National Library of Energy BETA

Sample records for rectangular pressure vessel

  1. 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;...

  2. 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...

  3. 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.

  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. 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.

  6. 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.

  7. 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.

  8. 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.

  9. 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.

  10. 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.

  11. 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.

  12. 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...

  13. 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.

  14. 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.

  15. 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.

  16. (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.

  17. 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

  18. 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

  19. 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.

  20. 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.

  1. 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...

  2. 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

  3. 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.

  4. 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

  5. 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

  6. 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.

  7. 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.

  8. 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.

  9. 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

  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

    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

  11. 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).

  12. High pressure ejection of melt from a reactor pressure vessel. The discharge phase. Revision 7

    SciTech Connect (OSTI)

    Pilch, M.; Tarbell, W.M.

    1985-09-01

    Recent probabilistic risk-assessment studies identified potential accident sequences in which reactor vessel failure occurs while the primary system is at elevated pressure. The phenomenology of the discharge phase is reviewed here. We propose an improved model for hole ablation following vessel failure, and we compare the model with experiment data. Gas blowthrough is identified as a mechanism that allows steam to escape through the vessel breach before melt ejection is complete. Gas blowthrough leads to pneumatic atomization of the remaining melt before significant depressurization of the primary system occurs.

  13. 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.

  14. 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.

  15. 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

  16. 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.

  17. 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.

  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. 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.

  20. Creep of A508/533 Pressure Vessel Steel

    SciTech Connect (OSTI)

    Richard Wright

    2014-08-01

    ABSTRACT Evaluation of potential Reactor Pressure Vessel (RPV) steels has been carried out as part of the pre-conceptual Very High Temperature Reactor (VHTR) design studies. These design studies have generally focused on American Society of Mechanical Engineers (ASME) Code status of the steels, temperature limits, and allowable stresses. Initially, three candidate materials were identified by this process: conventional light water reactor (LWR) RPV steels A508 and A533, 2¼Cr-1Mo in the annealed condition, and Grade 91 steel. The low strength of 2¼Cr-1Mo at elevated temperature has eliminated this steel from serious consideration as the VHTR RPV candidate material. Discussions with the very few vendors that can potentially produce large forgings for nuclear pressure vessels indicate a strong preference for conventional LWR steels. This preference is based in part on extensive experience with forging these steels for nuclear components. It is also based on the inability to cast large ingots of the Grade 91 steel due to segregation during ingot solidification, thus restricting the possible mass of forging components and increasing the amount of welding required for completion of the RPV. Grade 91 steel is also prone to weld cracking and must be post-weld heat treated to ensure adequate high-temperature strength. There are also questions about the ability to produce, and very importantly, verify the through thickness properties of thick sections of Grade 91 material. The availability of large components, ease of fabrication, and nuclear service experience with the A508 and A533 steels strongly favor their use in the RPV for the VHTR. Lowering the gas outlet temperature for the VHTR to 750°C from 950 to 1000°C, proposed in early concept studies, further strengthens the justification for this material selection. This steel is allowed in the ASME Boiler and Pressure Vessel Code for nuclear service up to 371°C (700°F); certain excursions above that temperature are allowed by Code Case N-499-2 (now incorporated as an appendix to Section III Division 5 of the Code). This Code Case was developed with a rather sparse data set and focused primarily on rolled plate material (A533 specification). Confirmatory tests of creep behavior of both A508 and A533 are described here that are designed to extend the database in order to build higher confidence in ensuring the structural integrity of the VHTR RPV during off-normal conditions. A number of creep-rupture tests were carried out at temperatures above the 371°C (700°F) Code limit; longer term tests designed to evaluate minimum creep behavior are ongoing. A limited amount of rupture testing was also carried out on welded material. All of the rupture data from the current experiments is compared to historical values from the testing carried out to develop Code Case N-499-2. It is shown that the A508/533 basemetal tested here fits well with the rupture behavior reported from the historical testing. The presence of weldments significantly reduces the time to rupture. The primary purpose of this report is to summarize and record the experimental results in a single document.

  1. 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

  2. A DISLOCATION-BASED CLEAVAGE INITIATION MODEL FOR PRESSURE VESSEL

    SciTech Connect (OSTI)

    Cochran, Kristine B; Erickson, Marjorie A; Williams, Paul T; Klasky, Hilda B; Bass, Bennett Richard

    2012-01-01

    Efforts are under way to develop a theoretical, multi-scale model for the prediction of fracture toughness of ferritic steels in the ductile-to-brittle transition temperature (DBTT) region that accounts for temperature, irradiation, strain rate, and material condition (chemistry and heat treatment) effects. This new model is intended to address difficulties associated with existing empirically-derived models of the DBTT region that cannot be extrapolated to conditions for which data are unavailable. Dislocation distribution equations, derived from the theories of Yokobori et al., are incorporated to account for the local stress state prior to and following initiation of a microcrack from a second-phase particle. The new model is the basis for the DISlocation-based FRACture (DISFRAC) computer code being developed at the Oak Ridge National Laboratory (ORNL). The purpose of this code is to permit fracture safety assessments of ferritic structures with only tensile properties required as input. The primary motivation for the code is to assist in the prediction of radiation effects on nuclear reactor pressure vessels, in parallel with the EURATOM PERFORM 60 project.

  3. 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.

  4. 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.

  5. 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...

  6. 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.

  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. Hydrogen degradation and microstructural effects of the near-threshold fatigue resistance of pressure vessel steels

    E-Print Network [OSTI]

    Fuquen-Molano, Rosendo

    1982-01-01

    Safety of pressure vessels for applications such as coal conversion reactors requires understanding of the mechanism of environmentally-induced crack propagation and the mechanism by which process-induced microstructures ...

  9. Stress and Fracture Mechanics Analyses of Boiling Water Reactor and Pressurized Water Reactor Pressure Vessel Nozzles

    SciTech Connect (OSTI)

    Yin, Shengjun; Bass, Bennett Richard; Stevens, Gary; Kirk, Mark

    2011-01-01

    This paper describes stress analysis and fracture mechanics work performed to assess boiling water reactor (BWR) and pressurized water reactor (PWR) nozzles located in the reactor pressure vessel (RPV) adjacent to the core beltline region. Various RPV nozzle geometries were investigated: 1. BWR recirculation outlet nozzle; 2. BWR core spray nozzle3 3. PWR inlet nozzle; ; 4. PWR outlet nozzle; and 5. BWR partial penetration instrument nozzle. The above nozzle designs 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-license (EOL) to require evaluation as part of establishing the allowed limits on heatup, cooldown, and hydrotest (leak test) conditions. These nozzles analyzed represent one each of the nozzle types potentially requiring evaluation. The purpose of the analyses performed on these nozzle designs was as follows: To model and understand differences in pressure and thermal stress results using a two-dimensional (2-D) axi-symmetric finite element model (FEM) versus a three-dimensional (3-D) FEM for all nozzle types. In particular, the ovalization (stress concentration) effect of two intersecting cylinders, which is typical of RPV nozzle configurations, was investigated; To verify the accuracy of a selected linear elastic fracture mechanics (LEFM) hand solution for stress intensity factor for a postulated nozzle corner crack for both thermal and pressure loading for all nozzle types; To assess the significance of attached piping loads on the stresses in the nozzle corner region; and To assess the significance of applying pressure on the crack face with respect to the stress intensity factor for a postulated nozzle corner crack.

  10. DOE H2 Program Annual Review, 5-20-2003 Insulated Pressure Vessels for

    E-Print Network [OSTI]

    range. J. We are generating tank performance data. K. Testing BOP components. L. Low venting losses) car, km 0 1 2 3 4 5 hydrogenlosses,kg low-pressure LH2 tank MLVSI insulated pressure vessel fueled with LH2 LH2 80 K CH2 1998: thermodynamic analysis 1999: cryogenic cycling 2001: DOT/ISO Tests 2003

  11. Development of a thin wall graphite/polyimide composite pressure vessel with a large aspect ratio

    SciTech Connect (OSTI)

    LaJeunesse, C.A.; Trinh, K.V.; Bartel, J.J.; Spingarn, J.R.

    1988-10-01

    A graphite/polyimide composite pressure vessel has been developed to contain corrosive gas mixtures up to 400 psig and 300/degree/F. The goal of this research project was to develop a lightweight, thin-walled, composite pressure vessel with an l/d aspect ratio of 42 capable of containing hydrogen fluoride (HF) and chlorine trifluoride (ClF/sub 3/). The vessel was to have a crown radius approaching infinity, a desired knuckle radius approaching zero, and a desired wall thickness of 0.023 in. In this paper the problems encountered and the iterative solutions in addition to the design, analysis, and fabrication of the vessel are presented. 3 refs., 14 figs., 2 tabs.

  12. 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.

  13. 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)

  14. Cryogenic Pressure Vessels: Progress and Plans | Department of Energy

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum Based| Department of Energy Whole-Home Gas8of EnergyHydrogenPressure

  15. Walking and Climbing Service Robots for Safety Inspection of Nuclear Reactor Pressure Vessels

    E-Print Network [OSTI]

    Chen, Sheng

    Walking and Climbing Service Robots for Safety Inspection of Nuclear Reactor Pressure Vessels B of Electronics and Computer Science, University of Southampton, Southampton, UK Abstract: Nuclear reactor and the usefulness of these robots for improving safety inspection of nuclear reactors in general are discussed

  16. 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

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

    E-Print Network [OSTI]

    Proceedings of PVP2006-ICPVT-11 2006 ASME Pressure Vessels and Piping Division Conference July 23 response leading to large deformations. Some issues in measurement technique and validation testing are then presented. The importance of wave reflection from bends, valves and dead ends is discussed, as well

  18. A Multiscale Modeling Approach to Analyze Filament-Wound Composite Pressure Vessels

    SciTech Connect (OSTI)

    Nguyen, Ba Nghiep; Simmons, Kevin L.

    2013-07-22

    A multiscale modeling approach to analyze filament-wound composite pressure vessels is developed in this article. The approach, which extends the Nguyen et al. model [J. Comp. Mater. 43 (2009) 217] developed for discontinuous fiber composites to continuous fiber ones, spans three modeling scales. The microscale considers the unidirectional elastic fibers embedded in an elastic-plastic matrix obeying the Ramberg-Osgood relation and J2 deformation theory of plasticity. The mesoscale behavior representing the composite lamina is obtained through an incremental Mori-Tanaka type model and the Eshelby equivalent inclusion method [Proc. Roy. Soc. Lond. A241 (1957) 376]. The implementation of the micro-meso constitutive relations in the ABAQUS® finite element package (via user subroutines) allows the analysis of a filament-wound composite pressure vessel (macroscale) to be performed. Failure of the composite lamina is predicted by a criterion that accounts for the strengths of the fibers and of the matrix as well as of their interface. The developed approach is demonstrated in the analysis of a filament-wound pressure vessel to study the effect of the lamina thickness on the burst pressure. The predictions are favorably compared to the numerical and experimental results by Lifshitz and Dayan [Comp. Struct. 32 (1995) 313].

  19. 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.

  20. Inspection and recertification of gas filled composite pressure vessels using acoustic emission

    SciTech Connect (OSTI)

    Mitchell, J.R.; Temowchek, S.J. [Physical Acoustics Corp., Lawrenceville, NJ (United States)

    1998-12-31

    Corrosion resistance and light weight have made composite materials the best choice for many high pressure gas applications. However, progress has been hampered by the limitations of traditional NDT inspection methods and lack of understanding about failure mechanisms. One solution which has emerged is the use of Acoustic Emission to monitor the composite pressure vessel during periodic proof tests. The emission generated can be used to determine the existence of hidden mechanical defects and corrosion which may have significantly lowered the burst strength. A data base of over 4,000 NGV (natural gas vehicle) containers will be used to exemplify the usefulness of the method.

  1. 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.

  2. 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.

  3. 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.

  4. D-Zero Central Calorimeter Technical Appendix to Cryogenic Pressure Vessels

    SciTech Connect (OSTI)

    Mulholland, G.T.; Rucinski, R.A.; /Fermilab

    1990-11-19

    DO (D Zero) is a large Liquid Argon (LAr) HEP Calorimeter designed to function in the laboratories P-Pbar collider at the DO section of the Tevatron accelerator. It contains 5,000 gls. of LAr in the CC cryostat, and 3,000 gls. in each of two, a north and south, EC cryostats. These low pressure vessels are filled with detector modules built of stainless steel, copper and depleted uranium. The LAr functions as the ionization medium, and the spatial and temporal of the collection of the charge of the electrons produced signals the passsage of charged particles. The collection of these charges in 4 pi is related to the energy of the particles, and their measurement is called calorimetry. The contained LAr (T=90K) is isolated from the ambient temperatures in specially designed, vacuum and superinsulated, vessels (cryostats) provided with liquid nitrogen, heat of vaporization, cooling.

  5. 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.

  6. The criteria of fracture in the case of the leak of pressure vessels

    SciTech Connect (OSTI)

    Habil; Ziliukas, A.

    1997-04-01

    In order to forecast the break of the high pressure vessels and the network of pipes in a nuclear reactor, according to the concept of leak before break of pressure vessels, it is necessary to analyze the conditions of project, production, and mounting quality as well as of exploitation. It is also necessary to evaluate the process of break by the help of the fracture criteria. In the Ignalina Nuclear Power Plant of, in Lithuania, the most important objects of investigation are: the highest pressure pipes, made of Japanese steel 19MN5 and having an anticorrosive austenitic: coal inside, the pipes of distribution, which arc made of 08X1810T steel. The steel of the network of pipes has a quality of plasticity: therefore the only criteria of fragile is impossible to apply to. The process of break would be best described by the universal criteria of elastic - plastic fracture. For this purpose the author offers the criterion of the double parameter.

  7. Supplementary neutron-flux calculations for the ORNL Pool Critical Assembly Pressure Vessel Facility

    SciTech Connect (OSTI)

    Maudlin, P.J.; Maerker, R.E.

    1982-01-01

    A three-dimensional Monte Carlo calculation using the MORSE code was performed to validate a procedure previously adopted in the ORNL discrete ordinate analysis of measurements made in the ORNL Pool Critical Assembly Pressure Vessel Facility. The results of these flux calculations agree, within statistical undertainties of about 5%, with those obtained from a discrete ordinate analysis employing the same procedure. This study therefore concludes that the procedure for combining several one- and two-dimensional discrete ordinate calculations into a three-dimensional flux is sufficiently accurate that it does not account for the existing discrepancies observed between calculations and measurements in this facility.

  8. Review of the Palisades pressure vessel accumulated fluence estimate and of the least squares methodology employed

    SciTech Connect (OSTI)

    Griffin, P.J.

    1998-05-01

    This report provides a review of the Palisades submittal to the Nuclear Regulatory Commission requesting endorsement of their accumulated neutron fluence estimates based on a least squares adjustment methodology. This review highlights some minor issues in the applied methodology and provides some recommendations for future work. The overall conclusion is that the Palisades fluence estimation methodology provides a reasonable approach to a {open_quotes}best estimate{close_quotes} of the accumulated pressure vessel neutron fluence and is consistent with the state-of-the-art analysis as detailed in community consensus ASTM standards.

  9. 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.

  10. Stress-intensity-factor influence coefficients for semielliptical inner-surface flaws in clad pressure vessels

    SciTech Connect (OSTI)

    Keeney, J.A.; Bryson, J.W.

    1995-12-31

    A problem of particular interest in pressure vessel technology is the calculation of accurate stress-intensity factors for semielliptical surface cracks in cylinders. Computing costs for direct solution techniques can be prohibitive when applied to three-dimensional (3-D) geometries with time-varying boundary conditions such as those associated with pressurized thermal shock. An alternative superposition technique requires the calculation of a set of influence coefficients for a given 3-D crack model that can be superimposed to obtain mode-I stress-intensity factors. This paper presents stress-intensity-factor influence coefficients (SIFICs) for axially and circumferentially oriented finite-length semielliptical inner-surface flaws with aspect ratios (total crack length (2c) to crack depth (a)) of 2, 6, and 10 for clad cylinders having an internal radius to wall thickness (t) ratio of 10. SIFICs are computed for flaw depths in the range of 0.01 {le} a/t {le} 0.5 and two cladding thicknesses. The incorporate of this SIFIC data base in fracture mechanics codes will facilitate the generation of fracture mechanics solutions for a wide range of flaw geometries as may be required in structural integrity assessments of pressurized-water and boiling-water reactors.

  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. 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.

  14. Evolution of Nickel-Manganese-Silicon Dominated Phases in Highly Irradiated Reactor Pressure Vessel Steels

    SciTech Connect (OSTI)

    Peter B Wells; Yuan Wu; Tim Milot; G. Robert Odette; Takuya Yamamoto; Brandon Miller; James Cole

    2014-11-01

    Formation of a high density of Ni-Mn-Si nm-scale precipitates in irradiated reactor pressure vessel steels, both with and without Cu, could lead to severe embrittlement. Models long ago predicted that these precipitates, which are not treated in current embrittlement regulations, would emerge only at high fluence. However, the mechanisms and variables that control Ni-Mn- Si precipitate formation, and their detailed characteristics, have not been well understood. High flux irradiations of six steels with systematic variations in Cu and Ni were carried out at ˜ 295±5°C to high and very high neutron fluences of ˜ 1.3x1020 and 1.1x1021 n/cm2. Atom probe tomography (APT) shows that significant mole fractions of these precipitates form in the Cu bearing steels at ˜ 1.3x1020 n/cm2, while they are only beginning to develop in Cu-free steels. However, large mole fractions, far in excess of those found in previous studies, are observed at 1.1x1021 n/cm2 at all Cu levels. The precipitates diffract, and in one case are compositionally and structurally consistent with the Mn6Ni16Si7 G-phase. At the highest fluence, the large precipitate mole fractions primarily depend on the steel Ni content, rather than Cu, and lead to enormous strength increases up to about 700 MPa. The implications of these results to light water reactor life extension are discussed briefly.

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

    SciTech Connect (OSTI)

    J. K. Wright; R. N. Wright

    2008-04-01

    The U.S. Department of Energy has selected the High Temperature Gas-cooled Reactor design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production. It will have an outlet gas temperature in the range of 900°C and a plant 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-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. The NGNP Materials Research and Development Program is responsible for performing research and development on likely NGNP materials in support of the NGNP design, licensing, and construction activities. 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. Studies of potential Reactor Pressure Vessel (RPV) steels have been carried out as part of the pre-conceptual design studies. These design studies generally focus on American Society of Mechanical Engineers (ASME) Code status of the steels, temperature limits, and allowable stresses. Three realistic candidate materials have been identified by this process: conventional light water reactor RPV steels A508/533, 2¼Cr-1Mo in the annealed condition, and modified 9Cr 1Mo ferritic martenistic steel. Based on superior strength and higher temperature limits, the modified 9Cr-1Mo steel has been identified by the majority of design engineers as the preferred choice for the RPV. All of the vendors have concluded, however, that with adequate engineered cooling of the vessel, the A508/533 steels are also acceptable.

  16. 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...

  17. TECHNICAL BASIS AND APPLICATION OF NEW RULES ON FRACTURE CONTROL OF HIGH PRESSURE HYDROGEN VESSEL IN ASME SECTION VIII, DIVISION 3 CODE

    SciTech Connect (OSTI)

    Rawls, G

    2007-04-30

    As a part of an ongoing activity to develop ASME Code rules for the hydrogen infrastructure, the ASME Boiler and Pressure Vessel Code Committee approved new fracture control rules for Section VIII, Division 3 vessels in 2006. These rules have been incorporated into new Article KD-10 in Division 3. The new rules require determining fatigue crack growth rate and fracture resistance properties of materials in high pressure hydrogen gas. Test methods have been specified to measure these fracture properties, which are required to be used in establishing the vessel fatigue life. An example has been given to demonstrate the application of these new rules.

