockwell Hanford Operations (Rockwell). Collectively, these vessels contain approximately 7,500 kCi of radioactive material. Sixteen vessels were transloaded into concrete overpacks and buried at the Hanford Site. The contents of the other three vessels were vitrified at Pacific Northwest Laboratory. Subsequent to placement of the SDS vessels in the burial grounds, DOE Order 5820.2A (DOE 1988) was issued in September 1988. This order requires wastes to be evaluated against 10 CFR 61.55 for radioactivity above greater-than-class C(GTCC) limits. Fourteen of the sixteen vessels buried at the Hanford Site have been determined to be GTCC waste. 5 refs., 3 figs., 3 tabs.

  3. Lightweight bladder lined pressure vessels

    DOE Patents [OSTI]

    Mitlitsky, Fred (1125 Canton Ave., Livermore, CA 94550); Myers, Blake (4650 Almond Cir., Livermore, CA 94550); Magnotta, Frank (1206 Bacon Way, Lafayette, CA 94549)

    1998-01-01

    A lightweight, low permeability liner for graphite epoxy composite compressed gas storage vessels. The liner is composed of polymers that may or may not be coated with a thin layer of a low permeability material, such as silver, gold, or aluminum, deposited on a thin polymeric layer or substrate which is formed into a closed bladder using torispherical or near torispherical end caps, with or without bosses therein, about which a high strength to weight material, such as graphite epoxy composite shell, is formed to withstand the storage pressure forces. The polymeric substrate may be laminated on one or both sides with additional layers of polymeric film. The liner may be formed to a desired configuration using a dissolvable mandrel or by inflation techniques and the edges of the film seamed by heat sealing. The liner may be utilized in most any type of gas storage system, and is particularly applicable for hydrogen, gas mixtures, and oxygen used for vehicles, fuel cells or regenerative fuel cell applications, high altitude solar powered aircraft, hybrid energy storage/propulsion systems, and lunar/Mars space applications, and other applications requiring high cycle life.

  4. Lightweight bladder lined pressure vessels

    DOE Patents [OSTI]

    Mitlitsky, F.; Myers, B.; Magnotta, F.

    1998-08-25

    A lightweight, low permeability liner is described for graphite epoxy composite compressed gas storage vessels. The liner is composed of polymers that may or may not be coated with a thin layer of a low permeability material, such as silver, gold, or aluminum, deposited on a thin polymeric layer or substrate which is formed into a closed bladder using tori spherical or near tori spherical end caps, with or without bosses therein, about which a high strength to weight material, such as graphite epoxy composite shell, is formed to withstand the storage pressure forces. The polymeric substrate may be laminated on one or both sides with additional layers of polymeric film. The liner may be formed to a desired configuration using a dissolvable mandrel or by inflation techniques and the edges of the film sealed by heat sealing. The liner may be utilized in most any type of gas storage system, and is particularly applicable for hydrogen, gas mixtures, and oxygen used for vehicles, fuel cells or regenerative fuel cell applications, high altitude solar powered aircraft, hybrid energy storage/propulsion systems, and lunar/Mars space applications, and other applications requiring high cycle life. 19 figs.

  5. International Hydrogen Fuel and Pressure Vessel Forum 2010 Proceedings...

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

    Hydrogen Fuel and Pressure Vessel Forum 2010 Proceedings International Hydrogen Fuel and Pressure Vessel Forum 2010 Proceedings Proceedings from the forum, which took place in...

  6. Automatic Lung Vessel Segmentation via Stacked Multiscale Feature Learning

    E-Print Network [OSTI]

    Toronto, University of

    Automatic Lung Vessel Segmentation via Stacked Multiscale Feature Learning Ryan Kiros, Karteek We introduce a representation learning approach to segmenting vessels in the lungs. Our algorithm

  7. Major deepwater pipelay vessel starts work in North Sea

    SciTech Connect (OSTI)

    Heerema, E.P.

    1998-05-04

    Industry`s deepwater pipelaying capability has received a boost this year with the entry into the world`s fleet of Solitaire, a dynamically positioned pipelay vessel of about 350 m including stinger. The converted bulk carrier, formerly the Trentwood, will arrive on station in the North Sea and begin laying pipe this month on Statoil`s Europipe II project, a 600-km, 42-in. OD gas pipeline from Norway to Germany. Next year, the vessel will install pipe for the Exxon U.S.A.`s Gulf of Mexico South Diana development (East Breaks Block 945) in a water depth of 1,643 m and for Mobil Oil Canada as part of the Sable Island Offshore and Energy Project offshore Nova Scotia. Using the S-lay mode, Solitaire is particularly well-suited for laying large lines economically, including the deepwater projects anticipated for the US Gulf of Mexico. Table 1 presents Solitaire`s technical specifications. The design, construction, pipelaying, and justification for building vessels such as the Solitaire are discussed.

  8. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Potential Grounding-10 8-9 7-8 6-7 5-6 4-5 3-4 2-3 1-2 0-1 11/17/2013 2 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010-4 2-3 1-2 0-1 11/17/2013 3 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 Draft #12;11/17/2013 4 GW

  9. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Potential Collision-8 6-7 5-6 4-5 3-4 2-3 1-2 0-1 VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 12/12/2013 2 GW-VCU Draft #12-4 2-3 1-2 0-1 12/12/2013 3 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 Draft #12;12/12/2013 4 GW

  10. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Potential Grounding-12 10-11 9-10 8-9 7-8 6-7 5-6 4-5 3-4 2-3 1-2 0-1 12/13/2013 2 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT-10 8-9 7-8 6-7 5-6 4-5 3-4 2-3 1-2 0-1 12/13/2013 3 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

  11. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Potential Collision-11 9-10 8-9 7-8 6-7 5-6 4-5 3-4 2-3 1-2 0-1 11/20/2013 2 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA-7 5-6 4-5 3-4 2-3 1-2 0-1 VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 11/20/2013 3 GW-VCU #12

  12. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Potential Grounding-11 9-10 8-9 7-8 6-7 5-6 4-5 3-4 2-3 1-2 0-1 12/13/2013 2 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA-8 6-7 5-6 4-5 3-4 2-3 1-2 0-1 12/13/2013 3 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 Draft #12

  13. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Oil Time Exposure Dr-8 6-7 5-6 4-5 3-4 2-3 1-2 0-1 12/12/2013 2 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 Draft #12-4 2-3 1-2 0-1 12/12/2013 3 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 Draft #12;12/12/2013 4 GW

  14. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Potential Grounding-11 9-10 8-9 7-8 6-7 5-6 4-5 3-4 2-3 1-2 0-1 VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 11/17/2013 2 GW-5 3-4 2-3 1-2 0-1 11/17/2013 3 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 Draft #12

  15. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Potential Grounding-10 8-9 7-8 6-7 5-6 4-5 3-4 2-3 1-2 0-1 11/17/2013 2 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010-5 3-4 2-3 1-2 0-1 11/17/2013 3 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 Draft #12

  16. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Oil Time Exposure Dr-10 8-9 7-8 6-7 5-6 4-5 3-4 2-3 1-2 0-1 12/13/2013 2 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010-8 6-7 5-6 4-5 3-4 2-3 1-2 0-1 12/13/2013 3 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 Draft #12

  17. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Oil Time Exposure Dr-8 6-7 5-6 4-5 3-4 2-3 1-2 0-1 12/13/2013 2 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 Draft #12-5 3-4 2-3 1-2 0-1 12/13/2013 3 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 Draft #12

  18. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Potential Grounding-12 10-11 9-10 8-9 7-8 6-7 5-6 4-5 3-4 2-3 1-2 0-1 11/20/2013 2 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT-8 6-7 5-6 4-5 3-4 2-3 1-2 0-1 11/20/2013 3 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 #12

  19. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Potential Grounding-10 8-9 7-8 6-7 5-6 4-5 3-4 2-3 1-2 0-1 12/19/2013 2 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010-5 3-4 2-3 1-2 0-1 12/19/2013 3 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 Draft #12

  20. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Potential Collision-10 8-9 7-8 6-7 5-6 4-5 3-4 2-3 1-2 0-1 12/23/2013 2 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010-7 5-6 4-5 3-4 2-3 1-2 0-1 12/23/2013 3 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 #12

  1. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Potential Grounding-10 8-9 7-8 6-7 5-6 4-5 3-4 2-3 1-2 0-1 12/12/2013 2 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010-5 3-4 2-3 1-2 0-1 12/12/2013 3 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 Draft #12

  2. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Potential Grounding-11 9-10 8-9 7-8 6-7 5-6 4-5 3-4 2-3 1-2 0-1 11/20/2013 2 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA-7 5-6 4-5 3-4 2-3 1-2 0-1 VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 11/20/2013 3 GW-VCU #12

  3. DEVELOPMENT OF ASME SECTION X CODE RULES FOR HIGH PRESSURE COMPOSITE HYDROGEN PRESSURE VESSELS WITH NON-LOAD SHARING LINERS

    SciTech Connect (OSTI)

    Rawls, G.; Newhouse, N.; Rana, M.; Shelley, B.; Gorman, M.

    2010-04-13

    The Boiler and Pressure Vessel Project Team on Hydrogen Tanks was formed in 2004 to develop Code rules to address the various needs that had been identified for the design and construction of up to 15000 psi hydrogen storage vessel. One of these needs was the development of Code rules for high pressure composite vessels with non-load sharing liners for stationary applications. In 2009, ASME approved new Appendix 8, for Section X Code which contains the rules for these vessels. These vessels are designated as Class III vessels with design pressure ranging from 20.7 MPa (3,000 ps)i to 103.4 MPa (15,000 psi) and maximum allowable outside liner diameter of 2.54 m (100 inches). The maximum design life of these vessels is limited to 20 years. Design, fabrication, and examination requirements have been specified, included Acoustic Emission testing at time of manufacture. The Code rules include the design qualification testing of prototype vessels. Qualification includes proof, expansion, burst, cyclic fatigue, creep, flaw, permeability, torque, penetration, and environmental testing.

  4. NSTX Weekly Report (Jan. 08, 2009) FY 2010 NSTX plasma operations

    E-Print Network [OSTI]

    Princeton Plasma Physics Laboratory

    joint resistances. Final wipe-downs of the NSTX vessel interior are in progress, as well-operational testing of the LLD heating system, and a 200 Amp test of the TF coil system to measure and document TF as the blackening of select in-vessel surfaces. The final inspection and photography of the vessel interior

  5. Pressurized fluidized bed reactor and a method of operating the same

    DOE Patents [OSTI]

    Isaksson, J.

    1996-02-20

    A pressurized fluid bed reactor power plant includes a fluidized bed reactor contained within a pressure vessel with a pressurized gas volume between the reactor and the vessel. A first conduit supplies primary gas from the gas volume to the reactor, passing outside the pressure vessel and then returning through the pressure vessel to the reactor, and pressurized gas is supplied from a compressor through a second conduit to the gas volume. A third conduit, comprising a hot gas discharge, carries gases from the reactor, through a filter, and ultimately to a turbine. During normal operation of the plant, pressurized gas is withdrawn from the gas volume through the first conduit and introduced into the reactor at a substantially continuously controlled rate as the primary gas to the reactor. In response to an operational disturbance of the plant, the flow of gas in the first, second, and third conduits is terminated, and thereafter the pressure in the gas volume and in the reactor is substantially simultaneously reduced by opening pressure relief valves in the first and third conduits, and optionally by passing air directly from the second conduit to the turbine. 1 fig.

  6. Pressurized fluidized bed reactor and a method of operating the same

    DOE Patents [OSTI]

    Isaksson, Juhani (Karhula, FI)

    1996-01-01

    A pressurized fluid bed reactor power plant includes a fluidized bed reactor contained within a pressure vessel with a pressurized gas volume between the reactor and the vessel. A first conduit supplies primary gas from the gas volume to the reactor, passing outside the pressure vessel and then returning through the pressure vessel to the reactor, and pressurized gas is supplied from a compressor through a second conduit to the gas volume. A third conduit, comprising a hot gas discharge, carries gases from the reactor, through a filter, and ultimately to a turbine. During normal operation of the plant, pressurized gas is withdrawn from the gas volume through the first conduit and introduced into the reactor at a substantially continuously controlled rate as the primary gas to the reactor. In response to an operational disturbance of the plant, the flow of gas in the first, second, and third conduits is terminated, and thereafter the pressure in the gas volume and in the reactor is substantially simultaneously reduced by opening pressure relief valves in the first and third conduits, and optionally by passing air directly from the second conduit to the turbine.

  7. Future characteristics of Offshore Support Vessels

    E-Print Network [OSTI]

    Rose, Robin Sebastian Koske

    2011-01-01

    The objective of this thesis is to examine trends in Offshore Support Vessel (OSV) design and determine the future characteristics of OSVs based on industry insight and supply chain models. Specifically, this thesis focuses ...

  8. Ion transport membrane module and vessel system

    DOE Patents [OSTI]

    Stein, VanEric Edward (Allentown, PA); Carolan, Michael Francis (Allentown, PA); Chen, Christopher M. (Allentown, PA); Armstrong, Phillip Andrew (Orefield, PA); Wahle, Harold W. (North Canton, OH); Ohrn, Theodore R. (Alliance, OH); Kneidel, Kurt E. (Alliance, OH); Rackers, Keith Gerard (Louisville, OH); Blake, James Erik (Uniontown, OH); Nataraj, Shankar (Allentown, PA); van Doorn, Rene Hendrik Elias (Obersulm-Willsbach, DE); Wilson, Merrill Anderson (West Jordan, UT)

    2008-02-26

    An ion transport membrane system comprising (a) a pressure vessel having an interior, an exterior, an inlet, and an outlet; (b) a plurality of planar ion transport membrane modules disposed in the interior of the pressure vessel and arranged in series, each membrane module comprising mixed metal oxide ceramic material and having an interior region and an exterior region, wherein any inlet and any outlet of the pressure vessel are in flow communication with exterior regions of the membrane modules; and (c) one or more gas manifolds in flow communication with interior regions of the membrane modules and with the exterior of the pressure vessel.The ion transport membrane system may be utilized in a gas separation device to recover oxygen from an oxygen-containing gas or as an oxidation reactor to oxidize compounds in a feed gas stream by oxygen permeated through the mixed metal oxide ceramic material of the membrane modules.

  9. Ion transport membrane module and vessel system

    DOE Patents [OSTI]

    Stein, VanEric Edward; Carolan, Michael Francis; Chen, Christopher M.; Armstrong, Phillip Andrew; Wahle, Harold W.; Ohrn, Theodore R.; Kneidel, Kurt E.; Rackers, Keith Gerard; Blake, James Erik; Nataraj, Shankar; van Doorn, Rene Hendrik Elias; Wilson, Merrill Anderson

    2007-02-20

    An ion transport membrane system comprising (a) a pressure vessel having an interior, an exterior, an inlet, and an outlet; (b) a plurality of planar ion transport membrane modules disposed in the interior of the pressure vessel and arranged in series, each membrane module comprising mixed metal oxide ceramic material and having an interior region and an exterior region, wherein any inlet and any outlet of the pressure vessel are in flow communication with exterior regions of the membrane modules; and (c) one or more gas manifolds in flow communication with interior regions of the membrane modules and with the exterior of the pressure vessel. The ion transport membrane system may be utilized in a gas separation device to recover oxygen from an oxygen-containing gas or as an oxidation reactor to oxidize compounds in a feed gas stream by oxygen permeated through the mixed metal oxide ceramic material of the membrane modules.

  10. Ion transport membrane module and vessel system

    DOE Patents [OSTI]

    Stein, VanEric Edward (Allentown, PA); Carolan, Michael Francis (Allentown, PA); Chen, Christopher M. (Allentown, PA); Armstrong, Phillip Andrew (Orefield, PA); Wahle, Harold W. (North Canton, OH); Ohrn, Theodore R. (Alliance, OH); Kneidel, Kurt E. (Alliance, OH); Rackers, Keith Gerard (Louisville, OH); Blake, James Erik (Uniontown, OH); Nataraj, Shankar (Allentown, PA); Van Doorn, Rene Hendrik Elias (Obersulm-Willsbach, DE); Wilson, Merrill Anderson (West Jordan, UT)

    2012-02-14

    An ion transport membrane system comprising (a) a pressure vessel having an interior, an exterior, an inlet, and an outlet; (b) a plurality of planar ion transport membrane modules disposed in the interior of the pressure vessel and arranged in series, each membrane module comprising mixed metal oxide ceramic material and having an interior region and an exterior region, wherein any inlet and any outlet of the pressure vessel are in flow communication with exterior regions of the membrane modules; and (c) one or more gas manifolds in flow communication with interior regions of the membrane modules and with the exterior of the pressure vessel. The ion transport membrane system may be utilized in a gas separation device to recover oxygen from an oxygen-containing gas or as an oxidation reactor to oxidize compounds in a feed gas stream by oxygen permeated through the mixed metal oxide ceramic material of the membrane modules.

  11. Neutron shielding panels for reactor pressure vessels

    DOE Patents [OSTI]

    Singleton, Norman R. (Murrysville, PA)

    2011-11-22

    In a nuclear reactor neutron panels varying in thickness in the circumferential direction are disposed at spaced circumferential locations around the reactor core so that the greatest radial thickness is at the point of highest fluence with lesser thicknesses at adjacent locations where the fluence level is lower. The neutron panels are disposed between the core barrel and the interior of the reactor vessel to maintain radiation exposure to the vessel within acceptable limits.

  12. Annabella: a North American coasting vessel 

    E-Print Network [OSTI]

    Claesson, Stefan Hans

    1998-01-01

    schooner in 1841. 53 26 Map of southern New Jersey. 60 27 28 Section lines of the preserved remains of Annabella. . . . . Lines of a Milford, Delaware vessel. . . . . . . . . . . . . . . . . . . 66 FIGURE Page 29 A billet head of a 19th... enrolment records. . 54 Measurements of Milford, Delaware-built sloops in comparison to Annabella, 69 Timber dimensions required for construction of 100 ton vessel by American Shipmaster's Association in 1882 compared to timber dimensions of Annabella...

  13. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Oil Time Exposure Dr TRAFFIC RISK ASSESSMENT (VTRA) 2010 Draft #12;T : GW - KM - DP & +VAR FV 3D Risk Profile All FV - Oil Time-12 10-11 9-10 8-9 7-8 6-7 5-6 4-5 3-4 2-3 1-2 0-1 12/23/2013 3 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT

  14. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Oil Time Exposure Dr TRAFFIC RISK ASSESSMENT (VTRA) 2010 Draft #12;U : GW - KM - DP & VAR 3D Risk Profile All FV - Oil Time-12 10-11 9-10 8-9 7-8 6-7 5-6 4-5 3-4 2-3 1-2 0-1 11/21/2013 3 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT

  15. Detailed Analysis of a Late-Phase Core-Melt Progression for the Evaluation of In-vessel Corium Retention

    SciTech Connect (OSTI)

    J. L. Rempe; R. J. Park; S. B. Kim; K. Y. Suh; F. B.Cheung

    2006-12-01

    Detailed analyses of a late-phase melt progression in the advanced power reactor (APR)1400 were completed to identify the melt and the thermal-hydraulic states of the in-vessel materials in the reactor vessel lower plenum at the time of reactor vessel failure to evaluate the candidate strategies for an in-vessel corium retention (IVR). Initiating events considered included high-pressure transients of a total loss of feed water (LOFW) and a station blackout (SBO) and low-pressure transients of a 0.0009-m2 small, 0.0093-m2 medium, and 0.0465-m2 large-break loss-of-coolant accident (LOCA) without safety injection. Best-estimate simulations for these low-probability events with conservative accident progression assumptions that lead to reactor vessel failure were performed by using the SCDAP/RELAP5/MOD3.3 computer code. The SCDAP/RELAP5/MOD3.3 results have shown that the pressurizer surge line failed before the reactor vessel failure, which results in a rapid decrease of the in-vessel pressure and a delay of the reactor vessel failure time of ~40 min in the high-pressure sequences of the total LOFW and the SBO transients. In all the sequences, ~80 to 90% of the core material was melted and relocated to the lower plenum of the reactor vessel at the time of reactor vessel failure. The maximum value of the volumetric heat source in the corium pool was estimated as 1.9 to 3.7 MW/m3. The corium temperature was ~2800 to 3400 K at the time of reactor vessel failure. The highest volumetric heat source sequence is predicted for the 0.0465-m2 large-break LOCA without safety injection in the APR1400, because this sequence leads to an early reactor vessel failure.

  16. PURE NIOBIUM AS A PRESSURE VESSEL MATERIAL

    SciTech Connect (OSTI)

    Peterson, T. J.; Carter, H. F.; Foley, M. H.; Klebaner, A. L.; Nicol, T. H.; Page, T. M.; Theilacker, J. C.; Wands, R. H.; Wong-Squires, M. L.; Wu, G. [Fermi National Accelerator Laboratory, Batavia, Illinois 60510 (United States)

    2010-04-09

    Physics laboratories around the world are developing niobium superconducting radio frequency (SRF) cavities for use in particle accelerators. These SRF cavities are typically cooled to low temperatures by direct contact with a liquid helium bath, resulting in at least part of the helium container being made from pure niobium. In the U.S., the Code of Federal Regulations allows national laboratories to follow national consensus pressure vessel rules or use of alternative rules which provide a level of safety greater than or equal to that afforded by ASME Boiler and Pressure Vessel Code. Thus, while used for its superconducting properties, niobium ends up also being treated as a material for pressure vessels. This report summarizes what we have learned about the use of niobium as a pressure vessel material, with a focus on issues for compliance with pressure vessel codes. We present results of a literature search for mechanical properties and tests results, as well as a review of ASME pressure vessel code requirements and issues.

  17. Reactor pressure vessel head vents and methods of using the same

    DOE Patents [OSTI]

    Gels, John L; Keck, David J; Deaver, Gerald A

    2014-10-28

    Internal head vents are usable in nuclear reactors and include piping inside of the reactor pressure vessel with a vent in the reactor upper head. Piping extends downward from the upper head and passes outside of the reactor to permit the gas to escape or be forcibly vented outside of the reactor without external piping on the upper head. The piping may include upper and lowers section that removably mate where the upper head joins to the reactor pressure vessel. The removable mating may include a compressible bellows and corresponding funnel. The piping is fabricated of nuclear-reactor-safe materials, including carbon steel, stainless steel, and/or a Ni--Cr--Fe alloy. Methods install an internal head vent in a nuclear reactor by securing piping to an internal surface of an upper head of the nuclear reactor and/or securing piping to an internal surface of a reactor pressure vessel.

  18. Fast neutron fluence of yonggwang nuclear unit 1 reactor pressure vessel

    SciTech Connect (OSTI)

    Yoo, C.; Km, B.; Chang, K.; Leeand, S.; Park, J.

    2006-07-01

    The Code of Federal Regulations, Title 10, Part 50, Appendix H, requires that the neutron dosimetry be present to monitor the reactor vessel throughout plant life. The Ex-Vessel Neutron Dosimetry System has been installed for Yonggwang Nuclear Unit 1 after complete withdrawal of all six in-vessel surveillance capsules. This system has been installed in the reactor cavity annulus in order to measure the fast neutron spectrum coming out through the reactor pressure vessel. Cycle specific neutron transport calculations were performed to obtain the energy dependent neutron flux throughout the reactor geometry including dosimetry positions. Comparisons between calculations and measurements were performed for the reaction rates of each dosimetry sensors and results show good agreements. (authors)

  19. Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2010-01-01

    1.1 This practice covers procedures for designing a surveillance program for monitoring the radiation-induced changes in the mechanical properties of ferritic materials in light-water moderated nuclear power reactor vessels. This practice includes the minimum requirements for the design of a surveillance program, selection of vessel material to be included, and the initial schedule for evaluation of materials. 1.2 This practice was developed for all light-water moderated nuclear power reactor vessels for which the predicted maximum fast neutron fluence (E > 1 MeV) at the end of license (EOL) exceeds 1 × 1021 neutrons/m2 (1 × 1017 n/cm2) at the inside surface of the reactor vessel. 1.3 This practice applies only to the planning and design of surveillance programs for reactor vessels designed and built after the effective date of this practice. Previous versions of Practice E185 apply to earlier reactor vessels. 1.4 This practice does not provide specific procedures for monitoring the radiation induced cha...

  20. IDS120h GEOMETRY SHIELDING VESSELS: STAINLESS STEEL vs. TUNGSTEN

    E-Print Network [OSTI]

    McDonald, Kirk

    IDS120h GEOMETRY SHIELDING VESSELS: STAINLESS STEEL vs. TUNGSTEN SHIELDING MATERIAL: 60%WC+40%H2 O shielding vessels (STST OR W) Different cases of shielding material. >mars1510/MCNP >10-11 MeV NEUTRON ENERGY CUTOFF >SHIELDING:60%WC+40%H2 O (STST or W VESSELS), 80%WC+20%He, 80%W+20%He (W VESSELS) >4 MW

  1. Tritium Reduction and Control in the Vacuum Vessel During TFTR Outage and Decommissioning *

    E-Print Network [OSTI]

    Tritium Reduction and Control in the Vacuum Vessel During TFTR Outage and Decommissioning * W nearly three years of D­T operations, TFTR underwent an extended outage during which large port covers of the torus, a three tier system was developed for the outage in order to reduce and control the free tritium

  2. Tritium Reduction and Control in the Vacuum Vessel During TFTR Outage and Decommissioning*

    E-Print Network [OSTI]

    Tritium Reduction and Control in the Vacuum Vessel During TFTR Outage and Decommissioning* W years of D-T operations, TFTR underwent an extended outage during which large port covers were removed, a three tier system was developed for the outage in order to reduce and control the free tritium

  3. A Synthesis of Cost and Revenue Surveys for Gulf of Mexico Shrimp Vessels

    E-Print Network [OSTI]

    may maximize the income of a fisherman while the verti cally integrated fishing firm may operate descriptive statis tics. For example, mean total revenue for surveyed vessels was reported as $60,142 (Warren in the survey data. For example, changes in the cost an

  4. High pressure feeder and method of operating to feed granular or fine materials

    DOE Patents [OSTI]

    Vimalchand, Pannalal; Liu, Guohai; Peng, Wan Wang

    2014-10-07

    A coal feed system to feed pulverized low rank coals containing up to 25 wt % moisture to gasifiers operating up to 1000 psig pressure is described. The system includes gas distributor and collector gas permeable pipes imbedded in the lock vessel. Different methods of operation of the feed system are disclosed to minimize feed problems associated with bridging and packing of the pulverized coal. The method of maintaining the feed system and feeder device exit pressures using gas addition or extraction with the pressure control device is also described.

  5. Probabilistic vessel axis tracing and its application to vessel segmentation with stream surfaces and minimum cost paths

    E-Print Network [OSTI]

    Chung, Albert C. S.

    Probabilistic vessel axis tracing and its application to vessel segmentation with stream surfaces May 2007 Available online 2 June 2007 Abstract We propose a novel framework to segment vessels on their cross-sections. It starts with a probabilistic vessel axis tracing in a gray-scale three

  6. Design and Operation of A Setup with A Camera and Adjustable Mirror to Inspect the Sense-Wire Planes of the Time Projection Chamber Inside the MicroBooNE Cryostat

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

    Carls, Benjamin; Horton-Smith, Glenn; James, Catherine C.; Kubinski, Robert M.; Pordes, Stephen; Schukraft, Anne; Strauss, Thomas

    2015-08-26

    Detectors in particle physics, particularly when including cryogenic components, are often enclosed in vessels that do not provide any physical or visual access to the detectors themselves after installation. However, it can be desirable for experiments to visually investigate the inside of the vessel. The MicroBooNE cryostat hosts a TPC with sense-wire planes, which had to be inspected for damage such as breakage or sagging. This inspection was performed after the transportation of the vessel with the enclosed detector to its final location, but before filling with liquid argon. Our paper describes an approach to view the inside of themore »MicroBooNE cryostat with a setup of a camera and a mirror through one of its cryogenic service nozzles. The paper also describes the camera and mirror chosen for the operation, the illumination, and the mechanical structure of the setup. It explains how the system was operated and demonstrates its performance.« less

  7. Next Generation Nuclear Plant Reactor Pressure Vessel Materials Research and Development Plan (PLN-2803)

    SciTech Connect (OSTI)

    J. K. Wright; R. N. Wright

    2010-07-01

    The U.S. Department of Energy (DOE) has selected the High-Temperature Gas-cooled Reactor (HTGR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production, with an outlet gas temperature in the range of 750°C, and a design service life of 60 years. The reactor design will be a graphite-moderated, helium-cooled, prismatic, or pebble bed reactor and use low-enriched uranium, Tri-Isotopic (TRISO)-coated fuel. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. Selection of the technology and design configuration for the NGNP must consider both the cost and risk profiles to ensure that the demonstration plant establishes a sound foundation for future commercial deployments. The NGNP challenge is to achieve a significant advancement in nuclear technology while setting the stage for an economically viable deployment of the new technology in the commercial sector soon after 2020. This technology development plan details the additional research and development (R&D) required to design and license the NGNP RPV, assuming that A 508/A 533 is the material of construction. The majority of additional information that is required is related to long-term aging behavior at NGNP vessel temperatures, which are somewhat above those commonly encountered in the existing database from LWR experience. Additional data are also required for the anticipated NGNP environment. An assessment of required R&D for a Grade 91 vessel has been retained from the first revision of the R&D plan in Appendix B in somewhat less detail. Considerably more development is required for this steel compared to A 508/A 533 including additional irradiation testing for expected NGNP operating temperatures, high-temperature mechanical properties, and extensive studies of long-term microstructural stability.

  8. Cavity closure arrangement for high pressure vessels

    DOE Patents [OSTI]

    Amtmann, Hans H. (San Diego, CA)

    1981-01-01

    A closure arrangement for a pressure vessel such as the pressure vessel of a high temperature gas-cooled reactor wherein a liner is disposed within a cavity penetration in the reactor vessel and defines an access opening therein. A closure is adapted for sealing relation with an annular mounting flange formed on the penetration liner and has a plurality of radially movable locking blocks thereon having outer serrations adapted for releasable interlocking engagement with serrations formed internally of the upper end of the penetration liner so as to effect high strength closure hold-down. In one embodiment, ramping surfaces are formed on the locking block serrations to bias the closure into sealed relation with the mounting flange when the locking blocks are actuated to locking positions.

  9. SAFETY MANAGEMENT MANUAL OSU SHIP OPERATIONS

    E-Print Network [OSTI]

    Kurapov, Alexander

    overboarding operations on the vessel. 7.16.2 Scope This procedure covers the design, installation, maintenance's equipment - is defined as machinery such as crane, winches, capstans, blocks and rigging regularly as machinery such as winches, cranes and blocks owned by OSU groups other than Ship Operations

  10. EDS V25 containment vessel explosive qualification test report.

    SciTech Connect (OSTI)

    Rudolphi, John Joseph

    2012-04-01

    The V25 containment vessel was procured by the Project Manager, Non-Stockpile Chemical Materiel (PMNSCM) as a replacement vessel for use on the P2 Explosive Destruction Systems. It is the first EDS vessel to be fabricated under Code Case 2564 of the ASME Boiler and Pressure Vessel Code, which provides rules for the design of impulsively loaded vessels. The explosive rating for the vessel based on the Code Case is nine (9) pounds TNT-equivalent for up to 637 detonations. This limit is an increase from the 4.8 pounds TNT-equivalency rating for previous vessels. This report describes the explosive qualification tests that were performed in the vessel as part of the process for qualifying the vessel for explosive use. The tests consisted of a 11.25 pound TNT equivalent bare charge detonation followed by a 9 pound TNT equivalent detonation.

  11. The impact of microwave stray radiation to in-vessel diagnostic components

    SciTech Connect (OSTI)

    Hirsch, M.; Laqua, H. P.; Hathiramani, D.; Baldzuhn, J.; Biedermann, C.; Cardella, A.; Erckmann, V.; König, R.; Köppen, M.; Zhang, D. [Max-Planck-Institut für Plasmaphysik, Teilinstitut Greifswald, EURATOM Association, D-17489 Greifswald (Germany); Oosterbeek, J.; Brand, H. von der; Parquay, S. [Technische Universiteit Eindhoven, department Technische Natuurkunde, working group for Plasma Physics and Radiation Technology, Den Doelch 2, 5612 AZ Eindhoven (Netherlands); Jimenez, R. [Centro de Investigationes Energeticas, Medioambientales y Technológicas, Association EURATOM/CIEMAT, Avenida Complutense 22, Madrid 28040 (Spain); Collaboration: W7-X Teasm

    2014-08-21

    Microwave stray radiation resulting from unabsorbed multiple reflected ECRH / ECCD beams may cause severe heating of microwave absorbing in-vessel components such as gaskets, bellows, windows, ceramics and cable insulations. In view of long-pulse operation of WENDELSTEIN-7X the MIcrowave STray RAdiation Launch facility, MISTRAL, allows to test in-vessel components in the environment of isotropic 140 GHz microwave radiation at power load of up to 50 kW/m{sup 2} over 30 min. The results show that both, sufficient microwave shielding measures and cooling of all components are mandatory. If shielding/cooling measures of in-vessel diagnostic components are not efficient enough, the level of stray radiation may be (locally) reduced by dedicated absorbing ceramic coatings on cooled structures.

  12. Maritime Interdiction Operations Small Craft Detection

    SciTech Connect (OSTI)

    Dougan, A D; Trombino, D; Dunlop, W; Bordetsky, A

    2010-01-26

    The Naval Postgraduate School has been conducting Tactical Network Topology (TNT) Maritime Interdiction Operations (MIO) experiments with Lawrence Livermore National Laboratory (LLNL) since early in 2005. In this work, we are investigating cutting edge technology to evaluate use of networks, advanced sensors and collaborative technology for globally-supported maritime interdiction operations. Some examples of our research include communications in harsh environments, between moving ships at sea; small boat drive-by radiation detection; network-centric collaboration with global partners; situational awareness; prototype sensors & biometric instruments. Since 2006, we have studied the concept of using a small vessel with fixed radiation sensors to do initial searches for illicit radioactive materials. In our work, we continue to evaluate concepts of operation for small boat monitoring. For example, in San Francisco Bay we established a simulated choke point using two RHIBs. Each RHIB had a large sodium iodide radiation sensor on board, mounted on the side nearest to the passing potential target boats. Once detections were made, notification over the network prompted a chase RHIB also equipped with a radiation sensor to further investigate the potential target. We have also used an unmanned surface vessel (USV) carrying a radiation sensor to perform the initial discovery. The USV was controlled remotely and to drive by boats in different configurations. The potential target vessels were arranged in a line, as a choke point and randomly spaced in the water. Search plans were problematic when weather, waves and drift complicated the ability to stay in one place. A further challenge is to both detect and identify the radioactive materials during the drive-by. Our radiation detection system, ARAM, Adaptable Radiation Area Monitor, is able to detect, alarm and quickly identify plausible radionuclides in real time. We have performed a number of experiments to better understand parameters of vessel speed, time, shielding, and distance in this complex three-dimensional space. At the NMIOTC in September 2009, we employed a dual detector portal followed by a chase. In this event, the challenge was to maintain communications after a lapse. When the chase went past the line-of sight reach of the Tactical Operational Center's (TOC) antenna, with interference from a fortress island in Suda Bay, Wave Relay extended the network for continued observation. Sodium iodide radiation detectors were mounted on two Hellenic Navy SEAL fast boats. After making the detection one of the portal boats maintained line-of sight while the other pursued the target vessel. Network access via Wave Relay antennas was maintained until the conclusion of the chase scenario. Progress has been made in the detection of radioactive materials in the maritime environment. The progression of the TNT MIO experiments has demonstrated the potential of the hardware to solve the problems encountered in this physically challenging environment. There continue to be interesting opportunities for research and development. These experiments provide a variety of platforms and motivated participants to perform real-world testing as solutions are made available.

  13. Classification of KdV vessels with constant parameters and two dimensional outer space

    E-Print Network [OSTI]

    Andrey Melnikov

    2014-07-06

    In this article we classify vessels producing solutions of some completely integrable PDEs, presenting a \\textit{unified} approach for them. The classification includes such important examples as Korteweg-de Vries (KdV) and evolutionary Non Linear Schr\\" odingier (ENLS) equations. In fact, employing basic matrix algebra techniques it is shown that there are exactly two canonical forms of such vessels, so that each canonical form generalize either KdV or ENLS equations. Particularly, Dirac canonical systems, whose evolution was recently inserted into the vessel theory, are shown to be equivalent to the ENLS equation in the sense of vessels. This work is important as a first step to classification of completely integrable PDEs, which are solvable by the theory of vessels. We note that a recent paper of the author, published in Journal of Mathematical Physics, showed that initial value problem with analytic initial potential for the KdV equation has at least a "narrowing" in time solution. The presented classification, inherits this idea and a similar theorem can be easily proved for the presented PDEs. Finally, the the resuts of the work serve as a basis for the investigation of the following problems: 1. hierarchy of the generalized KdV, ENLS equations (by generalizing the vessel equations), 2. new completely integrable PDEs (by changing the dimension of the outer space), 3. addressing the question of integrability of a given arbitrary PDE (the future classification will create a list of solvable by vessels equations, which may eventually include many existing classes of PDEs).

  14. In-Vessel Retention of Molten Corium: Lessons Learned and Outstanding Issues

    SciTech Connect (OSTI)

    J.L. Rempe; K.Y. Suh; F. B. Cheung; S. B. Kim

    2008-03-01

    In-vessel retention (IVR) of core melt is a key severe accident management strategy adopted by some operating nuclear power plants and proposed for some advanced light water reactors (ALWRs). If there were inadequate cooling during a reactor accident, a significant amount of core material could become molten and relocate to the lower head of the reactor vessel, as happened in the Three Mile Island Unit 2 (TMI-2) accident. If it is possible to ensure that the vessel head remains intact so that relocated core materials are retained within the vessel, the enhanced safety associated with these plants can reduce concerns about containment failure and associated risk. For example, the enhanced safety of the Advanced 600 MWe Pressurized Water Reactor (PWR) designed by Westinghouse (AP600), which relied upon External Reactor Vessel Cooling (ERVC) for IVR, resulted in the U.S. Nuclear Regulatory Commission (US NRC) approving the design without requiring certain conventional features common to existing Light Water Reactors (LWRs). However, it is not clear that the ERVC proposed for the AP600 could provide sufficient heat removal for higher-power reactors (up to 1500 MWe) without additional enhancements. This paper reviews efforts made and results reported regarding the enhancement of IVR in LWRs. Where appropriate, the paper identifies what additional data or analyses are needed to demonstrate that there is sufficient margin for successful IVR in high power thermal reactors.

  15. Solution of the KdV equation using evolutionary vessels

    E-Print Network [OSTI]

    Andrey Melnikov

    2011-11-09

    In this work we present a new method for solving of the Korteweg-de Vries (KdV) equation q'_t = - \\dfrac{3}{2} q q'_x + \\dfrac{1}{4} q"'_{xxx}. The proposed method is a particular case of the theory of evolutionary vessels, developed in this work. Inverse scattering of the Sturm-Liouville operator and evolution of its potential are the basic ingredients, similar to the existing methods developed by Gardner-Greene-Kruskal-Miura (1967), Zacharov-Shabbath (1974) and Peter Lax (1977). Evolutionary KdV vessel may be considered as a generalization of these previous works. The advantage of the new method is that it produces a unified approach to existing solutions of the KdV equation. For example, odd or even analytic, periodic, almost periodic solutions are shown to be particular cases of this theory. Generalizing this method we can also produce many PDEs, associated with integrable systems, in an arbitrary number of variables (in the spirit of Zakarov-Shabat).

  16. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    ASSESSMENT (VTRA) 2010 11/18/2013 2 GW-VCU Draft #12;P: BC & DH100 3D Risk Profile All FV - Pot. Ground. Oil OIL LOSS - PGO Draft #12;11/18/2013 5 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 POTENTIALVESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Potential Grounding

  17. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    COLLISION OIL LOSS - PCO Draft #12;11/18/2013 5 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 POTENTIALVESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Potential Collision Oil Loss Dr. J. Rene van Dorp and Dr. Jason R.W Merrick 11/18/2013 1 GW-VCU November 2013 CASE P: BASE

  18. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    ) 2010 Draft #12;11/18/2013 4 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 POTENTIAL GROUNDING OILVESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Potential Grounding Oil Loss Dr. J. Rene van Dorp and Dr. Jason R.W Merrick 11/18/2013 1 GW-VCU November 2013 CASE P: BASE

  19. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    COLLISION OIL LOSS - PCO Draft #12;11/19/2013 5 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 POTENTIALVESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Potential Collision Oil Loss Dr. J. Rene van Dorp and Dr. Jason R.W Merrick 11/19/2013 1 GW-VCU November 2013 CASE P: BASE

  20. VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010

    E-Print Network [OSTI]

    van Dorp, Johan René

    OIL LOSS - PGO Draft #12;11/19/2013 5 GW-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 POTENTIALVESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Potential Grounding Oil Loss Dr. J. Rene van Dorp and Dr. Jason R.W Merrick 11/19/2013 1 GW-VCU November 2013 CASE P: BASE

  1. Final Vitrification Melter And Vessels Evaluation Documentation

    Broader source: Energy.gov [DOE]

    DOE has prepared final evaluations and made waste incidental to reprocessing determinations for the vitrification melter and feed vessels (the concentrator feed makeup tank and the melter feed hold tank), used by DOE’s West Valley Demonstration Project as part of the process to vitrify waste from prior commercial reprocessing of spent nuclear fuel.

  2. Reactor pressure vessel with forged nozzles

    DOE Patents [OSTI]

    Desai, Dilip R. (Fremont, CA)

    1993-01-01

    Inlet nozzles for a gravity-driven cooling system (GDCS) are forged with a cylindrical reactor pressure vessel (RPV) section to which a support skirt for the RPV is attached. The forging provides enhanced RPV integrity around the nozzle and substantial reduction of in-service inspection costs by eliminating GDCS nozzle-to-RPV welds.

  3. THE WEST GERMAN RESEARCH VESSEL WALTHER HERWIG

    E-Print Network [OSTI]

    ....... .·. ... .. .........··...... 1 Lower deck aft........... ............... ............. ....... 1 Fish processing machinery and launched in 1963. The vessel was primarily designed as a stern trawler for use in high sea fisheries investigations with emphasis on mid- water and bottom trawling. Pertinent features of design, equipment

  4. Exploratory Dijkstra forest based automatic vessel segmentation

    E-Print Network [OSTI]

    Tomasi, Carlo

    , and follows vessel branching naturally and efficiently. To test our method, we constructed a retinal video code freely available online. © 2012 Optical Society of America OCIS codes: (100.0100) Image processing, "Automatic segmentation of seven retinal layers in SDOCT images congruent with expert manual segmentation

  5. Climate Data Operators (CDO)

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

    Climate Data Operators (CDO) Climate Data Operators (CDO) Description and Overview CDO is a large tool set for working on climate data. NetCDF 34, GRIB including SZIP compression,...

  6. What To Include In The Whistleblower Complaint? | National Nuclear...

    National Nuclear Security Administration (NNSA)

    Apply for Our Jobs Our Jobs Working at NNSA Blog Home About Us Our Operations Management and Budget Whistleblower Program What To Include In The Whistleblower Complaint?...

  7. Mast cells present protrusions into blood vessels upon tracheal allergen challenge in mice

    E-Print Network [OSTI]

    2015-01-01

    probe cutaneous blood vessels to capture immunoglobulin E.Protrusions into Blood Vessels upon Tracheal AllergenProtrusions into Blood Vessels upon Tracheal Allergen

  8. Extending vaterite microviscometry to ex vivo blood vessels by serial calibration

    E-Print Network [OSTI]

    Shreim, Samir G.; Steward, Earl; Botvinick, Elliot L.

    2011-01-01

    stresses doing in our blood vessels? ” Ann. Biomed. Eng. 19(to ex vivo blood vessels by serial calibration Samir G.implications in vessel mechanics and mechanotransduction.

  9. The "Empty Vessel" Physician: Physicians' Instrumentality Makes Them Seem Personally Empty

    E-Print Network [OSTI]

    Schroeder, J; Fishbach, A

    2015-01-01

    Article The ‘‘Empty Vessel’’ Physician: Physicians’emotionless ‘‘empty vessels’’: The higher is individuals’physicians as empty vessels for health care. Keywords

  10. Arborizing vessels under dermoscopy: A case of cellular neurothekeoma instead of basal cell carcinoma

    E-Print Network [OSTI]

    Aydingoz, Ikbal Esen; Mansur, Ayse Tulin; Dikicioglu-Cetin, Emel

    2013-01-01

    inspection disclosed prominent vessels. The background skinonly thick and arborizing vessels on the surface of theshowing arborizing vessels (Heine x10) Histopathology

  11. Cover Heated, Open Vessels, Energy Tips: STEAM, Steam Tip Sheet...

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

    9 Cover Heated, Open Vessels Open vessels that contain heated liquids often have high heat loss due to surface evaporation. Both energy and liquid losses are reduced by covering...

  12. Study Reveals Challenges and Opportunities Related to Vessels...

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

    Reveals Challenges and Opportunities Related to Vessels for U.S. Offshore Wind Study Reveals Challenges and Opportunities Related to Vessels for U.S. Offshore Wind October 1, 2013...

  13. aftercastle masted vessel with aftercastle is found on a Spanish

    E-Print Network [OSTI]

    masted vessel with aftercastle is found on a Spanish ations it would have any idea of crusader ships aces for the new tack as large as the crusader vessels (

  14. Seismic analysis of the Mirror Fusion Test Facility: soil structure interaction analyses of the Axicell vacuum vessel. Revision 1

    SciTech Connect (OSTI)

    Maslenikov, O.R.; Mraz, M.J.; Johnson, J.J.

    1986-03-01

    This report documents the seismic analyses performed by SMA for the MFTF-B Axicell vacuum vessel. In the course of this study we performed response spectrum analyses, CLASSI fixed-base analyses, and SSI analyses that included interaction effects between the vessel and vault. The response spectrum analysis served to benchmark certain modeling differences between the LLNL and SMA versions of the vessel model. The fixed-base analysis benchmarked the differences between analysis techniques. The SSI analyses provided our best estimate of vessel response to the postulated seismic excitation for the MFTF-B facility, and included consideration of uncertainties in soil properties by calculating response for a range of soil shear moduli. Our results are presented in this report as tables of comparisons of specific member forces from our analyses and the analyses performed by LLNL. Also presented are tables of maximum accelerations and relative displacements and plots of response spectra at various selected locations.

  15. Brian Somerday, an SNL researcher, prepares to load a hydrogen pressure vessel into a laboratory furnace.

    E-Print Network [OSTI]

    include hydrogen production, fuel cells, thermophysical properties, hydrogen storage materials, and carbonI2CNER n Brian Somerday, an SNL researcher, prepares to load a hydrogen pressure vessel into a laboratory furnace. Unequivocally Sandia's strong research record and industrial experience on hydrogen

  16. Tailoring Topology Optimization to Composite Pressure Vessel Design with Simultaneous

    E-Print Network [OSTI]

    Paulino, Glaucio H.

    $160/ship Comparison of CNG and LNG (Liquefied Natural Gas) Introduction ­ CNG Pressure Vessels MM;Introduction ­ CNG Pressure Vessels Compressed Natural Gas (CNG) Pressure Vessels CNG Cargo Containment System upon the number of ships used for the transport of the gas. MMscf/d - million standard cubic feet per

  17. Large Blood Vessels 1.1 Introduction --The Cardiovascular System

    E-Print Network [OSTI]

    Luo, Xiaoyu

    Chapter 1 Large Blood Vessels 1.1 Introduction -- The Cardiovascular System The heart is a pump vessels, the capillaries, in which the main ex- change processes between the blood and tissues take place- sue, collagen, with a few muscle cells. 3 #12;4 CHAPTER 1. LARGE BLOOD VESSELS Figure 1.1: Structure

  18. FEDERAL PERMIT APPLICATION FOR VESSELS FISHING FOR WRECKFISH

    E-Print Network [OSTI]

    1 FEDERAL PERMIT APPLICATION FOR VESSELS FISHING FOR WRECKFISH OFF THE SOUTH ATLANTIC STATES OMB can you bring to the dock when full? USCG DOCUMENTED VESSELS ONLY Gross Tons Net Tons Hull Material) United States Coast Guard (USCG) Certificate of Documentation or a copy of the State Vessel Registration

  19. Image Segmentation Methods for Detecting Blood Vessels in Angiography

    E-Print Network [OSTI]

    Chung, Albert C. S.

    Image Segmentation Methods for Detecting Blood Vessels in Angiography Albert C. S. Chung Lo Kwee-assisted detection and segmentation of blood vessels in angiography are crucial for endovascular treat- ments--Segmentation of Blood Vessels, Feature Detection, Statistical Segmentation, Active Contour Model, Angiography I

  20. Modeling Torsion of Blood Vessels in Surgical Simulation and Planning

    E-Print Network [OSTI]

    Leow, Wee Kheng

    Modeling Torsion of Blood Vessels in Surgical Simulation and Planning Hao LI a,1 , Wee Kheng LEOW a hybrid approach for modeling torsion of blood vessels that undergo deformation and joining. The proposed model takes 3D mesh of the blood vessel as input. It first fits a generalized cylinder to extract

  1. IDS120h GEOMETRY WITH SHIELDING VESSELS ENERGY FLOW ANALYSIS

    E-Print Network [OSTI]

    McDonald, Kirk

    IDS120h GEOMETRY WITH SHIELDING VESSELS ENERGY FLOW ANALYSIS SHIELDING MATERIAL: 60% W + 40% He vs SHIELDING Nicholas Souchlas, PBL (10/18/2011) 1 #12;IDS120h with shielding vessels. # Different cases ENERGY CUTOFF >SHIELDING: 60% W + 40% He , 80% W + 20% He, 88% W + 12% He ( WITH W VESSELS) >4 MW proton

  2. Vessel tractography using an intensity based tensor model

    E-Print Network [OSTI]

    Yanikoglu, Berrin

    Vessel tractography using an intensity based tensor model Suheyla Cetin1 , Gozde Unal1 , Ali Demir1 method, which is based on an intensity-based tensor that fits to a vessel. Our model is initialized with a single seed point and it is ca- pable of capturing whole vessel tree by an automatic branch detection

  3. (Irradiation embrittlement of reactor pressure vessels)

    SciTech Connect (OSTI)

    Corwin, W.R.

    1990-09-24

    The traveler served as a member of the two-man US Nuclear Regulatory Commission sponsored team who visited the Prometey Complex in Leningrad to assess the potential for expanded cooperative research concerning integrity of the primary pressure boundary in commercial light-water reactors. The emphasis was on irradiation embrittlement, structural analysis, and fracture mechanics research for reactor pressure vessels. At the irradiation seminar in Cologne, presentations were made by German, French, Finnish, Russian, and US delegations concerning many aspects of irradiation of pressure vessel steels. The traveler made presentations on mechanisms of irradiation embrittlement and on important aspects of the Heavy-Section Steel Irradiation Program results of irradiated fracture mechanics tests.

  4. Uncertainty quantification of a containment vessel dynamic response subjected to high-explosive detonation impulse loading

    SciTech Connect (OSTI)

    Rodriguez, E. A.; Pepin, J. E.; Thacker, B. H.; Riha, D. S.

    2002-01-01

    Los Alamos National Laboratory (LANL), in cooperation with Southwest Research Institute, has been developing capabilities to provide reliability-based structural evaluation techniques for performing weapon component and system reliability assessments. The development and applications of Probabilistic Structural Analysis Methods (PSAM) is an important ingredient in the overall weapon reliability assessments. Focus, herein, is placed on the uncertainty quantification associated with the structural response of a containment vessel for high-explosive (HE) experiments. The probabilistic dynamic response of the vessel is evaluated through the coupling of the probabilistic code NESSUS with the non-linear structural dynamics code, DYNA-3D. The probabilistic model includes variations in geometry and mechanical properties, such as Young's Modulus, yield strength, and material flow characteristics. Finally, the probability of exceeding a specified strain limit, which is related to vessel failure, is determined.