  18. Prediction and Monitoring Systems of Creep-Fracture Behavior of 9Cr-1Mo Steels for Teactor Pressure Vessels

    SciTech Connect (OSTI)

    Potirniche, Gabriel; Barlow, Fred D.; Charit, Indrajit; Rink, Karl

    2013-11-26

    A recent workshop on next-generation nuclear plant (NGNP) topics underscored the need for research studies on the creep fracture behavior of two materials under consideration for reactor pressure vessel (RPV) applications: 9Cr-1Mo and SA-5XX steels. This research project will provide a fundamental understanding of creep fracture behavior of modified 9Cr-1Mo steel welds for through modeling and experimentation and will recommend a design for an RPV structural health monitoring system. Following are the specific objectives of this research project: • Characterize metallurgical degradation in welded modified 9Cr-1Mo steel resulting from aging processes and creep service conditions. • Perform creep tests and characterize the mechanisms of creep fracture process. • Quantify how the microstructure degradation controls the creep strength of welded steel specimens. • Perform finite element (FE) simulations using polycrystal plasticity to understand how grain texture affects the creep fracture properties of welds. • Develop a microstructure-based creep fracture model to estimate RPVs service life . • Manufacture small, prototypic, cylindrical pressure vessels, subject them to degradation by aging, and measure their leak rates. • Simulate damage evolution in creep specimens by FE analyses. • Develop a model that correlates gas leak rates from welded pressure vessels with the amount of microstructural damage. • Perform large-scale FE simulations with a realistic microstructure to evaluate RPV performance at elevated temperatures and creep strength. • Develop a fracture model for the structural integrity of RPVs subjected to creep loads. • Develop a plan for a non-destructive structural health monitoring technique and damage detection device for RPVs.

  19. Creep behavior of a nuclear pressure vessel under severe accident conditions

    SciTech Connect (OSTI)

    Beghini, M.; Bertini, L.; Vitale, E.

    1996-12-31

    The results of a study on the creep behavior of the vessel lower head under severe accident conditions are reported. An experimental program aimed at the evaluation of the creep properties of A533grB steel at high temperature (800--1,100 C) and under biaxial loading is summarized and the main results reported. A Finite Element simulation of the lower head under severe accident conditions allows to show the effect of the main parameters affecting the time to rupture.

  20. The influence of selected containment structures on debris dispersal and transport following high pressure melt ejection from the reactor vessel

    SciTech Connect (OSTI)

    Pilch, M.; Tarbell, W.W.; Brockmann, J.E.

    1988-09-01

    High pressure expulsion of molten core debris from the reactor pressure vessel may result in dispersal of the debris from the reactor cavity. In most plants, the cavity exits into the containment such that the debris impinges on structures. Retention of the debris on the structures may affect the further transport of the debris throughout the containment. Two tests were done with scaled structural shapes placed at the exit of 1:10 linear scale models of the Zion cavity. The results show that the debris does not adhere significantly to structures. The lack of retention is attributed to splashing from the surface and reentrainment in the gas flowing over the surface. These processes are shown to be applicable to reactor scale. A third experiment was done to simulate the annular gap between the reactor vessel and cavity wall. Debris collection showed that the fraction of debris exiting through the gap was greater than the gap-to-total flow area ratio. Film records indicate that dispersal was primarily by entrainment of the molten debris in the cavity. 29 refs., 36 figs., 11 tabs.

  1. Effect of silicon on ultra-low temperature toughness of Nb–Ti microalloyed cryogenic pressure vessel steels

    SciTech Connect (OSTI)

    Qiu, J.A. [Hubei Collaborative Innovation Center for Advanced Steels, International Research Institute for Steel Technology, Wuhan University of Science and Technology, Wuhan 430081 (China); Wu, K.M., E-mail: wukaiming2000@yahoo.com [Hubei Collaborative Innovation Center for Advanced Steels, International Research Institute for Steel Technology, Wuhan University of Science and Technology, Wuhan 430081 (China); Li, J.H. [Hubei Collaborative Innovation Center for Advanced Steels, International Research Institute for Steel Technology, Wuhan University of Science and Technology, Wuhan 430081 (China); Research and Development Center of WISCO, Wuhan 430080 (China); Hodgson, P.D. [Hubei Collaborative Innovation Center for Advanced Steels, International Research Institute for Steel Technology, Wuhan University of Science and Technology, Wuhan 430081 (China); Institute for Frontier Materials, Deakin University, Geelong, Victoria 3220 (Australia); Hou, T.P. [Hubei Collaborative Innovation Center for Advanced Steels, International Research Institute for Steel Technology, Wuhan University of Science and Technology, Wuhan 430081 (China); Ding, Q.F. [Research and Development Center of WISCO, Wuhan 430080 (China)

    2013-09-15

    The effect of Si on the ultra-low temperature toughness of Nb–Ti microalloyed cryogenic pressure vessel steels was investigated by electron back-scattered diffraction and transmission electron microscope with energy dispersive spectroscopy. Equiaxed ferrite and bainite were obtained in the tempered steels with small Si additions. Nanosized Nb–Ti carbides (< 10 nm) were formed in the steel containing 0.05% Si, whereas much coarser carbides (> 30 nm) were found in the steel containing 0.47% Si. The ultra-low temperature toughness of the Nb–Ti microalloyed cryogenic pressure vessel steel was remarkably enhanced by the reduction in the Si content, which was attributed to the pre-existing iron carbide formation before the precipitation of nanosized Nb–Ti carbides during tempering. - Highlights: • Nanosized Nb-Ti carbides formed in the tempered steel with smaller Si addition. • Coarser Nb-Ti carbides formed in the tempered steel with more Si addition. • Pre-existing cememtites provide nucleation sites for Nb-Ti carbide precipitation. • Ultra-low temperature toughness was remarkably enhanced by Si content reduction.

  2. Potential high fluence response of pressure vessel internals constructed from austenitic stainless steels

    SciTech Connect (OSTI)

    Garner, F.A.; Greenwood, L.R. [Pacific Northwest Lab., Richland, WA (United States); Harrod, D.L. [Westinghouse Electric Corp., Pensacola, FL (United States)

    1993-08-01

    Many of the in-core components in pressurized water reactors are constructed of austenitic stainless steels. The potential behavior of these components can be predicted using data on similar steels irradiated at much higher displacement rates in liquid-metal reactors or water-cooled mixed-spectrum reactors. Consideration of the differences between the pressurized water environment and that of the other reactors leads to the conclusion that significant amounts of void swelling, irradiation creep, and embrittlement will occur in some components, and that the level of damage per atomic displacement may be larger in the pressurized water environment.

  3. Safety Evaluation Report: Development of Improved Composite Pressure Vessels for Hydrogen Storage, Lincoln Composites, Lincoln, NE, May 25, 2010

    SciTech Connect (OSTI)

    Fort, III, William C.; Kallman, Richard A.; Maes, Miguel; Skolnik, Edward G.; Weiner, Steven C.

    2010-12-22

    Lincoln Composites operates a facility for designing, testing, and manufacturing composite pressure vessels. Lincoln Composites also has a U.S. Department of Energy (DOE)-funded project to develop composite tanks for high-pressure hydrogen storage. The initial stage of this project involves testing the permeation of high-pressure hydrogen through polymer liners. The company recently moved and is constructing a dedicated research/testing laboratory at their new location. In the meantime, permeation tests are being performed in a corner of a large manufacturing facility. The safety review team visited the Lincoln Composites site on May 25, 2010. The project team presented an overview of the company and project and took the safety review team on a tour of the facility. The safety review team saw the entire process of winding a carbon fiber/resin tank on a liner, installing the boss and valves, and curing and painting the tank. The review team also saw the new laboratory that is being built for the DOE project and the temporary arrangement for the hydrogen permeation tests.

  4. 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.

  5. Experimental results of direct containment heating by high-pressure melt ejection into the Surtsey vessel: The DCH-3 and DCH-4 tests

    SciTech Connect (OSTI)

    Allen, M.D.; Pilch, M.; Brockmann, J.E.; Tarbell, W.W. (Sandia National Labs., Albuquerque, NM (United States)); Nichols, R.T. (Ktech Corp., Albuquerque, NM (United States)); Sweet, D.W. (AEA Technology, Winfrith (United Kingdom))

    1991-08-01

    Two experiments, DCH-3 and DCH-4, were performed at the Surtsey test facility to investigate phenomena associated with a high-pressure melt ejection (HPME) reactor accident sequence resulting in direct containment heating (DCH). These experiments were performed using the same experimental apparatus with identical initial conditions, except that the Surtsey test vessel contained air in DCH-3 and argon in DCH-4. Inerting the vessel with argon eliminated chemical reactions between metallic debris and oxygen. Thus, a comparison of the pressure response in DCH-3 and DCH-4 gave an indication of the DCH contribution due to metal/oxygen reactions. 44 refs., 110 figs., 43 tabs.

  6. Behavior of core debris ejected from a pressurized vessel into scaled reactor cavities

    SciTech Connect (OSTI)

    Tarbell, W.W.; Pilch, M.; Brockmann, J.E.

    1984-01-01

    Results from four recent 1:10 scale experiments are presented along with analyses of the possible consequences for plant geometries. The tests cover a range in initial system pressure from 4 to 12 MPa, with either dry or water-filled cavities. Nearly all of the core debris is dispersed from the cavity with less than five percent (5%) of the original mass found adhered to the exposed cavity surfaces. Those tests involving water in the cavity show the water being expelled as a slug ahead of the dispersed melt. Models for the interaction of the ejected core debris with the containment atmosphere show that both thermal and chemical energy is liberated from the debris. The calculated pressurization from direct heating of the containment atmosphere can threaten even the most robust containments. Models and experiments are currently being devised to study the possible mitigating effects of the above-cavity structures.

  7. Pressure and concentration dependences of the autoignition temperature for normal butane + air mixtures in a closed vessel

    SciTech Connect (OSTI)

    Chandraratna, M.R.; Griffiths, J.F. . School of Chemistry)

    1994-12-01

    The condition at which autoignition occurs in lean premixed n-butane + air mixtures over the composition range 0.2%--2.5% n-butane by volume (0.06 < [phi] < 0.66) were investigated experimentally. Total reactant pressure from 0.1 to 0.6 MPa (1--6 atm) were studied in a spherical, stainless-steel, closed vessel (0.5 dm[sup 3]). There is a critical transition from nonignition to ignition, at pressures above 0.1 MPa, as the mixture is enriched in the vicinity of 1% fuel vapor by volume. There is also a region of multiplicity, which exhibits three critical temperatures at a given composition. Chemical analyses show that partially oxygenated components,including many o-heterocyclic compounds, are important products of the lean combustion of butane at temperatures up to 800 K. The critical conditions for autoignition are discussed with regard to industrial ignition hazards, especially in the context of the autoignition temperature of alkanes given by ASTM or BS tests. The differences between the behavior of n-butane and the higher n-alkanes are explained. The experimental results are also used as a basis for testing a reduced kinetic model to represent the oxidation and autoignition of n-butane or other alkanes.

  8. Enhancements of a Combustion Vessel to Determine Laminar Flame Speeds of Hydrocarbon Blends with Helium Dilution at Elevated Temperatures and Pressures 

    E-Print Network [OSTI]

    Plichta, Drew

    2013-04-03

    speeds were those of methane, ethane, and propane fuel blends, as well as pure methane, at an elevated pressure of 5 atm and temperatures of 298 and 473 K, using a constant-volume, cylindrical combustion vessel. The current Aramco mechanism developed...

  9. Roadmap for Nondestructive Evaluation of Reactor Pressure Vessel Research and Development by the Light Water Reactor Sustainability Program

    SciTech Connect (OSTI)

    Smith, Cyrus M [ORNL; Nanstad, Randy K [ORNL; Clayton, Dwight A [ORNL; Matlack, Katie [Georgia Institute of Technology; Ramuhalli, Pradeep [Pacific Northwest National Laboratory (PNNL); Light, Glenn [Southwest Research Institute, San Antonio

    2012-09-01

    The Department of Energy s (DOE) Light Water Reactor Sustainability (LWRS) Program is a five year effort which works to develop the fundamental scientific basis to understand, predict, and measure changes in materials and systems, structure, and components as they age in environments associated with continued long-term operations of existing commercial nuclear power reactors. This year, the Materials Aging and Degradation (MAaD) Pathway of this program has placed emphasis on emerging Non-Destructive Evaluation (NDE) methods which support these objectives. DOE funded Research and Development (R&D) on emerging NDE techniques to support commercial nuclear reactor sustainability is expected to begin next year. This summer, the MAaD Pathway invited subject matter experts to participate in a series of workshops which developed the basis for the research plan of these DOE R&D NDE activities. This document presents the results of one of these workshops which are the DOE LWRS NDE R&D Roadmap for Reactor Pressure Vessels (RPV). These workshops made a substantial effort to coordinate the DOE NDE R&D with that already underway or planned by the Electric Power Research Institute (EPRI) and the Nuclear Regulatory Commission (NRC) through their representation at these workshops.

  10. Critical Heat Flux in Inclined Rectangular Narrow Gaps

    SciTech Connect (OSTI)

    Jeong J. Kim; Yong H. Kim; Seong J. Kim; Sang W. Noh; Kune Y. Suh; Joy L. Rempe; Fan-Bill Cheung; Sang B. Kim

    2004-06-01

    In light of the TMI-2 accident, in which the reactor vessel lower head survived the attack by molten core material, the in-vessel retention strategy was suggested to benefit from cooling the debris through a gap between the lower head and the core material. The GAMMA 1D (Gap Apparatus Mitigating Melt Attack One Dimensional) tests were conducted to investigate the critical heat flux (CHF) in narrow gaps with varying surface orientations. The CHF in an inclined gap, especially in case of the downward-facing narrow gap, is dictated by bubble behavior because the departing bubbles are squeezed. The orientation angle affects the bubble layer and escape of the bubbles from the narrow gap. The test parameters include gap sizes of 1, 2, 5 and 10 mm and the open periphery, and the orientation angles range from the fully downward-facing (180o) to the vertical (90o) position. The 15 ×35 mm copper test section was electrically heated by the thin film resistor on the back. The heater assembly was installed to the tip of the rotating arm in the heated water pool at the atmospheric pressure. The bubble behavior was photographed utilizing a high-speed camera through the Pyrex glass spacer. It was observed that the CHF decreased as the surface inclination angle increased and as the gap size decreased in most of the cases. However, the opposing results were obtained at certain surface orientations and gap sizes. Transition angles, at which the CHF changed in a rapid slope, were also detected, which is consistent with the existing literature. A semi-empirical CHF correlation was developed for the inclined narrow rectangular channels through dimensional analysis. The correlation provides with best-estimate CHF values for realistically assessing the thermal margin to failure of the lower head during a severe accident involving relocation of the core material.

  11. Random rectangular Graphs

    E-Print Network [OSTI]

    Estrada, Ernesto

    2015-01-01

    A generalization of the random geometric graph (RGG) model is proposed by considering a set of points uniformly and independently distributed on a rectangle of unit area instead of on a unit square \\left[0,1\\right]^{2}. The topological properties, such as connectivity, average degree, average path length and clustering, of the random rectangular graphs (RRGs) generated by this model are then studied as a function of the rectangle sides lengths a and b=1/a, and the radius r used to connect the nodes. When a=1 we recover the RGG, and when a\\rightarrow\\infty the very elongated rectangle generated resembles a one-dimensional RGG. We provided computational and analytical evidence that the topological properties of the RRG differ significantly from those of the RGG. The connectivity of the RRG depends not only on the number of nodes as in the case of the RGG, but also on the side length of the rectangle. As the rectangle is more elongated the critical radius for connectivity increases following first a power-law an...

  12. Specifications for the development of BUGLE-93: An ENDF/B-VI multigroup cross section library for LWR shielding and pressure vessel dosimetry

    SciTech Connect (OSTI)

    White, J.E.; Wright, R.Q.; Roussin, R.W.; Ingersoll, D.T.

    1992-11-01

    This report discusses specifications which have been developed for a new multigroup cross section library based on ENDF/B-VI data for light water reactor shielding and reactor pressure vessel dosimetry applications. The resulting broad-group library and an intermediate fine-group library are defined by the specifications provided in this report. Processing ENDF/B-VI into multigroup format for use in radiation transport codes will provide radiation shielding analysts with the most currently available nuclear data. it is expected that the general nature of the specifications will be useful in other applications such as reactor physics.

  13. Method and structure for cache aware transposition via rectangular...

    Office of Scientific and Technical Information (OSTI)

    via rectangular subsections A method and structure for transposing a rectangular matrix A in a computer includes subdividing the rectangular matrix A into one or more square...

  14. Evidence for neutron irradiation-induced metallic precipitates in model alloys and pressure-vessel weld steel

    E-Print Network [OSTI]

    Motta, Arthur T.

    -vessel weld steel Stephen E. Cumblidge a , Arthur T. Motta a,*, Gary L. Catchen a , Gerhard Brauer b , Juurgen-irradiated model alloys (1 · 1023 n/m2 , E > 0:5 MeV) and 73W-weld steel (to 1.8 · 1023 n/m2 , E > 1 Me examined in the as-irradiated state and after post-irradiation isochronal anneals to temperature up to 600

  15. Comparison of MELCOR modeling techniques and effects of vessel water injection on a low-pressure, short-term, station blackout at the Grand Gulf Nuclear Station

    SciTech Connect (OSTI)

    Carbajo, J.J.

    1995-06-01

    A fully qualified, best-estimate MELCOR deck has been prepared for the Grand Gulf Nuclear Station and has been run using MELCOR 1.8.3 (1.8 PN) for a low-pressure, short-term, station blackout severe accident. The same severe accident sequence has been run with the same MELCOR version for the same plant using the deck prepared during the NUREG-1150 study. A third run was also completed with the best-estimate deck but without the Lower Plenum Debris Bed (BH) Package to model the lower plenum. The results from the three runs have been compared, and substantial differences have been found. The timing of important events is shorter, and the calculated source terms are in most cases larger for the NUREG-1150 deck results. However, some of the source terms calculated by the NUREG-1150 deck are not conservative when compared to the best-estimate deck results. These results identified some deficiencies in the NUREG-1150 model of the Grand Gulf Nuclear Station. Injection recovery sequences have also been simulated by injecting water into the vessel after core relocation started. This marks the first use of the new BH Package of MELCOR to investigate the effects of water addition to a lower plenum debris bed. The calculated results indicate that vessel failure can be prevented by injecting water at a sufficiently early stage. No pressure spikes in the vessel were predicted during the water injection. The MELCOR code has proven to be a useful tool for severe accident management strategies.

  16. Influence of long-term thermal aging on the microstructural evolution of nuclear reactor pressure vessel materials: An atom probe study

    SciTech Connect (OSTI)

    Pareige, P.; Russell, K.F.; Stoller, R.E.; Miller, M.K. [Oak Ridge National Lab., TN (United States)

    1998-03-01

    Atom probe field ion microscopy (APFIM) investigations of the microstructure of unaged (as-fabricated) and long-term thermally aged ({approximately} 100,000 h at 280 C) surveillance materials from commercial reactor pressure vessel steels were performed. This combination of materials and conditions permitted the investigation of potential thermal-aging effects. This microstructural study focused on the quantification of the compositions of the matrix and carbides. The APFIM results indicate that there was no significant microstructural evolution after a long-term thermal exposure in weld, plate, or forging materials. The matrix depletion of copper that was observed in weld materials was consistent with the copper concentration in the matrix after the stress-relief heat treatment. The compositions of cementite carbides aged for 100,000 h were compared with the Thermocalc{trademark} prediction. The APFIM comparisons of materials under these conditions are consistent with the measured change in mechanical properties such as the Charpy transition temperature.

  17. 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.

  18. Evaluation on the Feasibility of Using Ultrasonic Testing of Reactor Pressure Vessel Welds for Assessing Flaw Density/Distribution per 10 CFR 50.61a, Alternate Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock

    SciTech Connect (OSTI)

    Sullivan, Edmund J.; Anderson, Michael T.

    2014-06-10

    This technical letter report provides the status of an assessment undertaken by PNNL at the request of the NRC to verify the capability of periodic ASME-required volumetric examinations of reactor vessels to characterize the density and distribution of flaws of interest for applying §50.61a on a plant-by-plant basis. The PTS rule, described in the Code of Federal Regulations, Title 10, Section 50.61 (§50.61), "Fracture Toughness Requirements for Protection against Pressurized Thermal Shock Events," establishes screening criteria to ensure that the potential for a reactor vessel to fail due to a PTS event is deemed to be acceptably low. Recently, the NRC completed a research program that concluded that the risk of through-wall cracking due to a PTS event is much lower than previously estimated. The NRC subsequently developed and promulgated an alternate PTS rule, §50.61a, that can be implemented by PWR licensees. The §50.61a rule differs from §50.61 in that it requires licensees who choose to follow this alternate method to analyze the results from periodic volumetric examinations required by the ASME Code, Section XI, Rules for Inservice Inspection (ISI) of Nuclear Power Plants.

  19. Measurements of wall heat (mass) transfer for flow through blockages with round and square holes in a wide rectangular channel 

    E-Print Network [OSTI]

    Cervantes, Joel

    2002-01-01

    Naphthalene sublimation and pressure measurement experiments were conducted to study heat (mass) transfer enhancement by blockages with staggered round and square holes for turbulent air flows through the holes in the blockages in an 8:1 rectangular...

  20. Particle Imaging Velocimetry Technique Development for Laboratory Measurement of Fracture Flow Inside a Pressure Vessel Using Neutron Imaging

    SciTech Connect (OSTI)

    Polsky, Yarom; Bingham, Philip R; Bilheux, Hassina Z; Carmichael, Justin R

    2015-01-01

    This paper will describe recent progress made in developing neutron imaging based particle imaging velocimetry techniques for visualizing and quantifying flow structure through a high pressure flow cell with high temperature capability (up to 350 degrees C). This experimental capability has great potential for improving the understanding of flow through fractured systems in applications such as enhanced geothermal systems (EGS). For example, flow structure measurement can be used to develop and validate single phase flow models used for simulation, experimentally identify critical transition regions and their dependence on fracture features such as surface roughness, and study multiphase fluid behavior within fractured systems. The developed method involves the controlled injection of a high contrast fluid into a water flow stream to produce droplets that can be tracked using neutron radiography. A description of the experimental setup will be provided along with an overview of the algorithms used to automatically track droplets and relate them to the velocity gradient in the flow stream. Experimental results will be reported along with volume of fluids based simulation techniques used to model observed flow.

  1. Field data on testing of natural gas vehicle (NGV) containers using proposed ASTM standard test method for examination of gas-filled filament-wound pressure vessels using acoustic emission (ASTM-E070403-95/1)

    SciTech Connect (OSTI)

    Fultineer, R.D. Jr.; Mitchell, J.R.

    1999-07-01

    There are many composite wrapped pressure vessels in service. These containers are most widely used for gas storage in natural gas vehicles (NGV). A standard has been developed for the testing of these vessels by the subcommittee ASTM E07.04.03 Acoustic Emission (AE) applications. The AE test method is supported by both field test data and laboratory destructive testing. The test method describes a global volumetric testing technique which is offered as an alternative to the current practice of visual inspection.

  2. Scaling Law of Coherent Synchrotron Radiation in a Rectangular...

    Office of Scientific and Technical Information (OSTI)

    Scaling Law of Coherent Synchrotron Radiation in a Rectangular Chamber Citation Details In-Document Search Title: Scaling Law of Coherent Synchrotron Radiation in a Rectangular...

  3. DESIGN AND FABRICATION OF A RECTANGULAR HE-COOLED REFRACTORY FOAM HX-CHANNEL FOR DIVERTOR APPLICATIONS

    E-Print Network [OSTI]

    Ghoniem, Nasr M.

    .williams@ultramet.com A rectangular single channel low pressure drop helium-cooled refractory metal heat exchanger (HX) tube the path of helium flow through foam to about 11 mm and thus the pressure drop through the porous media surfaces, such as a flat-plate divertor, without substantially increasing the coolant pressure losses. We

  4. Electrochemical apparatus comprising modified disposable rectangular...

    Office of Scientific and Technical Information (OSTI)

    include more than one cuvette, which in practice is a disposable rectangular glass or plastic cuvette modified by drilling the hole(s) through. The apparatus include two plates...

  5. In-service Inspection Ultrasonic Testing of Reactor Pressure Vessel Welds for Assessing Flaw Density and Size Distribution per 10 CFR 50.61a, Alternate Fracture Toughness Requirements

    SciTech Connect (OSTI)

    Sullivan, Edmund J.; Anderson, Michael T.; Norris, Wallace

    2012-09-17

    Pressurized thermal shock (PTS) events are system transients in a pressurized water reactor (PWR) in which there is a rapid operating temperature cool-down that results in cold vessel temperatures with or without repressurization of the vessel. The rapid cooling of the inside surface of the reactor pressure vessel (RPV) causes thermal stresses that can combine with stresses caused by high pressure. The aggregate effect of these stresses is an increase in the potential for fracture if a pre-existing flaw is present in a material susceptible to brittle failure. The ferritic, low alloy steel of the reactor vessel beltline adjacent to the core, where neutron radiation gradually embrittles the material over the lifetime of the plant, can be susceptible to brittle fracture. The PTS rule, described in the Code of Federal Regulations, Title 10, Section 50.61 (§50.61), “Fracture Toughness Requirements for Protection against Pressurized Thermal Shock Events,” adopted on July 23, 1985, establishes screening criteria to ensure that the potential for a reactor vessel to fail due to a PTS event is deemed to be acceptably low. The U.S. Nuclear Regulatory Commission (NRC) completed a research program that concluded that the risk of through-wall cracking due to a PTS event is much lower than previously estimated. The NRC subsequently developed a rule, §50.61a, published on January 4, 2010, entitled “Alternate Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events” (75 FR 13). Use of the new rule by licensees is optional. The §50.61a rule differs from §50.61 in that it requires licensees who choose to follow this alternate method to analyze the results from periodic volumetric examinations required by the ASME Code, Section XI, Rules for Inservice Inspection (ISI) of Nuclear Power Plants. These analyses are intended to determine if the actual flaw density and size distribution in the licensee’s reactor vessel beltline welds are bounded by the flaw density and size distribution values used in the PTS technical basis. Under a contract with the NRC, Pacific Northwest National Laboratory (PNNL) has been working on a program to assess the ability of current inservice inspection (ISI)-ultrasonic testing (UT) techniques, as qualified through ASME Code, Appendix VIII, Supplements 4 and 6, to detect small fabrication or inservice-induced flaws located in RPV welds and adjacent base materials. As part of this effort, the investigators have pursued an evaluation, based on the available information, of the capability of UT to provide flaw density/distribution inputs for making RPV weld assessments in accordance with §50.61a. This paper presents the results of an evaluation of data from the 1993 Browns Ferry Nuclear Plant, Unit 3, Spirit of Appendix VIII reactor vessel examination, a comparison of the flaw density/distribution from this data with the distribution in §50.61a, possible reasons for differences, and plans and recommendations for further work in this area.

  6. Electrochemical apparatus comprising modified disposable rectangular cuvette

    DOE Patents [OSTI]

    Dattelbaum, Andrew M; Gupta, Gautam; Morris, David E

    2013-09-10

    Electrochemical apparatus includes a disposable rectangular cuvette modified with at least one hole through a side and/or the bottom. Apparatus may include more than one cuvette, which in practice is a disposable rectangular glass or plastic cuvette modified by drilling the hole(s) through. The apparatus include two plates and some means of fastening one plate to the other. The apparatus may be interfaced with a fiber optic or microscope objective, and a spectrometer for spectroscopic studies. The apparatus are suitable for a variety of electrochemical experiments, including surface electrochemistry, bulk electrolysis, and flow cell experiments.

  7. Ultrasonic liquid-level detector for varying temperature and pressure environments

    DOE Patents [OSTI]

    Anderson, R.L.; Miller, G.N.

    1981-10-26

    An ultrasonic liquid level detector for use in varying temperature and pressure environments, such as a pressurized water nuclear reactor vessel, is provided. The detector employs ultrasonic extensional and torsional waves launched in a multiplexed alternating sequence into a common sensor. The sensor is a rectangular cross section stainless steel rod which extends into the liquid medium whose level is to be detected. The sensor temperature derived from the extensional wave velocity measurements is used to compensate for the temperature dependence of the torsional wave velocity measurements which are also level dependent. The torsional wave velocity measurements of a multiple reflection sensor then provide a measurement of liquid level over a range of several meters with a small uncertainty over a temperature range of 20 to 250/sup 0/C and pressures up to 15 MPa.

  8. Pressure surge attenuator

    DOE Patents [OSTI]

    Christie, Alan M. (Swissvale, PA); Snyder, Kurt I. (Murrysville, PA)

    1985-01-01

    A pressure surge attenuation system for pipes having a fluted region opposite crushable metal foam. As adapted for nuclear reactor vessels and heads, crushable metal foam is disposed to attenuate pressure surges.

  9. Coupling of twin rectangular supersonic jets

    E-Print Network [OSTI]

    Raman, G.; Taghavi, Ray

    1998-01-01

    J. Fluid Mech. (1998), vol. 354, pp. 123{146. Printed in the United Kingdom c? 1998 Cambridge University Press 123 Coupling of twin rectangular supersonic jets By GANESH RAMAN 1 AND RAY TAGHAVI 2 1 NYMA, Inc., Experimental Fluid Dynamics Section... on twin supersonic jets that screech at a discrete frequency. The present fundamental research program on twin-jet coupling was undertaken to resolve numerous issues underlined by Tam & Seiner (1987), and Morris (1990). Tam & Seiner (1987) pointed...

  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)

    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.

  11. 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.

  12. 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.

  13. Alternating current loss reduction for rectangular busbars by...

    Office of Scientific and Technical Information (OSTI)

    Alternating current loss reduction for rectangular busbars by covering their edges with low permeable magnetic caps Citation Details In-Document Search Title: Alternating current...

  14. 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

  15. Hybrid Automata-based CEGAR for Rectangular Hybrid Systems

    E-Print Network [OSTI]

    Liberzon, Daniel

    Hybrid Automata-based CEGAR for Rectangular Hybrid Systems Pavithra Prabhakar, Sridhar Duggirala- example guided abstraction-refinement (CEGAR) for systems modelled as rectangular hybrid automata. The main difference, between our ap- proach and previous proposals for CEGAR for hybrid automata

  16. Fresnel approximations for acoustic fields of rectangularly symmetric sources

    E-Print Network [OSTI]

    Mast, T. Douglas

    Fresnel approximations for acoustic fields of rectangularly symmetric sources T. Douglas Masta for determining the acoustic fields of rectangularly symmetric, baffled, time-harmonic sources under the Fresnel. The expressions presented are generalized to three different Fresnel approximations that correspond, respectively

  17. Pressure suppression containment system

    DOE Patents [OSTI]

    Gluntz, Douglas M. (San Jose, CA); Townsend, Harold E. (San Jose, CA)

    1994-03-15

    A pressure suppression containment system includes a containment vessel surrounding a reactor pressure vessel and defining a drywell therein containing a non-condensable gas. An enclosed wetwell pool is disposed inside the containment vessel, and a gravity driven cooling system (GDCS) pool is disposed above the wetwell pool in the containment vessel. The wetwell pool includes a plenum for receiving the non-condensable gas carried with steam from the drywell following a loss-of coolant-accident (LOCA). The wetwell plenum is vented to a plenum above the GDCS pool following the LOCA for suppressing pressure rise within the containment vessel. A method of operation includes channeling steam released into the drywell following the LOCA into the wetwell pool for cooling along with the non-condensable gas carried therewith. The GDCS pool is then drained by gravity, and the wetwell plenum is vented into the GDCS plenum for channeling the non-condensable gas thereto.

  18. Pressure suppression containment system

    DOE Patents [OSTI]

    Gluntz, D.M.; Townsend, H.E.

    1994-03-15

    A pressure suppression containment system includes a containment vessel surrounding a reactor pressure vessel and defining a drywell therein containing a non-condensable gas. An enclosed wetwell pool is disposed inside the containment vessel, and a gravity driven cooling system (GDCS) pool is disposed above the wetwell pool in the containment vessel. The wetwell pool includes a plenum for receiving the non-condensable gas carried with steam from the drywell following a loss-of-coolant-accident (LOCA). The wetwell plenum is vented to a plenum above the GDCS pool following the LOCA for suppressing pressure rise within the containment vessel. A method of operation includes channeling steam released into the drywell following the LOCA into the wetwell pool for cooling along with the non-condensable gas carried therewith. The GDCS pool is then drained by gravity, and the wetwell plenum is vented into the GDCS plenum for channeling the non-condensable gas thereto. 6 figures.

  19. 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.

  20. 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

  1. 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).

  2. 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.

  3. Physics from Angular Projection of Rectangular Grids

    E-Print Network [OSTI]

    Ashmeet Singh

    2014-12-08

    In this paper, we present a mathematical model for the angular projection of a rectangular arrangement of points in a grid. This simple, yet interesting problem, has both a scholarly value and applications for data extraction techniques to study the physics of various systems. Our work can interest undergraduate students to understand subtle points in the angular projection of a grid and describes various quantities of interest in the projection with completeness and sufficient rigour. We show that for certain angular ranges, the projection has non-distinctness, and calculate the details of such angles, and correspondingly, the number of distinct points and the total projected length. We focus on interesting trends obtained for the projected length of the grid elements and present a simple application of the model to determine the geometry of an unknown grid whose spatial extensions are known, using measurement of the grid projection at two angles only. Towards the end, our model is shown to have potential applications in various branches of physical sciences including crystallography, astrophysics and bulk properties of materials.

  4. Acoustic-Gravity Waves Interacting with a Rectangular Trench

    E-Print Network [OSTI]

    Kadri, Usama

    2015-01-01

    A mathematical solution of the two-dimensional linear problem of an acoustic-gravity wave interacting with a rectangular trench, in a compressible ocean, is presented. Expressions for the flow field on both sides of the ...

  5. Uniformly Loaded Rectangular Thin Plates with Symmetrical Boundary Conditions

    E-Print Network [OSTI]

    Milan Batista

    2010-01-27

    In the article the Fourier series analytical solutions of uniformly loaded rectangular thin plates with symmetrical boundary conditions are considered. For all the cases the numerical values are tabulated.

  6. KRONECKER COEFFICIENTS FOR SOME NEAR-RECTANGULAR VASU V. TEWARI

    E-Print Network [OSTI]

    Fournier, John J.F.

    KRONECKER COEFFICIENTS FOR SOME NEAR-RECTANGULAR PARTITIONS VASU V. TEWARI Abstract. We give function, Young tableau, near-rectangle, bounded height. 1 #12;2 VASU V. TEWARI computing them

  7. The optimization of solar radiation upon a rectangular building 

    E-Print Network [OSTI]

    Ingle, James Allen

    1973-01-01

    THE OPTIMIZATION OF SOLAR RADIATION UPON A RECTANGULAR BUILDING A Thesis by JAMES ALLEN INGLF. Submitted to the Graduate College of Texas AAM University in Partial fulfillment of the requirement for the degree of MASTER OF SCIENCE August 19... 3 Major Subjeoti Meteorology THE OPTIMIZATION OF SOLAR RADIATION UPON A RECTANGULAR BUILDING A Thesis by JAILS ALLEN INGLE Approved as to style and content bye Cha an of ittee Mr, ' ohn F, Griffiths Member Dro Robert CD Runnels Head...

  8. Pressurized fluidized bed reactor

    DOE Patents [OSTI]

    Isaksson, J.

    1996-03-19

    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.

  9. Pressurized fluidized bed reactor

    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.

  10. CC Pressure Test

    SciTech Connect (OSTI)

    Dixon, K.; /Fermilab

    1990-07-12

    The inner vessel heads including bypass and beam tubes had just been welded into place and dye penetrant checked. The vacuum heads were not on at this time but the vacuum shell was on covering the piping penetrating into the inner vessel. Signal boxes with all feed through boards, the instrumentation box, and high voltage boxes were all installed with their pump outs capped. All 1/4-inch instrumentation lines were terminated at their respective shutoff valves. All vacuum piping used for pumping down the inner vessel was isolated using o-ring sealed blind flanges. PV215A (VAT Series 12), the 4-inch VRC gate valve isolating the cyropump, and the rupture disk had to be removed and replaced with blind flanges before pressurizing due to their pressure limitations. Stresses in plates used as blind flanges were checked using Code calcualtions. Before the CC test, vacuum style blanks and clamps were hydrostatically pressure tested to 150% of the maximum test pressure, 60 psig. The Code inspector and Research Division Safety had all given their approval to the test pressure and procedure prior to filling the vessel with argon. The test was a major success. Based on the lack of any distinguishable pressure drop indicated on the pressure gages, the vessel appeared to be structurally sound throughout the duration of the test (approx. 3 hrs.). A major leak in the instrumentation tubing was discovered at half of the maximum test pressure and was quickly isolated by crimping and capping with a compression fitting. There were some slight deviations in the actual procedure used. The 44 psig relief valve located just outside the cleanroom had to be capped until the pressure in the vessel indicated 38 psi. This was to allow higher supply pressures and hence, higher flows through the pressurizing line. Also, in order to get pressure readings at the cryostat without exposing any personnel to the potentially dangerous stored energy near the maximum test pressure, a camera was installed at the top of the vessel to view the indicator mounted there. The monitor was viewed at the ante room adjacent to the cleanroom. The holding pressure of 32 psig (4/5 of the maximum test pressure) was only maintained for about 20 minutes instead of the half hour recommendation in the procedure. We felt that this was sufficient time to Snoop test and perform the pressure drop test. After the test was completed, the inspector for CBI Na-Con and the Research Divison Safety Officer signed all of required documentation.

  11. 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

  12. 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

  13. 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

  14. 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

  15. 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

  16. A Direct Approach to the Electromagnetic Casimir Energy in a Rectangular Waveguide

    E-Print Network [OSTI]

    Madad Ali Valuyan; Reza Moazzemi; Siamak S. Gousheh

    2008-06-10

    In this paper we compute the leading order Casimir energy for the electromagnetic field (EM) in an open ended perfectly conducting rectangular waveguide in three spatial dimensions by a direct approach. For this purpose we first obtain the second quantized expression for the EM field with boundary conditions which would be appropriate for a waveguide. We then obtain the Casimir energy by two different procedures. Our main approach does not contain any analytic continuation techniques. The second approach involves the routine zeta function regularization along with some analytic continuation techniques. Our two approaches yield identical results. This energy has been calculated previously for the EM field in a rectangular waveguide using an indirect approach invoking analogies between EM fields and massless scalar fields, and using complicated analytic continuation techniques, and the results are identical to ours. We have also calculated the pressures on different sides and the total Casimir energy per unit length, and plotted these quantities as a function of the cross-sectional dimensions of the waveguide. We also present a physical discussion about the rather peculiar effect of the change in the sign of the pressures as a function of the shape of the cross-sectional area.