  5. Standard Guide for In-Service Annealing of Light-Water Moderated Nuclear Reactor Vessels

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2003-01-01

    1.1 This guide covers the general procedures to be considered for conducting an in-service thermal anneal of a light-water moderated nuclear reactor vessel and demonstrating the effectiveness of the procedure. The purpose of this in-service annealing (heat treatment) is to improve the mechanical properties, especially fracture toughness, of the reactor vessel materials previously degraded by neutron embrittlement. The improvement in mechanical properties generally is assessed using Charpy V-notch impact test results, or alternatively, fracture toughness test results or inferred toughness property changes from tensile, hardness, indentation, or other miniature specimen testing (1). 1.2 This guide is designed to accommodate the variable response of reactor-vessel materials in post-irradiation annealing at various temperatures and different time periods. Certain inherent limiting factors must be considered in developing an annealing procedure. These factors include system-design limitations; physical constrain...

  6. Countries Gasoline Prices Including Taxes

    Gasoline and Diesel Fuel Update (EIA)

    Crude oil, gasoline, heating oil, diesel, propane, and other liquids including biofuels and natural gas liquids. Natural Gas Exploration and reserves, storage, imports and...

  7. Weld Repair of a Stamped Pressure Vessel in a Radiologically Controlled Zone

    SciTech Connect (OSTI)

    Cannell, Gary L.; Huth, Ralph J.; Hallum, Randall T.

    2013-08-26

    In September 2012 an ASME B&PVC Section VIII stamped pressure vessel located at the DOE Hanford Site Effluent Treatment Facility (ETF) developed a through-wall leak. The vessel, a steam/brine heat exchanger, operated in a radiologically controlled zone (by the CH2MHill PRC or CHPRC), had been in service for approximately 17 years. The heat exchanger is part of a single train evaporator process and its failure caused the entire system to be shut down, significantly impacting facility operations. This paper describes the activities associated with failure characterization, technical decision making/planning for repair by welding, logistical challenges associated with performing work in a radiologically controlled zone, performing the repair, and administrative considerations related to ASME code requirements.

  8. Confinement Vessel Assay System: Calibration and Certification Report

    SciTech Connect (OSTI)

    Frame, Katherine C. [Los Alamos National Laboratory; Bourne, Mark M. [Los Alamos National Laboratory; Crooks, William J. [Los Alamos National Laboratory; Evans, Louise [Los Alamos National Laboratory; Gomez, Cipriano [Retired CMR-OPS: OPERATIONS; Mayo, Douglas R. [Los Alamos National Laboratory; Miko, David K. [Los Alamos National Laboratory; Salazar, William R. [Los Alamos National Laboratory; Stange, Sy [Los Alamos National Laboratory; Vigil, Georgiana M. [Los Alamos National Laboratory

    2012-07-17

    Los Alamos National Laboratory has a number of spherical confinement vessels (CVs) remaining from tests involving nuclear materials. These vessels have an inner diameter of 6 feet with 1 to 2 inch thick steel walls. The goal of the Confinement Vessel Disposition (CVD) project is to remove debris and reduce contamination inside the vessels. The Confinement Vessel Assay System (CVAS) was developed to measure the amount of SNM in CVs before and after cleanout. Prior to cleanout, the system will be used to perform a verification measurement of each vessel. After cleanout, the system will be used to perform safeguards-quality assays of {le} 100-g {sup 239}Pu equivalent in a vessel for safeguards termination. The system was calibrated in three different mass regions (low, medium, and high) to cover the entire plutonium mass range that will be assayed. The low mass calibration and medium mass calibration were verified for material positioned in the center of an empty vessel. The systematic uncertainty due to position bias was estimated using an MCNPX model to simulate the response of the system to material localized at various points along the inner surface of the vessel. The background component due to cosmic ray spallation was determined by performing measurements of an empty vessel and comparing to measurements in the same location with no vessel present. The CVAS has been tested and calibrated in preparation for verification and safeguards measurements of CVs before and after cleanout.

  9. Neutralino relic density including coannihilations

    E-Print Network [OSTI]

    Paolo Gondolo; Joakim Edsjo

    1997-11-25

    We give an overview of our precise calculation of the relic density of the lightest neutralino, in which we included relativistic Boltzmann averaging, subthreshold and resonant annihilations, and coannihilation processes with charginos and neutralinos.

  10. Pressure vessel sliding support unit and system using the sliding support unit

    DOE Patents [OSTI]

    Breach, Michael R.; Keck, David J.; Deaver, Gerald A.

    2013-01-15

    Provided is a sliding support and a system using the sliding support unit. The sliding support unit may include a fulcrum capture configured to attach to a support flange, a fulcrum support configured to attach to the fulcrum capture, and a baseplate block configured to support the fulcrum support. The system using the sliding support unit may include a pressure vessel, a pedestal bracket, and a plurality of sliding support units.

  11. Potential for AP600 in-vessel retention through ex-vessel flooding

    SciTech Connect (OSTI)

    Rempe, J.L.; Knudson, D.L.; Allison, C.M.; Thinnes, G.L.; Atwood, C.L.

    1997-12-01

    External reactor vessel cooling (ERVC) is a new severe accident management strategy that involves flooding the reactor cavity to submerge the reactor vessel in an attempt to cool core debris that has relocated to the vessel lower head. Advanced and existing light water reactors (LWRs) are considering ERVC as an accident management strategy for in-vessel retention (IVR) of relocated debris. In the probabilistic risk assessment (PRA) for the AP600 design, Westinghouse credits ERVC for preventing vessel failure during postulated severe accidents with successful reactor coolant system (RCS) depressurization and reactor cavity flooding. To support the Westinghouse position on IVR, DOE contracted the University of California--Santa Barbara (UCSB) to produce the peer-reviewed report. To assist in the NRC`s evaluation of IVR of core melt by ex-vessel flooding of the AP6OO, the Idaho National Engineering and Environmental Laboratory (INEEL) was tasked to perform: An in-depth critical review of the UCSB study and the model that UCSB used to assess ERVC effectiveness; An in-depth review of the UCSB study peer review comments and of UCSB`s resolution method to identify areas where technical concerns weren`t addressed; and An independent analysis effort to investigate the impact of residual concerns on the margins to failure and conclusions presented in the UCSB study. This report summarizes results from these tasks. As discussed in Sections 1.1 and 1.2, INEEL`s review of the UCSB study and peer reviewer comments suggested that additional analysis was needed to assess: (1) the integral impact of peer reviewer-suggested changes to input assumptions and uncertainties and (2) the challenge present by other credible debris configurations. Section 1.3 summarized the corresponding analysis approach developed by INEEL. The remainder of this report provides more detailed descriptions of analysis methodology, input assumptions, and results.

  12. Engine lubrication circuit including two pumps

    DOE Patents [OSTI]

    Lane, William H.

    2006-10-03

    A lubrication pump coupled to the engine is sized such that the it can supply the engine with a predetermined flow volume as soon as the engine reaches a peak torque engine speed. In engines that operate predominately at speeds above the peak torque engine speed, the lubrication pump is often producing lubrication fluid in excess of the predetermined flow volume that is bypassed back to a lubrication fluid source. This arguably results in wasted power. In order to more efficiently lubricate an engine, a lubrication circuit includes a lubrication pump and a variable delivery pump. The lubrication pump is operably coupled to the engine, and the variable delivery pump is in communication with a pump output controller that is operable to vary a lubrication fluid output from the variable delivery pump as a function of at least one of engine speed and lubrication flow volume or system pressure. Thus, the lubrication pump can be sized to produce the predetermined flow volume at a speed range at which the engine predominately operates while the variable delivery pump can supplement lubrication fluid delivery from the lubrication pump at engine speeds below the predominant engine speed range.

  13. Low Temperature Irradiation Embrittlement of Reactor Pressure Vessel Steels

    SciTech Connect (OSTI)

    Wang, Jy-An John

    2015-08-01

    The embrittlement trend curve development project for HFIR reactor pressure vessel (RPV) steels was carried out with three major tasks. Which are (1) data collection to match that used in HFIR steel embrittlement trend published in 1994 Journal Nuclear Material by Remec et. al, (2) new embrittlement data of A212B steel that are not included in earlier HFIR RPV trend curve, and (3) the adjustment of nil-ductility-transition temperature (NDTT) shift data with the consideration of the irradiation temperature effect. An updated HFIR RPV steel embrittlement trend curve was developed, as described below. NDTT( C) = 23.85 log(x) + 203.3 log (x) + 434.7, with 2- uncertainty of 34.6 C, where parameter x is referred to total dpa. The developed update HFIR RPV embrittlement trend curve has higher embrittlement rate compared to that of the trend curve developed in 1994.

  14. Cryogenic Pressure Vessel workshop, LLNL, February 15, 2011, p. 1 Cryogenic Pressure Vessels

    E-Print Network [OSTI]

    , February 15, 2011, p. 8 In both industrial and laboratory environments, low heat transfer requires : demonstration 2007-2009: compact vessels 2010: para-ortho H2 conversion 2011: LH2 pump #12;Cryogenic Pressure, February 15, 2011, p. 4 H2 Temperature H2 Pressure H2 massHeat input Drop in apparent heat flux due to para

  15. Office of River Protection Looks Back on 2014 Achievements, Including...

    Energy Savers [EERE]

    the testing time needed to resolve concerns with high solids waste in pulse jet mixed vessels. The test plan will evaluate the use of smaller, standardized vessels that are...

  16. Forum Agenda: International Hydrogen Fuel and Pressure Vessel...

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

    Workshop Agenda: Compressed Natural Gas and Hydrogen Fuels, Lesssons Learned for the Safe Deployment of Vehicles R&D of Large Stationary HydrogenCNGHCNG Storage Vessels...

  17. Webinar: Material Characterization of Storage Vessels for Fuel Cell Forklifts

    Broader source: Energy.gov [DOE]

    Video recording of the webinar titled, Material Characterization of Storage Vessels for Fuel Cell Forklifts, originally presented on August 14, 2012.

  18. Stress analysis and evaluation of a rectangular pressure vessel...

    Office of Scientific and Technical Information (OSTI)

    States)) 42 ENGINEERING; 12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; PRESSURE VESSELS; STRESS ANALYSIS; RADIOACTIVE WASTE STORAGE;...

  19. DETERMINATION OF LIQUID FILM THICKNESS FOLLOWING DRAINING OF CONTACTORS, VESSELS, AND PIPES IN THE MCU PROCESS

    SciTech Connect (OSTI)

    Poirier, M; Fernando Fondeur, F; Samuel Fink, S

    2006-06-06

    The Department of Energy (DOE) identified the caustic side solvent extraction (CSSX) process as the preferred technology to remove cesium from radioactive waste solutions at the Savannah River Site (SRS). As a result, Washington Savannah River Company (WSRC) began designing and building a Modular CSSX Unit (MCU) in the SRS tank farm to process liquid waste for an interim period until the Salt Waste Processing Facility (SWPF) begins operations. Both the solvent and the strip effluent streams could contain high concentrations of cesium which must be removed from the contactors, process tanks, and piping prior to performing contactor maintenance. When these vessels are drained, thin films or drops will remain on the equipment walls. Following draining, the vessels will be flushed with water and drained to remove the flush water. The draining reduces the cesium concentration in the vessels by reducing the volume of cesium-containing material. The flushing, and subsequent draining, reduces the cesium in the vessels by diluting the cesium that remains in the film or drops on the vessel walls. MCU personnel requested that Savannah River National Laboratory (SRNL) researchers conduct a literature search to identify models to calculate the thickness of the liquid films remaining in the contactors, process tanks, and piping following draining of salt solution, solvent, and strip solution. The conclusions from this work are: (1) The predicted film thickness of the strip effluent is 0.010 mm on vertical walls, 0.57 mm on horizontal walls and 0.081 mm in horizontal pipes. (2) The predicted film thickness of the salt solution is 0.015 mm on vertical walls, 0.74 mm on horizontal walls, and 0.106 mm in horizontal pipes. (3) The predicted film thickness of the solvent is 0.022 mm on vertical walls, 0.91 mm on horizontal walls, and 0.13 mm in horizontal pipes. (4) The calculated film volume following draining is: (a) Salt solution receipt tank--1.6 gallons; (b) Salt solution feed tank--1.6 gallons; (c) Decontaminated salt solution hold tank--1.6 gallons; (d) Contactor drain tank--0.40 gallons; (e) Strip effluent hold tank--0.33 gallons; (f) Decontaminated salt solution decanter--0.37 gallons; (g) Strip effluent decanter--0.14 gallons; (h) Solvent hold tank--0.30 gallon; and (i) Corrugated piping between contactors--16-21 mL. (5) After the initial vessel draining, flushing the vessels with 100 gallons of water using a spray nozzle that produces complete vessel coverage and draining the flush water reduces the source term by the following amounts: (i) Salt solution receipt tank--63X; (ii) Salt solution feed tank--63X; (iii) Decontaminated salt solution hold tank--63X; (iv) Contactor drain tank--250X; (v) Strip effluent hold tank--300X; (vi) Decontaminated salt solution decanter--270X; (vii) Strip effluent decanter--710X; (viii) Solvent hold tank--330X. Understand that these estimates of film thickness are based on laboratory testing and fluid mechanics theory. The calculations assume drainage occurs by film flow. Much of the data used to develop the models came from tests with very ''clean'' fluids. Impurities in the fluids and contaminants on the vessels walls could increase liquid holdup. The application of film thickness models and source term reduction calculations should be considered along with operational conditions and H-Tank Farm/Liquid Waste operating experience. These calculations exclude the PVV/HVAC duct work and piping, as well as other areas that area outside the scope of this report.

  20. Fukushima Daiichi Unit 1 Ex-Vessel Prediction: Core Concrete Interaction

    SciTech Connect (OSTI)

    Robb, Kevin R; Farmer, Mitchell; Francis, Matthew W

    2015-01-01

    Lower head failure and corium concrete interaction were predicted to occur at Fukushima Daiichi Unit 1 (1F1) by several different system-level code analyses, including MELCOR v2.1 and MAAP5. Although these codes capture a wide range of accident phenomena, they do not contain detailed models for ex-vessel core melt behavior. However, specialized codes exist for analysis of ex-vessel melt spreading (e.g., MELTSPREAD) and long-term debris coolability (e.g., CORQUENCH). On this basis, an analysis was carried out to further evaluate ex-vessel behavior for 1F1 using MELTSPREAD and CORQUENCH. Best-estimate melt pour conditions predicted by MELCOR v2.1 and MAAP5 were used as input. MELTSPREAD was then used to predict the spatially dependent melt conditions and extent of spreading during relocation from the vessel. The results of the MELTSPREAD analysis are reported in a companion paper. This information was used as input for the long-term debris coolability analysis with CORQUENCH.

  1. Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels, E 706 (IH)

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2010-01-01

    1.1 This guide discusses test procedures that can be used in conjunction with, but not as alternatives to, those required by Practices E185 and E2215 for the surveillance of nuclear reactor vessels. The supplemental mechanical property tests outlined permit the acquisition of additional information on radiation-induced changes in fracture toughness, notch ductility, and yield strength properties of the reactor vessel steels. 1.2 This guide provides recommendations for the preparation of test specimens for irradiation, and identifies special precautions and requirements for reactor surveillance operations and postirradiation test planning. Guidance on data reduction and computational procedures is also given. Reference is made to other ASTM test methods for the physical conduct of specimen tests and for raw data acquisition.

  2. Directing all emergency activities including evacuation of personnel.

    E-Print Network [OSTI]

    Johnson, Eric E.

    for employees who perform or shut down critical plant operations. · Systems to account for all employees after· Directing all emergency activities including evacuation of personnel. · Ensuring that outside emergency services are notified when necessary. · Directing the shutdown of plant operations when necessary

  3. Application of Negligible Creep Criteria to Candidate Materials for HTGR Pressure Vessels

    SciTech Connect (OSTI)

    Jetter, Robert I [Consultant; Sham, Sam [ORNL; Swindeman, Robert W [Consultant

    2011-01-01

    Two of the proposed High Temperature Gas Reactors (HTGRs) under consideration for a demonstration plant have the design object of avoiding creep effects in the reactor pressure vessel (RPV) during normal operation. This work addresses the criteria for negligible creep in Subsection NH, Division 1 of the ASME B&PV (Boiler and Pressure Vessel) Code, Section III, other international design codes and some currently suggested criteria modifications and their impact on permissible operating temperatures for various reactor pressure vessel materials. The goal of negligible creep could have different interpretations depending upon what failure modes are considered and associated criteria for avoiding the effects of creep. It is shown that for the materials of this study, consideration of localized damage due to cycling of peak stresses results in a lower temperature for negligible creep than consideration of the temperature at which the allowable stress is governed by creep properties. In assessing the effect of localized cyclic stresses it is also shown that consideration of cyclic softening is an important effect that results in a higher estimated temperature for the onset of significant creep effects than would be the case if the material were cyclically hardening. There are other considerations for the selection of vessel material besides avoiding creep effects. Of interest for this review are (1) the material s allowable stress level and impact on wall thickness (the goal being to minimize required wall thickness) and (2) ASME Code approval (inclusion as a permitted material in the relevant Section and Subsection of interest) to expedite regulatory review and approval. The application of negligible creep criteria to two of the candidate materials, SA533 and Mod 9Cr-1Mo (also referred to as Grade 91), and to a potential alternate, normalized and tempered 2 Cr-1Mo, is illustrated and the relative advantages and disadvantages of the materials are discussed.

  4. Irradiation effects in low-alloy reactor pressure vessel steels (Heavy-Section Steel Technology Program Series 4 and 5)

    SciTech Connect (OSTI)

    Berggren, R.G.; McGowan, J.J.; Menke, B.H.; Nanstad, R.K.; Thoms, K.R.

    1984-01-01

    Multiple testing is done at two laboratories of typical nuclear pressure vessel materials (both irradiated and unirradiated) and statistical analyses of the test results. Multiple tests are conducted at each of several test temperatures for each material, standard deviations are determined, and results from the two laboratories are compared. The Fourth Heavy-Section Steel Technology (HSST) Irradiation Series, almost completed, was aimed at elastic-plastic and fully plastic fracture toughness of low-copper weldments (current practice welds). A typical nuclear pressure vessel plate steel was included for statistical purposes. The Fifth HSST Irradiation Series, now in progress, is aimed at determining the shape of the K/sub IR/ curve after significant radiation-induced shift of the transition temperatures. This series includes irradiated test specimens of thicknesses up to 100 mm and weldment compositions typical of early nuclear power reactor pressure vessel welds.

  5. Vessel Segmentation in Angiograms using Hysteresis Thresholding Alexandru-Paul Condurache

    E-Print Network [OSTI]

    Lübeck, Universität zu

    Vessel Segmentation in Angiograms using Hysteresis Thresholding Alexandru-Paul Condurache.e. vessel imaging after the injection of a radiopaque substance) is a widely used procedure for vessel- lature it is needed to measure the angiogram area covered by vessels and/or the vessel length

  6. Equilibrium and Stability of Rectangular Liquid-filled Vessels 

    E-Print Network [OSTI]

    Trahan, Russell E

    2012-07-11

    Here we focus on the stability characteristics of a rectangular liquid-filled vessel. The position vector of the center of gravity of the liquid volume is derived and used to express the equilibrium angles of the vessel. Analysis of the potential...

  7. Handling Whiting Aboard Fishing Vessels JOSEPH J. L1CCIARDELLO

    E-Print Network [OSTI]

    Handling Whiting Aboard Fishing Vessels JOSEPH J. L1CCIARDELLO Introduction The same fundamental principles for handling fresh fish in general aboard fishing vessels apply to whiting. There- fore, this article will review the factors which influence the quality of fish aboard fishing boats and will offer re

  8. 2004 Saltwater Charter Vessel Logbook State of Alaska

    E-Print Network [OSTI]

    2004 Saltwater Charter Vessel Logbook State of Alaska Department of Fish & Game Division of Sport copy. 2004 Saltwater CharterVessel Logbook Sign-Out For ADF&G Use Only State of Alaska Department for 2004 or register simultaneously when picking up a logbook). Business Mailing Address: Business Phone

  9. Thrust allocation with power management functionality on dynamically positioned vessels

    E-Print Network [OSTI]

    Johansen, Tor Arne

    Thrust allocation with power management functionality on dynamically positioned vessels Aleksander Veksler,1 Tor Arne Johansen,1 Roger Skjetne2 Abstract--A thrust allocation method with capabilities are fairly straightforward. Index Terms--Thrust Allocation, Surface Vessels, Power Man- agement I

  10. CHARACTERIZATION OF RADIOACTIVITY IN THE REACTOR VESSEL OF THE HEAVY WATER COMPONENT TEST REACTOR

    SciTech Connect (OSTI)

    Vinson, Dennis

    2010-06-01

    The Heavy Water Component Test Reactor (HWCTR) facility is a pressurized heavy water reactor that was used to test candidate fuel designs for heavy water power reactors. The reactor operated at nominal power of 50 MW{sub th}. The reactor coolant loop operated at 1200 psig and 250 C. Two isolated test loop were designed into the reactor to provide special test conditions. Fig. 1 shows a cut-away view of the reactor. The two loops are contained in four inch diameter stainless steel piping. The HWCTR was operated for only a short duration, from March 1962 to December 1964 in order to test the viability of test fuel elements and other reactor components for use in a heavy water power reactor. The reactor achieved 13,882 MWd of total power while testing 36 different fuel assemblies. In the course of operation, HWCTR experienced the cladding failures of 10 separate test fuel assemblies. In each case, the cladding was breached with some release of fuel core material into the isolated test loop, causing fission product and actinide contamination in the main coolant loop and the liquid and boiling test loops. Despite the contribution of the contamination from the failed fuel, the primary source of radioactivity in the HWCTR vessel and internals is the activation products in the thermal shields, and to a lesser degree, activation products in the reactor vessel walls and liner. A detailed facility characterization report of the HWCTR facility was completed in 1996. Many of the inputs and assumptions in the 1996 characterization report were derived from the HWCTR decommissioning plan published in 1975. The current paper provides an updated assessment of the radioisotopic characteristics of the HWCTR vessel and internals to support decommissioning activities on the facility.

  11. Vessel Monitoring System (VMS) Power Down Exemption Request Regulations implementing the requirements for the vessel monitoring system (VMS) within the NMFS Northeast

    E-Print Network [OSTI]

    Vessel Monitoring System (VMS) Power Down Exemption Request Regulations implementing the requirements for the vessel monitoring system (VMS) within the NMFS Northeast Region allow for vessels to be exempt from the requirement to transmit the vessel's location at all times if one or more

  12. Conduct of Operations

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

    2010-06-29

    This Order defines the requirements for establishing and implementing Conduct of Operations Programs at Department of Energy (DOE), including National Nuclear Security Administration (NNSA), facilities and projects. Cancels DOE O 5480.19. Admin Chg 1, 6-25-13

  13. Conduct of Operations

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

    2010-06-29

    This Order defines the requirements for establishing and implementing Conduct of Operations Programs at Department of Energy (DOE), including National Nuclear Security Administration (NNSA), facilities and projects. Admin Chg 2, dated 12-3-14, supersedes Admin Chg 1.

  14. Fundamental Study on the Effects of Irreversible Electroporation Pulses on Blood Vessels with Application to Medical Treatment

    E-Print Network [OSTI]

    Maor, Elad

    2009-01-01

    Remodeling of Blood Vessels,” Biomechanics: MechanicalDifferences in compensatory vessel enlargement, not intimalLuminal Narrowing After Deep Vessel Wall Injury : Insights

  15. The Research Vessel SurfaceThe Research Vessel Surface Meteorology Data Center ArchiveMeteorology Data Center Archive

    E-Print Network [OSTI]

    The Research Vessel SurfaceThe Research Vessel Surface Meteorology Data Center ArchiveMeteorology Data Center Archive Shawn R. Smith and Jennifer M. Lovell In collaboration with: Mark A. Bourassa University www.coaps.fsu.edu/WOCE #12;Who we areWho we are Data center specializing in the quality review

  16. INAA and distribution patterns of Classic Mimbres Black-on-white vessels during the Classic period 

    E-Print Network [OSTI]

    Dahlin, Eleanor Sherlock

    2003-01-01

    of the project were: (1) bowls were distributed throughout the Mimbres cultural system more often than jars; (2) vessel movement between sites within a region exceeded vessel movement between regions; (3) the Mimbres manufactured vessels at the village level; and...

  17. Alzheimer disease macrophages shuttle amyloid-beta from neurons to vessels, contributing to amyloid angiopathy

    E-Print Network [OSTI]

    2009-01-01

    myocytes of leptomeningeal vessels. Acta Neuropathol 87:233–amyloid in the cortical vessel wall in Alzheimer’s disease.beta from neurons to vessels, contributing to amyloid

  18. Blood vessel detection in retinal images and its application in diabetic retinopathy screening 

    E-Print Network [OSTI]

    Zhang, Ming

    2009-05-15

    In this dissertation, I investigated computing algorithms for automated retinal blood vessel detection. Changes in blood vessel structures are important indicators of many diseases such as diabetes, hypertension, etc. Blood vessel is also very...

  19. A critical contraction frequency in lymphatic vessels: transition to a state of partial summation 

    E-Print Network [OSTI]

    Meisner, Joshua Keith

    2009-06-02

    Although lymphatic vessel behavior is analogous to hearts (e.g. systole and diastole) and blood vessels (e.g. basal tone), hearts and blood vessels have fundamentally different contractile properties. While summation during contraction is minimized...

  20. Design and operation of a setup with a camera and adjustable mirror to inspect the sense-wire planes of the Time Projection Chamber inside the MicroBooNE cryostat

    E-Print Network [OSTI]

    Benjamin Carls; Glenn Horton-Smith; Catherine C. James; Robert M. Kubinski; Stephen Pordes; Anne Schukraft; Thomas Strauss

    2015-08-26

    Detectors in particle physics, particularly when including cryogenic components, are often enclosed in vessels that do not provide any physical or visual access to the detectors themselves after installation. However, it can be desirable for experiments to visually investigate the inside of the vessel. The MicroBooNE cryostat hosts a TPC with sense-wire planes, which had to be inspected for damage such as breakage or sagging. This paper describes an approach to view the inside of the MicroBooNE cryostat with a setup of a camera and a mirror through one of its cryogenic service nozzles. The paper describes the camera and mirror chosen for the operation, the illumination, and the mechanical structure of the setup. It explains how the system was operated and demonstrates its performance.