  17. 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

  18. Pressure sensor for sealed containers

    DOE Patents [OSTI]

    Hodges, Franklin R. (Loudon, TN)

    2001-01-01

    A magnetic pressure sensor for sensing a pressure change inside a sealed container. The sensor includes a sealed deformable vessel having a first end attachable to an interior surface of the sealed container, and a second end. A magnet mounted to the vessel second end defining a distance away from the container surface provides an externally detectable magnetic field. A pressure change inside the sealed container causes deformation of the vessel changing the distance of the magnet away from the container surface, and thus the detectable intensity of the magnetic field.

  19. Pressure suppression system

    DOE Patents [OSTI]

    Gluntz, D.M.

    1994-10-04

    A pressure suppression system includes a containment vessel surrounding a reactor pressure vessel and defining a drywell therein containing a non-condensable gas. An enclosed wetwell pool is disposed inside the containment vessel, and an enclosed gravity driven cooling system (GDCS) pool is disposed above the wetwell pool in the containment vessel. The GDCS pool includes a plenum for receiving through an inlet the non-condensable gas carried with steam from the drywell following a loss-of-coolant accident (LOCA). A condenser is disposed in the GDCS plenum for condensing the steam channeled therein and to trap the non-condensable gas therein. A method of operation includes draining the GDCS pool following the LOCA and channeling steam released into the drywell following the LOCA into the GDCS plenum for cooling along with the non-condensable gas carried therewith for trapping the gas therein. 3 figs.

  20. Pressure suppression system

    DOE Patents [OSTI]

    Gluntz, Douglas M. (San Jose, CA)

    1994-01-01

    A pressure suppression system includes a containment vessel surrounding a reactor pressure vessel and defining a drywell therein containing a non-condensable gas. An enclosed wetwell pool is disposed inside the containment vessel, and an enclosed gravity driven cooling system (GDCS) pool is disposed above the wetwell pool in the containment vessel. The GDCS pool includes a plenum for receiving through an inlet the non-condensable gas carried with steam from the drywell following a loss-of-coolant accident (LOCA). A condenser is disposed in the GDCS plenum for condensing the steam channeled therein and to trap the non-condensable gas therein. A method of operation includes draining the GDCS pool following the LOCA and channeling steam released into the drywell following the LOCA into the GDCS plenum for cooling along with the non-condensable gas carried therewith for trapping the gas therein.

  1. 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 ...

  2. 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.

  3. 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.

  4. Flow adjustment and interior flow associated with a rectangular porous obstruction

    E-Print Network [OSTI]

    Rominger, Jeffrey Tsaros

    The flow at the leading edge and in the interior of a rectangular porous obstruction is described through experiments and scaling. The porous obstruction consists of an emergent, rectangular array of cylinders in shallow ...

  5. The study and characterization of the major flow through rectangular slit virtual impactor 

    E-Print Network [OSTI]

    Gupta, Amit

    2002-01-01

    The major flow through a rectangular slit virtual impactor was experimentally studied. The impactor was a two-dimensional rectangular slit dichotomous sampler. A series of experiments were performed using monodisperse liquid oleic acid particles...

  6. Graph Expansion Analysis for Communication Costs of Fast Rectangular Matrix Multiplication

    E-Print Network [OSTI]

    California at Berkeley, University of

    Graph Expansion Analysis for Communication Costs of Fast Rectangular Matrix Multiplication Grey analysis of computational DAGs is useful for obtaining communication cost lower bounds where previous to fast algorithms for rectangular matrix multiplication, obtaining a new class of communication cost

  7. High pressure melt ejection

    SciTech Connect (OSTI)

    Tarbell, W.W.; Brockmann, J.E.; Pilch, M.

    1983-01-01

    Recent probabilistic risk assessments have identified the potential for reactor pressure vessel failure while the reactor coolant system is at elevated pressure. The analyses postulate that the blowdown of steam and hydrogen into the reactor cavity will cause the core material to be swept from the cavity region into the containment building. The High Pressure Melt Streaming (HIPS) program is an experimental study of the high pressure ejection of molten material and subsequent interactions within a concrete cavity. The program focuses on using prototypic system conditions and scaled models of reactor geometries to accurately simulate the ex-vessel processes during high-pressure accident sequences. Scaling analyses of the experiment show that the criteria established for core debris removal from the cavity are met or exceeded. Tests are performed at two scales, representing 1/10th and 1/20th linear reproductions of the Zion reactor plant. Results of the 1/20th scale tests are presented.

  8. OSS 19.4 Pressure Safety 3/27/95

    Broader source: Energy.gov [DOE]

    The objective of this surveillance is to evaluate the contractor's implementation of programs to ensure the integrity of pressure vessels and minimize risks from failure of vessels to the public...

  9. 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.

  10. Radial Eigenmodes for a Toroidal Waveguide with Rectangular Cross Section

    SciTech Connect (OSTI)

    Rui Li

    2012-07-01

    In applying mode expansion to solve the CSR impedance for a section of toroidal vacuum chamber with rectangular cross section, we identify the eigenvalue problem for the radial eigenmodes which is different from that for cylindrical structures. In this paper, we present the general expressions of the radial eigenmodes, and discuss the properties of the eigenvalues on the basis of the Sturm-Liouville theory.

  11. High pressure liquid level monitor

    DOE Patents [OSTI]

    Bean, Vern E. (Frederick, MD); Long, Frederick G. (Ijamsville, MD)

    1984-01-01

    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.

  12. Radial pressure flange seal

    DOE Patents [OSTI]

    Batzer, Thomas H. (Livermore, CA); Call, Wayne R. (Tracy, CA)

    1989-01-01

    This invention provides an all metal seal for vacuum or pressure vessels or systems. This invention does not use gaskets. The invention uses a flange which fits into a matching groove. Fluid pressure is applied in a chamber in the flange causing at least one of the flange walls to radially press against a side of the groove creating the seal between the flange wall and the groove side.

  13. Radial pressure flange seal

    DOE Patents [OSTI]

    Batzer, T.H.; Call, W.R.

    1989-01-24

    This invention provides an all metal seal for vacuum or pressure vessels or systems. This invention does not use gaskets. The invention uses a flange which fits into a matching groove. Fluid pressure is applied in a chamber in the flange causing at least one of the flange walls to radially press against a side of the groove creating the seal between the flange wall and the groove side. 5 figs.

  14. High pressure furnace

    DOE Patents [OSTI]

    Morris, D.E.

    1993-09-14

    A high temperature high pressure furnace has a hybrid partially externally heated construction. A metallic vessel fabricated from an alloy having a composition of at least 45% nickel, 15% chrome, and 10% tungsten is utilized (the preferred alloy including 55% nickel, 22% chrome, 14% tungsten, 2% molybdenum, 3% iron (maximum) and 5% cobalt (maximum)). The disclosed alloy is fabricated into 11/4 or 2 inch, 32 mm or 50 mm bar stock and has a length of about 22 inches, 56 cm. This bar stock has an aperture formed therein to define a closed high temperature, high pressure oxygen chamber. The opposite and closed end of the vessel is provided with a small blind aperture into which a thermocouple can be inserted. The closed end of the vessel is inserted into an oven, preferably heated by standard nickel chrome electrical elements and having a heavily insulated exterior. 19 figures.

  15. High pressure furnace

    DOE Patents [OSTI]

    Morris, Donald E. (Kensington, CA)

    1993-01-01

    A high temperature high pressure furnace has a hybrid partially externally heated construction. A metallic vessel fabricated from an alloy having a composition of at least 45% nickel, 15% chrome, and 10% tungsten is utilized (the preferred alloy including 55% nickel, 22% chrome, 14% tungsten, 2% molybdenum, 3% iron (maximum) and 5% cobalt (maximum). The disclosed alloy is fabricated into 11/4 or 2 inch, 32 mm or 50 mm bar stock and has a length of about 22 inches, 56 cm. This bar stock has an aperture formed therein to define a closed high temperature, high pressure oxygen chamber. The opposite and closed end of the vessel is provided with a small blind aperture into which a thermocouple can be inserted. The closed end of the vessel is inserted into an oven, preferably heated by standard nickel chrome electrical elements and having a heavily insulated exterior.

  16. Single module pressurized fuel cell turbine generator system

    DOE Patents [OSTI]

    George, Raymond A. (Pittsburgh, PA); Veyo, Stephen E. (Murrysville, PA); Dederer, Jeffrey T. (Valencia, PA)

    2001-01-01

    A pressurized fuel cell system (10), operates within a common pressure vessel (12) where the system contains fuel cells (22), a turbine (26) and a generator (98) where preferably, associated oxidant inlet valve (52), fuel inlet valve (56) and fuel cell exhaust valve (42) are outside the pressure vessel.

  17. 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

  18. 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).

  19. Bonfire Tests of High Pressure Hydrogen Storage Tanks

    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.

  20. Corner heating in rectangular solid oxide electrochemical cell generators

    DOE Patents [OSTI]

    Reichner, Philip (Plum Boro, PA)

    1989-01-01

    Disclosed is an improvement in a solid oxide electrochemical cell generator 1 having a rectangular design with four sides that meet at corners, and containing multiplicity of electrically connected fuel cells 11, where a fuel gas is passed over one side of said cells and an oxygen containing gas is passed into said cells, and said fuel is burned to form heat, electricity, and an exhaust gas. The improvement comprises passing the exhaust gases over the multiplicity of cells 11 in such a way that more of the heat in said exhaust gases flows at the corners of the generator, such as through channels 19.

  1. Improved approximate formulas for flux from cylindrical and rectangular sources

    SciTech Connect (OSTI)

    Wallace, O.J.; Bokharee, S.A.

    1993-03-01

    This report provides two new approximate formulas for the flux at detector points outside the radial and axial extensions of a homogeneous cylindrical source and improved approximate formulas for the flux at points opposite rectangular surface sources. These formulas extend the range of geometries for which analytic approximations may be used by shield design engineers to make rapid scoping studies and check more extensive calculations for reasonableness. These formulas can be used to support skeptical, independent evaluations and are also valuable teaching tools for introducing shield designers to complex shield analyses.

  2. DEVELOPING FLOW AND HEAT TRANSFER IN STRONGLY CURVED DUCTS OF RECTANGULAR CROSS-SECTION

    E-Print Network [OSTI]

    Yee, G.

    2010-01-01

    DEVELOpiNG FLOW AND HEAT TRANSFER IN STRONGLY CURVED DUCTS9092 Developing Flow and Heat Transfer in Strongly CurvedForced Convection Heat Transfer in Curved Rectangular

  3. Measurement strategy for rectangular electrical capacitance tomography sensor

    SciTech Connect (OSTI)

    Ye, Jiamin; Ge, Ruihuan; Qiu, Guizhi; Wang, Haigang [Institute of Engineering Thermophysics, Chinese Academy of Sciences, Beijing, 100190 (China)

    2014-04-11

    To investigate the influence of the measurement strategy for the rectangular electrical capacitance tomography (ECT) sensor, a Finite Element Method (FEM) is utilized to create the model for simulation. The simulation was carried out using COMSOL Multiphysics(trade mark, serif) and Matlab(trade mark, serif). The length-width ratio of the rectangular sensing area is 5. Twelve electrodes are evenly arranged surrounding the pipe. The covering ratio of the electrodes is 90%. The capacitances between different electrode pairs are calculated for a bar distribution. The air of the relative permittivity 1.0 and the material of the permittivity 3.0 are used for the calibration. The relative permittivity of the second phase is 3.0. The noise free and noise data are used for the image reconstruction using the Linear Back Projection (LBP). The measurement strategies with 1-, 2- and 4- electrode excitation are compared using the correlation coefficient. Preliminary results show that the measurement strategy with 2-electrode excitation outperforms other measurement strategies with 1- or 4-electrode excitation.

  4. 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

  5. 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.

  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. Pressurized security barrier and alarm system

    DOE Patents [OSTI]

    Carver, Don W. (Knoxville, TN)

    1995-01-01

    A security barrier for placement across a passageway is made up of interconnected pressurized tubing made up in a grid pattern with openings too small to allow passage. The tubing is connected to a pressure switch, located away from the barrier site, which activates an alarm upon occurrence of a pressure drop. A reinforcing bar is located inside and along the length of the tubing so as to cause the tubing to rupture and set off the alarm upon an intruder's making an attempt to crimp and seal off a portion of the tubing by application of a hydraulic tool. Radial and rectangular grid patterns are disclosed.

  8. Pressurized security barrier and alarm system

    DOE Patents [OSTI]

    Carver, D.W.

    1995-04-11

    A security barrier for placement across a passageway is made up of interconnected pressurized tubing made up in a grid pattern with openings too small to allow passage. The tubing is connected to a pressure switch, located away from the barrier site, which activates an alarm upon occurrence of a pressure drop. A reinforcing bar is located inside and along the length of the tubing so as to cause the tubing to rupture and set off the alarm upon an intruder`s making an attempt to crimp and seal off a portion of the tubing by application of a hydraulic tool. Radial and rectangular grid patterns are disclosed. 7 figures.

  9. Shear Stress in Smooth Rectangular Open-Channel Flows and Pierre Y. Julien2

    E-Print Network [OSTI]

    Julien, Pierre Y.

    Shear Stress in Smooth Rectangular Open-Channel Flows Junke Guo1 and Pierre Y. Julien2 Abstract: The average bed and sidewall shear stresses in smooth rectangular open-channel flows are determined after solving the continuity and momentum equations. The analysis shows that the shear stresses are function

  10. Heat transfer enhancement for turbulent flow through blockages with elongated holes in a rectangular channel 

    E-Print Network [OSTI]

    Lee, Yonghee

    2007-09-17

    In this thesis, turbulent forced convective heat transfer downstream of blockages with elongated holes in a rectangular channel was studied. The rectangular channel has a width-to-height ratio of 12:1. The blockages have the same cross section...

  11. CRAD, Pressurized Systems and Cryogens Assessment Plan

    Office of Energy Efficiency and Renewable Energy (EERE)

    Assure personnel health and safety through regularly scheduled inspections and maintenance on pressure vessels and equipment, compressed gases and gas cylinders, vacuum equipment and systems, hydraulics, and cryogenic materials and systems.

  12. 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)

  13. 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.

  14. 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.

  15. Study of instabilities and quasi-two-dimensional turbulence in volumetrically heated magnetohydrodynamic flows in a vertical rectangular duct

    E-Print Network [OSTI]

    Abdou, Mohamed

    magnetohydrodynamic flows in a vertical rectangular duct N. Vetcha, S. Smolentsev, M. Abdou, and R. Moreau Citation in a vertical rectangular duct N. Vetcha,1 S. Smolentsev,1,a) M. Abdou,1 and R. Moreau2 1 Mechanical 2013; published online 15 February 2013) We consider magnetohydrodynamic (MHD) rectangular duct flows

  16. 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.

  17. Normalization of tumour blood vessels improves the delivery of nanomedicines in a size-dependent manner

    E-Print Network [OSTI]

    Chauhan, Vikash P.

    The blood vessels of cancerous tumours are leaky and poorly organized. This can increase the interstitial fluid pressure inside tumours and reduce blood supply to them, which impairs drug delivery. Anti-angiogenic ...

  18. High pressure xenon ionization detector

    DOE Patents [OSTI]

    Markey, J.K.

    1989-11-14

    A method is provided for detecting ionization comprising allowing particles that cause ionization to contact high pressure xenon maintained at or near its critical point and measuring the amount of ionization. An apparatus is provided for detecting ionization, the apparatus comprising a vessel containing a ionizable medium, the vessel having an inlet to allow high pressure ionizable medium to enter the vessel, a means to permit particles that cause ionization of the medium to enter the vessel, an anode, a cathode, a grid and a plurality of annular field shaping rings, the field shaping rings being electrically isolated from one another, the anode, cathode, grid and field shaping rings being electrically isolated from one another in order to form an electric field between the cathode and the anode, the electric field originating at the anode and terminating at the cathode, the grid being disposed between the cathode and the anode, the field shaping rings being disposed between the cathode and the grid, the improvement comprising the medium being xenon and the vessel being maintained at a pressure of 50 to 70 atmospheres and a temperature of 0 to 30 C. 2 figs.

  19. High pressure xenon ionization detector

    DOE Patents [OSTI]

    Markey, John K. (New Haven, CT)

    1989-01-01

    A method is provided for detecting ionization comprising allowing particles that cause ionization to contact high pressure xenon maintained at or near its critical point and measuring the amount of ionization. An apparatus is provided for detecting ionization, the apparatus comprising a vessel containing a ionizable medium, the vessel having an inlet to allow high pressure ionizable medium to enter the vessel, a means to permit particles that cause ionization of the medium to enter the vessel, an anode, a cathode, a grid and a plurality of annular field shaping rings, the field shaping rings being electrically isolated from one another, the anode, cathode, grid and field shaping rings being electrically isolated from one another in order to form an electric field between the cathode and the anode, the electric field originating at the anode and terminating at the cathode, the grid being disposed between the cathode and the anode, the field shaping rings being disposed between the cathode and the grid, the improvement comprising the medium being xenon and the vessel being maintained at a pressure of 50 to 70 atmospheres and a temperature of 0.degree. to 30.degree. C.

  20. 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

  1. DEVELOPING FLOW AND HEAT TRANSFER IN STRONGLY CURVED DUCTS OF RECTANGULAR CROSS-SECTION

    E-Print Network [OSTI]

    Yee, G.

    2010-01-01

    123. HUMPHREY, J.A.C. , "Flow in Ducts with Curvature andViscous Flow in Curved Ducts of Rectangular Cross-Sections,"Laminar Flow in a Square Duct of Strong Curvature,1I J.

  2. Interaction of water waves with fluidized mud in a rectangular trench 

    E-Print Network [OSTI]

    Lemasson, Wilfrid Joel Christian

    1994-01-01

    The dynamic response of fluidized mud in a rectangular trench to water waves propagating over the trench was studied experimentally. It was shown that the motion of the fluid mud became large compared to the surface wave ...

  3. Jet impingement heat transfer in two-pass rotating rectangular channels 

    E-Print Network [OSTI]

    Zhang, Yuming

    1996-01-01

    The combined effects of rotation and jet impingement on local heat transfer in a two-pass rotating rectangular channel is studied. The results of an experimental investigation on the surface heat transfer coefficients under a perforated plate...

  4. Experimental Two-Phase Flow Characterization of Subcooled Boiling in a Rectangular Channel 

    E-Print Network [OSTI]

    Estrada Perez, Carlos E.

    2010-01-16

    On the efforts to provide a reliable source of experimental information on turbulent subcooled boiling ow, time resolved Particle Tracking Velocimetry (PTV) experiments were carried out using HFE-301 refrigerant ow through a vertical rectangular...

  5. THE DEVELOPMENT OF LARGE RECTANGULAR CERAMIC INSULATORS FOR ION ACCELERATORS FOR THE NEUTRAL-BEAM PROGRAM

    E-Print Network [OSTI]

    Paterson, J.A.

    2010-01-01

    OF LARGE RECTANGULAR CERAMIC INSULATORS FOR ION ACCELERATORSj o i n t d e t a i l the Ceramic Shop. Thanks are also dueC. P. Smith, "Machinable Class Ceramics, Nev Materials for

  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 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

  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-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

  8. Thermal vibration of a rectangular single-layered graphene sheet with quantum effects

    SciTech Connect (OSTI)

    Wang, Lifeng, E-mail: walfe@nuaa.edu.cn; Hu, Haiyan [State Key Laboratory of Mechanics and Control of Mechanical Structures, Nanjing University of Aeronautics and Astronautics, 210016 Nanjing (China)

    2014-06-21

    The thermal vibration of a rectangular single-layered graphene sheet is investigated by using a rectangular nonlocal elastic plate model with quantum effects taken into account when the law of energy equipartition is unreliable. The relation between the temperature and the Root of Mean Squared (RMS) amplitude of vibration at any point of the rectangular single-layered graphene sheet in simply supported case is derived first from the rectangular nonlocal elastic plate model with the strain gradient of the second order taken into consideration so as to characterize the effect of microstructure of the graphene sheet. Then, the RMS amplitude of thermal vibration of a rectangular single-layered graphene sheet simply supported on an elastic foundation is derived. The study shows that the RMS amplitude of the rectangular single-layered graphene sheet predicted from the quantum theory is lower than that predicted from the law of energy equipartition. The maximal relative difference of RMS amplitude of thermal vibration appears at the sheet corners. The microstructure of the graphene sheet has a little effect on the thermal vibrations of lower modes, but exhibits an obvious effect on the thermal vibrations of higher modes. The quantum effect is more important for the thermal vibration of higher modes in the case of smaller sides and lower temperature. The relative difference of maximal RMS amplitude of thermal vibration of a rectangular single-layered graphene sheet decreases monotonically with an increase of temperature. The absolute difference of maximal RMS amplitude of thermal vibration of a rectangular single-layered graphene sheet increases slowly with the rising of Winkler foundation modulus.

  9. 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...

  10. Heat Transfer Enhancement in Rectangular Channel with Compound Cooling Techniques 

    E-Print Network [OSTI]

    Krad, Belal

    2013-11-27

    to analyze heat transfer and pressure loss characteristics to determine which configuration had the overall best performance. Two different flow configurations were considered, a uniform channel flow setup as well as a jet impingement setup. There were a...

  11. 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.

  12. 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.

  13. 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)

  14. 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.

  15. 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.

  16. 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.

  17. ENSC 283: Center of Pressure and Hydrostatic Force on a submerged body School of Engineering Science

    E-Print Network [OSTI]

    Bahrami, Majid

    should be included. The water vessel is designed as a ring segment with constant cross-section. The top of water in the vessel. At a water level, , below the 100 mm mark, the height of the active surface changes in a way that only the moment due to hydrostatic pressure distribution on the vertical end of water vessel

  18. From micro- to nano-scale molding of metals : size effect during molding of single crystal Al with rectangular strip punches.

    SciTech Connect (OSTI)

    Chen, K.; Meng, W. J.; Mei, F.; Hiller, J.; Miller, D. J. (Materials Science Division); (Louisiana State Univ.); (Enervana Tech. LLC)

    2011-02-01

    A single crystal Al specimen was molded at room temperature with long, rectangular, strip diamond punches. Quantitative molding response curves were obtained at a series of punch widths, ranging from 5 {micro}m to 550 nm. A significant size effect was observed, manifesting itself in terms of significantly increasing characteristic molding pressure as the punch width decreases to 1.5 {micro}m and below. A detailed comparison of the present strip punch molding results was made with Berkovich pyramidal indentation on the same single crystal Al specimen. The comparison reveals distinctly different dependence of the characteristic pressure on corresponding characteristic length. The present results show the feasibility of micro-/nano-scale compression molding as a micro-/nano-fabrication technique, and offer an experimental test case for size-dependent plasticity theories.

  19. Digital material skins : for reversible reusable pressure vessels

    E-Print Network [OSTI]

    Hovsepian, Sarah

    2012-01-01

    Spacecraft missions have traditionally sacrificed fully functional hardware and entire vehicles to achieve mission objectives. Propellant tanks are typically jettisoned at different stages in a spacecraft mission and left ...

  20. International Hydrogen Fuel and Pressure Vessel Forum 2010 Beijing, China

    E-Print Network [OSTI]

    challenges in harmonizing test protocols and requirements for compressed natural gas (CNG), hydrogen, and CNG-up on technical topics and issues identified during a previous international workshop on hydrogen and CNG fuels information and data on testing and certification of storage tanks for compressed hydrogen, CNG, and HCNG

  1. Roadmap for Nondestructive Evaluation of Reactor Pressure Vessel...

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

    These techniques may offer a method for nondestructive characterization of RPV steel which can then possibly be correlated to its fracture toughness. LWRS NDE RD...

  2. Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program:

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

    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 WebQuantity of Natural GasAdjustmentsShirleyEnergyTher i nAandSummary From: JuliaDepartment-8-2008 October5 ofCTIAR.

  3. International Hydrogen Fuel and Pressure Vessel Forum | Department of

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:Financing Tool Fits the BillDepartment of EnergyDemonstrationDepartmentOil

  4. Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program:

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious RankADVANCED MANUFACTURINGEnergy BillsNo. 195 - Oct. 7,DOE HDBK-1113-2008Broadband Plan

  5. Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program:

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious RankADVANCED MANUFACTURINGEnergy BillsNo. 195 - Oct. 7,DOE HDBK-1113-2008Broadband PlanInitial Assessment of

  6. International Hydrogen Fuel and Pressure Vessel Forum - Presentations |

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious RankADVANCED MANUFACTURING OFFICE INDUSTRIALU.S. Department of Energy |June 2015AmericanSupplyDepartment of

  7. International Hydrogen Fuel and Pressure Vessel Forum 2010 Proceedings |

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious RankADVANCED MANUFACTURING OFFICE INDUSTRIALU.S. Department of Energy |June 2015AmericanSupplyDepartment

  8. Forum Agenda: International Hydrogen Fuel and Pressure Vessel Forum |

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum12, 2015ExecutiveFluorescent LampFort Collins, Colorado on Track to NetDepartment

  9. Roadmap for Nondestructive Evaluation of Reactor Pressure Vessel Research

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on DeliciousMathematicsEnergyInterestedReplacement-2-A WholesaleRetrofitElectrical Equipment To BeDepartment ofand

  10. Lightweight cryogenic-compatible pressure vessels for vehicular fuel

    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 would likeUniverseIMPACTThousand CubicResourcelogo and-E C H2015Tray and Enclosure |

  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 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

  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 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

  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 & 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

  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/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

  15. Development and test of a rectangular CERN ConFlat-type flange

    E-Print Network [OSTI]

    Miarnau Marin, Ana; Veness, Raymond

    2015-01-01

    Standard circular ConFlat® (CF) flanges are widely used in industry due to their high sealing reliability after being subjected to a bakeout process. The Beam Gas Ionisation (BGI) instrument for the CERN Proton Synchrotron accelerator will require a CF-like rectangular sealing system. Although rectangular CF-type flanges with plastically deforming metal seals have been used, no published designs with validated tests for bakeout under UHV conditions are available. Existing circular CERN CF flanges were compared and a design for a rectangular CF flange was proposed. Two prototypes were manufactured along with copper gaskets. The flanges and gaskets were cleaned and prepared for extensive vacuum testing after bakeout cycles up to 350 °C. This paper summarises the design, analysis and manufacturing process and describes the testing procedures and results. Additionally, the limitations when designing a flange of any shape were explored.

  16. 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.

  17. A Five-dimensional Visualization of the Pressure-induced Phase...

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

    by changing the external pressure which can be well controlled using high-pressure vessels such as diamond anvil cells. Numerous studies on BiNiO3 have been carried out using...

  18. 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

  19. VOL. 28, NO. 8, AUGUST 1990 AIAA JOURNAL 1447 Flow Distortion in a Circular-to-Rectangular Transition Duct

    E-Print Network [OSTI]

    Leu, Tzong-Shyng "Jeremy"

    -to-Rectangular Transition Duct J. J. Miau,* T. S. Leu,? J. H. Chou,f S. A. Lint National Cheng Kung University, Tainan, Taiwan, Republic of China Experiments were made for three circular-to-rectangular transition ducts of the transition duct. The results indicate that the major driving force for flow in the duct to behave three

  20. 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...

  1. Development of Larger Diameter High Pressure CNG Cylinder Manufactured by Piercing and Drawing for Natural Gas Vehicle

    Office of Energy Efficiency and Renewable Energy (EERE)

    These slides were presented at the International Hydrogen Fuel and Pressure Vessel Forum on September 27 – 29, 2010, in Beijing, China.

  2. Ground vibration due to a high-speed moving harmonic rectangular load on a

    E-Print Network [OSTI]

    Avignon et des Pays de Vaucluse, Université de

    Ground vibration due to a high-speed moving harmonic rectangular load on a poroviscoelastic half'Avignon, Facult´e des Sciences, 33 rue Louis Pasteur, F-84000 Avignon, France RUNNING TITLE: Vibrations induced) #12;Abstract The transmission of vibrations in the ground, due to a high-speed moving vertical har

  3. Repulsive Casimir forces produced in rectangular cavities: Possible measurements and applications

    E-Print Network [OSTI]

    A. Gusso; A. G. M. Schmidt

    2006-01-13

    We perform a theoretical analysis of a setup intended to measure the repulsive (outward) Casimir forces predicted to exist inside of perfectly conducting rectangular cavities. We consider the roles of the conductivity of the real metals, of the temperature and surface roughness. The use of this repulsive force to reduce friction and wear in micro and nanoelectromechanical systems (MEMS and NEMS) is also considered.

  4. Sensors and Actuators A 127 (2006) 270275 Plastic 95-GHz rectangular waveguides by micro molding technologies

    E-Print Network [OSTI]

    Lin, Liwei

    2006-01-01

    Sensors and Actuators A 127 (2006) 270­275 Plastic 95-GHz rectangular waveguides by micro molding technologies Firas Sammouraa,, Yu-Chuan Sua, Ying Caib, Chen-Yu Chic, Bala Elamaranc, Liwei Lina, Jung at Arlington, Arlington, TX 76019-0016, USA c Agilent Technologies, 1400 Fountain Grove Pky, San Rosa, CA 95403

  5. Recharge/seepage from an array of rectangular Mahender Choudhary a

    E-Print Network [OSTI]

    Chahar, B. R.

    Recharge/seepage from an array of rectangular channels Mahender Choudhary a , Bhagu R. Chahar b@civil.iitd.ac.in, chahar_br@yahoo.com (B.R. Chahar). Journal of Hydrology (2007) 343, 71­79 available at www

  6. 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.

  7. 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.

  8. Pressure Safety Program Implementation at ORNL

    SciTech Connect (OSTI)

    Lower, Mark; Etheridge, Tom; Oland, C. Barry

    2013-01-01

    The Oak Ridge National Laboratory (ORNL) is a US Department of Energy (DOE) facility that is managed by UT-Battelle, LLC. In February 2006, DOE promulgated worker safety and health regulations to govern contractor activities at DOE sites. These regulations, which are provided in 10 CFR 851, Worker Safety and Health Program, establish requirements for worker safety and health program that reduce or prevent occupational injuries, illnesses, and accidental losses by providing DOE contractors and their workers with safe and healthful workplaces at DOE sites. The regulations state that contractors must achieve compliance no later than May 25, 2007. According to 10 CFR 851, Subpart C, Specific Program Requirements, contractors must have a structured approach to their worker safety and health programs that at a minimum includes provisions for pressure safety. In implementing the structured approach for pressure safety, contractors must establish safety policies and procedures to ensure that pressure systems are designed, fabricated, tested, inspected, maintained, repaired, and operated by trained, qualified personnel in accordance with applicable sound engineering principles. In addition, contractors must ensure that all pressure vessels, boilers, air receivers, and supporting piping systems conform to (1) applicable American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (2004) Sections I through XII, including applicable code cases; (2) applicable ASME B31 piping codes; and (3) the strictest applicable state and local codes. When national consensus codes are not applicable because of pressure range, vessel geometry, use of special materials, etc., contractors must implement measures to provide equivalent protection and ensure a level of safety greater than or equal to the level of protection afforded by the ASME or applicable state or local codes. This report documents the work performed to address legacy pressure vessel deficiencies and comply with pressure safety requirements in 10 CFR 851. It also describes actions taken to develop and implement ORNL’s Pressure Safety Program.

  9. 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

  10. 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

  11. 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

  12. Analysis of In-Vessel Late Phase Melt Progression Using SCDAP/RELAP5/MOD3.3

    SciTech Connect (OSTI)

    Park, R.J.; Kim, S.B.; Kim, H.D. [Korea Atomic Energy Research Institute, Yuseong, P.O.Box 105, Daejeon, 305-600 (Korea, Republic of)

    2004-07-01

    High-pressure in-vessel melt progressions of the KSNP (Korean Standard Nuclear Power Plant) have been analyzed using the SCDAP/RELAP5/MOD3.3 computer code. The total loss of feed water (LOFW) to the steam generators with/without intentional RCS depressurization using the safety depressurization system (SDS) and the station blackout (SBO) have been simulated from transient initiation to reactor vessel failure. The SCDAP/RELAP5/MOD3.3 results have shown that the pressure boundary of the reactor coolant system did not fail before reactor vessel failure in the high-pressure sequences of the LOFW and the SBO transients of the KSNP. In all the high-pressure transients, approximately 20-30 % of the core material was melted and relocated to the lower plenum of the reactor vessel at the time of reactor vessel failure. Intentional RCS depressurization using the SDS for the total LOFW delays reactor vessel failure for approximately 5 hours by actuation of the safety injection tanks. At the time of reactor vessel failure, approximately 50-60 % of the fuel rod cladding was oxidized for the total LOFW and the SBO transients of the KSNP. (authors)

  13. 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

  14. 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:

  15. 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.

  16. 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)

  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 & 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

  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 + 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

  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 & 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

  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 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

  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 + 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

  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 + 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

  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 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

  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 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

  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 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

  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 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

  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 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

  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 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

  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 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

  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 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

  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-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

  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 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

  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-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

  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-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

  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-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

  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-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

  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-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

  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 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

  19. 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

  20. 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

  1. 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

  2. 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

  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-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

  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 #12VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 3D Relative Risk Profile Comparison Potential Collision

  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;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

  6. 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

  7. 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

  8. 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

  9. 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

  10. 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

  11. 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

  12. 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

  13. 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

  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 #12;T-VCU VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 POTENTIAL COLLISION OIL LOSS - PCO Draft #12;DEFINITION OF 15

  15. 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

  16. 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

  17. 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

  18. 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

  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 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

  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 ­ 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

  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 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

  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 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

  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 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

  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 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

  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 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

  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 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

  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-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

  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 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

  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 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

  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 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

  11. 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

  12. PRESSURIZED EQUIPMENT AND SYSTEMS Table Of Contents

    E-Print Network [OSTI]

    US Army Corps of Engineers

    and tests will be performed by personnel qualified in accordance with the ASME Code or the NBBI. 20.A.02 placed in service and after any repair or modification. b. Unless State or local codes specify more. Inspections of pressure vessels prior to being placed in service shall be in accordance with the ASME "Boiler

  13. A multiresolution finite element method based on a new locking-free rectangular Mindlin plate element

    E-Print Network [OSTI]

    Xia, Yi-Ming

    2015-01-01

    A locking-free rectangular Mindlin plate element with a new multi-resolution analysis (MRA) is proposed and a multireolution finite element method is hence presented. The MRA framework is formulated out of a mutually nesting displacement subspace sequence. The MRA endows the proposed element with the resolution level (RL) to adjust the element node number, thus modulating structural analysis accuracy accordingly. As a result, the traditional 4-node rectangular Mindlin plate element and method is a mono-resolution one and also a special case of the proposed element and method. The meshing for the monoresolution plate element model is based on the empiricism while the RL adjusting for the multiresolution is laid on the rigorous mathematical basis. The accuracy of a structural analysis is actually determined by the RL, not by the mesh. The rational MRA enables the implementation of the multiresolution Mindlin plate element method to be more rational and efficient than that of the conventional monoresolution or o...

  14. Analytical solution for free vibrations of simply supported transversally inextensible homogeneous rectangular plate

    E-Print Network [OSTI]

    Milan Batista

    2010-07-16

    In article, the exact solution of sinusoidal loaded simply supported elastic transversally inextensible rectangular plate is given. The expressions for displacement and stress components are derived and asymptotic expansion with respect to plate thickness are present. The frequency factors for plate thickness to width ratio 0.01, 0.1, 0.2 and 0.4 and various ratios of plate length to width are given.

  15. Two Channel Dielectric-Lined Rectangular High Transformer Ratio Accelerator Structure Experiment

    SciTech Connect (OSTI)

    Shchelkunov, S. V.; LaPointe, M. A. [Beam Physics Laboratory, Yale University, 272 Whitney Avenue, New Haven, CT 06511 (United States); Hirshfield, J. L. [Beam Physics Laboratory, Yale University, 272 Whitney Avenue, New Haven, CT 06511 (United States); Omega-P, Inc., 258 Bradley St., New Haven, CT 06510 (United States); Marshall, T. C. [Columbia University, New York, NY 10027 (United States); Omega-P, Inc., 258 Bradley St., New Haven, CT 06510 (United States); Sotnikov, G. [NSC Kharkov Institute of Physics and Technology, Kharkov (Ukraine); Omega-P, Inc., 258 Bradley St., New Haven, CT 06510 (United States); Gai, Wei; Conde, M.; Power, J.; Mihalcea, D. [Argonne National Laboratory, Argonne, IL 60439 (United States)

    2010-11-04

    Current status of a two-channel cm-scale rectangular dielectric lined wakefield accelerator structure is described. This structure is installed at the Argonne Wakefield Accelerator facility (AWA), and is presently being evaluated. The device has a transformer ratio of {approx}12.5:1. When driven by a {approx}50 nC single drive bunch it is expected to obtain {approx}6 MV/m acceleration gradient. Related issues are discussed.

  16. GARCON: Genetic Algorithm for Rectangular Cuts OptimizatioN. User's manual for version 2.0

    E-Print Network [OSTI]

    S. Abdullin; D. Acosta; P. Bartalini; R. Cavanaugh; A. Drozdetskiy; G. Karapostoli; G. Mitselmakher; Yu. Pakhotin; B. Scurlock; M. Spiropulu

    2006-05-17

    This paper presents GARCON program, illustrating its functionality on a simple HEP analysis example. The program automatically performs rectangular cuts optimization and verification for stability in a multi-dimensional phase space. The program has been successfully used by a number of very different analyses presented in the CMS Physics Technical Design Report. The current version GARCON 2.0 incorporates the feedback the authors have received. User's Manual is included as a part of the note.

  17. Experimental research on heat transfer of natural convection in vertical rectangular channels with large aspect ratio

    SciTech Connect (OSTI)

    Lu, Qing; Qiu, Suizheng; Su, Guanghui [State Key Laboratory of Multi Phase Flow in Power Engineering, Xi'an JIaotong University, Xi'an, Shaanxi 710049 (China); School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an, Shaanxi 710049 (China); Tian, Wenxi; Ye, Zhonghao [School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an, Shaanxi 710049 (China)

    2010-01-15

    This work presents the experimental research on the steady laminar natural convection heat transfer of air in three vertical thin rectangular channels with different gap clearance. The much higher ratio of width to gap clearance (60-24) and the ratio of length to gap clearance (800-320) make the rectangular channels similar with the coolant flow passage in plate type fuel reactors. The vertical rectangular channels were composed of two stainless steal plates and were heated by electrical heating rods. The wall temperatures were detected with the K-type thermocouples which were inserted into the blind holes drilled in the steal plates. Also the air temperatures at the inlet and outlet of the channel were detected. The wall heat fluxes added to the air flow were calculated by the Fourier heat conduction law. The heat transfer characteristics were analyzed, and the average Nusselt numbers in all the three channels could be well correlated with the Rayleigh number or the modified Rayleigh number in a uniform correlation. Furthermore, the maximum wall temperatures were investigated, which is a key parameter for the fuel's integrity during some accidents. It was found that even the wall heat flux was up to 1500 W/m{sup 2}, the maximum wall temperature was lower than 350 C. All this work is valuable for the plate type reactor's design and safety analysis. (author)

  18. 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

  19. V1.6 Development of Advanced Manufacturing Technologies for Low Cost Hydrogen Storage Vessels

    SciTech Connect (OSTI)

    Leavitt, Mark; Lam, Patrick; Nelson, Karl M.; johnson, Brice A.; Johnson, Kenneth I.; Alvine, Kyle J.; Ruiz, Antonio; Adams, Jesse

    2012-10-01

    The goal of this project is to develop an innovative manufacturing process for Type IV high-pressure hydrogen storage vessels, with the intent to significantly lower manufacturing costs. Part of the development is to integrate the features of high precision AFP and commercial FW. Evaluation of an alternative fiber to replace a portion of the baseline fiber will help to reduce costs further.