  1. #include #include

    E-Print Network [OSTI]

    Kessler, Christoph

    ] (where a[n] = +infty). C's * bsearch() can't be used, it requires a[j]==key. */ int findloc( void *key Combine­CRCW BSP­Quicksort * variant by Gerbessiotis/Valiant JPDC 22(1994) * implemented in NestStep­C. */ int N=10; // default value /** findloc(): find largest index j in [0..n­1] with * a[j

  2. Optimisation of out-vessel magnetic diagnostics for plasma boundary reconstruction in tokamaks

    E-Print Network [OSTI]

    Romero, J A

    2013-01-01

    To improve the low frequency spectrum of magnetic field measurements of future tokamak reactors such as ITER, several steady state magnetic sensor technologies have been considered. For all the studied technologies it is always advantageous to place the sensors outside the vacuum vessel and as far away from the reactor core to minimize radiation damage and temperature effects, but not so far as to compromise the accuracy of the equilibrium reconstruction. We have studied to what extent increasing the distance between out-vessel sensors and plasma can be compensated for sensor accuracy and/or density before the limit imposed by the degeneracy of the problem is reached. The study is particularized for the Swiss TCV tokamak, due to the quality of its magnetic data and its ability to operate with a wide range of plasma shapes and divertor configurations. We have scanned the plasma boundary reconstruction error as function of out-vessel sensor density, accuracy and distance to the plasma. The study is performed fo...

  3. Welding the AT-400A Containment Vessel

    SciTech Connect (OSTI)

    Brandon, E.

    1998-11-01

    Early in 1994, the Department of Energy assigned Sandia National Laboratories the responsibility for designing and providing the welding system for the girth weld for the AT-400A containment vessel. (The AT-400A container is employed for the shipment and long-term storage of the nuclear weapon pits being returned from the nation's nuclear arsenal.) Mason Hanger Corporation's Pantex Plant was chosen to be the production facility. The project was successfully completed by providing and implementing a turnkey welding system and qualified welding procedure at the Pantex Plant. The welding system was transferred to Pantex and a pilot lot of 20 AT-400A containers with W48 pits was welded in August 1997. This document is intended to bring together the AT-400A welding system and product (girth weld) requirements and the activities conducted to meet those requirements. This document alone is not a complete compilation of the welding development activities but is meant to be a summary to be used with the applicable references.

  4. Pipeline and Pressure Vessel R&D under the Hydrogen Regional...

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

    Pipeline and Pressure Vessel R&D under the Hydrogen Regional Infrastructure Program In Pennsylvania Pipeline and Pressure Vessel R&D under the Hydrogen Regional Infrastructure...

  5. Pore space analysis of beech wood: the vessel network

    E-Print Network [OSTI]

    Philipp Hass; Falk K. Wittel; S. A. McDonald; F. Marone; M. Stampanoni; Hans J. Herrmann; Peter Niemz

    2015-09-10

    Water transport in wood is vital for the survival of trees. With synchrotron radiation X-ray tomographic microscopy (SRXTM), it becomes possible to characterize and quantify the 3D network formed by vessels that are responsible for longitudinal transport. In the present paper, the spatial size dependence of vessels and the organization inside single growth rings in terms of vessel induced porosity was studied by SRXTM. Network characteristics, such as connectivity, were deduced by digital image analysis from the processed tomographic data and related to known complex network topologies.

  6. PERFORMANCE OF A CONTAINMENT VESSEL CLOSURE FOR RADIOACTIVE GAS CONTENTS

    SciTech Connect (OSTI)

    Blanton, P.; Eberl, K.

    2010-07-09

    This paper presents a summary of the design and testing of the containment vessel closure for the Bulk Tritium Shipping Package (BTSP). This package is a replacement for a package that has been used to ship tritium in a variety of content configurations and forms since the early 1970s. The containment vessel closure incorporates features specifically designed for the containment of tritium when subjected to the normal and hypothetical conditions required of Type B radioactive material shipping Packages. The paper discusses functional performance of the containment vessel closure of the BTSP prototype packages and separate testing that evaluated the performance of the metallic C-Rings used in a mock BTSP closure.

  7. Float level switch for a nuclear power plant containment vessel

    DOE Patents [OSTI]

    Powell, J.G.

    1993-11-16

    This invention is a float level switch used to sense rise or drop in water level in a containment vessel of a nuclear power plant during a loss of coolant accident. The essential components of the device are a guide tube, a reed switch inside the guide tube, a float containing a magnetic portion that activates a reed switch, and metal-sheathed, ceramic-insulated conductors connecting the reed switch to a monitoring system outside the containment vessel. Special materials and special sealing techniques prevent failure of components and allow the float level switch to be connected to a monitoring system outside the containment vessel. 1 figures.

  8. Float level switch for a nuclear power plant containment vessel

    DOE Patents [OSTI]

    Powell, James G. (Clifton Park, NY)

    1993-01-01

    This invention is a float level switch used to sense rise or drop in water level in a containment vessel of a nuclear power plant during a loss of coolant accident. The essential components of the device are a guide tube, a reed switch inside the guide tube, a float containing a magnetic portion that activates a reed switch, and metal-sheathed, ceramic-insulated conductors connecting the reed switch to a monitoring system outside the containment vessel. Special materials and special sealing techniques prevent failure of components and allow the float level switch to be connected to a monitoring system outside the containment vessel.

  9. Prestressed-concrete pressure vessels and their applicability to advanced-energy-system concepts

    SciTech Connect (OSTI)

    Naus, D.J

    1983-01-01

    Prestressed concrete pressure vessels (PCPVs) are, in essence, spaced steel structures since their strength is derived from a multitude of steel elements made up of deformed reinforcing bars and prestressing tendons which are present in sufficient quantities to carry tension loads imposed on the vessel. Other major components of a PCPV include the concrete, liner and cooling system, and insulation. PCPVs exhibit a number of advantages which make them ideally suited for application to advanced energy concepts: fabricability in virtually any size and shape using available technology, improved safety, reduced capital costs, and a history of proven performance. PCPVs have many applications to both nuclear- and non-nuclear-based energy systems concepts. Several of these concepts will be discussed as well as the research and development activities conducted at ORNL in support of PCPV development.

  10. RADIATION DOSIMETRY OF THE PRESSURE VESSEL INTERNALS OF THE HIGH FLUX BEAM REACTOR.

    SciTech Connect (OSTI)

    HOLDEN,N.E.; RECINIELLO,R.N.; HU,J.P.; RORER,D.C.

    2002-08-18

    In preparation for the eventual decommissioning of the High Flux Beam Reactor after the permanent removal of its fuel elements from the Brookhaven National Laboratory, both measurements and calculations of the decay gamma-ray dose rate have been performed for the reactor pressure vessel and vessel internal structures which included the upper and lower thermal shields, the transition plate, and the control rod blades. The measurements were made using Red Perspex{trademark} polymethyl methacrylate high-level film dosimeters, a Radcal ''peanut'' ion chamber, and Eberline's high-range ion chamber. To compare with measured gamma-ray dose rate, the Monte Carlo MCNP code and geometric progressive Microshield code were used to model the gamma transport and dose buildup.

  11. A Program for Risk Assessment Associated with IGSCC of BWR Vessel Internals

    SciTech Connect (OSTI)

    A. G. Ware; D. K. Morton; J. D. Page; M. E. Nitzel; S. A. Eide; T. -Y. Chang

    1999-08-01

    A program is being carried out for the US Nuclear Regulatory Commission (NRC) by the Idaho National Engineering and Environmental Laboratory (INEEL), to conduct an independent risk assessment of the consequences of failures initiated by intergranular stress corrosion cracking (IGSCC) of the reactor vessel internals of boiling water reactor (BWR) plants. The overall project objective is to assess the potential consequences and risks associated with the failure of IGSCC-susceptible BWR vessel internals, both singly and in combination with the failures of others, with specific consideration given to potential cascading and common mode effects on system performance. This paper presents a description of the overall program that is underway to modify an existing probabilistic risk assessment (PRA) of the BWR/4 plant to include IGSCC-initiated failures, subsequently to complete a quantitative PRA.

  12. In-vessel coolability and retention of a core melt

    SciTech Connect (OSTI)

    Theofanous, T.G.; Liu, C.; Additon, S. [Univ. of California, Santa Barbara, CA (United States)] [and others

    1997-02-01

    The efficacy of external flooding of a reactor vessel as a severe accident management strategy is assessed for an AP600-like reactor design. The overall approach is based on the Risk Oriented Accident Analysis Methodology (ROAAM), and the assessment includes consideration of bounding scenarios and sensitivity studies, as well as arbitrary parametric evaluations that allow the delineation of the failure boundaries. The technical treatment in this assessment includes: (a) new data on energy flow from either volumetrically heated pools or non-heated layers on top, boiling and critical heat flux in inverted, curved geometries, emissivity of molten (superheated) samples of steel, and chemical reactivity proof tests, (b) a simple but accurate mathematical formulation that allows prediction of thermal loads by means of convenient hand calculations, (c) a detailed model programmed on the computer to sample input parameters over the uncertainty ranges, and to produce probability distributions of thermal loads and margins for departure from nucleate boiling at each angular position on the lower head, and (d) detailed structural evaluations that demonstrate that departure from nucleate boiling is a necessary and sufficient criterion for failure. Quantification of the input parameters is carried out for an AP600-like design, and the results of the assessment demonstrate that lower head failure is {open_quotes}physically unreasonable.{close_quotes} Use of this conclusion for any specific application is subject to verifying the required reliability of the depressurization and cavity-flooding systems, and to showing the appropriateness (in relation to the database presented here, or by further testing as necessary) of the thermal insulation design and of the external surface properties of the lower head, including any applicable coatings.

  13. Development of an Enhanced Core Catcher for Improving In-Vessel Retention Margins

    SciTech Connect (OSTI)

    Rempe, J.L. [Idaho National Engineering and Environmental Laboratory (United States); Condie, K.G. [Idaho National Engineering and Environmental Laboratory (United States); Knudson, D.L. [Idaho National Engineering and Environmental Laboratory (United States); Suh, K.Y. [Seoul National University (Korea, Republic of); Cheung, F.B. [The Pennsylvania State University (United States); Kim, S.B. [Korea Atomic Energy Research Institute (Korea, Republic of)

    2005-11-15

    In-vessel retention (IVR) of core melt that may relocate to the lower head of a reactor vessel is a key severe accident management strategy adopted by some operating nuclear power plants and proposed for several advanced light water reactors. A U.S.-Korean International Nuclear Energy Research Initiative project has been initiated to explore design enhancements that could increase the margin for IVR for advanced reactors with higher power levels [up to 1500 MW(electric)]. As part of this effort, an enhanced in-vessel core catcher is being designed and evaluated. To reduce cost and simplify manufacture and installation, this new core catcher design consists of several interlocking sections that are machined to fit together when inserted into the lower head. If needed, the core catcher can be manufactured with holes to accommodate lower head penetrations. Each section of the core catcher consists of two material layers with an option to add a third layer (if deemed necessary). The first is a base material that has the capability to support and contain the mass of core materials that may relocate during a severe accident; the second is an oxide coating on top of the base material, which resists interactions with high-temperature core materials; and the third is an optional coating on the bottom side of the base material to protect it from oxidation during the lifetime of the reactor. This paper summarizes results from the in-vessel core catcher design and evaluation efforts, focusing on recently obtained results from materials interaction tests and prototypic testing activities.

  14. Fractals and fractal dimension of systems of blood vessels: An analogy between artery trees, river networks, and urban hierarchies

    E-Print Network [OSTI]

    Chen, Yanguang

    2015-01-01

    An analogy between the fractal nature of networks of arteries and that of systems of rivers has been drawn in the previous works. However, the deep structure of the hierarchy of blood vessels has not yet been revealed. This paper is devoted to researching the fractals, allometric scaling, and hierarchy of blood vessels. By analogy with Horton-Strahler's laws of river composition, three exponential laws have been put forward. These exponential laws can be reconstructed and transformed into three linear scaling laws, which can be named composition laws of blood vessels network. From these linear scaling laws it follows a set of power laws, including the three-parameter Zipf's law on the rank-size distribution of blood vessel length and the allometric scaling law on the length-diameter relationship of blood vessels in different orders. The models are applied to the observed data on human beings and animals early given by other researchers, and an interesting finding is that human bodies more conform to natural r...

  15. Advances in crack-arrest technology for reactor pressure vessels

    SciTech Connect (OSTI)

    Bass, B.R.; Pugh, C.E.

    1988-01-01

    The Heavy-Section Steel Technology (HSST) Program at the Oak Ridge National Laboratory (ORNL) under the sponsorship of the US Nuclear Regulatory Commission is continuing to improve the understanding of conditions that govern the initiation, rapid propagation, arrest, and ductile tearing of cracks in reactor pressure vessel (RPV) steels. This paper describes recent advances in a coordinated effort being conducted under the HSST Program by ORNL and several subcontracting groups to develop the crack-arrest data base and the analytical tools required to construct inelastic dynamic fracture models for RPV steels. Large-scale tests are being carried out to generate crack-arrest toughness data at temperatures approaching and above the onset of Charpy upper-shelf behavior. Small- and intermediate-size specimens subjected to static and dynamic loading are being developed and tested to provide additional fracture data for RPV steels. Viscoplastic effects are being included in dynamic fracture models and computer programs and their utility validated through analyses of data from carefully controlled experiments. Recent studies are described that examine convergence problems associated with energy-based fracture parameters in viscoplastic-dynamic fracture applications. Alternative techniques that have potential for achieving convergent solutions for fracture parameters in the context of viscoplastic-dynamic models are discussed. 46 refs., 15 figs., 3 tabs.

  16. OPERATIONAL RISK RODNEY COLEMAN

    E-Print Network [OSTI]

    Coleman, Rodney

    the business environment. These include terrorism, civil unrest, systems fail- ings including hacking RISKS ARISING FROM BUSINESS ACTIVITY You lose business opportunities while your computer systems a business beyond those from its money-making activities. This is operational risk, often shortened to oprisk

  17. Cover Heated, Open Vessels - Steam Tip Sheet #19

    SciTech Connect (OSTI)

    2012-01-01

    This revised AMO steam tip sheet on covering heated, open vessels provides how-to advice for improving industrial steam systems using low-cost, proven practices and technologies.

  18. Modeling the Behavior of a Vessel under Runaway Conditions 

    E-Print Network [OSTI]

    Kanes, Rym

    2015-08-11

    -heating occurs, thereby leading to a runaway reaction. The overpressurization of the vessel following the runaway may lead to an industrial accident, a thermal explosion, resulting in damages to people, property and the environment. Emergency relief systems (ERS...

  19. 2005 ASME Pressure Vessels and Piping Conference Denver, Colorado, USA

    E-Print Network [OSTI]

    Özer, Mutlu

    1 DRAFT 2005 ASME Pressure Vessels and Piping Conference Denver, Colorado, USA July 17-21, 2005 subjected to lateral earthquake loads. The results are verified with different codes (e.g. Eurocode8, API

  20. Design and development activities for in-vessel and in-port components of ITER microwave diagnostics

    E-Print Network [OSTI]

    Sirinelli, Antoine; Feder, Russel; Giacomin, Thibaud; Hanson, Gregory; Johnson, David; Lukyanov, Vitaliy; Maquet, Philippe; Martin, Alex; Oosterbeek, Johan W; Penot, Christophe; Portalès, Mickaël; Roman, Catalin; Sanchez, Paco; Shelukhin, Dmitry; Udintsev, Victor S; Vayakis, George; Vershkov, Vladimir; Walsh, Michael J; Zolfaghari, Ali; Zvonkov, Alexander

    2015-01-01

    The ITER tokamak will be operating with 5 microwave diagnostic systems. While they rely on different physics, they share a common need: transmitting low and high power microwave in the range of 12 GHz to 1000 GHz(different bandwidths for different diagnostics) between the plasma and a diagnostic area tens of meters away. The designs proposed for vacuum windows, in-vessel waveguides and antennas are presented together with the development activities needed to finalise this work.

  1. operations center

    National Nuclear Security Administration (NNSA)

    servers and other critical Operations Center equipment

  2. Independent air supply system filtered to protect against biological and radiological agents (99.7%).
  3. <...

  4. High Temperature Electrolysis Pressurized Experiment Design, Operation, and Results

    SciTech Connect (OSTI)

    J.E. O'Brien; X. Zhang; G.K. Housley; K. DeWall; L. Moore-McAteer

    2012-09-01

    A new facility has been developed at the Idaho National Laboratory for pressurized testing of solid oxide electrolysis stacks. Pressurized operation is envisioned for large-scale hydrogen production plants, yielding higher overall efficiencies when the hydrogen product is to be delivered at elevated pressure for tank storage or pipelines. Pressurized operation also supports higher mass flow rates of the process gases with smaller components. The test stand can accommodate planar cells with dimensions up to 8.5 cm x 8.5 cm and stacks of up to 25 cells. It is also suitable for testing other cell and stack geometries including tubular cells. The pressure boundary for these tests is a water-cooled spool-piece pressure vessel designed for operation up to 5 MPa. Pressurized operation of a ten-cell internally manifolded solid oxide electrolysis stack has been successfully demonstrated up 1.5 MPa. The stack is internally manifolded and operates in cross-flow with an inverted-U flow pattern. Feed-throughs for gas inlets/outlets, power, and instrumentation are all located in the bottom flange. The entire spool piece, with the exception of the bottom flange, can be lifted to allow access to the internal furnace and test fixture. Lifting is accomplished with a motorized threaded drive mechanism attached to a rigid structural frame. Stack mechanical compression is accomplished using springs that are located inside of the pressure boundary, but outside of the hot zone. Initial stack heatup and performance characterization occurs at ambient pressure followed by lowering and sealing of the pressure vessel and subsequent pressurization. Pressure equalization between the anode and cathode sides of the cells and the stack surroundings is ensured by combining all of the process gases downstream of the stack. Steady pressure is maintained by means of a backpressure regulator and a digital pressure controller. A full description of the pressurized test apparatus is provided in this report. Results of initial testing showed the expected increase in open-cell voltage associated with elevated pressure. However, stack performance in terms of area-specific resistance was enhanced at elevated pressure due to better gas diffusion through the porous electrodes of the cells. Some issues such as cracked cells and seals were encountered during testing. Full resolution of these issues will require additional testing to identify the optimum test configurations and protocols.

  5. Identification and assessment of BWR in-vessel severe accident mitigation strategies

    SciTech Connect (OSTI)

    Hodge, S.A.; Cleveland, J.C.; Kress, T.S.; Petek, M. [Oak Ridge National Lab., TN (United States)

    1992-10-01

    This report provides the results of work carried out in support of the US Nuclear Regulatory Commission Accident Management Research Program to develop a technical basis for evaluating the effectiveness and feasibility of current and proposed strategies for boiling water reactor (BWR) severe accident management. First, the findings of an assessment of the current status of accident management strategies for the mitigation of in-vessel events for BWR severe accident sequences are described. This includes a review of the BWR Owners` Group Emergency Procedure Guidelines (EPGSs) to determine the extent to which they currently address the characteristic events of an unmitigated severe accident and to provide the basis for recommendations for enhancement of accident management procedures. Second, where considered necessary, new candidate accident management strategies are proposed for mitigation of the late-phase (after core damage has occurred) events. Finally, recommendations are made for consideration of additional strategies where warranted, and two of the four candidate strategies identified by this effort are assessed in detail: (1) preparation of a boron solution for reactor vessel refill should control blade damage occur during a period of temporary core dryout and (2) containment flooding to maintain the core debris within the reactor vessel if the injection systems cannot be restored.

  6. Identification and assessment of BWR in-vessel severe accident mitigation strategies

    SciTech Connect (OSTI)

    Hodge, S.A.; Cleveland, J.C.; Kress, T.S.; Petek, M. (Oak Ridge National Lab., TN (United States))

    1992-10-01

    This report provides the results of work carried out in support of the US Nuclear Regulatory Commission Accident Management Research Program to develop a technical basis for evaluating the effectiveness and feasibility of current and proposed strategies for boiling water reactor (BWR) severe accident management. First, the findings of an assessment of the current status of accident management strategies for the mitigation of in-vessel events for BWR severe accident sequences are described. This includes a review of the BWR Owners' Group Emergency Procedure Guidelines (EPGSs) to determine the extent to which they currently address the characteristic events of an unmitigated severe accident and to provide the basis for recommendations for enhancement of accident management procedures. Second, where considered necessary, new candidate accident management strategies are proposed for mitigation of the late-phase (after core damage has occurred) events. Finally, recommendations are made for consideration of additional strategies where warranted, and two of the four candidate strategies identified by this effort are assessed in detail: (1) preparation of a boron solution for reactor vessel refill should control blade damage occur during a period of temporary core dryout and (2) containment flooding to maintain the core debris within the reactor vessel if the injection systems cannot be restored.

  7. Refractory lining system for high wear area of high temperature reaction vessel

    DOE Patents [OSTI]

    Hubble, David H. (Export, PA); Ulrich, Klaus H. (Duisburg, DE)

    1998-01-01

    A refractory-lined high temperature reaction vessel comprises a refractory ring lining constructed of refractory brick, a cooler, and a heat transfer medium disposed between the refractory ring lining and the cooler. The refractory brick comprises magnesia (MgO) and graphite. The heat transfer medium contacts the refractory brick and a cooling surface of the cooler, and is composed of a material that accommodates relative movement between the refractory brick and the cooler. The brick is manufactured such that the graphite has an orientation providing a high thermal conductivity in the lengthwise direction through the brick that is higher than the thermal conductivity in directions perpendicular to the lengthwise direction. The graphite preferably is flake graphite, in the range of about 10 to 20 wt %, and has a size distribution selected to provide maximum brick density. The reaction vessel may be used for performing a reaction process including the steps of forming a layer of slag on a melt in the vessel, the slag having a softening point temperature range, and forming a protective frozen layer of slag on the interior-facing surface of the refractory lining in at least a portion of a zone where the surface contacts the layer of slag, the protective frozen layer being maintained at or about the softening point of the slag.

  8. Theoretical Analysis of a Spectrophotometric Technique for Measuring Oxygen Saturation in Retinal Vessels

    E-Print Network [OSTI]

    van Vliet, Lucas J.

    Vessels M. Üzümcü1 , F.M. Vos1 , A.M. Vossepoel1 , G.L. van der Heijde2 1. Pattern Recognition Group], the formation of pathological new vessels [2]. Such new vessels block sensitive areas of the retina and can a fluorescent dye is injected in the patient, which spreads all over the body through the blood vessels. Upon

  9. Identification of Vessels from Engine Sounds by Spectral Comparison and Verification

    E-Print Network [OSTI]

    Sidorov, Nikita

    Identification of Vessels from Engine Sounds by Spectral Comparison and Verification J. Yuan First, The University of Manchester #12;1 Identification of Vessels from Engine Sounds by Spectral Comparison consider the problem of identifying a vessel from its engine sound. A database of known vessels is used

  10. Retinal Blood Vessels Segmentation Using the Radial Projection and Supervised Classification

    E-Print Network [OSTI]

    Cheung, Yiu-ming

    Retinal Blood Vessels Segmentation Using the Radial Projection and Supervised Classification Qinmu: ymc@comp.hkbu.edu.hk Abstract The low-contrast and narrow blood vessels in retinal images of improving detection of such vessels, we propose the ra- dial projection method to locate the vessel

  11. Vessel Segmentation and Analysis in Laboratory Skin Transplant Micro-angiograms

    E-Print Network [OSTI]

    Lübeck, Universität zu

    Vessel Segmentation and Analysis in Laboratory Skin Transplant Micro-angiograms Alexandru transplantations depends on the adequate revascularization of the trans- planted dermal matrix. To induce vessel and length of newly grown vessels have to be measured in micro-angiograms (x-ray images of the blood vessels

  12. Vessel Activity Report Page 1 of 2 Revised: August 25, 2011

    E-Print Network [OSTI]

    Vessel Activity Report Page 1 of 2 Revised: August 25, 2011 Instructions U.S. VESSEL ACTIVITY vessel greater than 60 ft (18.3 m) length overall (LOA), a catcher/processor, or a mothership required-586-7313 or electronic file to enf.dataclerk@noaa.gov before the vessel crosses the seaward boundary of the Exclusive

  13. Targeted insult to subsurface cortical blood vessels using ultrashort laser pulses: three models of stroke

    E-Print Network [OSTI]

    Cai, Long

    Targeted insult to subsurface cortical blood vessels using ultrashort laser pulses: three models a vessel for injury and to measure blood-flow dynamics. We irradiated the vessel with high-fluence, ultrashort laser pulses and achieved three forms of vascular insult. (i) Vessel rupture was induced

  14. Standard practice for evaluation of surveillance capsules from light-water moderated nuclear power reactor vessels

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2010-01-01

    Standard practice for evaluation of surveillance capsules from light-water moderated nuclear power reactor vessels

  15. Operating Reserves and Variable Generation

    SciTech Connect (OSTI)

    Ela, E.; Milligan, M.; Kirby, B.

    2011-08-01

    This report tries to first generalize the requirements of the power system as it relates to the needs of operating reserves. It also includes a survey of operating reserves and how they are managed internationally in system operations today and then how new studies and research are proposing they may be managed in the future with higher penetrations of variable generation.

  16. Engineering functional blood vessels in vivo

    E-Print Network [OSTI]

    Au, Pakwai

    2008-01-01

    At the present time, there are many hurdles to overcome in order to create a long-lasting and engineered tissue for tissue transplant in patients. The challenges include the isolation and expansion of appropriate cells, ...

  17. Coiled tubing; Operations and services

    SciTech Connect (OSTI)

    Welch, J.L.; Stephens, R.K. )

    1992-09-01

    This paper reports on coiled tubing units which are used for many types of remedial well operations, including sand plugbacks, cement squeezes, fill cleanouts, underreaming, acid stimulations, and fishing. Fishing operations include removal of inflatable bridge plugs, lock mandrels stuck in profile nipples, coiled tubing, coiled tubing bottomhole assemblies (BHAs) and wireline. Recommended guidelines for selecting candidates, proper tool string configuration and operational techniques are presented here to assist coiled tubing supervisors and company representatives in the planning and implementation of efficient and effective fishing operations. Treatment of these areas are not intended to be exhaustive, but rather generally representative of common applications. Each fishing operation requires individualized analysis and planning.