  20. Pressurized melt ejection into scaled reactor cavities

    SciTech Connect (OSTI)

    Tarbell, W.W.; Pilch, M.; Brockmann, J.E.; Ross, J.W.; Gilbert, D.W.

    1986-10-01

    This report describes four tests performed in the High-Pressure Melt Streaming Program (HIPS) using linear-scaled cavities of the Zion Nuclear Power Plant. These experiments were conducted to study the phenomena involved in high-pressure ejection of core debris into the cavity beneath the reactor pressure vessel. One-tenth and one-twentieth linear scale models of reactor cavities were constructed and instrumented. The first test used an apparatus constructed of alumina firebrick to minimize the potential interaction between the ejected melt and cavity material. The remaining three experiments used scaled representations of the Zion nuclear plant geometry, constructed of prototypic concrete composition.

  1. 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.

  2. Upflow bioreactor with septum and pressure release mechanism

    DOE Patents [OSTI]

    Hansen, Conly L.; Hansen, Carl S.; Pack, Kevin; Milligan, John; Benefiel, Bradley C.; Tolman, C. Wayne; Tolman, Kenneth W.

    2010-04-20

    An upflow bioreactor includes a vessel having an inlet and an outlet configured for upflow operation. A septum is positioned within the vessel and defines a lower chamber and an upper chamber. The septum includes an aperture that provides fluid communication between the upper chamber and lower chamber. The bioreactor also includes means for releasing pressure buildup in the lower chamber. In one configuration, the septum includes a releasable portion having an open position and a closed position. The releasable portion is configured to move to the open position in response to pressure buildup in the lower chamber. In the open position fluid communication between the lower chamber and the upper chamber is increased. Alternatively the lower chamber can include a pressure release line that is selectively actuated by pressure buildup. The pressure release mechanism can prevent the bioreactor from plugging and/or prevent catastrophic damage to the bioreactor caused by high pressures.

  3. 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

  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 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

  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 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

  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 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

  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 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

  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-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

  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 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

  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-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

  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 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

  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 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

  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-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

  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-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

  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 & +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

  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 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

  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 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

  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-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

  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-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

  20. 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.

  1. Early results of microwave transmission experiments through an overly dense rectangular plasma sheet with microparticle injection

    SciTech Connect (OSTI)

    Gillman, Eric D.; Amatucci, W. E.

    2014-06-15

    These experiments utilize a linear hollow cathode to create a dense, rectangular plasma sheet to simulate the plasma layer surrounding vehicles traveling at hypersonic velocities within the Earth's atmosphere. Injection of fine dielectric microparticles significantly reduces the electron density and therefore lowers the electron plasma frequency by binding a significant portion of the bulk free electrons to the relatively massive microparticles. Measurements show that microwave transmission through this previously overly dense, impenetrable plasma layer increases with the injection of alumina microparticles approximately 60 ?m in diameter. This method of electron depletion is a potential means of mitigating the radio communications blackout experienced by hypersonic vehicles.

  2. Photon exchange and entanglement formation during the transmission through a rectangular quantum barrier

    E-Print Network [OSTI]

    Georg Sulyok; Katharina Durstberger-Rennhofer; Johann Summhammer

    2014-10-17

    When a quantum particle traverses a rectangular potential created by a quantum field both photon exchange and entanglement between particle and field take place. We present analytic results for the transition amplitudes of any possible photon exchange processes for an incoming plane wave and initial Fock, thermal and coherent field states. We show that for coherent field states the entanglement correlates the particle's position to the photon number in the field instead of the particle's energy as usual. Besides entanglement formation, remarkable differences to the classical field treatment also appear with respect to the symmetry between photon emission and absorption, resonance effects and if the field initially occupies the vacuum state.

  3. Critical heat flux for free convection boiling in thin rectangular channels

    SciTech Connect (OSTI)

    Cheng, Lap Y.; Tichler, P.R.

    1991-01-01

    A review of the experimental data on free convection boiling critical heat flux (CHF) in vertical rectangular channels reveals three mechanisms of burnout. They are the pool boiling limit, the circulation limit, and the flooding limit associated with a transition in flow regime from churn to annular flow. The dominance of a particular mechanism depends on the dimensions of the channel. Analytical models were developed for each free convection boiling limit. Limited agreement with data is observed. A CHF correlation, which is valid for a wide range of gap sizes, was constructed from the CHFs calculated according to the three mechanisms of burnout. 17 refs., 7 figs.

  4. 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

  5. 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

  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 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

  7. 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

  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 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

  9. 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

  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 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

  11. 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

  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 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

  13. 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

  14. 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.

  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;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

  16. 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.

  17. Pressure Safety of JLAB 12GeV Upgrade Cryomodule

    SciTech Connect (OSTI)

    Cheng, Gary [JLAB; Wiseman, Mark A. [JLAB; Daly, Ed [JLAB

    2009-11-01

    This paper reviews pressure safety considerations, per the US Department of Energy (DOE) 10CFR851 Final Rule [1], which are being implemented during construction of the 100 Megavolt Cryomodule (C100 CM) for Jefferson Lab’s 12 GeV Upgrade Project. The C100 CM contains several essential subsystems that require pressure safety measures: piping in the supply and return end cans, piping in the thermal shield and the helium headers, the helium vessel assembly which includes high RRR niobium cavities, the end cans, and the vacuum vessel. Due to the vessel sizes and pressure ranges, applicable national consensus code rules are applied. When national consensus codes are not applicable, equivalent design and fabrication approaches are identified and implemented. Considerations for design, material qualification, fabrication, inspection and examination are summarized. In addition, JLAB’s methodologies for implementation of the 10 CFR 851 requirements are described.

  18. Detailed Analysis of In-Vessel Melt Progression in the Loss of Coolant Accident of OPR1000

    SciTech Connect (OSTI)

    Park, R.J.; Kim, S.B.; Kim, H.D. [Korea Atomic Energy Research Institute, 150 Dukjin-dong, Yuseong-gu, Daejeon, 305-353 (Korea, Republic of)

    2006-07-01

    An in-vessel severe accident progression has been analyzed to generate the basic data for an evaluation of the in-vessel severe accident management strategies and to identify the thermal hydraulic condition of the reactor vessel and the damage state of the in-vessel materials at a reactor vessel failure by using the SCDAP/RELAP5/MOD3.3 computer code during the Loss Of Coolant Accident (LOCA) without the Safety Injection (SI) of the OPR (Optimized Pressurize Reactor) 1000. Best estimate calculation of the small break LOCAs of 1.35 inch and 2 inch, the medium break LOCAs of 3 inch and a 4.28 inch, and a large break LOCA of 9.8 inch without the SI have been performed from a transient initiation to a reactor vessel failure. The SCDAP/RELAP5/MOD3.3 results have shown that in all the transients, approximately 30-40 % of the core material was melted and relocated to the lower plenum of the reactor vessel at the time of a reactor vessel failure. In the small and large break LOCAs, the reactor vessel failed at an early time of approximately 70-110 minutes after the transients were initiated. Since the Safety Injection Tanks (SITs) were actuated effectively in the medium break LOCAs, the reactor vessel failed at a later time of approximately 200-400 minutes after the transients were initiated. At the time of a reactor vessel failure, approximately 45-55 % of the fuel rod cladding was oxidized in the small and medium break LOCAs. However, approximately 20 % of the fuel rod cladding was oxidized because of a coolant loss through the break in the large break LOCA of the OPR1000. (authors)

  19. Transient PVT measurements and model predictions for vessel heat transfer. Part II.

    SciTech Connect (OSTI)

    Felver, Todd G.; Paradiso, Nicholas Joseph; Winters, William S., Jr.; Evans, Gregory Herbert; Rice, Steven F.

    2010-07-01

    Part I of this report focused on the acquisition and presentation of transient PVT data sets that can be used to validate gas transfer models. Here in Part II we focus primarily on describing models and validating these models using the data sets. Our models are intended to describe the high speed transport of compressible gases in arbitrary arrangements of vessels, tubing, valving and flow branches. Our models fall into three categories: (1) network flow models in which flow paths are modeled as one-dimensional flow and vessels are modeled as single control volumes, (2) CFD (Computational Fluid Dynamics) models in which flow in and between vessels is modeled in three dimensions and (3) coupled network/CFD models in which vessels are modeled using CFD and flows between vessels are modeled using a network flow code. In our work we utilized NETFLOW as our network flow code and FUEGO for our CFD code. Since network flow models lack three-dimensional resolution, correlations for heat transfer and tube frictional pressure drop are required to resolve important physics not being captured by the model. Here we describe how vessel heat transfer correlations were improved using the data and present direct model-data comparisons for all tests documented in Part I. Our results show that our network flow models have been substantially improved. The CFD modeling presented here describes the complex nature of vessel heat transfer and for the first time demonstrates that flow and heat transfer in vessels can be modeled directly without the need for correlations.

  20. 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

  1. 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

  2. Pressure transducer

    DOE Patents [OSTI]

    Anderson, Thomas T. (Downers Grove, IL); Roop, Conard J. (Lockport, IL); Schmidt, Kenneth J. (Midlothian, IL); Gunchin, Elmer R. (Lockport, IL)

    1989-01-01

    A pressure transducer suitable for use in high temperature environments includes two pairs of induction coils, each pair being bifilarly wound together, and each pair of coils connected as opposite arms of a four arm circuit; an electrically conductive target moveably positioned between the coil pairs and connected to a diaphragm such that deflection of the diaphragm causes axial movement of the target and an unbalance in the bridge output.

  3. 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.

  4. 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.

  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 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

  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 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

  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 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

  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 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

  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 12/13/2013 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

  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 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

  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 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

  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-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

  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-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

  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-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

  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-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

  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 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

  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-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

  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-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

  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-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

  20. IEEE TRANSACTIONS ON ANTENNAS AND PROPAGATION, VOL. 48, NO. 2, FEBRUARY 2000 333 Fig. 3. Electric shielding effectiveness at the center of rectangular cavity with

    E-Print Network [OSTI]

    Patwari, Neal

    shielding effectiveness at the center of rectangular cavity with multiple slots as a function of the number of slots; a = 1 cm, T = 3a, = 20 cm, h = 50 cm, d = 0:4 cm, = 0 . of the magnetic shielding effectiveness the electric shielding effectiveness of the 2-D rectangular cavity with a slot and the measured one

  1. 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 ...

  2. Advanced Pressure Boundary Materials

    SciTech Connect (OSTI)

    Santella, Michael L; Shingledecker, John P

    2007-01-01

    Increasing the operating temperatures of fossil power plants is fundamental to improving thermal efficiencies and reducing undesirable emissions such as CO{sub 2}. One group of alloys with the potential to satisfy the conditions required of higher operating temperatures is the advanced ferritic steels such as ASTM Grade 91, 9Cr-2W, and 12Cr-2W. These are Cr-Mo steels containing 9-12 wt% Cr that have martensitic microstructures. Research aimed at increasing the operating temperature limits of the 9-12 wt% Cr steels and optimizing them for specific power plant applications has been actively pursued since the 1970's. As with all of the high strength martensitic steels, specifying upper temperature limits for tempering the alloys and heat treating weldments is a critical issue. To support this aspect of development, thermodynamic analysis was used to estimate how this critical temperature, the A{sub 1} in steel terminology, varies with alloy composition. The results from the thermodynamic analysis were presented to the Strength of Weldments subgroup of the ASME Boiler & Pressure Vessel Code and are being considered in establishing maximum postweld heat treatment temperatures. Experiments are also being planned to verify predictions. This is part of a CRADA project being done with Alstom Power, Inc.

  3. Treating exhaust gas from a pressurized fluidized bed reaction system

    DOE Patents [OSTI]

    Isaksson, J.; Koskinen, J.

    1995-08-22

    Hot gases from a pressurized fluidized bed reactor system are purified. Under super atmospheric pressure conditions hot exhaust gases are passed through a particle separator, forming a filtrate cake on the surface of the separator, and a reducing agent--such as an NO{sub x} reducing agent (like ammonia)--is introduced into the exhaust gases just prior to or just after particle separation. The retention time of the introduced reducing agent is enhanced by providing a low gas velocity (e.g. about 1--20 cm/s) during passage of the gas through the filtrate cake while at super atmospheric pressure. Separation takes place within a distinct pressure vessel, the interior of which is at a pressure of about 2--100 bar, and introduction of reducing agent can take place at multiple locations (one associated with each filter element in the pressure vessel), or at one or more locations just prior to passage of clean gas out of the pressure vessel (typically passed to a turbine). 8 figs.

  4. Treating exhaust gas from a pressurized fluidized bed reaction system

    DOE Patents [OSTI]

    Isaksson, Juhani (Karhula, FI); Koskinen, Jari (Karhula, FI)

    1995-01-01

    Hot gases from a pressurized fluidized bed reactor system are purified. Under superatmospheric pressure conditions hot exhaust gases are passed through a particle separator, forming a flitrate cake on the surface of the separator, and a reducing agent--such as an NO.sub.x reducing agent (like ammonia), is introduced into the exhaust gases just prior to or just after particle separation. The retention time of the introduced reducing agent is enhanced by providing a low gas velocity (e.g. about 1-20 cm/s) during passage of the gas through the filtrate cake while at superatmospheric pressure. Separation takes place within a distinct pressure vessel the interior of which is at a pressure of about 2-100 bar, and-introduction of reducing agent can take place at multiple locations (one associated with each filter element in the pressure vessel), or at one or more locations just prior to passage of clean gas out of the pressure vessel (typically passed to a turbine).

  5. 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...

  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 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

  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 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

  8. Density modification by two superposing TE{sub 10} modes in a plasma filled rectangular waveguide

    SciTech Connect (OSTI)

    Tomar, Sanjay K.; Malik, Hitendra K. [Plasma Waves and Particle Acceleration Laboratory, Department of Physics, Indian Institute of Technology Delhi, New Delhi 110 016 (India)] [Plasma Waves and Particle Acceleration Laboratory, Department of Physics, Indian Institute of Technology Delhi, New Delhi 110 016 (India)

    2013-07-15

    Microwave and plasma interaction is examined via two fundamental TE{sub 10} modes propagating in a plasma filled rectangular waveguide after superposing at a smaller angle. The propagation of the resultant mode realized from these two modes is governed by a wave equation obtained using the Maxwell's equations. This equation is solved numerically using fourth order Runge-Kutta method for the field amplitude of the microwave in the waveguide considering the waveguide to be made up of a perfect conductor and filled with different types of initial plasma density distributions, viz. homogeneous density, linear density with gradient in the propagation direction, and the density with Gaussian profile along the waveguide width. A phenomenon similar to the duct formation by high power microwaves is found to take place, where the plasma density attains interesting profiles. These profiles can be controlled by the angle of superposition, phase difference between the fields of the two modes, microwave frequency and microwave field amplitude.

  9. Microwave breakdown for the TE{sub 10} mode in a rectangular waveguide

    SciTech Connect (OSTI)

    Malik, Hitendra K.; Aria, Anil K. [Plasma Waves and Particle Acceleration Laboratory, Department of Physics, Indian Institute of Technology Delhi, New Delhi–110 016 (India)] [Plasma Waves and Particle Acceleration Laboratory, Department of Physics, Indian Institute of Technology Delhi, New Delhi–110 016 (India)

    2013-08-15

    Microwave breakdown is studied for the lowest order TE{sub 10} mode in a rectangular waveguide with the help of direct variational approach via the continuity equation along with the use of ionisation and attachment frequency. We investigate the role of the ionisation, attachment of electron with neutral gas or air molecules and the diffusion on microwave breakdown threshold in the waveguide filled with air or Ar Gas. We examine the effect of different gases and microwave parameters on the diffusion length and the breakdown threshold of electric field of continuous microwave and pulsed microwave. We also employ numerical approach for obtaining the results and compare them with the ones of variational approach.

  10. Lyapunov exponents for products of rectangular real, complex and quaternionic Ginibre matrices

    E-Print Network [OSTI]

    J. R. Ipsen

    2015-03-26

    We study the joint density of eigenvalues for products of independent rectangular real, complex and quaternionic Ginibre matrices. In the limit where the number of matrices tends to infinity, it is shown that the joint probability density function for the eigenvalues forms a permanental point process for all three classes. The moduli of the eigenvalues become uncorrelated and log-normal distributed, while the distribution for the phases of the eigenvalues depends on whether real, complex or quaternionic Ginibre matrices are considered. In the derivation for a product of real matrices, we explicitly use the fact that all eigenvalues become real when the number of matrices tends to infinity. Finally, we compare our results with known results for the Lyapunov exponents as well as numerical simulations.

  11. Formation of Rectangular Packing and One-Dimensional Lines of C60 on 11-Phenoxyundecanethiol Self-Assembled Monolayers on

    E-Print Network [OSTI]

    Sibener, Steven

    Formation of Rectangular Packing and One-Dimensional Lines of C60 on 11-Phenoxyundecanethiol Self Institute and Department of Chemistry, The University of Chicago, 929 E. 57th Street, Chicago, Illinois. We discuss the possible causes for the formation of this structure as well as the differences between

  12. Tilt Beam Characteristic by Changing Length of Finite-Sized Square Dielectric Substrate of One Arm Rectangular Spiral Antenna

    E-Print Network [OSTI]

    De Flaviis, Franco

    Tilt Beam Characteristic by Changing Length of Finite-Sized Square Dielectric Substrate of One Arm by changing the length of finite-sized square dielectric substrate of one arm rectangular spiral antenna has). Horizontal spiral arm length (HL) is varied from HL=0.8o to HL=5.2o to choose the length that yields

  13. Matrix Operations Recall that an matrix A is a rectangular array of scalars arranged in rows and

    E-Print Network [OSTI]

    Lee, Carl

    Matrix Operations Recall that an matrix A is a rectangular array of scalars arranged in rows and columns: We will also denote the matrix A by . In the case we call a square matrix. If all the entries of the matrix A are zero, we call A the zero matrix and denote it by . The term matrix was first used in 1850

  14. Heat Transfer in Rectangular Channels (AR=2:1) of the Gas Turbine Blade at High Rotation Numbers 

    E-Print Network [OSTI]

    Lei, Jiang 1980-

    2011-08-03

    phenomena in the turn region, especially near hub portion is rare. This dissertation is to study the heat transfer in rectangular channels with turns in the tip or the hub portion respectively at high rotation numbers close to the engine condition...

  15. In-vessel melt retention as a severe accident management strategy for the Loviisa Nuclear Power Plant

    SciTech Connect (OSTI)

    Kymaelaeinen, O.; Tuomisto, H. [IVO International Ltd., Vantaa (Finland); Theofanous, T.G. [Univ. of California, Santa Barbara, CA (United States)

    1997-02-01

    The concept of lower head coolability and in-vessel retention of corium has been approved as a basic element of the severe accident management strategy for IVO`s Loviisa Plant (VVER-440) in Finland. The selected approach takes advantage of the unique features of the plant such as low power density, reactor pressure vessel without penetrations at the bottom and ice-condenser containment which ensures flooded cavity in all risk significant sequences. The thermal analyses, which are supported by experimental program, demonstrate that in Loviisa the molten corium on the lower head of the reactor vessel is coolable externally with wide margins. This paper summarizes the approach and the plant modifications being implemented. During the approval process some technical concerns were raised, particularly with regard to thermal loadings caused by contact of cool cavity water and hot corium with the reactor vessel. Resolution of these concerns is also discussed.

  16. 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.

  17. 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

  18. 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

  19. 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.

  20. 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.

  1. 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

  2. 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.

  3. Linear stability of magnetohydrodynamic flow in a perfectly conducting rectangular duct

    E-Print Network [OSTI]

    Priede, J?nis; Molokov, Sergei

    2011-01-01

    We analyse numerically the linear stability of a liquid metal flow in a rectangular duct with perfectly electrically conducting walls subject to a uniform transverse magnetic field. A vector stream function formulation is used with Chebyshev collocation method to solve the eigenvalue problem for small-amplitude perturbations. A relatively weak magnetic field is found to render the flow linearly unstable as two weak jets appear close to the centre of the duct at the Hartmann number Ha \\approx 9.6. In a sufficiently strong magnetic field, the instability following the jets becomes confined in the layers of characteristic thickness \\delta \\sim Ha^{-1/2} located at the walls parallel to the magnetic field. In this case the instability is determined by \\delta, which results in both the critical Reynolds and wavenumbers numbers scaling as \\sim \\delta^{-1}. Instability modes can have one of the four different symmetry combinations along and across the magnetic field. The most unstable is a pair of modes with an even...

  4. 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

  5. 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

  6. 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

  7. 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

  8. 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

  9. 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.

  10. 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.

  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. 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

  13. 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

  14. 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

  15. 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

  16. Numerical simulation of the non-isothermal developing flow of a nonlinear viscoelastic fluid in a rectangular channel 

    E-Print Network [OSTI]

    Nikoleris, Teo

    1988-01-01

    NUMERICAL SIMULATION OF THE NON-ISOTHERMAL DEVELOPING FLOXV OF A NONLINEAR VISCOELASTIC FLUID IN A RECTANGULAR CHANNEL A Thesis by TEO NIKOLERIS Submitted to the Graduate College of Texas A&M University in partial fulfillment... developing flow of a nonlinear viscoelas- tic fluid. The temperature dependence of the rheological parameters was imposed using an Arrhenius-like exponential relationship. The flow was creeping, at the early stages of thermal development and wall cooling...

  17. An exact solution of the time-dependent Schrödinger equation with a rectangular potential for real and imaginary time

    E-Print Network [OSTI]

    Victor F. Los; Mykola "Nicholas" V. Los

    2015-09-09

    A propagator for the one dimensional time-dependent Schr\\"odinger equation with an asymmetric rectangular potential is obtained using the multiple-scattering theory approach. It allows for the consideration of the reflection and transmission processes as the particle scattering at the potential jump (in contrast to the conventional wave-like picture) and for accounting for the nonclassical counterintuitive contribution of the backward-moving component of the wave packet attributed to the particle. This propagator completely resolves the corresponding time-dependent Schr\\"odinger equation (defines the wave function ${\\psi}(x,t)$) and allows for considering the quantum mechanical effects of a particle reflection from the potential downward step/well and a particle tunneling through the potential barrier as a function of time. These results are related to fundamental issues such as measuring time in quantum mechanics (tunneling time, time of arrival, dwell time). For imaginary time, which represents an inverse temperature $(t\\rightarrow-i{\\hbar}/k_{B}T)$, the obtained propagator is equivalent to the density matrix for a particle that is in a heat bath and is subject to a rectangular potential. If one shifts to imaginary time $(t\\rightarrow-it)$, the matrix element of the calculated propagator in the spatial basis provides a solution to the diffusion-like equation with a rectangular potential. The obtained exact results are presented as the integrals from elementary functions and thus allow for a numerical visualization of the probability density $|\\psi(x,t)|^2$, the density matrix and the solution of the diffusion-like equation. The results obtained may also be useful for spintronics applications due to the fact that the asymmetric (spin-dependent) rectangular potential can model the potential profile in layered magnetic nanostructures.

  18. Integral regular truncated pyramids with rectangular bases and the diophantine equation x^2+y^2+z^2= t^2

    E-Print Network [OSTI]

    Konstantine Zelator

    2012-10-23

    A regular truncated pyramid with rectangular bases;consists of two rectangular bases whose centers are orthogonally aligned with respect to the parallel planes containing their bases; and two pairs of congruent isosceles trapezoids(the four lateral faces). Thrre are six lengths involved:the larger base dimensions a and b; a>(or=)b. The smaller base dimensions c and d; c>(or=d). The height H, and the common length t of the four lateral faces. When a,b,c,d,H,t, and the volume V are all positive integers; we have an integral regular truncated pyramid with rectangular bases(see Definition 1 in the introduction). The two key geometric conditions that the above six lengths must satisfy are, a/b=c/d(see Section 3) and the equation, 4t^2= 4H^2+(a-c)^2+(b-d)^2 (*), derived in Section4. When H,a,c,b,d,t; are all positive integers. A modulo4 congruence shows that both the positive integers a-c and b-d; must be even. Consequently, equation (*) reduces to the equation, t^2= H^2+x^2+y^2 (**). All the positive integer solutions to (**) can be found, parametrically described, in reference [1]. Using the general positive integer solution to (**), we Proposition 1(Section7); which gives precise conditions that describe the set of all integral regular truncated pyramids with rectangular bases. In Proposition 2, we describe a 3-parameter family of such pyramids. In Proposition 3, we describe the square case: a=b> c=d.

  19. Aerosol source term in high pressure melt ejection

    SciTech Connect (OSTI)

    Brockmann, J.E.; Tarbell, W.W.

    1984-11-01

    Pressurized ejection of melt from a reactor pressure vessel has been identified as an important element of a severe reactor accident. Copious aerosol production is observed when thermitically generated melts pressurized with nitrogen or carbon dioxide to 1.3 to 17 MPa are ejected into an air atmosphere. Aerosol particle size distributions measured in the tests have modes of about 0.5, 5, and > 10 ..mu..m. Mechanisms leading to formation of these multimodal size distributions are suggested. This aerosol is a potentially important fission product source term that has not been considered in previous severe accident analyses.

  20. 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

  1. 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.

  2. 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

  3. 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

  4. 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...

  5. 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...

  6. 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 (

  7. 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

  8. 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

  9. 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

  10. 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

  11. 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

  12. 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

  13. 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

  14. 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.

  15. Peristaltic Pumping of Blood Through Small Vessels of Varying Cross-section

    E-Print Network [OSTI]

    J. C. Misra; S. Maiti

    2012-01-30

    The paper is devoted to a study of the peristaltic motion of blood in the micro-circulatory system. The vessel is considered to be of varying cross-section. The progressive peristaltic waves are taken to be of sinusoidal nature. Blood is considered to be a Herschel-Bulkley fluid. Of particular concern here is to investigate the effects of amplitude ratio, mean pressure gradient, yield stress and the power law index on the velocity distribution, streamline pattern and wall shear stress. On the basis of the derived analytical expression, extensive numerical calculations have been made. The study reveals that velocity of blood and wall shear stress are appreciably affected due to the non-uniform geometry of blood vessels. They are also highly sensitive to the magnitude of the amplitude ratio and the value of the fluid index.

  16. Role of ex-vessel interactions in determining the severe reactor-accident source term for fission products. [PWR; BWR

    SciTech Connect (OSTI)

    Powers, D.A.; Brockmann, J.E.; Bradley, D.R.; Tarbell, W.W.

    1983-01-01

    The role fission-product release and aerosol generation outside the primary system can have in determining the severe reactor-accident source term is reviewed. Recent analytical and experimental studies of major causes of ex-vessel fission product release and aerosol generation are described. The ejection of molten-core debris from a pressurized-reactor vessel is shown to be a potentially large source of aerosols that has not been recognized in past severe-accident evaluations. A mechanistic model of fission-product release during core-debris interactions with concrete is discussed. Calculations with this model are compared to correlations of experimental data and previous estimates of ex-vessel fission-product release. Predictions with the mechanistic model agree quite well with the data correlations but do not agree at all well with estimates made in the past.

  17. 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.

  18. 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.

  19. 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.

  20. Rarefied gas flow in a rectangular enclosure induced by non-isothermal walls

    SciTech Connect (OSTI)

    Vargas, Manuel; Tatsios, Giorgos; Valougeorgis, Dimitris; Stefanov, Stefan

    2014-05-15

    The flow of a rarefied gas in a rectangular enclosure due to the non-isothermal walls with no synergetic contributions from external force fields is investigated. The top and bottom walls are maintained at constant but different temperatures and along the lateral walls a linear temperature profile is assumed. Modeling is based on the direct numerical solution of the Shakhov kinetic equation and the Direct Simulation Monte Carlo (DSMC) method. Solving the problem both deterministically and stochastically allows a systematic comparison and verification of the results as well as the exploitation of the numerical advantages of each approach in the investigation of the involved flow and heat transfer phenomena. The thermally induced flow is simulated in terms of three dimensionless parameters characterizing the problem, namely, the reference Knudsen number, the temperature ratio of the bottom over the top plates, and the enclosure aspect ratio. Their effect on the flow configuration and bulk quantities is thoroughly examined. Along the side walls, the gas flows at small Knudsen numbers from cold-to-hot, while as the Knudsen number is increased the gas flows from hot-to-cold and the thermally induced flow configuration becomes more complex. These flow patterns with the hot-to-cold flow to be extended to the whole length of the non-isothermal side walls may exist even at small temperature differences and then, they are enhanced as the temperature difference between the top and bottom plates is increased. The cavity aspect ratio also influences this flow configuration and the hot-to-cold flow is becoming more dominant as the depth compared to the width of the cavity is increased. To further analyze the flow patterns a novel solution decomposition into ballistic and collision parts is introduced. This is achieved by accordingly modifying the indexing process of the typical DSMC algorithm. The contribution of each part of the solution is separately examined and a physical interpretation of the flow configuration, including the hot-to-cold flow close to the side walls, in the whole range of the Knudsen number is provided.

  1. Analyses of High Pressure Molten Debris Dispersion for a Typical PWR Plant

    SciTech Connect (OSTI)

    Osamu KAawabata; Mitsuhiro Kajimoto [Japan Nuclear Energy Safety Organization (Japan)

    2006-07-01

    In such severe core damage accident, as small LOCAs with no ECCS injection or station blackout, in which the primary reactor system remains pressurized during core melt down, certain modes of vessel failure would lead to a high pressure ejection of molten core material. In case of a local failure of the lower head, the molten materials would initially be ejected into the cavity beneath the pressure vessel may subsequently be swept out from the cavity to the containment atmosphere and it might cause the early containment failure by direct contact of containment steel liner with core debris. When the contribution of a high-pressure scenario in a core damage frequency increases, early conditional containment failure probability may become large. In the present study, the verification analysis of PHOENICS code and the combining analysis with MELCOR and PHOENICS codes were performed to examine the debris dispersion behavior during high pressure melt ejection. The PHOENICS code which can treat thermal hydraulic phenomena, was applied to the verification analysis for melt dispersion experiments conducted by the Purdue university in the United States. A low pressure melt dispersion experiment at initial pressure 1.4 MPas used metal woods as a molten material was simulated. The analytical results with molten debris dispersion mostly from the model reactor cavity compartment showed an agreement with the experimental result, but the analysis result of a volumetric median diameter of the airborne debris droplets was estimated about 1.5 times of the experimental result. The injection rates of molten debris and steam after reactor vessel failure for a typical PWR plant were analyzed using the MELCOR code. In addition, PHOENICS was applied to a 3D analysis for debris dispersion with low primary pressure at the reactor vessel failure. The analysis result showed that almost all the molten debris were dispersed from the reactor vessel cavity compartment by about 45 seconds after the start of steam release. (authors)

  2. Comparison of high pressure transient PVT measurements and model predictions. Part I.

    SciTech Connect (OSTI)

    Felver, Todd G.; Paradiso, Nicholas Joseph; Evans, Gregory Herbert; Rice, Steven F.; Winters, William Stanley, Jr.

    2010-07-01

    A series of experiments consisting of vessel-to-vessel transfers of pressurized gas using Transient PVT methodology have been conducted to provide a data set for optimizing heat transfer correlations in high pressure flow systems. In rapid expansions such as these, the heat transfer conditions are neither adiabatic nor isothermal. Compressible flow tools exist, such as NETFLOW that can accurately calculate the pressure and other dynamical mechanical properties of such a system as a function of time. However to properly evaluate the mass that has transferred as a function of time these computational tools rely on heat transfer correlations that must be confirmed experimentally. In this work new data sets using helium gas are used to evaluate the accuracy of these correlations for receiver vessel sizes ranging from 0.090 L to 13 L and initial supply pressures ranging from 2 MPa to 40 MPa. The comparisons show that the correlations developed in the 1980s from sparse data sets perform well for the supply vessels but are not accurate for the receivers, particularly at early time during the transfers. This report focuses on the experiments used to obtain high quality data sets that can be used to validate computational models. Part II of this report discusses how these data were used to gain insight into the physics of gas transfer and to improve vessel heat transfer correlations. Network flow modeling and CFD modeling is also discussed.

  3. 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.

  4. Method for forming a bladder for fluid storage vessels

    DOE Patents [OSTI]

    Mitlitsky, Fred (Livermore, CA); Myers, Blake (Livermore, CA); Magnotta, Frank (Lafayette, CA)

    2000-01-01

    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.

  5. Pressure Relief Devices for High-Pressure Gaseous Storage Systems: Applicability to Hydrogen Technology

    SciTech Connect (OSTI)

    Kostival, A.; Rivkin, C.; Buttner, W.; Burgess, R.

    2013-11-01

    Pressure relief devices (PRDs) are viewed as essential safety measures for high-pressure gas storage and distribution systems. These devices are used to prevent the over-pressurization of gas storage vessels and distribution equipment, except in the application of certain toxic gases. PRDs play a critical role in the implementation of most high-pressure gas storage systems and anyone working with these devices should understand their function so they can be designed, installed, and maintained properly to prevent any potentially dangerous or fatal incidents. As such, the intention of this report is to introduce the reader to the function of the common types of PRDs currently used in industry. Since high-pressure hydrogen gas storage systems are being developed to support the growing hydrogen energy infrastructure, several recent failure incidents, specifically involving hydrogen, will be examined to demonstrate the results and possible mechanisms of a device failure. The applicable codes and standards, developed to minimize the risk of failure for PRDs, will also be reviewed. Finally, because PRDs are a critical component for the development of a successful hydrogen energy infrastructure, important considerations for pressure relief devices applied in a hydrogen gas environment will be explored.

  6. SU-E-T-598: The Effects of Arm Speed for Quality Assurance and Commissioning Measurements in Rectangular and Cylindrical Scanners

    SciTech Connect (OSTI)

    Bakhtiari, M; Schmitt, J [RadAmerica, LLC--MedStar Health, Baltimore, MD (United States)

    2014-06-01

    Purpose: Cylindrical and rectangular scanning water tanks are examined with different scanning speeds to investigate the TG-106 criteria and the errors induced in the measurements. Methods: Beam profiles were measured in a depth of R50 for a low-energy electron beam (6 MeV) using rectangular and cylindrical tanks. The speeds of the measurements (arm movement) were varied in different profile measurements. Each profile was measured with a certain speed to obtain the average and standard deviation as a parameter for investigating the reproducibility and errors. Results: At arm speeds of ?0.8 mm/s the errors were as large as 2% and 1% with rectangular and cylindrical tanks, respectively. The errors for electron beams and for photon beams in other depths were within the TG-106 criteria of 1% for both tank shapes. Conclusion: The measurements of low-energy electron beams in a depth of R50, as an extreme case scenario, are sensitive to the speed of the measurement arms for both rectangular and cylindrical tanks. The measurements in other depths, for electron beams and photon beams, with arm speeds of less than 1 cm/s are within the TG-106 criteria. An arm speed of 5 mm/s appeared to be optimal for fast and accurate measurements for both cylindrical and rectangular tanks.

  7. PressurePressure Indiana Coal Characteristics

    E-Print Network [OSTI]

    Fernández-Juricic, Esteban

    TimeTime PressurePressure · Indiana Coal Characteristics · Indiana Coals for Coke · Coal Indiana Total Consumption Electricity 59,664 Coke 4,716 Industrial 3,493 Major Coal- red power plantsTransportation in Indiana · Coal Slurry Ponds Evaluation · Site Selection for Coal Gasification · Coal-To-Liquids Study, CTL

  8. 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.

  9. A multiple scattering theory approach to solving the time-dependent Schrödinger equation with an asymmetric rectangular potential

    E-Print Network [OSTI]

    Victor F. Los; Nicholas V. Los

    2015-06-29

    An exact time-dependent solution for the wave function $\\psi(r,t)$ of a particle moving in the presence of an asymmetric rectangular well/barrier potential varying in one dimension is obtained by applying a novel for this problem approach using multiple scattering theory (MST) for the calculation of the space-time propagator. This approach, based on the localized at the potential jumps effective potentials responsible for transmission through and reflection from the considered rectangular potential, enables considering these processes from a particle (rather than a wave) point of view. The solution describes these quantum phenomena as a function of time and is related to the fundamental issues (such as measuring time) of quantum mechanics. It is presented in terms of integrals of elementary functions and is a sum of the forward- and backward-moving components of the wave packet. The relative contribution of these components and their interference as well as of the potential asymmetry to the probability density $|\\psi(x,t)|^2$ and particle dwell time is considered and numerically visualized for narrow and broad energy (momentum) distributions of the initial Gaussian wave packet. The obtained solution is also related to the kinetic theory of nanostructures due to the fact that the considered potential can model the spin-dependent potential profile of the magnetic multilayers used in spintronics devices.

  10. Ray Tracing through the Edge Focusing of Rectangular Benders and an Improved Model for the Los Alamos Proton Storage Ring

    SciTech Connect (OSTI)

    Kolski, Jeffrey S. [Los Alamos National Laboratory; Barlow, David B. [Los Alamos National Laboratory; Macek, Robert J. [Los Alamos National Laboratory; McCrady, Rodney C. [Los Alamos National Laboratory

    2011-01-01

    Particle ray tracing through simulated 3D magnetic fields was executed to investigate the effective quadrupole strength of the edge focusing of the rectangular bending magnets in the Los Alamos Proton Storage Ring (PSR). The particle rays receive a kick in the edge field of the rectangular dipole. A focal length may be calculated from the particle tracking and related to the fringe field integral (FINT) model parameter. This tech note introduces the baseline lattice model of the PSR and motivates the need for an improvement in the baseline model's vertical tune prediction, which differs from measurement by .05. An improved model of the PSR is created by modifying the fringe field integral parameter to those suggested by the ray tracing investigation. This improved model is then verified against measurement at the nominal PSR operating set point and at set points far away from the nominal operating conditions. Lastly, Linear Optics from Closed Orbits (LOCO) is employed in an orbit response matrix method for model improvement to verify the quadrupole strengths of the improved model.