  18. Pressurized reactor system and a method of operating the same

    DOE Patents [OSTI]

    Isaksson, J.M.

    1996-06-18

    A method and apparatus are provided for operating a pressurized reactor system in order to precisely control the temperature within a pressure vessel in order to minimize condensation of corrosive materials from gases on the surfaces of the pressure vessel or contained circulating fluidized bed reactor, and to prevent the temperature of the components from reaching a detrimentally high level, while at the same time allowing quick heating of the pressure vessel interior volume during start-up. Super-atmospheric pressure gas is introduced from the first conduit into the fluidized bed reactor and heat derived reactions such as combustion and gasification are maintained in the reactor. Gas is exhausted from the reactor and pressure vessel through a second conduit. Gas is circulated from one part of the inside volume to another to control the temperature of the inside volume, such as by passing the gas through an exterior conduit which has a heat exchanger, control valve, blower and compressor associated therewith, or by causing natural convection flow of circulating gas within one or more generally vertically extending gas passages entirely within the pressure vessel (and containing heat exchangers, flow rate control valves, or the like therein). Preferably, inert gas is provided as a circulating gas, and the inert gas may also be used in emergency shut-down situations. In emergency shut-down reaction gas being supplied to the reactor is cut off, while inert gas from the interior gas volume of the pressure vessel is introduced into the reactor. 2 figs.

  19. Pressurized reactor system and a method of operating the same

    DOE Patents [OSTI]

    Isaksson, Juhani M. (Karhula, FI)

    1996-01-01

    A method and apparatus are provided for operating a pressurized reactor system in order to precisely control the temperature within a pressure vessel in order to minimize condensation of corrosive materials from gases on the surfaces of the pressure vessel or contained circulating fluidized bed reactor, and to prevent the temperature of the components from reaching a detrimentally high level, while at the same time allowing quick heating of the pressure vessel interior volume during start-up. Superatmospheric pressure gas is introduced from the first conduit into the fluidized bed reactor and heat derived reactions such as combustion and gassification are maintained in the reactor. Gas is exhausted from the reactor and pressure vessel through a second conduit. Gas is circulated from one part of the inside volume to another to control the temperature of the inside volume, such as by passing the gas through an exterior conduit which has a heat exchanger, control valve, blower and compressor associated therewith, or by causing natural convection flow of circulating gas within one or more generally vertically extending gas passages entirely within the pressure vessel (and containing heat exchangers, flow rate control valves, or the like therein). Preferably, inert gas is provided as a circulating gas, and the inert gas may also be used in emergency shut-down situations. In emergency shut-down reaction gas being supplied to the reactor is cut off, while inert gas from the interior gas volume of the pressure vessel is introduced into the reactor.

  20. Operating Costs

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

    1997-03-28

    This chapter is focused on capital costs for conventional construction and environmental restoration and waste management projects and examines operating cost estimates to verify that all elements of the project have been considered and properly estimated.

  21. Program desk manual for occupational safety and health -- U.S. Department of Energy Richland Operations, Office of Environment Safety and Health

    SciTech Connect (OSTI)

    Musen, L.G.

    1998-08-27

    The format of this manual is designed to make this valuable information easily accessible to the user as well as enjoyable to read. Each chapter contains common information such as Purpose, Scope, Policy and References, as well as information unique to the topic at hand. This manual can also be provided on a CD or Hanford Internet. Major topics include: Organization and program for operational safety; Occupational medicine; Construction and demolition; Material handling and storage; Hoisting and rigging; Explosives; Chemical hazards; Gas cylinders; Electrical; Boiler and pressure vessels; Industrial fire protection; Industrial hygiene; and Safety inspection checklist.

  22. Abstract--In our novel technique of tumor vessels treatment, High Z (HZ) contrast atoms are injected into the blood vessel

    E-Print Network [OSTI]

    Nahar, Sultana Nurun

    Abstract--In our novel technique of tumor vessels treatment, High Z (HZ) contrast atoms are injected into the blood vessel and the tumor region is irradiated with "narrowband" fluorescence photon (FP/ml and 9.05 nmol/ml, respectively. I. BACKGROUND AND INTRODUCTION ESTRUCTION of tumor vessels

  1. Prices include compostable serviceware and linen tablecloths

    E-Print Network [OSTI]

    California at Davis, University of

    APPETIZERS Prices include compostable serviceware and linen tablecloths for the food tables.ucdavis.edu. BUTTERNUT SQUASH & BLACK BEAN ENCHILADAS #12;BUFFETS Prices include compostable serviceware and linen

  2. Margin for In-Vessel Retention in the APR1400 - VESTA and SCDAP/RELAP5-3D Analyses

    SciTech Connect (OSTI)

    Joy Rempe; D. Knudson

    2004-12-01

    If cooling is inadequate during a reactor accident, a significant amount of core material could become molten and relocate to the lower head of the reactor vessel, as happened in the Three Mile Island Unit 2 (TMI-2) accident. If it is possible to ensure that the lower head remains intact so that relocated core materials are retained within the vessel, the enhanced safety associated with such plants can reduce concerns about containment failure and associated risk. For example, the enhanced safety of the Westinghouse Advanced 600 MWe pressurized water reactor (PWR) (AP600), which relied upon external reactor vessel cooling (ERVC) for in-vessel retention (IVR), resulted in the U.S. Nuclear Regulatory Commission (USNRC) approving the design without requiring certain conventional features common to existing light water reactors (LWRs). IVR of core melt is therefore a key severe accident management strategy adopted by some operating nuclear power plants and proposed for some advanced LWRs. However, it is not clear that currently proposed ERVC without additional enhancements could provide sufficient heat removal for higher-power reactors (up to 1500 MWe). Hence, a three-year, United States (U.S.) -Korean International Nuclear Energy Research Initiative (INERI) project was initiated in which the Idaho National Engineering and Environmental Laboratory (INEEL), Seoul National University (SNU), Pennsylvania State University (PSU), and the Korean Atomic Energy Research Institute (KAERI) explored options, such as enhanced ERVC performance and an enhanced in-vessel core catcher (IVCC), that have the potential to ensure that IVR is feasible for higher power reactors.

  3. Sterilization of fermentation vessels by ethanol/water mixtures

    DOE Patents [OSTI]

    Wyman, C.E.

    1999-02-09

    A method is described for sterilizing process fermentation vessels with a concentrated alcohol and water mixture integrated in a fuel alcohol or other alcohol production facility. Hot, concentrated alcohol is drawn from a distillation or other purification stage and sprayed into the empty fermentation vessels. This sterilizing alcohol/water mixture should be of a sufficient concentration, preferably higher than 12% alcohol by volume, to be toxic to undesirable microorganisms. Following sterilization, this sterilizing alcohol/water mixture can be recovered back into the same distillation or other purification stage from which it was withdrawn. The process of this invention has its best application in, but is not limited to, batch fermentation processes, wherein the fermentation vessels must be emptied, cleaned, and sterilized following completion of each batch fermentation process. 2 figs.

  4. Sterilization of fermentation vessels by ethanol/water mixtures

    DOE Patents [OSTI]

    Wyman, Charles E. (Lakewood, CO)

    1999-02-09

    A method for sterilizing process fermentation vessels with a concentrated alcohol and water mixture integrated in a fuel alcohol or other alcohol production facility. Hot, concentrated alcohol is drawn from a distillation or other purification stage and sprayed into the empty fermentation vessels. This sterilizing alcohol/water mixture should be of a sufficient concentration, preferably higher than 12% alcohol by volume, to be toxic to undesirable microorganisms. Following sterilization, this sterilizing alcohol/water mixture can be recovered back into the same distillation or other purification stage from which it was withdrawn. The process of this invention has its best application in, but is not limited to, batch fermentation processes, wherein the fermentation vessels must be emptied, cleaned, and sterilized following completion of each batch fermentation process.

  5. Lightweight cryogenic-compatible pressure vessels for vehicular fuel storage

    DOE Patents [OSTI]

    Aceves, Salvador; Berry, Gene; Weisberg, Andrew H.

    2004-03-23

    A lightweight, cryogenic-compatible pressure vessel for flexibly storing cryogenic liquid fuels or compressed gas fuels at cryogenic or ambient temperatures. The pressure vessel has an inner pressure container enclosing a fuel storage volume, an outer container surrounding the inner pressure container to form an evacuated space therebetween, and a thermal insulator surrounding the inner pressure container in the evacuated space to inhibit heat transfer. Additionally, vacuum loss from fuel permeation is substantially inhibited in the evacuated space by, for example, lining the container liner with a layer of fuel-impermeable material, capturing the permeated fuel in the evacuated space, or purging the permeated fuel from the evacuated space.

  6. Device for automating in vitro characterization of lymphatic vessel function 

    E-Print Network [OSTI]

    Rajagopalan, Shruti

    2005-02-17

    the experimental set-up. Poutin Q VDA Poutin Q VDA Figure 10: The experimental set-up to characterize isolated bovine mesenteric lymphangions. This set-up was used to measure the diameter of the vessel using the Video Dimension Analyzer (VDA... the steady state error and then fine-tuning it. The output of the PI controller is a flow signal (Qs). The pump, connected via an RS232 port, matches this flow, Q, which affects the pressure, P, in the lymphatic vessel, via outflow resistance of the clamp...

  7. Ex-vessel demand by size for the Gulf shrimp 

    E-Print Network [OSTI]

    Chui, Margaret Kam-Too

    1980-01-01

    EX-VESSEL DEMAND BY SIZE FOR THE GULF SHRIMP A Thesis by MARGARET RAM-TOO CHUI Submitted to the Graduate College of Texas A&M University in partial fulfillment of the requirement for the degree of MASTER OF SCIENCE August 1980 Major... Subject: Agricultural Economics EX-VESSEL DEMAND BY SIZE FOR SHRIMP IN THE GULF OF MEXICO A Thesis by MARGARET KAM-TOO CHUI Approved as to style and content by: ai an of Committee) (Hea f ep tment) (Member) (Member) August 1980 ABSTRACT Ex...

  8. In-Vessel Retention Technology Development and Use for Advanced PWR Designs in the USA and Korea

    SciTech Connect (OSTI)

    T.G. Theofanous; S.J. Oh; J.H. Scobel

    2004-05-18

    In-Vessel Retention (IVR) of molten core debris by means of external reactor vessel flooding is a cornerstone of severe accident management for Westinghouse's AP600 (advanced passive light water reactor) design. The case for its effectiveness (made in previous work by the PI) has been thoroughly documented, reviewed as part of the licensing certification, and accepted by the US Nuclear Regulatory Commission. A successful IVR would terminate a severe accident, passively, with the core in a stable, coolable configuration (within the lower head), thus avoiding the largely uncertain accident evolution with the molten debris on the containment floor. This passive plant design has been upgraded by Westinghouse to the AP1000, a 1000 MWe plant very similar to the AP600. The severe accident management approach is very similar too, including In-Vessel Retention as the cornerstone feature, and initial evaluations indicated that this would be feasible at the higher power as well. A similar strategy is adopted in Korea for the APR1400 plant. The overall goal of this project is to provide experimental data and develop the necessary basic understanding so as to allow the robust extension of the AP600 In-Vessel Retention strategy for severe accident management to higher power reactors, and in particular, to the AP1000 advanced passive design.

  9. Operating Strategies

    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: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration wouldMass mapSpeeding access toOctober 1996Technologies /JuneOperating Oak Ridge'sOPERATING

  10. Conduct of Operations

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

    2010-06-29

    This Order defines the requirements for establishing and implementing Conduct of Operations Programs at Department of Energy (DOE), including National Nuclear Security Administration (NNSA), facilities and projects. Cancels DOE O 5480.19. Admin Chg 1, dated 6-25-13, cancels DOE O 422.1. Certified 12-3-14.

  11. Assemblies and methods for mitigating effects of reactor pressure vessel expansion

    DOE Patents [OSTI]

    Challberg, R.C.; Gou, P.F.; Chu, C.L.; Oliver, R.P.

    1999-07-27

    Support assemblies for allowing RPV radial expansion while simultaneously limiting horizontal, vertical, and azimuthal movement of the RPV within a nuclear reactor are described. In one embodiment, the support assembly includes a support block and a guide block. The support block includes a first portion and a second portion, and the first portion is rigidly coupled to the RPV adjacent the first portion. The guide block is rigidly coupled to a reactor pressure vessel support structure and includes a channel sized to receive the second portion of the support block. The second portion of the support block is positioned in the guide block channel to movably couple the guide block to the support block. 6 figs.

  12. Assemblies and methods for mitigating effects of reactor pressure vessel expansion

    DOE Patents [OSTI]

    Challberg, Roy C. (Livermore, CA); Gou, Perng-Fei (Saratoga, CA); Chu, Cherk Lam (San Jose, CA); Oliver, Robert P. (Topsham, ME)

    1999-01-01

    Support assemblies for allowing RPV radial expansion while simultaneously limiting horizontal, vertical, and azimuthal movement of the RPV within a nuclear reactor are described. In one embodiment, the support assembly includes a support block and a guide block. The support block includes a first portion and a second portion, and the first portion is rigidly coupled to the RPV adjacent the first portion. The guide block is rigidly coupled to a reactor pressure vessel support structure and includes a channel sized to receive the second portion of the support block. The second portion of the support block is positioned in the guide block channel to movably couple the guide block to the support block.

  13. Ion transport membrane module and vessel system with directed internal gas flow

    DOE Patents [OSTI]

    Holmes, Michael Jerome (Thompson, ND); Ohrn, Theodore R. (Alliance, OH); Chen, Christopher Ming-Poh (Allentown, PA)

    2010-02-09

    An ion transport membrane system comprising (a) a pressure vessel having an interior, an inlet adapted to introduce gas into the interior of the vessel, an outlet adapted to withdraw gas from the interior of the vessel, and an axis; (b) a plurality of planar ion transport membrane modules disposed in the interior of the pressure vessel and arranged in series, each membrane module comprising mixed metal oxide ceramic material and having an interior region and an exterior region; and (c) one or more gas flow control partitions disposed in the interior of the pressure vessel and adapted to change a direction of gas flow within the vessel.

  14. Experimental Study on the Improved In-Vessel Corium Retention Concepts for the Severe Accident Management

    SciTech Connect (OSTI)

    Kang, K.H.; Park, R.J.; Koo, K.M.; Kim, S.B.; Kim, H.D. [Korea Atomic Energy Research Institute, 150, Dukjin-Dong, Yusong-Gu, Taejon 305-353 (Korea, Republic of)

    2002-07-01

    Feasibility experiments were performed for the assessment of improved In-Vessel Corium Retention (IVR) concepts using an internal engineered gap device and also a dual strategy of In/Ex-vessel cooling using the LAVA experimental facility. The internal engineered gap device made of carbon steel was installed inside the LAVA lower head vessel and it made a uniform gap with the vessel by 10 mm. In/Ex-vessel cooling in the dual strategy experiment was performed installing an external guide vessel outside the LAVA lower head vessel at a uniform gap of 25 mm. The LAVA lower head vessel was a hemispherical test vessel simulated with a 1/8 linear scale mock-up of the reactor vessel lower plenum with an inner diameter of 500 mm and thickness of 25 mm. In both of the tests, Al{sub 2}O{sub 3} melt was delivered into about 50 K subcooled water inside the lower head vessel under the elevated pressure. Temperatures of the internal engineered gap device and the lower head vessel were measured by K-type thermocouples embedded radially in the 3 mm depth of the lower head vessel outer surface and in the 4 mm depth of the internal engineered gap device, respectively. In the dual strategy experiment, the Ex-vessel cooling featured pool boiling in the gap between the lower head vessel and the external guide vessel. It could be found from the experimental results that the internal engineered gap device was intact and so the vessel experienced little thermal and mechanical attacks in the internal engineered gap device experiment. And also the vessel was effectively cooled via mutual boiling heat removal in- and ex-vessel in the dual strategy experiment. Compared with the previous LAVA experimental results performed for the investigation of the inherent in-vessel gap cooling, it could be confirmed that the Ex-vessel cooling measure was dominant over the In-vessel cooling measure in this study. It is concluded that the improved cooling measures using a internal engineered gap device and a dual strategy promote the cooling characteristics of the lower head vessel and so enhance the integrity of the vessel in the end. (authors)

  15. Generic BWR-4 degraded core in-vessel study. Status report

    SciTech Connect (OSTI)

    Not Available

    1984-11-01

    Original intent of this project was to produce a phenomenological study of the in-vessel degradation which occurs during the TQUX and TQUV sequences for a generic BWR-4 from the initiation of the FSAR Chapter 15 operational transient through core debris bed formation to the failure of the primary pressure boundary. Bounding calculations were to be performed for the two high pressure and low pressure non-LOCA scenarios to assess the uncertainties in the current state of knowledge regarding the source terms for containment integrity studies. Source terms as such were defined in terms of hydrogen generation, unreacted metal, and coolant inventroy, and in terms of the form, sequencing and mode of dispersal through the primary vessel boundary. Fission product release was not to be considered as part of this study. Premature termination of the project, however, led to the dicontinuation of work on an as is basis. Work on the in-core phase from the point of scram to core debris bed formation was largely completed. A preliminary scoping calculation on the debris bed phase had been initiated. This report documents the status of the study at termination.

  16. Assessment of blood vessel mimics with optical coherence tomography

    E-Print Network [OSTI]

    Barton, Jennifer K.

    of a tissue-engineered blood vessel mimic BVM and the response of this lining to a bare metal stent. We. We determine that 1 the OCT endoscope can be repeatedly inserted without visible damage to the BVM for monitoring the BVM cellular lining, and that OCT may facilitate the use of BVMs for early stage device

  17. Revised: 05/12/2015 CATCHER VESSEL DFL

    E-Print Network [OSTI]

    Revised: 05/12/2015 CATCHER VESSEL DFL LONGLINE AND POT GEAR MANAGEMENT PROGRAM (Check GEAR TYPE (check one) Pot Jig Troll Handline Hook & Line Other If Hook & Line, complete boxes immediately below. Complete these boxes once per delivery GEAR ID LENGTH OF SKATE (feet) GEAR TYPE FIXED HOOK

  18. Macrosegregation and Microstructural Evolution in a Pressure-Vessel Steel

    E-Print Network [OSTI]

    Cambridge, University of

    for how the segregation might be minimised, and its detrimental effects suppressed by heat treatments. 1's knowledge) investigations have not been made into how macrosegregation in pressure-vessel steels can affect be prevented, and how its effects might be suppressed. 2. Experimental SA508 Grade 3 material was obtained from

  19. MFR PAPER 1254 Humpback Whales in Hawaii: Vessel Census, 1976

    E-Print Network [OSTI]

    seen during a subsequent monk seal survey off the Leeward Islands. INTRODUCTION Humpback whales Hawaiian Islands during a vessel survey from 24 February to 6 March 7976. Indications, Megaptera novaeangliae, wintering in Hawaiian waters, were surveyed by the Marine Mammal Division (MMD

  20. Sampling and Analysis Plan for PUREX canyon vessel flushing

    SciTech Connect (OSTI)

    Villalobos, C.N.

    1995-03-01

    A sampling and analysis plan is necessary to provide direction for the sampling and analytical activities determined by the data quality objectives. This document defines the sampling and analysis necessary to support the deactivation of the Plutonium-Uranium Extraction (PUREX) facility vessels that are regulated pursuant to Washington Administrative Code 173-303.

  1. In-vessel coolability and retention of a core melt. Volume 1

    SciTech Connect (OSTI)

    Theofanous, T.G.; Liu, C.; Additon, S.; Angelini, S.; Kymaelaeinen, O.; Salmassi, T. [California Univ., Santa Barbara, CA (United States). Center for Risk Studies and Safety

    1996-10-01

    The efficacy of external flooding of a reactor vessel as a severe accident management strategy is assessed for an AP600-like reactor design. The overall approach is based on the Risk Oriented Accident Analysis Methodology (ROAAM), and the assessment includes consideration of bounding scenarios and sensitivity studies, as well as arbitrary parametric evaluations that allow the delineation of the failure boundaries. Quantification of the input parameters is carried out for an AP600-like design, and the results of the assessment demonstrate that lower head failure is physically unreasonable. Use of this conclusion for any specific application is subject to verifying the required reliability of the depressurization and cavity-flooding systems, and to showing the appropriateness (in relation to the database presented here, or by further testing as necessary) of the thermal insulation design and of the external surface properties of the lower head, including any applicable coatings. The AP600 is particularly favorable to in-vessel retention. Some ideas to enhance the assessment basis as well as performance in this respect, for applications to larger and/or higher power density reactors are also provided.

  2. In-vessel coolability and retention of a core melt. Volume 2

    SciTech Connect (OSTI)

    Theofanous, T.G.; Liu, C.; Additon, S.; Angelini, S.; Kymaelaeinen, O.; Salmassi, T. [California Univ., Santa Barbara, CA (United States). Center for Risk Studies and Safety

    1996-10-01

    The efficacy of external flooding of a reactor vessel as a severe accident management strategy is assessed for an AP600-like reactor design. The overall approach is based on the Risk Oriented Accident Analysis Methodology (ROAAM), and the assessment includes consideration of bounding scenarios and sensitivity studies, as well as arbitrary parametric evaluations that allow the delineation of the failure boundaries. Quantification of the input parameters is carried out for an AP600-like design, and the results of the assessment demonstrate that lower head failure is physically unreasonable. Use of this conclusion for any specific application is subject to verifying the required reliability of the depressurization and cavity-flooding systems, and to showing the appropriateness (in relation to the database presented here, or by further testing as necessary) of the thermal insulation design and of the external surface properties of the lower head, including any applicable coatings. The AP600 is particularly favorable to in-vessel retention. Some ideas to enhance the assessment basis as well as performance in this respect, for applications to larger and/or higher power density reactors are also provided.

  3. Operation Poorman

    SciTech Connect (OSTI)

    Pruvost, N.; Tsitouras, J.

    1981-03-18

    The objectives of Operation Poorman were to design and build a portable seismic system and to set up and use this system in a cold-weather environment. The equipment design uses current technology to achieve a low-power, lightweight system that is configured into three modules. The system was deployed in Alaska during wintertime, and the results provide a basis for specifying a mission-ready seismic verification system.

  4. Substituted Adamantyl-Urea Inhibitors of the Soluble Epoxide Hydrolase Dilate Mesenteric Resistance Vessels

    E-Print Network [OSTI]

    Hammock, Bruce D.

    Vessels Jeffrey J. Olearczyk, Mary B. Field, In-Hae Kim, Christophe Morisseau, Bruce D. Hammock, and John experiments, denuding mesenteric resistance vessels did not alter AUDA-induced relaxation. Taken together

  5. Effects of ionizing radiation on normal and tumor-associated lymphatic vessels

    E-Print Network [OSTI]

    Lobo, Jennifer D

    2007-01-01

    Lymphatic vessels play a crucial role in both the pathophysiology of tumors and in the spread cancer cells to lymph nodes. The effects of radiation on these vessels, however, are largely unknown. Here, we seek to describe ...

  6. Proceeding of the International Conference & Exhibition on Pressure Vessels and Piping, "OPE 2006 CHENNAI",

    E-Print Network [OSTI]

    Dunin-Borkowski, Rafal E.

    Proceeding of the International Conference & Exhibition on Pressure Vessels and Piping, "OPE 2006 on Pressure Vessels and Piping, "OPE 2006 ­ CHENNAI", 7-9, February 2006, Chennai, India B8-2 (Page 2

  7. Assessment of Vessel Requirements for the U.S. Offshore Wind...

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

    Douglas-Westwood Page 22 Overview of the Vessel-Related Aspects of the Offshore Wind Industry Part 1 Overview of the Vessel-Related Aspects of the Offshore Wind Industry ...

  8. Nonlinear Response and Stability Analysis of Vessel Rolling Motion in Random Waves Using Stochastic Dynamical Systems 

    E-Print Network [OSTI]

    Su, Zhiyong

    2012-10-19

    Response and stability of vessel rolling motion with strongly nonlinear softening stiffness will be studied in this dissertation using the methods of stochastic dynamical systems. As one of the most classic stability failure modes of vessel dynamics...

  9. LOW ALLOY STEELS FOR THICK WALL PRESSURE VESSELS Yearly Report for Period Oct. 1, 1976 to Sept. 30, 1977.

    E-Print Network [OSTI]

    Horn, R.M.

    2011-01-01

    FOR THICK WALL PRESSURE VESSELS R. M, Horn, E. R. Parker,FOR THICK WALL PRESSURE VESSELS Yearly Report f o r PeriodManufacture Pressure Vessel Fabrication Under ASME Code

  10. LOW ALLOY STEELS FOR THICK WALL PRESSURE VESSELS Yearly Report for Period Oct. 1, 1976 to Sept. 30, 1977.

    E-Print Network [OSTI]

    Horn, R.M.

    2011-01-01

    Vessel Fabrication Under ASME Code Current Pressure Vessel Sc a t i o n under the ASME code current s t e e l s , and (VESSEL FABRICATION UNDER ASME CODE Interactions with Babcock

  11. INSTRUMENTATION, INCLUDING NUCLEAR AND PARTICLE DETECTORS; RADIATION

    Office of Scientific and Technical Information (OSTI)

    interval technical basis document Chiaro, P.J. Jr. 44 INSTRUMENTATION, INCLUDING NUCLEAR AND PARTICLE DETECTORS; RADIATION DETECTORS; RADIATION MONITORS; DOSEMETERS;...

  12. Operations Information

    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: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration wouldMass mapSpeeding access toOctober 1996Technologies /JuneOperating Oakoak ridge

  13. Operations Office

    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: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration wouldMass mapSpeeding access toOctober 1996Technologies /JuneOperating Oakoak

  14. Segmentation of vessels using weighted local variances and an active contour model

    E-Print Network [OSTI]

    Chung, Albert C. S.

    Segmentation of vessels using weighted local variances and an active contour model W. K. Law is a challenging problem. This paper presents a novel approach to segment- ing blood vessels using weighted local variances and an ac- tive contour model. In this work, the vessel boundary orien- tation is estimated

  15. Under consideration for publication in J. Fluid Mech. 1 Shallow-water sloshing in vessels undergoing

    E-Print Network [OSTI]

    Bridges, Tom

    Under consideration for publication in J. Fluid Mech. 1 Shallow-water sloshing in vessels-water equations, for sloshing in three dimensions (two horizontal and one vertical) in a vessel which is undergoing rigid-body motion in 3-space, are derived. The rigid-body motion of the vessel (roll-pitch-yaw and

  16. An LDA-based relative hysteresis classifier with application to segmentation of retinal vessels

    E-Print Network [OSTI]

    Lübeck, Universität zu

    An LDA-based relative hysteresis classifier with application to segmentation of retinal vessels hysteresis methods and, for the problem of retina vessel segmentation, to known dedicated methods on similar, to support medical diagnosis and for intervention planning. To this end, the retinal vessels need

  17. Discrimination of Large Venous Vessels in Time-Course Spiral Blood-Oxygen-Level-DependentMagnetic-

    E-Print Network [OSTI]

    Glover, Gary H.

    Discrimination of Large Venous Vessels in Time-Course Spiral Blood for discriminating blood-oxygen- level-dependent (BOLD)signal changesoriginatingfrom large venous vessels and those,whereas the signal in pixels cor- related with visible vessels and sulci was generally delayed from 8 to 14 s

  18. Vessel and Aneurysm Reconstruction using Speed and Flow Coherence Information in

    E-Print Network [OSTI]

    Chung, Albert C. S.

    Vessel and Aneurysm Reconstruction using Speed and Flow Coherence Information in Phase Contrast-MRA) is a non-invasive method for 3D vessel delineation, which for each voxel not only provides measurement the form of phase images). In this thesis, we present a new approach to reconstructing vessels

  19. A tool for the quantification of radial neo-vessels in chick chorioallantoic membrane angiogenic assays

    E-Print Network [OSTI]

    Signoroni, Alberto

    A tool for the quantification of radial neo-vessels in chick chorioallantoic membrane angiogenic, and Stefania Mitola2 Abstract-- Angiogenesis, the process of new blood vessels formation, plays a key role chorioallantoic mem- brane (CAM). At day 11 of development CAM is completely vascularized and neo-vessels induced

  20. J. Fluid Mech. (in press) 1 Shallow-water sloshing in vessels undergoing

    E-Print Network [OSTI]

    Bridges, Tom

    J. Fluid Mech. (in press) 1 Shallow-water sloshing in vessels undergoing prescribed rigid vertical) in a vessel which is undergoing rigid-body motion in 3-space, are derived. The rigid-body motion of the vessel (roll- pitch-yaw and/or surge-sway-heave) is modelled exactly and the only approximations

  1. High-resolution imaging of vessels in the isolated rat brain M. F. Valverde Salzmann1

    E-Print Network [OSTI]

    High-resolution imaging of vessels in the isolated rat brain M. F. Valverde Salzmann1 , N for the distribution of vessels in the rat brain. Angiography is able to use the blood flow in the brain of the living of this study was to obtain a full picture of vessels even down to relatively small size in the isolated rat

  2. Investigation of the cerebral hemodynamic response function in single blood vessels by functional

    E-Print Network [OSTI]

    Duong, Timothy Q.

    Investigation of the cerebral hemodynamic response function in single blood vessels by functional blood vessels of rats after left forepaw stimulation. In this system, we analyzed the spatiotemporal), and hemoglobin oxygen saturation (SO2). Changes in specific cerebral vessels corresponding to various electrical

  3. Vessel Segmentation Using A Shape Driven Flow Delphine Nain, Anthony Yezzi and Greg Turk

    E-Print Network [OSTI]

    Turk, Greg

    Vessel Segmentation Using A Shape Driven Flow Delphine Nain, Anthony Yezzi and Greg Turk Georgia. We present a segmentation method for vessels using an im- plicit deformable model with a soft shape prior. Blood vessels are chal- lenging structures to segment due to their branching and thinning geome

  4. Blood flow through axially symmetric sections of compliant vessels: new effective closed models

    E-Print Network [OSTI]

    Canic, Suncica

    Blood flow through axially symmetric sections of compliant vessels: new effective closed models S-Stokes) equations for blood flow in compliant vessels. Several "effec- tive" one-dimensional models have been used independent ring model) to model the vessel wall behavior. In this work we obtain an effective system

  5. Vessel and Intracranial Aneurysm Segmentation Using Multi-range Filters and Local Variances

    E-Print Network [OSTI]

    Chung, Albert C. S.

    Vessel and Intracranial Aneurysm Segmentation Using Multi-range Filters and Local Variances Max W,achung}@cse.ust.hk Abstract. Segmentation of vessels and brain aneurysms on non-invasive and flow-sensitive phase contrast and local variances to perform segmentation of vessels and intracranial aneurysms on PCMRA images

  6. IDS120h GEOMETRY WITH SHIELDING VESSELS ENERGY FLOW ANALYSIS CONTINUED

    E-Print Network [OSTI]

    McDonald, Kirk

    IDS120h GEOMETRY WITH SHIELDING VESSELS ENERGY FLOW ANALYSIS CONTINUED SHIELDING MATERIAL: 60% W with shielding vessels. # Different cases of shielding material. # N = 100,000 AND N = 500,000 events simulations CUTOFF >SHIELDING: 60% W + 40% He , 80% W + 20% He, 88% W + 12% He ( WITH W VESSELS) >4 MW proton beam

  7. Author's personal copy The behaviors of ferromagnetic nano-particles in and around blood vessels

    E-Print Network [OSTI]

    Rubloff, Gary W.

    Author's personal copy The behaviors of ferromagnetic nano-particles in and around blood vessels Blood vessels Treatment depth Non-dimensional parameters In-vivo experiments a b s t r a c t In magnetic, and the applied magnetic fields. Using physical first-principles and a sophisticated vessel-membrane-tissue (VMT

  8. Segmentation of retinal vessels with a hysteresis binary-classification paradigm

    E-Print Network [OSTI]

    Lübeck, Universität zu

    Segmentation of retinal vessels with a hysteresis binary-classification paradigm Alexandru P Building 64 D-23562 Luebeck, Germany Abstract Vessel segmentation in photographies of the retina is needed a paradigm of hysteresis- classifier design that we apply to the problem of vessel segmentation. Before

  9. IDS120h: Be WINDOW DETAILED CALCULATION, SHIELDING VESSELS, RESULTS FOR DIFFERENT

    E-Print Network [OSTI]

    McDonald, Kirk

    IDS120h: Be WINDOW DETAILED CALCULATION, SHIELDING VESSELS, RESULTS FOR DIFFERENT GLOBAL STEPS with different STEPEM, STEPH global steps, and introducing shielding vessels. >mars1510/MCNP >10-11 MeV NEUTRON Be Window Hg Pool SC8 SC 7 SC 6 SH 2 SH 4 SH 3 #12;IDS120h:SHIELDING VESSELS. RESULTS FOR 0.5 cm THIKNESS

  10. VESSEL SEGMENTATION IN MEDICAL IMAGING USING A TIGHT-FRAME BASED ALGORITHM

    E-Print Network [OSTI]

    Chan, Raymond

    VESSEL SEGMENTATION IN MEDICAL IMAGING USING A TIGHT-FRAME BASED ALGORITHM XIAOHAO CAI, RAYMOND vessels in magnetic resonance angiography images. Our method iteratively refines a region that encloses the potential boundary of the vessels. At each iteration, we apply the tight-frame algorithm to denoise

  11. Nuclear Propelled Vessels and Neutrino Oscillation Experiments J. Detwiler, G. Gratta, N. Tolich, and Y. Uchida

    E-Print Network [OSTI]

    Gratta, Giorgio

    Nuclear Propelled Vessels and Neutrino Oscillation Experiments J. Detwiler, G. Gratta, N. Tolich given, until now, to the background due to nuclear propelled vessels to these experiments. Although we estimate that the total thermal power generated by such vessels is just a few percent of the total nuclear

  12. PREDICTIVE DISPLAYS FOR SURVEY VESSELS Briana Sullivan, Colin Ware and Matthew Plumlee

    E-Print Network [OSTI]

    Ware, Colin

    PREDICTIVE DISPLAYS FOR SURVEY VESSELS Briana Sullivan, Colin Ware and Matthew Plumlee Center in the vessel's heading. Predictive displays are a common way of mitigating the effect of lag on human control. Accordingly we developed a predictive display to show the position and heading of a vessel a short time

  13. Retinal Vessel Extraction Using Multiscale Matched Filters, Confidence and Edge Measures

    E-Print Network [OSTI]

    Bystroff, Chris

    Retinal Vessel Extraction Using Multiscale Matched Filters, Confidence and Edge Measures Michal of improving detection of low-contrast and narrow vessels and eliminating false detections at non-vascular structures, a new technique is presented for extracting vessels in retinal images. The core of the technique

  14. ON A MODEL FOR CONTINUOUS SEDIMENTATION IN VESSELS WITH DISCONTINUOUSLY VARYING CROSS-SECTIONAL AREA

    E-Print Network [OSTI]

    ON A MODEL FOR CONTINUOUS SEDIMENTATION IN VESSELS WITH DISCONTINUOUSLY VARYING CROSS]. However, we now consider that the cross-sectional area of the settling vessel is not constant in both for continuous sedimentation in a vessel with varying cross section. In the formulation of the #12;nal initial

  15. NOTE ON THE OPTIMAL INTERCEPT TIME OF VESSELS TO A NONZERO RANGE

    E-Print Network [OSTI]

    Gander, Martin J.

    NOTE ON THE OPTIMAL INTERCEPT TIME OF VESSELS TO A NONZERO RANGE MARTIN J. GANDER \\Lambda Abstract. There is an even simpler solution to the optimal intercept problem of vessels to a nonzero range. Key words. intercept AMS subject classifications. 00A08 In [1] the authors consider the problem of a patrol vessel

  16. The Segmentation of the Supraorbital Vessels in Thermal Imagery The Department of Computer Science

    E-Print Network [OSTI]

    The Segmentation of the Supraorbital Vessels in Thermal Imagery Zhen Zhu The Department of Computer with the activation of the corrugator muscle on the forehead. The vessels that supply blood to the corrugator muscle, pro- portionally to its degree of activation, are the supraorbital vessels. The rate of blood flow

  17. Vessel Segmentation in 2D-Projection Images Using a Supervised Linear Hysteresis Classifier

    E-Print Network [OSTI]

    Lübeck, Universität zu

    Vessel Segmentation in 2D-Projection Images Using a Supervised Linear Hysteresis Classifier, Germany Abstract 2D projection imaging is a widely used procedure for vessel visualization. For the subsequent analysis of the vasculature, precise measurements of e.g. vessel area, ves- sel length

  18. Proceedings of PVP2006-ICPVT-11 2006 ASME Pressure Vessels and Piping Division Conference

    E-Print Network [OSTI]

    Barr, Al

    - tions contained in NFPA 69 [11] which refers to the ASME Boiler and Pressure Vessel Code Section VIII- 1 Copyright c 2006 by ASME #12;vision within the ASME Boiler and Pressure Vessel or Piping CodesProceedings of PVP2006-ICPVT-11 2006 ASME Pressure Vessels and Piping Division Conference July 23

  19. Chapter 10: FTU Operation

    SciTech Connect (OSTI)

    Angelini, B.M.; Apicella, M.L.; Buceti, G.; Centioli, C.; Crisanti, F.; Iannone, F.; Mazza, G.; Mazzitelli, G.; Panella, M.; Vitale, V.

    2004-05-15

    Some specific points of the Frascati Tokamak Upgrade (FTU) operation are presented for plasma performance as well as for the machine availability and the development of new tools needed to operate in a complex scenario needed for tokamak research. The different techniques adopted for wall conditioning of the FTU are reviewed. Plasmas with low Z{sub eff} have been achieved including those at low density and high additional heating power. The obtained experimental results are discussed in terms of better operation and plasma performance achieved. As with any other large - and thus long-lasting - experiments, a mixture of old and new technological solutions inserted in an open source framework characterizes the FTU data control and acquisition systems. We give some information on the original architecture and try to detail its current state. The high level of reliability presently achieved is discussed.

  20. Reactor operation safety information document

    SciTech Connect (OSTI)

    Not Available

    1990-01-01

    The report contains a reactor facility description which includes K, P, and L reactor sites, structures, operating systems, engineered safety systems, support systems, and process and effluent monitoring systems; an accident analysis section which includes cooling system anomalies, radioactive materials releases, and anticipated transients without scram; a summary of onsite doses from design basis accidents; severe accident analysis (reactor core disruption); a description of operating contractor organization and emergency planning; and a summary of reactor safety evolution. (MB)

  1. Jam proof closure assembly for lidded pressure vessels

    DOE Patents [OSTI]

    Cioletti, Olisse C. (Pittsburgh, PA)

    1992-01-01

    An expendable closure assembly is provided for use (in multiple units) with a lockable pressure vessel cover along its rim, such as of an autoclave. This assembly is suited to variable compressive contact and locking with the vessel lid sealing gasket. The closure assembly consists of a thick walled sleeve insert for retention in the under bores fabricated in the cover periphery and the sleeve is provided with internal threading only. A snap serves as a retainer on the underside of the sleeve, locking it into an under bore retention channel. Finally, a standard elongate externally threaded bolt is sized for mating cooperation with the so positioned sleeve, whereby the location of the bolt shaft in the cover bore hole determines its compressive contact on the underlying gasket.

  2. The coolability limits of a reactor pressure vessel lower head

    SciTech Connect (OSTI)

    Theofanous, T.G.; Syri, S. [Univ. of California, Santa Barbara, CA (United States)

    1995-09-01

    Configuration II of the ULPU experimental facility is described, and from a comprehensive set of experiments are provided. The facility affords full-scale simulations of the boiling crisis phenomenon on the hemispherical lower head of a reactor pressure vessel submerged in water, and heated internally. Whereas Configuration I experiments (published previously) established the lower limits of coolability under low submergence, pool-boiling conditions, with Configuration II we investigate coolability under conditions more appropriate to practical interest in severe accident management; that is, heat flux shapes (as functions of angular position) representative of a core melt contained by the lower head, full submergence of the reactor pressure vessel, and natural circulation. Critical heat fluxes as a function of the angular position on the lower head are reported and related the observed two-phase flow regimes.

  3. Lessons Learned From Developing Reactor Pressure Vessel Steel Embrittlement Database

    SciTech Connect (OSTI)

    Wang, Jy-An John

    2010-08-01

    Materials behaviors caused by neutron irradiation under fission and/or fusion environments can be little understood without practical examination. Easily accessible material information system with large material database using effective computers is necessary for design of nuclear materials and analyses or simulations of the phenomena. The developed Embrittlement Data Base (EDB) at ORNL is this comprehensive collection of data. EDB database contains power reactor pressure vessel surveillance data, the material test reactor data, foreign reactor data (through bilateral agreements authorized by NRC), and the fracture toughness data. The lessons learned from building EDB program and the associated database management activity regarding Material Database Design Methodology, Architecture and the Embedded QA Protocol are described in this report. The development of IAEA International Database on Reactor Pressure Vessel Materials (IDRPVM) and the comparison of EDB database and IAEA IDRPVM database are provided in the report. The recommended database QA protocol and database infrastructure are also stated in the report.

  4. THE IMPACT OF OZONE ON THE LOWER FLAMMABLE LIMIT OF HYDROGEN IN VESSELS CONTAINING SAVANNAH RIVER SITE HIGH LEVEL WASTE

    SciTech Connect (OSTI)

    Sherburne, Carol [Savannah River Site (SRS), Aiken, SC (United States). Savannah River Remediation, LLC; Osterberg, Paul [Fauske and Associates, LLC, Burr Ridge, IL (United States); Johnson, Tom [Fauske and Associates, LLC, Burr Ridge, IL (United States); Frawely, Thomas [Fauske and Associates, LLC, Burr Ridge, IL (United States)

    2013-01-23

    The Savannah River Site, in conjunction with AREVA Federal services, has designed a process to treat dissolved radioactive waste solids with ozone. It is known that in this radioactive waste process, radionuclides radiolytically break down water into gaseous hydrogen and oxygen, which presents a well defined flammability hazard. Flammability limits have been established for both ozone and hydrogen separately; however, there is little information on mixtures of hydrogen and ozone. Therefore, testing was designed to provide critical flammability information necessary to support safety related considerations for the development of ozone treatment and potential scale-up to the commercial level. Since information was lacking on flammability issues at low levels of hydrogen and ozone, a testing program was developed to focus on filling this portion of the information gap. A 2-L vessel was used to conduct flammability tests at atmospheric pressure and temperature using a fuse wire ignition source at 1 percent ozone intervals spanning from no ozone to the Lower Flammable Limit (LFL) of ozone in the vessel, determined as 8.4%(v/v) ozone. An ozone generator and ozone detector were used to generate and measure the ozone concentration within the vessel in situ, since ozone decomposes rapidly on standing. The lower flammability limit of hydrogen in an ozone-oxygen mixture was found to decrease from the LFL of hydrogen in air, determined as 4.2 % (v/v) in this vessel. From the results of this testing, Savannah River was able to develop safety procedures and operating parameters to effectively minimize the formation of a flammable atmosphere.

  5. Response of a water-filled spherical vessel to an internal explosion

    SciTech Connect (OSTI)

    Lewis, M.W.; Wilson, T.L.

    1997-06-01

    Many problems of interest to the defense community involve fluid-structure interaction (FSI). Such problems include underwater blast loading of structures, bubble dynamics and jetting around structures, and hydrodynamic ram events. These problems may involve gas, fluid, and solid dynamics, nonlinear material behavior, cavitation, reaction kinetics, material failure, and nonlinearity that is due to varying geometry and contact conditions within a structure or between structures. Here, the authors model the response of a water-filled, thick-walled, spherical steel vessel to an internal explosion of 30 grams of C-4 with FSI2D--a two-dimensional coupled finite element and finite volume hydrodynamics code. The gas phase detonation products were modeled with a Becker-Kistiakowsky-Wilson high-explosive equation of state. Predictions from a fully coupled model were compared to experimental results in the form of strain gauge traces. Agreement was reasonably good. Additionally, the calculation was run in an uncoupled mode to understand the importance of fluid-structure interaction in this problem. The uncoupled model results in an accumulation of nonphysical energy in the vessel.

  6. A cog-like vessel from the Netherlands 

    E-Print Network [OSTI]

    Van de Moortel, Aleydis Maria P. A.

    1987-01-01

    on the Bosshoimen wreck. Maria Jacobsen is thanked for translating the Danish and Swedish articles. Many of the observations and interpretations found in this thesis are the results of Fruitful discussions. I want to thank warmly my chairman, J. Richard Steffy... and dimensions ln cm. . . . . . 76 3. Port garboard curvature. 81 4. Sheer height ratios of cog ? 1 ike vessels. . . 176 5. EFFective wind power and total hull resistance versus ship and wind velocity . 201 6. Hul'1 dimensions in Amsterdam and Frisian...

  7. A Markov method for generating capacity reliability evaluation including operating considerations 

    E-Print Network [OSTI]

    Asgarpoor, Sohrab

    1981-01-01

    =NN 00 61 1=1 N OQ 61 J= I N E( I J)=O CONTINUE KG=0 00 30 KK I NLL (F(KK NE I) GO TO 31 GQ TO 32 IF(I OAO&KK) LT LOAD(KK-I IF(LOAD(KK) GT ~ LQAD(KX-I IF&KG GT ~ OI GO TQ 44 CQ TQ 32 N=NN 00 36 J I N SD & KK ~ J) =58& KK-I J )-SB (K CONTINUE... N=NN UNITS WHICH HAS FAILED IN CLASS ) I 6), IF& J& ~ V(J) 5X, I5) &) 0 70 33 )) GQ TQ 32 K+I ~ J) 33 CALL MOOST &A ~ IF D V CAP ~ 4EW 4 LQAD LAM Ul?N NC, N KK ~ ALPHA ~ ST 1 CAPP KL NT I NF, CAPS ~ KAPS 53 SD 'VR NU PS, TS DELTS) 84 85 86...

  8. Floating point only SIMD instruction set architecture including compare, select, Boolean, and alignment operations

    DOE Patents [OSTI]

    Gschwind, Michael K. (Chappaqua, NY)

    2011-03-01

    Mechanisms for implementing a floating point only single instruction multiple data instruction set architecture are provided. A processor is provided that comprises an issue unit, an execution unit coupled to the issue unit, and a vector register file coupled to the execution unit. The execution unit has logic that implements a floating point (FP) only single instruction multiple data (SIMD) instruction set architecture (ISA). The floating point vector registers of the vector register file store both scalar and floating point values as vectors having a plurality of vector elements. The processor may be part of a data processing system.

  9. Operational Impacts of Responsive Electricity Loads: A Modeling Framework Including Policy Implications for Cyprus

    E-Print Network [OSTI]

    Bruchon, Matthew Bremer

    2013-01-01

    In order to meet EU mandates, the island nation of Cyprus must raise penetration of renewable energy from roughly 5% in 2013 to 16% in 2020. This means Cyprus will need economical ways of balancing intermittency, a special ...

  10. PipelineSeptember 2013 Volume 5, Issue 5 FM Included in Campus Operations

    E-Print Network [OSTI]

    of Optimizing the University's Physical Assets; Ensuring a Safe University; and Providing a Memorable Student of the Dinkytown bikeway, which connects the Mississippi River to TCF Bank Stadium. The bikeway was made possible. The trail runs along the

  11. Course may include: Research in Education

    E-Print Network [OSTI]

    Course may include: Research in Education Statistics in Education Theories of Educational Admin Policy Analysis Sociological Aspects of Education Approaches to Literacy Development Information and Communication Technologies Issues in Education Final Project Seminar Master of Education Educational

  12. ILC Operating Scenarios

    E-Print Network [OSTI]

    T. Barklow; J. Brau; K. Fujii; J. Gao; J. List; N. Walker; K. Yokoya

    2015-06-25

    The ILC Technical Design Report documents the design for the construction of a linear collider which can be operated at energies up to 500 GeV. This report summarizes the outcome of a study of possible running scenarios, including a realistic estimate of the real time accumulation of integrated luminosity based on ramp-up and upgrade processes. The evolution of the physics outcomes is emphasized, including running initially at 500 GeV, then at 350 GeV and 250 GeV. The running scenarios have been chosen to optimize the Higgs precision measurements and top physics while searching for evidence for signals beyond the standard model, including dark matter. In addition to the certain precision physics on the Higgs and top that is the main focus of this study, there are scientific motivations that indicate the possibility for discoveries of new particles in the upcoming operations of the LHC or the early operation of the ILC. Follow-up studies of such discoveries could alter the plan for the centre-of-mass collision energy of the ILC and expand the scientific impact of the ILC physics program. It is envisioned that a decision on a possible energy upgrade would be taken near the end of the twenty year period considered in this report.

  13. Operational health physics training

    SciTech Connect (OSTI)

    1992-06-01

    The initial four sections treat basic information concerning atomic structure and other useful physical quantities, natural radioactivity, the properties of {alpha}, {beta}, {gamma}, x rays and neutrons, and the concepts and units of radiation dosimetry (including SI units). Section 5 deals with biological effects and the risks associated with radiation exposure. Background radiation and man-made sources are discussed next. The basic recommendations of the ICRP concerning dose limitations: justification, optimization (ALARA concepts and applications) and dose limits are covered in Section seven. Section eight is an expanded version of shielding, and the internal dosimetry discussion has been extensively revised to reflect the concepts contained in the MIRD methodology and ICRP 30. The remaining sections discuss the operational health physics approach to monitoring radiation. Individual sections include radiation detection principles, instrument operation and counting statistics, health physics instruments and personnel monitoring devices. The last five sections deal with the nature of, operation principles of, health physics aspects of, and monitoring approaches to air sampling, reactors, nuclear safety, gloveboxes and hot cells, accelerators and x ray sources. Decontamination, waste disposal and transportation of radionuclides are added topics. Several appendices containing constants, symbols, selected mathematical topics, and the Chart of the Nuclides, and an index have been included.

  14. Gas storage materials, including hydrogen storage materials

    DOE Patents [OSTI]

    Mohtadi, Rana F; Wicks, George G; Heung, Leung K; Nakamura, Kenji

    2014-11-25

    A material for the storage and release of gases comprises a plurality of hollow elements, each hollow element comprising a porous wall enclosing an interior cavity, the interior cavity including structures of a solid-state storage material. In particular examples, the storage material is a hydrogen storage material, such as a solid state hydride. An improved method for forming such materials includes the solution diffusion of a storage material solution through a porous wall of a hollow element into an interior cavity.

  15. Gas storage materials, including hydrogen storage materials

    DOE Patents [OSTI]

    Mohtadi, Rana F; Wicks, George G; Heung, Leung K; Nakamura, Kenji

    2013-02-19

    A material for the storage and release of gases comprises a plurality of hollow elements, each hollow element comprising a porous wall enclosing an interior cavity, the interior cavity including structures of a solid-state storage material. In particular examples, the storage material is a hydrogen storage material such as a solid state hydride. An improved method for forming such materials includes the solution diffusion of a storage material solution through a porous wall of a hollow element into an interior cavity.

  16. Scramjet including integrated inlet and combustor

    SciTech Connect (OSTI)

    Kutschenreuter, P.H. Jr.; Blanton, J.C.

    1992-02-04

    This patent describes a scramjet engine. It comprises: a first surface including an aft facing step; a cowl including: a leading edge and a trailing edge; an upper surface and a lower surface extending between the leading edge and the trailing edge; the cowl upper surface being spaced from and generally parallel to the first surface to define an integrated inlet-combustor therebetween having an inlet for receiving and channeling into the inlet-combustor supersonic inlet airflow; means for injecting fuel into the inlet-combustor at the step for mixing with the supersonic inlet airflow for generating supersonic combustion gases; and further including a spaced pari of sidewalls extending between the first surface to the cowl upper surface and wherein the integrated inlet-combustor is generally rectangular and defined by the sidewall pair, the first surface and the cowl upper surface.

  17. Purge gas protected transportable pressurized fuel cell modules and their operation in a power plant

    DOE Patents [OSTI]

    Zafred, P.R.; Dederer, J.T.; Gillett, J.E.; Basel, R.A.; Antenucci, A.B.

    1996-11-12

    A fuel cell generator apparatus and method of its operation involves: passing pressurized oxidant gas and pressurized fuel gas into modules containing fuel cells, where the modules are each enclosed by a module housing surrounded by an axially elongated pressure vessel, and where there is a purge gas volume between the module housing and pressure vessel; passing pressurized purge gas through the purge gas volume to dilute any unreacted fuel gas from the modules; and passing exhaust gas and circulated purge gas and any unreacted fuel gas out of the pressure vessel; where the fuel cell generator apparatus is transportable when the pressure vessel is horizontally disposed, providing a low center of gravity. 11 figs.

  18. Purge gas protected transportable pressurized fuel cell modules and their operation in a power plant

    DOE Patents [OSTI]

    Zafred, Paolo R. (Pittsburgh, PA); Dederer, Jeffrey T. (Valencia, PA); Gillett, James E. (Greensburg, PA); Basel, Richard A. (Plub Borough, PA); Antenucci, Annette B. (Pittsburgh, PA)

    1996-01-01

    A fuel cell generator apparatus and method of its operation involves: passing pressurized oxidant gas, (O) and pressurized fuel gas, (F), into fuel cell modules, (10 and 12), containing fuel cells, where the modules are each enclosed by a module housing (18), surrounded by an axially elongated pressure vessel (64), where there is a purge gas volume, (62), between the module housing and pressure vessel; passing pressurized purge gas, (P), through the purge gas volume, (62), to dilute any unreacted fuel gas from the modules; and passing exhaust gas, (82), and circulated purge gas and any unreacted fuel gas out of the pressure vessel; where the fuel cell generator apparatus is transpatable when the pressure vessel (64) is horizontally disposed, providing a low center of gravity.

  19. Predicting target vessel location on robot-assisted coronary artery bypass graft using CT to ultrasound registration

    SciTech Connect (OSTI)

    Cho, Daniel S.; Linte, Cristian; Chen, Elvis C. S.; Bainbridge, Daniel; Wedlake, Chris; Moore, John; Barron, John; Patel, Rajni; Peters, Terry

    2012-03-15

    Purpose: Although robot-assisted coronary artery bypass grafting (RA-CABG) has gained more acceptance worldwide, its success still depends on the surgeon's experience and expertise, and the conversion rate to full sternotomy is in the order of 15%-25%. One of the reasons for conversion is poor pre-operative planning, which is based solely on pre-operative computed tomography (CT) images. In this paper, the authors propose a technique to estimate the global peri-operative displacement of the heart and to predict the intra-operative target vessel location, validated via both an in vitro and a clinical study. Methods: As the peri-operative heart migration during RA-CABG has never been reported in the literatures, a simple in vitro validation study was conducted using a heart phantom. To mimic the clinical workflow, a pre-operative CT as well as peri-operative ultrasound images at three different stages in the procedure (Stage{sub 0}--following intubation; Stage{sub 1}--following lung deflation; and Stage{sub 2}--following thoracic insufflation) were acquired during the experiment. Following image acquisition, a rigid-body registration using iterative closest point algorithm with the robust estimator was employed to map the pre-operative stage to each of the peri-operative ones, to estimate the heart migration and predict the peri-operative target vessel location. Moreover, a clinical validation of this technique was conducted using offline patient data, where a Monte Carlo simulation was used to overcome the limitations arising due to the invisibility of the target vessel in the peri-operative ultrasound images. Results: For the in vitro study, the computed target registration error (TRE) at Stage{sub 0}, Stage{sub 1}, and Stage{sub 2} was 2.1, 3.3, and 2.6 mm, respectively. According to the offline clinical validation study, the maximum TRE at the left anterior descending (LAD) coronary artery was 4.1 mm at Stage{sub 0}, 5.1 mm at Stage{sub 1}, and 3.4 mm at Stage{sub 2}. Conclusions: The authors proposed a method to measure and validate peri-operative shifts of the heart during RA-CABG. In vitro and clinical validation studies were conducted and yielded a TRE in the order of 5 mm for all cases. As the desired clinical accuracy imposed by this procedure is on the order of one intercostal space (10-15 mm), our technique suits the clinical requirements. The authors therefore believe this technique has the potential to improve the pre-operative planning by updating peri-operative migration patterns of the heart and, consequently, will lead to reduced conversion to conventional open thoracic procedures.

  20. Electric Power Monthly, August 1990. [Glossary included

    SciTech Connect (OSTI)

    Not Available

    1990-11-29

    The Electric Power Monthly (EPM) presents monthly summaries of electric utility statistics at the national, Census division, and State level. The purpose of this publication is to provide energy decisionmakers with accurate and timely information that may be used in forming various perspectives on electric issues that lie ahead. Data includes generation by energy source (coal, oil, gas, hydroelectric, and nuclear); generation by region; consumption of fossil fuels for power generation; sales of electric power, cost data; and unusual occurrences. A glossary is included.

  1. MOTIVATION INCLUDED OR EXCLUDED FROM Mihaela Cocea

    E-Print Network [OSTI]

    Cocea, Mihaela

    MOTIVATION ­ INCLUDED OR EXCLUDED FROM E-LEARNING Mihaela Cocea National College of Ireland Mayor, Dublin 1, Ireland sweibelzahl@ncirl.ie ABSTRACT The learners' motivation has an impact on the quality-Learning, motivation has been mainly considered in terms of instructional design. Research in this direction suggests

  2. Energy Consumption of Personal Computing Including Portable

    E-Print Network [OSTI]

    Namboodiri, Vinod

    processing unit (CPU) processing power and capacity of mass storage devices doubles every 18 months. Such growth in both processing and storage capabilities fuels the production of ever more powerful portableEnergy Consumption of Personal Computing Including Portable Communication Devices Pavel Somavat1

  3. Course may include: Research in Education

    E-Print Network [OSTI]

    Development Information and Communication Technologies Issues in Education Final Project Seminar Master, the Final Project Seminar. This graduate program will allow you to develop your skills and knowledgeCourse may include: Research in Education Qualitative Methods in Educational Research Fundamentals

  4. Communication in automation, including networking and wireless

    E-Print Network [OSTI]

    Antsaklis, Panos

    Communication in automation, including networking and wireless Nicholas Kottenstette and Panos J and networking in automation is given. Digital communication fundamentals are reviewed and networked control are presented. 1 Introduction 1.1 Why communication is necessary in automated systems Automated systems use

  5. ADDITIONAL STRESS AND FRACTURE MECHANICS ANALYSES OF PRESSURIZED WATER REACTOR PRESSURE VESSEL NOZZLES

    SciTech Connect (OSTI)

    Walter, Matthew; Yin, Shengjun; Stevens, Gary; Sommerville, Daniel; Palm, Nathan; Heinecke, Carol

    2012-01-01

    In past years, the authors have undertaken various studies of nozzles in both boiling water reactors (BWRs) and pressurized water reactors (PWRs) located in the reactor pressure vessel (RPV) adjacent to the core beltline region. Those studies described stress and fracture mechanics analyses performed to assess various RPV nozzle geometries, which were selected based on their proximity to the core beltline region, i.e., those nozzle configurations that are located close enough to the core region such that they may receive sufficient fluence prior to end-of-life (EOL) to require evaluation of embrittlement as part of the RPV analyses associated with pressure-temperature (P-T) limits. In this paper, additional stress and fracture analyses are summarized that were performed for additional PWR nozzles with the following objectives: To expand the population of PWR nozzle configurations evaluated, which was limited in the previous work to just two nozzles (one inlet and one outlet nozzle). To model and understand differences in stress results obtained for an internal pressure load case using a two-dimensional (2-D) axi-symmetric finite element model (FEM) vs. a three-dimensional (3-D) FEM for these PWR nozzles. In particular, the ovalization (stress concentration) effect of two intersecting cylinders, which is typical of RPV nozzle configurations, was investigated. To investigate the applicability of previously recommended linear elastic fracture mechanics (LEFM) hand solutions for calculating the Mode I stress intensity factor for a postulated nozzle corner crack for pressure loading for these PWR nozzles. These analyses were performed to further expand earlier work completed to support potential revision and refinement of Title 10 to the U.S. Code of Federal Regulations (CFR), Part 50, Appendix G, Fracture Toughness Requirements, and are intended to supplement similar evaluation of nozzles presented at the 2008, 2009, and 2011 Pressure Vessels and Piping (PVP) Conferences. This work is also relevant to the ongoing efforts of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code, Section XI, Working Group on Operating Plant Criteria (WGOPC) efforts to incorporate nozzle fracture mechanics solutions into a revision to ASME B&PV Code, Section XI, Nonmandatory Appendix G.

  6. Automatic segmentation of cortical vessels in pre-and post-tumor resection laser range scan images

    E-Print Network [OSTI]

    Miga, Michael I.

    Automatic segmentation of cortical vessels in pre- and post- tumor resection laser range scan have developed a method, which permits this registration using vessels visible in the images. But, vessel segmentation required the localization of starting and ending points for each vessel segment. Here

  7. Stresses and Deformations in Outer & Inner Shielding Vessels of IDS120 Bob Weggel, M.O.R.E., LLC

    E-Print Network [OSTI]

    McDonald, Kirk

    Stresses and Deformations in Outer & Inner Shielding Vessels of IDS120 Bob Weggel, M.O.R.E., LLC December 5, 2011 Fig. 1: Cross section of resistive coils, superconducting coils, shielding vessels and shielding. Vessels start at -3 meters (upstream) and end at +3 meters (downstream). Outer vessel: rmax = 1

  8. IDS120h GEOMETRY WITH SHIELDING VESSELS SHIELDING MATERIAL: 60% W + 40% He vs. 60% WC + 40% H2O

    E-Print Network [OSTI]

    McDonald, Kirk

    IDS120h GEOMETRY WITH SHIELDING VESSELS SHIELDING MATERIAL: 60% W + 40% He vs. 60% WC + 40% H2O FOR VESSELS Nicholas Souchlas, PBL (11/15/2011) 1 #12;IDS120h with shielding vessels. # Different cases and BP2 with Be sections (N=100,000). # N = 100,000 simulation with supporting ribs for vessels. >mars

  9. Development of a Process to Build Polyimide Insulated Magnets For Operation at 350C

    SciTech Connect (OSTI)

    Zatz, Irving J.

    2013-07-09

    An extensive R&D program has been conducted that has confirmed the feasibility of designing and fabricating copper alloy magnets that can successfully operate at temperatures as high as 350C. The process, originally developed for the possibility of manufacturing in-vessel resonant magnetic field perturbation (RMP) coils for JET, has been optimized for insulated magnet (and, potentially, other high temperature component) applications. One of the benefits of high temperature operation is that active cooling may no longer be required, greatly simplifying magnet/component design. These elevated temperatures are beyond the safe operating limits of conventional OFHC copper and the epoxies that bond and insulate the turns of typical magnets. This would necessitate the use an alternative copper alloy conductor such as C18150 (CuCrZr). Coil manufacture with polyimide is very similar to conventional epoxy bonded coils. Conductors would be dry wound then impregnated with polyimide of low enough viscosity to permit saturation, then cured; similar to the vacuum pressure impregnation process used for conventional epoxy bonded coils. Representative polyimide insulated coils were mechanically tested at both room temperature and 350C. Mechanical tests included turn-to-turn shear bond strength and overall polyimide adhesion strength, as well as the flexural strength of a 48-turn polyimide-bonded coil bundle. This paper will detail the results of the testing program on coil samples. These results demonstrate mechanical properties as good, or better than epoxy bonded magnets, even at 350C.

  10. Advanced Models of LWR Pressure Vessel Embrittlement for Low Flux-HighFluence Conditions

    SciTech Connect (OSTI)

    Odette, G. Robert; Yamamoto, Takuya

    2013-06-17

    Neutron embrittlement of reactor pressure vessels (RPVs) is an unresolved issue for light water reactor life extension, especially since transition temperature shifts (TTS) must be predicted for high 80-year fluence levels up to approximately 1,020 n/cm{sup 2}, far beyond the current surveillance database. Unfortunately, TTS may accelerate at high fluence, and may be further amplified by the formation of late blooming phases that result in severe embrittlement even in low-copper (Cu) steels. Embrittlement by this mechanism is a potentially significant degradation phenomenon that is not predicted by current regulatory models. This project will focus on accurately predicting transition temperature shifts at high fluence using advanced physically based, empirically validated and calibrated models. A major challenge is to develop models that can adjust test reactor data to account for flux effects. Since transition temperature shifts depend on synergistic combinations of many variables, flux-effects cannot be treated in isolation. The best current models systematically and significantly under-predict transition temperature at high fluence, although predominantly for irradiations at much higher flux than actual RPV service. This project will integrate surveillance, test reactor and mechanism data with advanced models to address a number of outstanding RPV embrittlement issues. The effort will include developing new databases and preliminary models of flux effects for irradiation conditions ranging from very low (e.g., boiling water reactor) to high (e.g., accelerated test reactor). The team will also develop a database and physical models to help predict the conditions for the formation of Mn-Ni-Si late blooming phases and to guide future efforts to fully resolve this issue. Researchers will carry out other tasks on a best-effort basis, including prediction of transition temperature shift attenuation through the vessel wall, remediation of embrittlement by annealing, and fracture toughness master curve issues.

  11. Subterranean barriers including at least one weld

    DOE Patents [OSTI]

    Nickelson, Reva A.; Sloan, Paul A.; Richardson, John G.; Walsh, Stephanie; Kostelnik, Kevin M.

    2007-01-09

    A subterranean barrier and method for forming same are disclosed, the barrier including a plurality of casing strings wherein at least one casing string of the plurality of casing strings may be affixed to at least another adjacent casing string of the plurality of casing strings through at least one weld, at least one adhesive joint, or both. A method and system for nondestructively inspecting a subterranean barrier is disclosed. For instance, a radiographic signal may be emitted from within a casing string toward an adjacent casing string and the radiographic signal may be detected from within the adjacent casing string. A method of repairing a barrier including removing at least a portion of a casing string and welding a repair element within the casing string is disclosed. A method of selectively heating at least one casing string forming at least a portion of a subterranean barrier is disclosed.

  12. Photoactive devices including porphyrinoids with coordinating additives

    DOE Patents [OSTI]

    Forrest, Stephen R; Zimmerman, Jeramy; Yu, Eric K; Thompson, Mark E; Trinh, Cong; Whited, Matthew; Diev, Vlacheslav

    2015-05-12

    Coordinating additives are included in porphyrinoid-based materials to promote intermolecular organization and improve one or more photoelectric characteristics of the materials. The coordinating additives are selected from fullerene compounds and organic compounds having free electron pairs. Combinations of different coordinating additives can be used to tailor the characteristic properties of such porphyrinoid-based materials, including porphyrin oligomers. Bidentate ligands are one type of coordinating additive that can form coordination bonds with a central metal ion of two different porphyrinoid compounds to promote porphyrinoid alignment and/or pi-stacking. The coordinating additives can shift the absorption spectrum of a photoactive material toward higher wavelengths, increase the external quantum efficiency of the material, or both.

  13. On-Site Oxy-Lance Size Reduction of South Texas Project Reactor Vessel Heads - 12324

    SciTech Connect (OSTI)

    Posivak, Edward [WMG, inc. (United States); Keeney, Gilbert; Wheeler, Dean [Shaw Group (United States)

    2012-07-01

    On-Site Oxy-Lance size reduction of mildly radioactive large components has been accomplished at other operating plants. On-Site Oxy-Lance size reduction of more radioactive components like Reactor Vessel Heads had previously been limited to decommissioning projects. Building on past decommissioning and site experience, subcontractors for South Texas Project Nuclear Operating Company (STPNOC) developed an innovative integrated system to control smoke, radioactive contamination, worker dose, and worker safety. STP's innovative, easy to use CEDM containment that provided oxy lance access, smoke control, and spatter/contamination control was the key to successful segmentation for cost-effective and ALARA packaging and transport for disposal. Relative to CEDM milling, STP oxy-lance segmentation saved approximately 40 person- REM accrued during 9,000 hours logged into the radiological controlled area (RCA) during more than 3,800 separate entries. Furthermore there were no personnel contamination events or respiratory uptakes of radioactive material during the course of the entire project. (authors)

  14. Power generation method including membrane separation

    DOE Patents [OSTI]

    Lokhandwala, Kaaeid A. (Union City, CA)

    2000-01-01

    A method for generating electric power, such as at, or close to, natural gas fields. The method includes conditioning natural gas containing C.sub.3+ hydrocarbons and/or acid gas by means of a membrane separation step. This step creates a leaner, sweeter, drier gas, which is then used as combustion fuel to run a turbine, which is in turn used for power generation.

  15. Rotor assembly including superconducting magnetic coil

    DOE Patents [OSTI]

    Snitchler, Gregory L. (Shrewsbury, MA); Gamble, Bruce B. (Wellesley, MA); Voccio, John P. (Somerville, MA)

    2003-01-01

    Superconducting coils and methods of manufacture include a superconductor tape wound concentrically about and disposed along an axis of the coil to define an opening having a dimension which gradually decreases, in the direction along the axis, from a first end to a second end of the coil. Each turn of the superconductor tape has a broad surface maintained substantially parallel to the axis of the coil.

  16. Nuclear reactor shield including magnesium oxide

    DOE Patents [OSTI]

    Rouse, Carl A. (Del Mar, CA); Simnad, Massoud T. (La Jolla, CA)

    1981-01-01

    An improvement in nuclear reactor shielding of a type used in reactor applications involving significant amounts of fast neutron flux, the reactor shielding including means providing structural support, neutron moderator material, neutron absorber material and other components as described below, wherein at least a portion of the neutron moderator material is magnesium in the form of magnesium oxide either alone or in combination with other moderator materials such as graphite and iron.

  17. Electric power monthly, September 1990. [Glossary included

    SciTech Connect (OSTI)

    Not Available

    1990-12-17

    The purpose of this report is to provide energy decision makers with accurate and timely information that may be used in forming various perspectives on electric issues. The power plants considered include coal, petroleum, natural gas, hydroelectric, and nuclear power plants. Data are presented for power generation, fuel consumption, fuel receipts and cost, sales of electricity, and unusual occurrences at power plants. Data are compared at the national, Census division, and state levels. 4 figs., 52 tabs. (CK)

  18. Reactor Vessel Removal: Improving Performance Big Rock Point Lessons Learned

    SciTech Connect (OSTI)

    Daly, P.T. [BNG America, D and D Operations, 804 South Illinois Avenue, Oak Ridge, TN 37830 (United States)

    2006-07-01

    The Big Rock Point (BRP) reactor vessel was successfully removed, packaged in a Type B shipping container, transported, and buried. The process took almost 4 years of work by many people and a variety of companies. This paper will discuss several areas that can reduce schedule time, resulting in reduced cost and employee dose exposure. For maximum cost effectiveness, these lessons should be applied during the planning stages when developing baseline cost and schedule, As Low As Reasonably Achievable (ALARA) budgets, and work processes. (authors)

  19. Vessel eddy current measurement for the National Spherical Torus Experiment

    SciTech Connect (OSTI)

    Gates, D.A.; Menard, J.E.; Marsala, R.J. [Princeton Plasma Physics Laboratory, P.O. Box 451, Princeton, New Jersey 08543 (United States)

    2004-12-01

    A simple analog circuit that measures the National Spherical Torus Experiment (NSTX) axisymmetric eddy current distribution has been designed and constructed. It is based on simple circuit model of the NSTX vacuum vessel that was calibrated using a special axisymmetric eddy current code which was written so that accuracy was maintained in the vicinity of the current filaments [J. Menard, J. Fusion Tech. (to be published)]. The measurement and the model have been benchmarked against data from numerous vacuum shots and they are in excellent agreement. This is an important measurement that helps give more accurate equilibrium reconstructions.

  20. Linear and multilinear fractional operators: weighted inequalities, sharp bounds, and other properties

    E-Print Network [OSTI]

    Moen, Kabe

    2009-04-27

    In this work we consider various fractional operators, including the classical fractional integral operators, related fractional maximal functions, multilinear fractional integral operators, and multisublinear fractional ...

  1. A VIRTUAL OPERATING SYSTEM

    E-Print Network [OSTI]

    Hall, Dennis E.

    2013-01-01

    Unix time-sharing operating system. D. Hall, D. Scherrer, J.Prentice~Hall, Hansen, "Operating System Principles", Inc. ,of California. A Virtual Operating System Dennis E. Hall

  2. Formal Specification of Operating System Operations

    E-Print Network [OSTI]

    Black, Paul E.

    Formal Specification of Operating System Operations Dan Zhou Department of Computer Science.black@nist.gov This paper describes the development of a formal specification for a secure operating system architecture operations. We also provide a uniform environment for system commands that change the security state

  3. A simplified model for red cell dynamics in small blood vessels

    E-Print Network [OSTI]

    Piero Olla

    1998-11-20

    A simple mechanism for the confinement of red cells in the middle of narrow blood vessels is proposed. In the presence of a quadratic shear, red cells deform in such a way to loose fore-aft symmetry and to achieve a fixed orientation with respect to the flow. This leads to a drift away from the vessel walls, when the vessel diameter goes below a critical value depending on the viscoelastic properties and the dimensions of the cell.

  4. Thin film application device and method for coating small aperture vacuum vessels

    SciTech Connect (OSTI)

    Walters, Dean R; Este, Grantley O

    2015-01-27

    A device and method for coating an inside surface of a vessel is provided. In one embodiment, a coating device comprises a power supply and a diode in electrical communication with the power supply, wherein electrodes comprising the diode reside completely within the vessel. The method comprises reversibly sealing electrodes in a vessel, sputtering elemental metal or metal compound on the surface while maintaining the surface in a controlled atmosphere.

  5. 2/3/2015 ACJ Operations Management

    E-Print Network [OSTI]

    Tipple, Brett

    2/3/2015 ACJ Operations Management Overview Operations Management involves working within process flows, enhancing output quality, and managing the supply chain. Careers for majors include working in service and manufacturing firms to manage the transformation of inputs into outputs. The operations

  6. The power of simplification: Operator interface with the AP1000{sup R} during design-basis and beyond design-basis events

    SciTech Connect (OSTI)

    Williams, M. G.; Mouser, M. R.; Simon, J. B.

    2012-07-01

    The AP1000{sup R} plant is an 1100-MWe pressurized water reactor with passive safety features and extensive plant simplifications that enhance construction, operation, maintenance, safety and cost. The passive safety features are designed to function without safety-grade support systems such as component cooling water, service water, compressed air or HVAC. The AP1000 passive safety features achieve and maintain safe shutdown in case of a design-basis accident for 72 hours without need for operator action, meeting the expectations provided in the European Utility Requirements and the Utility Requirement Document for passive plants. Limited operator actions may be required to maintain safe conditions in the spent fuel pool (SFP) via passive means. This safety approach therefore minimizes the reliance on operator action for accident mitigation, and this paper examines the operator interaction with the Human-System Interface (HSI) as the severity of an accident increases from an anticipated transient to a design basis accident and finally, to a beyond-design-basis event. The AP1000 Control Room design provides an extremely effective environment for addressing the first 72 hours of design-basis events and transients, providing ease of information dissemination and minimal reliance upon operator actions. Symptom-based procedures including Emergency Operating Procedures (EOPs), Abnormal Operating Procedures (AOPs) and Alarm Response Procedures (ARPs) are used to mitigate design basis transients and accidents. Use of the Computerized Procedure System (CPS) aids the operators during mitigation of the event. The CPS provides cues and direction to the operators as the event progresses. If the event becomes progressively worse or lasts longer than 72 hours, and depending upon the nature of failures that may have occurred, minimal operator actions may be required outside of the control room in areas that have been designed to be accessible using components that have been designed to be reliable in these conditions. The primary goal of any such actions is to maintain or refill the passive inventory available to cool the core, containment and spent fuel pool in the safety-related and seismically qualified Passive Containment Cooling Water Storage Tank (PCCWST). The seismically-qualified, ground-mounted Passive Containment Cooling Ancillary Water Storage Tank (PCCAWST) is also available for this function as appropriate. The primary effect of these actions would be to increase the coping time for the AP1000 during design basis events, as well as events such as those described above, from 72 hours without operator intervention to 7 days with minimal operator actions. These Operator actions necessary to protect the health and safety of the public are addressed in the Post-72 Hour procedures, as well as some EOPs, AOPs, ARPs and the Severe Accident Management Guidelines (SAMGs). Should the event continue to become more severe and plant conditions degrade further with indications of inadequate core cooling, the SAMGs provide guidance for strategies to address these hypothetical severe accident conditions. The AP1000 SAMG diagnoses and actions are prioritized to first utilize the AP1000 features that are expected to retain a damaged core inside the reactor vessel. Only one strategy is undertaken at any time. This strategy will be followed and its effectiveness evaluated before other strategies are undertaken. This is a key feature of both the symptom-oriented AP1000 EOPs and the AP1000 SAMGs which maximizes the probability of retaining a damaged core inside the reactor vessel and containment while minimizing the chances for confusion and human errors during implementation. The AP1000 SAMGs are simple and straight-forward and have been developed with considerable input from human factors and plant operations experts. Most importantly, and different from severe accident management strategies for other plants, the AP1000 SAMGs do not require diagnosis of the location of the core (i.e., whether reactor vessel failure has occurred). This is a fun

  7. Optical panel system including stackable waveguides

    DOE Patents [OSTI]

    DeSanto, Leonard (Dunkirk, MD); Veligdan, James T. (Manorville, NY)

    2007-11-20

    An optical panel system including stackable waveguides is provided. The optical panel system displays a projected light image and comprises a plurality of planar optical waveguides in a stacked state. The optical panel system further comprises a support system that aligns and supports the waveguides in the stacked state. In one embodiment, the support system comprises at least one rod, wherein each waveguide contains at least one hole, and wherein each rod is positioned through a corresponding hole in each waveguide. In another embodiment, the support system comprises at least two opposing edge structures having the waveguides positioned therebetween, wherein each opposing edge structure contains a mating surface, wherein opposite edges of each waveguide contain mating surfaces which are complementary to the mating surfaces of the opposing edge structures, and wherein each mating surface of the opposing edge structures engages a corresponding complementary mating surface of the opposite edges of each waveguide.

  8. Thermovoltaic semiconductor device including a plasma filter

    DOE Patents [OSTI]

    Baldasaro, Paul F. (Clifton Park, NY)

    1999-01-01

    A thermovoltaic energy conversion device and related method for converting thermal energy into an electrical potential. An interference filter is provided on a semiconductor thermovoltaic cell to pre-filter black body radiation. The semiconductor thermovoltaic cell includes a P/N junction supported on a substrate which converts incident thermal energy below the semiconductor junction band gap into electrical potential. The semiconductor substrate is doped to provide a plasma filter which reflects back energy having a wavelength which is above the band gap and which is ineffectively filtered by the interference filter, through the P/N junction to the source of radiation thereby avoiding parasitic absorption of the unusable portion of the thermal radiation energy.

  9. Simple Model of Membrane Proteins Including Solvent

    E-Print Network [OSTI]

    D. L. Pagan; A. Shiryayev; T. P. Connor; J. D. Gunton

    2006-03-04

    We report a numerical simulation for the phase diagram of a simple two dimensional model, similar to one proposed by Noro and Frenkel [J. Chem. Phys. \\textbf{114}, 2477 (2001)] for membrane proteins, but one that includes the role of the solvent. We first use Gibbs ensemble Monte Caro simulations to determine the phase behavior of particles interacting via a square-well potential in two dimensions for various values of the interaction range. A phenomenological model for the solute-solvent interactions is then studied to understand how the fluid-fluid coexistence curve is modified by solute-solvent interactions. It is shown that such a model can yield systems with liquid-liquid phase separation curves that have both upper and lower critical points, as well as closed loop phase diagrams, as is the case with the corresponding three dimensional model.

  10. High-pressure Storage Vessels for Hydrogen, Natural Gas and Hydrogen-Natural Gas Blends

    Broader source: Energy.gov [DOE]

    These slides were presented at the International Hydrogen Fuel and Pressure Vessel Forum on September 27 – 29, 2010, in Beijing, China.

  11. Nuclear reactor having a polyhedral primary shield and removable vessel insulation

    DOE Patents [OSTI]

    Ekeroth, D.E.; Orr, R.

    1993-12-07

    A nuclear reactor is provided having a generally cylindrical reactor vessel disposed within an opening in a primary shield. The opening in the primary shield is defined by a plurality of generally planar side walls forming a generally polyhedral-shaped opening. The reactor vessel is supported within the opening in the primary shield by reactor vessel supports which are in communication and aligned with central portions of some of the side walls. The reactor vessel is connected to the central portions of the reactor vessel supports. A thermal insulation polyhedron formed from a plurality of slidably insertable and removable generally planar insulation panels substantially surrounds at least a portion of the reactor vessel and is disposed between the reactor vessel and the side walls of the primary shield. The shape of the insulation polyhedron generally corresponds to the shape of the opening in the primary shield. Reactor monitoring instrumentation may be mounted in the corners of the opening in the primary shield between the side walls and the reactor vessel such that insulation is not disposed between the instrumentation and the reactor vessel. 5 figures.

  12. Nuclear reactor having a polyhedral primary shield and removable vessel insulation

    DOE Patents [OSTI]

    Ekeroth, Douglas E. (Delmont, PA); Orr, Richard (Pittsburgh, PA)

    1993-01-01

    A nuclear reactor is provided having a generally cylindrical reactor vessel disposed within an opening in a primary shield. The opening in the primary shield is defined by a plurality of generally planar side walls forming a generally polyhedral-shaped opening. The reactor vessel is supported within the opening in the primary shield by reactor vessel supports which are in communication and aligned with central portions of some of the side walls. The reactor vessel is connected to the central portions of the reactor vessel supports. A thermal insulation polyhedron formed from a plurality of slidably insertable and removable generally planar insulation panels substantially surrounds at least a portion of the reactor vessel and is disposed between the reactor vessel and the side walls of the primary shield. The shape of the insulation polyhedron generally corresponds to the shape of the opening in the primary shield. Reactor monitoring instrumentation may be mounted in the corners of the opening in the primary shield between the side walls and the reactor vessel such that insulation is not disposed between the instrumentation and the reactor vessel.

  13. R&D of Large Stationary Hydrogen/CNG/HCNG Storage Vessels

    Broader source: Energy.gov [DOE]

    These slides were presented at the International Hydrogen Fuel and Pressure Vessel Forum on September 27 – 29, 2010, in Beijing, China.

  14. A LITERATURE REVIEW ON DURABILITY EVALUATION OF CRANKSHAFTS INCLUDING COMPARISONS OF COMPETING

    E-Print Network [OSTI]

    Fatemi, Ali

    such as residual stresses on fatigue behavior and methods of their production in crankshafts. The common crankshaft to their durability performance. This is followed by a discussion of durability assessment procedures used. The operating sources include oil absence, defective lubrication on journals, high operating oil temperature

  15. Optical Measurement Technologies for High Temperature, Radiation Exposure, and Corrosive Environments—Significant Activities and Findings: In-vessel Optical Measurements for Advanced SMRs

    SciTech Connect (OSTI)

    Anheier, Norman C.; Cannon, Bret D.; Qiao, Hong (Amy) [Amy; Suter, Jonathan D.

    2012-09-01

    Development of advanced Small Modular Reactors (aSMRs) is key to providing the United States with a sustainable, economically viable, and carbon-neutral energy source. The aSMR designs have attractive economic factors that should compensate for the economies of scale that have driven development of large commercial nuclear power plants to date. For example, aSMRs can be manufactured at reduced capital costs in a factory and potentially shorter lead times and then be shipped to a site to provide power away from large grid systems. The integral, self-contained nature of aSMR designs is fundamentally different than conventional reactor designs. Future aSMR deployment will require new instrumentation and control (I&C) architectures to accommodate the integral design and withstand the extreme in-vessel environmental conditions. Operators will depend on sophisticated sensing and machine vision technologies that provide efficient human-machine interface for in-vessel telepresence, telerobotic control, and remote process operations. The future viability of aSMRs is dependent on understanding and overcoming the significant technical challenges involving in-vessel reactor sensing and monitoring under extreme temperatures, pressures, corrosive environments, and radiation fluxes

  16. Hydro-ball in-core instrumentation system and method of operation

    DOE Patents [OSTI]

    Tower, Stephen N. (Washington Township, Westmoreland County, PA); Veronesi, Luciano (O'Hara Township, Allegheny County, PA); Braun, Howard E. (Pittsburgh, PA)

    1990-01-01

    A hydro-ball in-core instrumentation system employs detector strings each comprising a wire having radiation sensitive balls affixed diametrically at spaced positions therealong and opposite tip ends of which are transportable by fluid drag through interior passageways. In the passageways primary coolant is caused to flow selectively in first and second opposite directions for transporting the detector strings from stored positions in an exterior chamber to inserted positions within the instrumentation thimbles of the fuel rod assemblies of a pressure vessel, and for return. The coolant pressure within the detector passageways is the same as that within the vessel; face contact, disconnectable joints between sections of the interior passageways within the vessel facilitate assembly and disassembly of the vessel for refueling and routine maintenance operations. The detector strings may pass through a very short bend radius thereby minimizing space requirements for the connections of the instrumentation system to the vessel and concomitantly the vessel containment structure. Improved radiation mapping and a significant reduction in potential exposure of personnel to radiation are provided. Both top head and bottom head penetration embodiments are disclosed.

  17. Preliminary Risk Assessment Associated with IGSCC of BWR Vessel Internals

    SciTech Connect (OSTI)

    A. Ware; K. Morton; M. Nitzel; N. Chokshi; T-Y. Chang

    1999-08-01

    BWR core shrouds and other reactor internals important to safety are experiencing intergranular stress corrosion cracking (IGSCC). The United States Nuclear Regulatory Commission (NRC) has followed the problem, and as part of its investigations, contracted with the Idaho National Engineering and Environmental Laboratory (INEEL) to conduct a risk assessment. The overall project objective is to assess the potential consequences and risks associated with the failure of IGSCC-susceptible BWR vessel internals, with specific consideration given to potential cascading and common mode effects. The paper presents an overview of the program, discusses the results of a preliminary qualitative assessment, and summarizes a simplified risk assessment that was conducted on sequences resulting from failures of jet pump components of a BWR/4 plant.

  18. The behavior of shallow flaws in reactor pressure vessels

    SciTech Connect (OSTI)

    Rolfe, S.T. (Kansas Univ., Lawrence, KS (United States))

    1991-11-01

    Both analytical and experimental studies have shown that the effect of crack length, a, on the elastic-plastic toughness of structural steels is significant. The objective of this report is to recommend those research investigations that are necessary to understand the phenomenon of shallow behavior as it affects fracture toughness so that the results can be used properly in the structural margin assessment of reactor pressure vessels (RPVs) with flaws. Preliminary test results of A 533 B steel show an elevated crack-tip-opening displacement (CTOD) toughness similar to that observed for structural steels tested at the University of Kansas. Thus, the inherent resistance to fracture initiation of A 533 B steel with shallow flaws appears to be higher than that used in the current American Society of Mechanical Engineers (ASME) design curves based on testing fracture mechanics specimens with deep flaws. If this higher toughness of laboratory specimens with shallow flaws can be transferred to a higher resistance to failure in RPV design or analysis, then the actual margin of safety in nuclear vessels with shallow flaws would be greater than is currently assumed on the basis of deep-flaw test results. This elevation in toughness and greater resistance to fracture would be a very desirable situation, particularly for the pressurized-thermal shock (PTS) analysis in which shallow flaws are assumed to exist. Before any advantage can be taken of this possible increase in initiation toughness, numerous factors must be analyzed to ensure the transferability of the data. This report reviews those factors and makes recommendations of studies that are needed to assess the transferability of shallow-flaw toughness test results to the structural margin assessment of RPV with shallow flaws. 14 refs., 8 figs.

  19. NSTX Weekly Report (June 18, 2010) FY 2010 NSTX plasma operations

    E-Print Network [OSTI]

    Princeton Plasma Physics Laboratory

    as well as dual probe lithium evaporation. Commissioning of new coil protection circuitry and the integrated system testing required for combined PF4 and PF5 coil operation were successfully completed on the vessel next week for a period of extended lithium evaporation in preparation for an upcoming Liquid

  20. NSTX Weekly Report (June 11, 2010) FY 2010 NSTX plasma operations

    E-Print Network [OSTI]

    Princeton Plasma Physics Laboratory

    heating, as well as dual probe lithium evaporation. The lithium (LITER) probe in the Bay F #12;position vacuum vessel. Operations resumed on Friday June 11 after the elevated leakage current issue was cleared. Also this week, a peer review of the new tangential FIDA diagnostic was held. Access to the NSTX test

  1. NSTX Weekly Report (May 28, 2010) FY 2010 NSTX plasma operations

    E-Print Network [OSTI]

    Princeton Plasma Physics Laboratory

    in NSTX" by J.-W. Ahn (ORNL). Both talks were well received. Fourteen poster presentations were given Lithium Evaporation onto the NSTX Vessel Walls" by D. Stotler, "Macroscopic Motion of Liquid Metal Plasma operations resumed this past week after completion of combined field power testing, leading to the successful

  2. Defense waste processing facility radioactive operations. Part 1 - operating experience

    SciTech Connect (OSTI)

    Little, D.B.; Gee, J.T.; Barnes, W.M.

    1997-12-31

    The Savannah River Site`s Defense Waste Processing Facility (DWPF) near Aiken, SC is the nation`s first and the world`s largest vitrification facility. Following a ten year construction program and a 3 year non-radioactive test program, DWPF began radioactive operations in March 1996. This paper presents the results of the first 9 months of radioactive operations. Topics include: operations of the remote processing equipment reliability, and decontamination facilities for the remote processing equipment. Key equipment discussed includes process pumps, telerobotic manipulators, infrared camera, Holledge{trademark} level gauges and in-cell (remote) cranes. Information is presented regarding equipment at the conclusion of the DWPF test program it also discussed, with special emphasis on agitator blades and cooling/heating coil wear. 3 refs., 4 figs.

  3. Electra-optical device including a nitrogen containing electrolyte

    DOE Patents [OSTI]

    Bates, J.B.; Dudney, N.J.; Gruzalski, G.R.; Luck, C.F.

    1995-10-03

    Described is a thin-film battery, especially a thin-film microbattery, and a method for making same having application as a backup or primary integrated power source for electronic devices. The battery includes a novel electrolyte which is electrochemically stable and does not react with the lithium anode and a novel vanadium oxide cathode. Configured as a microbattery, the battery can be fabricated directly onto a semiconductor chip, onto the semiconductor die or onto any portion of the chip carrier. The battery can be fabricated to any specified size or shape to meet the requirements of a particular application. The battery is fabricated of solid state materials and is capable of operation between {minus}15 C and 150 C.

  4. Electra-optical device including a nitrogen containing electrolyte

    DOE Patents [OSTI]

    Bates, John B. (Oak Ridge, TN); Dudney, Nancy J. (Knoxville, TN); Gruzalski, Greg R. (Oak Ridge, TN); Luck, Christopher F. (Knoxville, TN)

    1995-01-01

    Described is a thin-film battery, especially a thin-film microbattery, and a method for making same having application as a backup or primary integrated power source for electronic devices. The battery includes a novel electrolyte which is electrochemically stable and does not react with the lithium anode and a novel vanadium oxide cathode Configured as a microbattery, the battery can be fabricated directly onto a semiconductor chip, onto the semiconductor die or onto any portion of the chip carrier. The battery can be fabricated to any specified size or shape to meet the requirements of a particular application. The battery is fabricated of solid state materials and is capable of operation between -15.degree. C. and 150.degree. C.

  5. Fuel cell repeater unit including frame and separator plate

    SciTech Connect (OSTI)

    Yamanis, Jean; Hawkes, Justin R; Chiapetta, Jr., Louis; Bird, Connie E; Sun, Ellen Y; Croteau, Paul F

    2013-11-05

    An example fuel cell repeater includes a separator plate and a frame establishing at least a portion of a flow path that is operative to communicate fuel to or from at least one fuel cell held by the frame relative to the separator plate. The flow path has a perimeter and any fuel within the perimeter flow across the at least one fuel cell in a first direction. The separator plate, the frame, or both establish at least one conduit positioned outside the flow path perimeter. The conduit is outside of the flow path perimeter and is configured to direct flow in a second, different direction. The conduit is fluidly coupled with the flow path.

  6. Minoan Vessels with Figure-Eight Shields: Antecedents to the Knossos Throneroom Alabastra

    E-Print Network [OSTI]

    Rehak, Paul

    1992-01-01

    stream_size 10 stream_content_type text/plain stream_name Rehak_VesselsFig8.pdf.txt stream_source_info Rehak_VesselsFig8.pdf.txt Content-Encoding ISO-8859-1 Content-Type text/plain; charset=ISO-8859-1 ...

  7. Southwest Research Institute (SwRI) designs, analyzes, and fabricates pressure vessels

    E-Print Network [OSTI]

    Chapman, Clark R.

    vessels using: n ASME B&PV Code, Section VIII, Division 1 n ASME B&PV Code, Section VIII, Division 2 n ASME B&PV Code, Section VIII, Division 3 n ASME Pressure Vessels for Human Occupancy n American Bureau for the Design, Fabrication, and Erection of Structural Steel for Buildings" n Fabrication n ASME B&PV Code

  8. Lasers in Surgery and Medicine 44:144151 (2012) Photocoagulation of Dermal Blood Vessels With Multiple

    E-Print Network [OSTI]

    Choi, Bernard

    2012-01-01

    exposure (RE), pulse repetition rate (fr), total number of pulses (np), and length of vessel irradiated­22]. Histological evaluation of laser-irradiated normal and PWS skin revealed that MLP induced coagulation of deeper were varied. Blood vessels in the window were irradiated with either SLP with RE of 4­7 J/cm2 or MLP

  9. NEUTRON DAMAGE IN REACTOR PRESSURE-VESSEL STEEL EXAMINED WITH POSITRON ANNIHILATION LIFETIME SPECTROSCOPY

    E-Print Network [OSTI]

    Motta, Arthur T.

    annealing the samples at 280' C. INTRODUCTION Reactor pressure-vessel steel embrittlement is one ofthe mostNEUTRON DAMAGE IN REACTOR PRESSURE-VESSEL STEEL EXAMINED WITH POSITRON ANNIHILATION LIFETIME spectroscopy to study the development of damage and annealing behavior ofneutron-irradiated reactor pressure

  10. Estimated Impacts on Ex-Vessel Brown Shrimp Prices and Value as a Result of the

    E-Print Network [OSTI]

    Estimated Impacts on Ex-Vessel Brown Shrimp Prices and Value as a Result of the Texas Closure Regulation JOHN R. POFFENBERGER Introduction Changes in commodity prices may result from any regulatory shrimp landings in Texas and therefore could be expected to affect ex-vessel or dockside prices

  11. On Chip Implementation of a Pixel-Parallel Approach for Retinal Vessel Tree Extraction

    E-Print Network [OSTI]

    Dudek, Piotr

    On Chip Implementation of a Pixel-Parallel Approach for Retinal Vessel Tree Extraction C. Alonso Univ. A Coru~na. SPAIN mgpenedo@udc.es Abstract-- Retinal vessel tree extraction from angiography applications. From the image processing point of view, many algorithms and strategies have been developed

  12. Transportation System Concept of Operations

    SciTech Connect (OSTI)

    N. Slater-Thompson

    2006-08-16

    The Nuclear Waste Policy Act of 1982 (NWPA), as amended, authorized the DOE to develop and manage a Federal system for the disposal of SNF and HLW. OCRWM was created to manage acceptance and disposal of SNF and HLW in a manner that protects public health, safety, and the environment; enhances national and energy security; and merits public confidence. This responsibility includes managing the transportation of SNF and HLW from origin sites to the Repository for disposal. The Transportation System Concept of Operations is the core high-level OCRWM document written to describe the Transportation System integrated design and present the vision, mission, and goals for Transportation System operations. By defining the functions, processes, and critical interfaces of this system early in the system development phase, programmatic risks are minimized, system costs are contained, and system operations are better managed, safer, and more secure. This document also facilitates discussions and understanding among parties responsible for the design, development, and operation of the Transportation System. Such understanding is important for the timely development of system requirements and identification of system interfaces. Information provided in the Transportation System Concept of Operations includes: the functions and key components of the Transportation System; system component interactions; flows of information within the system; the general operating sequences; and the internal and external factors affecting transportation operations. The Transportation System Concept of Operations reflects OCRWM's overall waste management system policies and mission objectives, and as such provides a description of the preferred state of system operation. The description of general Transportation System operating functions in the Transportation System Concept of Operations is the first step in the OCRWM systems engineering process, establishing the starting point for the lower level descriptions. of subsystems and components, and the Transportation System Requirements Document. Other program and system documents, plans, instructions, and detailed designs will be consistent with and informed by the Transportation System Concept of Operations. The Transportation System Concept of Operations is a living document, enduring throughout the OCRWM systems engineering lifecycle. It will undergo formal approval and controlled revisions as appropriate while the Transportation System matures. Revisions will take into account new policy decisions, new information available through system modeling, engineering investigations, technical analyses and tests, and the introduction of new technologies that can demonstrably improve system performance.

  13. Ionic liquids, electrolyte solutions including the ionic liquids, and energy storage devices including the ionic liquids

    DOE Patents [OSTI]

    Gering, Kevin L.; Harrup, Mason K.; Rollins, Harry W.

    2015-12-08

    An ionic liquid including a phosphazene compound that has a plurality of phosphorus-nitrogen units and at least one pendant group bonded to each phosphorus atom of the plurality of phosphorus-nitrogen units. One pendant group of the at least one pendant group comprises a positively charged pendant group. Additional embodiments of ionic liquids are disclosed, as are electrolyte solutions and energy storage devices including the embodiments of the ionic liquid.

  14. Blood Vessel Normalization in the Hamster Oral Cancer Model for Experimental Cancer Therapy Studies

    SciTech Connect (OSTI)

    Ana J. Molinari; Romina F. Aromando; Maria E. Itoiz; Marcela A. Garabalino; Andrea Monti Hughes; Elisa M. Heber; Emiliano C. C. Pozzi; David W. Nigg; Veronica A. Trivillin; Amanda E. Schwint

    2012-07-01

    Normalization of tumor blood vessels improves drug and oxygen delivery to cancer cells. The aim of this study was to develop a technique to normalize blood vessels in the hamster cheek pouch model of oral cancer. Materials and Methods: Tumor-bearing hamsters were treated with thalidomide and were compared with controls. Results: Twenty eight hours after treatment with thalidomide, the blood vessels of premalignant tissue observable in vivo became narrower and less tortuous than those of controls; Evans Blue Dye extravasation in tumor was significantly reduced (indicating a reduction in aberrant tumor vascular hyperpermeability that compromises blood flow), and tumor blood vessel morphology in histological sections, labeled for Factor VIII, revealed a significant reduction in compressive forces. These findings indicated blood vessel normalization with a window of 48 h. Conclusion: The technique developed herein has rendered the hamster oral cancer model amenable to research, with the potential benefit of vascular normalization in head and neck cancer therapy.

  15. Design and fabrication of the vacuum vessel for the Advanced Toroidal Facility

    SciTech Connect (OSTI)

    Chipley, K.K.; Frey, G.N.

    1985-01-01

    The vacuum vessel for the Advanced Toroidal Facility (ATF) is a heavily contoured and very complex formed vessel that is specifically designed to allow for maximum plasma volume in a pure stellarator arrangement. The design of the facility incorporates an internal vessel that is closely fitted to the two helical field coils following the winding law theta = 1/6phi. Metallic seals have been incorporated throughout the system to minimize impurities. The vessel has been fabricated utilizing a comprehensive set of tooling fixtures specifically designed for the task of forming 6-mm stainless steel plate to the complex shape. Computer programs were used to develop a series of ribs that essentially form an internal mold of the vessel. Plates were press-formed with multiple compound curves, fitted to the fixture, and joined with full-penetration welds. 7 refs., 8 figs.

  16. Method of operating a thermoelectric generator

    DOE Patents [OSTI]

    Reynolds, Michael G; Cowgill, Joshua D

    2013-11-05

    A method for operating a thermoelectric generator supplying a variable-load component includes commanding the variable-load component to operate at a first output and determining a first load current and a first load voltage to the variable-load component while operating at the commanded first output. The method also includes commanding the variable-load component to operate at a second output and determining a second load current and a second load voltage to the variable-load component while operating at the commanded second output. The method includes calculating a maximum power output of the thermoelectric generator from the determined first load current and voltage and the determined second load current and voltage, and commanding the variable-load component to operate at a third output. The commanded third output is configured to draw the calculated maximum power output from the thermoelectric generator.

  17. Design Of JET ELM Control Coils For Operation At 350 C

    SciTech Connect (OSTI)

    Zatz, I J; Brooks, A; Cole, M; Neilson, G H; Lowry, C; Mardenfeld, M; Omran, H; Thompson, V; Todd, T

    2010-09-20

    A study has confirmed the feasibility of designing, fabricating and installing resonant magnetic field perturbation (RMP) coils in JET1 with the objective of controlling edge localized modes (ELM). A system of two rows of in-vessel coils, above the machine midplane, has been chosen as it not only can investigate the physics of and achieve the empirical criteria for ELM suppression, but also permits variation of the spectra allowing for comparison with other experiments. These coils present several engineering challenges. Conditions in JET necessitate the installation of these coils via remote handling, which will impose weight, dimensional and logistical limitations. And while the encased coils are designed to be conventionally wound and bonded, they will not have the usual benefit of active cooling. Accordingly, coil temperatures are expected to reach 350 C during bakeout as well as during plasma operations. These elevated temperatures are beyond the safe operating limits of conventional OFHC copper and the epoxies that bond and insulate the turns of typical coils. This has necessitated the use of an alternative copper alloy conductor C18150 (CuCrZr). More importantly, an alternative to epoxy had to be found. An R&D program was initiated to find the best available insulating and bonding material. The search included polyimides and ceramic polymers. The scope and status of this R&D program, as well as the critical engineering issues encountered to date are reviewed and discussed.

  18. Performing a local barrier operation

    DOE Patents [OSTI]

    Archer, Charles J; Blocksome, Michael A; Ratterman, Joseph D; Smith, Brian E

    2014-03-04

    Performing a local barrier operation with parallel tasks executing on a compute node including, for each task: retrieving a present value of a counter; calculating, in dependence upon the present value of the counter and a total number of tasks performing the local barrier operation, a base value, the base value representing the counter's value prior to any task joining the local barrier; calculating, in dependence upon the base value and the total number of tasks performing the local barrier operation, a target value of the counter, the target value representing the counter's value when all tasks have joined the local barrier; joining the local barrier, including atomically incrementing the value of the counter; and repetitively, until the present value of the counter is no less than the target value of the counter: retrieving the present value of the counter and determining whether the present value equals the target value.

  19. Performing a local barrier operation

    DOE Patents [OSTI]

    Archer, Charles J; Blocksome, Michael A; Ratterman, Joseph D; Smith, Brian E

    2014-03-04

    Performing a local barrier operation with parallel tasks executing on a compute node including, for each task: retrieving a present value of a counter; calculating, in dependence upon the present value of the counter and a total number of tasks performing the local barrier operation, a base value of the counter, the base value representing the counter's value prior to any task joining the local barrier; calculating, in dependence upon the base value and the total number of tasks performing the local barrier operation, a target value, the target value representing the counter's value when all tasks have joined the local barrier; joining the local barrier, including atomically incrementing the value of the counter; and repetitively, until the present value of the counter is no less than the target value of the counter: retrieving the present value of the counter and determining whether the present value equals the target value.

  20. Helpful Hints for Operating Schools 

    E-Print Network [OSTI]

    McClure, J. D.; Schreppler, S.; Cliver, R. E.

    2004-01-01

    operations program. This paper will discuss helpful hints that schools can use to maintain a proper building environment and save energy at the same time. Two case studies will also be included. The first is the TEAMS program, developed by Carrollton...