  11. Comparison of non-neutral electron plasma confinement in harmonic and rectangular potentials in a very dense regime

    SciTech Connect (OSTI)

    Mohamed, T. [Atomic Physics Laboratory, RIKEN, 2-1 Hirosawa, Wako, Saitama 351-0198 (Japan); Physics department, Faculty of Science, Beni-Suef University (Egypt); Mohri, A. [Atomic Physics Laboratory, RIKEN, 2-1 Hirosawa, Wako, Saitama 351-0198 (Japan); Yamazaki, Y. [Atomic Physics Laboratory, RIKEN, 2-1 Hirosawa, Wako, Saitama 351-0198 (Japan); Institute of Physics, University of Tokyo, Komaba, Meguro-ku, Tokyo 153-8902 (Japan)

    2013-01-15

    Confinement of high density electron plasmas in a strong uniform magnetic field was experimentally studied in a multi-ring trap (MRT). The trap was housed inside a bore tube and surrounded by a superconducting solenoid. A 5 T magnetic field was used to provide radial confinement while an electrostatic harmonic or rectangular potential well was used for axial confinement. For trapped electrons of N = 1.2 Multiplication-Sign 10{sup 10} in a harmonic potential well (HPW) with the trap length of L{sub T} = 320 mm, the plasma lifetime was about 10{sup 4} s and it became much longer at lower N = 4.5 Multiplication-Sign 10{sup 9}. Such long holding times were achieved without application of rotating electric fields. Contrastingly, in a rectangular potential well (RPW), the plasma of N = 1.2 Multiplication-Sign 10{sup 10} under the same trap length expanded to cover the whole Faraday Cup within 200 s, where its radial expansion rate was {eta} = 3.2 Multiplication-Sign 10{sup -2} mm/s, which was 20 times faster than HPW. The lifetime for RPW became shorter with increasing L{sub T} and scaled as 1/[L{sub T}]{sup 2}. This scaling found for high density plasmas is similar to the obtained one with different Penning-Malmberg traps at UC San Diego (USCD).

  12. Pressurized solid oxide fuel cell integral air accumular containment

    DOE Patents [OSTI]

    Gillett, James E.; Zafred, Paolo R.; Basel, Richard A.

    2004-02-10

    A fuel cell generator apparatus contains at least one fuel cell subassembly module in a module housing, where the housing is surrounded by a pressure vessel such that there is an air accumulator space, where the apparatus is associated with an air compressor of a turbine/generator/air compressor system, where pressurized air from the compressor passes into the space and occupies the space and then flows to the fuel cells in the subassembly module, where the air accumulation space provides an accumulator to control any unreacted fuel gas that might flow from the module.

  13. 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.

  14. 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.

  15. 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.

  16. Revisedversion (Jan. 95) Submittedto theJournal ofPressureVesselTechnology

    E-Print Network [OSTI]

    Cizelj, Leon

    efficientand moresafe, especiallybecause of strong suppressioneffect on probabjlity of multiple tube rupture

  17. Modeling of Late Blooming Phases and Precipitation Kinetics in Aging Reactor Pressure Vessel (RPV) Steels

    SciTech Connect (OSTI)

    Yongfeng Zhang; Pritam Chakraborty; S. Bulent Biner

    2013-09-01

    The principle work at the atomic scale is to develop a predictive quantitative model for the microstructure evolution of RPV steels under thermal aging and neutron radiation. We have developed an AKMC method for the precipitation kinetics in bcc-Fe, with Cu, Ni, Mn and Si being the alloying elements. In addition, we used MD simulations to provide input parameters (if not available in literature). MMC simulations were also carried out to explore the possible segregation/precipitation morphologies at the lattice defects. First we briefly describe each of the simulation algorithms, then will present our results.

  18. 1 Copyright 2012 by ASME Proceedings of the ASME 2012 Pressure Vessels & Piping Division Conference

    E-Print Network [OSTI]

    Giurgiutiu, Victor

    requirements for monitoring and inspection of dry storage systems as part of aging management plans. FIGURE 1.S. Department of Energy (DOE) as a high priority cross-cutting need. Monitoring is necessary to determine: DRY CASK STORAGE SYSTEM FOR SPENT NUCLEAR FUEL Structural health monitoring offers the solution

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

    E-Print Network [OSTI]

    & Supply Company (Pittsburgh, PA, USA) ­ Produced by Dura-Bond Pipe, LLC (Steelton, PA, USA) ­ Heat number 6104042; Heat code 801; Pipe number A1060 #12;Pipeline Subtask ­ Cathodic Charging Effort (Base Metal.35 Engineering Strain EngineeringStress(MPa) #12;600 Phase I ­ Representative Result (Heat Affected Zone) 500 400

  20. Systems Engineering of Chemical Hydrogen Storage, Pressure Vessel and Balance of Plant for Onboard Hydrogen Storage

    SciTech Connect (OSTI)

    Brooks, Kriston P.; Simmons, Kevin L.; Weimar, Mark R.

    2014-09-02

    This is the annual report for the Hydrogen Storage Engineering Center of Excellence project as required by DOE EERE's Fuel Cell Technologies Office. We have been provided with a specific format. It describes the work that was done with cryo-sorbent based and chemical-based hydrogen storage materials. Balance of plant components were developed, proof-of-concept testing performed, system costs estimated, and transient models validated as part of this work.

  1. Research and Development Roadmaps for Nondestructive Evaluation of Cables, Concrete, Reactor Pressure Vessels, and Piping Fatigue

    SciTech Connect (OSTI)

    Clayton, Dwight A.; Bakhtiari, Sasan; Smith, Cyrus M.; Simmons, Kevin L.; Ramuhalli, Pradeep; Coble, Jamie B.; Brenchley, David L.; Meyer, Ryan M.

    2013-04-16

    The purpose of the Materials Aging and Degradation Pathway is to develop the scientific basis for understanding and predicting long-term environmental degradation behavior of materials in nuclear power plants and to provide data and methods to assess the performance of systems, structures, and components essential to safe and sustained nuclear power plant operations. The understanding of aging-related phenomena and their impacts on systems, structures, and components is expected to be a significant issue for any nuclear power plant planning for long-term operations (i.e., service beyond the initial license renewal period). Management of those phenomena and their impacts during long-term operations can be better enabled by improved methods and techniques for detection, monitoring, and prediction of systems, structures, and components degradation.

  2. Design of pressure vessels using shape optimization: An integrated approach R.C. Carbonari a

    E-Print Network [OSTI]

    Paulino, Glaucio H.

    Catarina, Bom Retiro, Joinville, SC 89223-100, Brazil c CENPES, PDP/Métodos Científicos, Petrobras, Brazil

  3. Proceedings of PVP 2008 2008 ASME Pressure Vessels and Piping Division Conference

    E-Print Network [OSTI]

    Eindhoven, Technische Universiteit

    , Chicago, Illinois, USA PVP2008-61336 DEVELOPMENT OF A NUMERICAL OPTIMISATION METHOD FOR BLOWING GLASS Box 513, 5600 MB Eindhoven The Netherlands ABSTRACT Industrial glass blowing is an essential stage for forward glass blow process simulation have been developed. A considerable challenge is the inverse problem

  4. 1 Copyright 2015 by ASME Proceedings of the ASME 2015 Pressure Vessels & Piping Division Conference

    E-Print Network [OSTI]

    Tijsseling, A.S.

    is of importance for pipeline filling [6- 11], surcharged sewers and geysering [12-15], waterhammer [16-18], steam condensation [19-20], and auto-ignition of combustible fluid due to rapid compression [21-23]. The practical utility of the models proposed in [21-22] is discussed in [23]. Entrapped air at a blind flange

  5. File:06HIGBoilerPressureVesselPermit.pdf | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QA J-E-1ORDExplorationInjectionPermit (1).pdf Jump to: navigation,source History View

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

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious RankADVANCED MANUFACTURINGEnergy Bills andOrder 422.1,an R7-Compatible Cumulative Damage Ellen P.Program In

  7. Cryogenic Pressure Vessels for H2 Vehicles Rapidly Refueled by LH2 pump to 700 bar

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum Based| Department of Energy Whole-Home Gas8of EnergyHydrogen

  8. Non-Newtonian characteristics of peristaltic flow of blood in micro-vessels

    E-Print Network [OSTI]

    S. Maiti; J. C. Misra

    2012-12-14

    Of concern in the paper is a generalized theoretical study of the non-Newtonian characteristics of peristaltic flow of blood through micro-vessels, e.g. arterioles. The vessel is considered to be of variable cross-section and blood to be a Herschel-Bulkley type of fluid. The progressive wave front of the peristaltic flow is supposed sinusoidal/straight section dominated (SSD) (expansion/contraction type); Reynolds number is considered to be small with reference to blood flow in the micro-circulatory system. The equations that govern the non-Newtonian peristaltic flow of blood are considered to be non-linear. The objective of the study has been to examine the effect of amplitude ratio, mean pressure gradient, yield stress and the power law index on the velocity distribution, wall shear stress, streamline pattern and trapping. It is observed that the numerical estimates for the aforesaid quantities in the case of peristaltic transport of the blood in a channel are much different from those for flow in an axisymmetric vessel of circular cross-section. The study further shows that peristaltic pumping, flow velocity and wall shear stress are significantly altered due to the non-uniformity of the cross-sectional radius of blood vessels of the micro-circulatory system. Moreover, the magnitude of the amplitude ratio and the value of the fluid index are important parameters that affect the flow behaviour. Novel features of SSD wave propagation that affect the flow behaviour of blood have also been discussed.

  9. Pressure reducing regulator

    DOE Patents [OSTI]

    Whitehead, John C. (Davis, CA); Dilgard, Lemoyne W. (Willits, CA)

    1995-01-01

    A pressure reducing regulator that controls its downstream or outlet pressure to a fixed fraction of its upstream or inlet pressure. The regulator includes a housing which may be of a titanium alloy, within which is located a seal or gasket at the outlet end which may be made of annealed copper, a rod, and piston, each of which may be made of high density graphite. The regulator is insensitive to temperature by virtue of being without a spring or gas sealed behind a diaphragm, and provides a reference for a system in which it is being used. The rod and piston of the regulator are constructed, for example, to have a 1/20 ratio such that when the downstream pressure is less than 1/20 of the upstream pressure the regulator opens and when the downstream pressure exceeds 1/20 of the upstream pressure the regulator closes.

  10. Pressure reducing regulator

    DOE Patents [OSTI]

    Whitehead, J.C.; Dilgard, L.W.

    1995-10-10

    A pressure reducing regulator that controls its downstream or outlet pressure to a fixed fraction of its upstream or inlet pressure is disclosed. The regulator includes a housing which may be of a titanium alloy, within which is located a seal or gasket at the outlet end which may be made of annealed copper, a rod, and piston, each of which may be made of high density graphite. The regulator is insensitive to temperature by virtue of being without a spring or gas sealed behind a diaphragm, and provides a reference for a system in which it is being used. The rod and piston of the regulator are constructed, for example, to have a 1/20 ratio such that when the downstream pressure is less than 1/20 of the upstream pressure the regulator opens and when the downstream pressure exceeds 1/20 of the upstream pressure the regulator closes. 10 figs.

  11. Analysis of heat transfer and pressure drop for fin-and-tube heat exchangers with rectangular winglet-type vortex generators

    E-Print Network [OSTI]

    Zhang, Yuwen

    , air-conditioning and refrigeration) systems, petrochemical industry, and electronics cooling impact. A high-efficiency compact heat exchanger is effective to achieve such goals as improving energy channel in the air flow direction. The effects of attack angle of RWPs, row-number of RWPs and placement

  12. Sandia Energy - High Pressure Chemistry

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

    High Pressure Chemistry Home Transportation Energy Predictive Simulation of Engines Combustion Chemistry Combustion Kinetics High Pressure Chemistry High Pressure ChemistryAshley...

  13. 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

  14. 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

  15. 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

  16. 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

  17. Equivalence of zeta function technique and Abel-Plana formula in regularizing the Casimir energy of hyper-rectangular cavities

    E-Print Network [OSTI]

    Rui-hui Lin; Xiang-hua Zhai

    2014-12-02

    Zeta function regularization is an effective method to extract physical significant quantities from infinite ones. It is regarded as mathematically simple and elegant but the isolation of the physical divergency is hidden in its analytic continuation. By contrast, Abel-Plana formula method permits explicit separation of divergent terms. In regularizing the Casimir energy for a massless scalar field in a $D$-dimensional rectangular box, we give the rigorous proof of the equivalence of the two methods by deriving the reflection formula of Epstein zeta function from repeatedly application of Abel-plana formula and giving the physical interpretation of the infinite integrals. Our study may help with the confidence of choosing any regularization method at convenience among the frequently used ones, especially the zeta function method, without the doubts of physical meanings or mathematical consistency.

  18. Derivation and generalization of the dispersion relation of rising-sun magnetron with sectorial and rectangular cavities

    SciTech Connect (OSTI)

    Shi, Di-Fu; Qian, Bao-Liang; Wang, Hong-Gang; Li, Wei

    2013-12-15

    Field analysis method is used to derive the dispersion relation of rising-sun magnetron with sectorial and rectangular cavities. This dispersion relation is then extended to the general case in which the rising-sun magnetron can be with multi-group cavities of different shapes and sizes, and from which the dispersion relations of conventional magnetron, rising-sun magnetron, and magnetron-like device can be obtained directly. The results show that the relative errors between the theoretical and simulation values of the dispersion relation are less than 3%, the relative errors between the theoretical and simulation values of the cutoff frequencies of ? mode are less than 2%. In addition, the influences of each structure parameter of the magnetron on the cutoff frequency of ? mode and on the mode separation are investigated qualitatively and quantitatively, which may be of great interest to designing a frequency tuning magnetron.

  19. High-frame rate, fast neutron imaging of two-phase flow in a thin rectangular channel

    E-Print Network [OSTI]

    Zboray, R; Dangendorf, V; Stark, M; Tittelmeier, K; Cortesi, M; Adams, R

    2015-01-01

    We have demonstrated the feasibility of performing high-frame-rate, fast neutron radiography of air-water two-phase flows in a thin channel with rectangular cross section. The experiments have been carried out at the accelerator facility of the Physikalisch-Technische Bundesanstalt. A polychromatic, high-intensity fast neutron beam with average energy of 6 MeV was produced by 11.5 MeV deuterons hitting a thick Be target. Image sequences down to 10 millisecond exposure times were obtained using a fast-neutron imaging detector developed in the context of fast-neutron resonance imaging. Different two-phase flow regimes such as bubbly slug and churn flows have been examined. Two phase flow parameters like the volumetric gas fraction, bubble size and bubble velocities have been measured. The first results are promising, improvements for future experiments are also discussed.

  20. 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.

  1. 3D NUMERICAL STUDY OF MHD FLOW IN A RECTANGULAR DUCT WITH A FLOW CHANNEL INSERT Damien Sutevski, Sergey Smolentsev, Neil Morley, Mohamed Abdou

    E-Print Network [OSTI]

    Abdou, Mohamed

    3D NUMERICAL STUDY OF MHD FLOW IN A RECTANGULAR DUCT WITH A FLOW CHANNEL INSERT Damien Sutevski of magnetohydrodynamic (MHD) flows in poloidal ducts of the Dual-Coolant Lead-Lithium (DCLL) blanket with an insulating- conducting FCI. The FCI and duct geometry match those of an experiment performed recently in Southwestern

  2. Effect of rib spacing on heat transfer and friction in a rotating two-pass rectangular (AR=1:2) channel 

    E-Print Network [OSTI]

    Liu, Yao-Hsien

    2006-10-30

    The research focuses on testing the heat transfer enhancement in a channel for different spacing of the rib turbulators. Those ribs are put on the surface in the two pass rectangular channel with an aspect ratio of AR=1:2. ...

  3. 1 Rectangular Bunched Rutile TiO2 Nanorod Arrays Grown on Carbon 2 Fiber for Dye-Sensitized Solar Cells

    E-Print Network [OSTI]

    Wang, Zhong L.

    a study of rectangular bunched 13 TiO2 nanorod (NR) arrays grown on carbon fibers (CFs) 14 from titanium are fabricated by using etched TiO2 18 NR-coated CFs as the photoanode. An absolute energy 19 conversion (CFs). Relative to the traditional photoanode, CFs are 47 flexible, conductive, and stable in liquid

  4. 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

  5. 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

  6. 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

  7. 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

  8. Two-phase flow and pressure drop in flow passages of compact heat exchangers

    SciTech Connect (OSTI)

    Wambsganss, M.W.; Jendrzejczyk, J.A.; France, D.M.

    1992-01-01

    Two-phase flow experiments were performed with air/water mixtures in a small rectangular channel measuring 9.52 {times} 1.59 mm (aspects ratio equal to 6), for applications to compact heat exchangers. Pressure drop and flow pattern definition data were obtained over a large range of mass qualities (0.0002 to 1), and in the case of flow pattern data, a large range of mass fluxes (50 to 2,000 kg/m{sup 2}s). A flow pattern map, based on visual observations and photographs of the flow patterns, is presented and compared with a map developed for a rectangular channel of the same aspect ratio but with dimensions twice those of the test channel, and with a map developed for a circular tube with the same hydraulic diameter of 3 mm. Pressure drop data are presented as a function of both mass quality and Martinelli parameter and are compared with state-of-the-art correlations and a modified Chisholm correlation. 13 refs.

  9. Two-phase flow and pressure drop in flow passages of compact heat exchangers

    SciTech Connect (OSTI)

    Wambsganss, M.W.; Jendrzejczyk, J.A.; France, D.M.

    1992-02-01

    Two-phase flow experiments were performed with air/water mixtures in a small rectangular channel measuring 9.52 {times} 1.59 mm (aspects ratio equal to 6), for applications to compact heat exchangers. Pressure drop and flow pattern definition data were obtained over a large range of mass qualities (0.0002 to 1), and in the case of flow pattern data, a large range of mass fluxes (50 to 2,000 kg/m{sup 2}s). A flow pattern map, based on visual observations and photographs of the flow patterns, is presented and compared with a map developed for a rectangular channel of the same aspect ratio but with dimensions twice those of the test channel, and with a map developed for a circular tube with the same hydraulic diameter of 3 mm. Pressure drop data are presented as a function of both mass quality and Martinelli parameter and are compared with state-of-the-art correlations and a modified Chisholm correlation. 13 refs.

  10. High temperature pressure gauge

    DOE Patents [OSTI]

    Echtler, J. Paul (Pittsburgh, PA); Scandrol, Roy O. (Library, PA)

    1981-01-01

    A high temperature pressure gauge comprising a pressure gauge positioned in fluid communication with one end of a conduit which has a diaphragm mounted in its other end. The conduit is filled with a low melting metal alloy above the diaphragm for a portion of its length with a high temperature fluid being positioned in the remaining length of the conduit and in the pressure gauge.

  11. 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...

  12. 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

  13. 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...

  14. 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...

  15. 6151 Pressure Systems

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

    requirements for specific uses. Usersexperimenters planning to incorporate pressure or vacuum systems in a physics experiment must also comply with ES&H Manual Chapter 3120 The...

  16. Experiments on Corium Dispersion after Lower Head Failure at Moderate Pressure

    SciTech Connect (OSTI)

    BLANCHAT,THOMAS K.; GARGALLO,M.; JACOBS,G.; MEYER,L.; WILHELM,D.

    1999-09-21

    Concerning the mitigation of high pressure core melt scenarios, the design objective for future PWRS is to transfer high pressure core melt to low pressure core melt sequences, by means of pressure relief valves at the primary circuit, with such a discharge capacity to limit the pressure in the reactor coolant system to less than 20 bar. Studies have shown that in late in-vessel reflooding scenarios there may be a time window where the pressure is indeed in this range, at the moment of the reactor vessel rupture. It has to be verified that large quantities of corium released from the vessel after failure at pressures <20 bar cannot be carried out of the reactor pit, because the melt collecting and cooling concept of future PWRs would be rendered useless. Existing experiments investigated the melt dispersal phenomena in the context of the DCH resolution for existing power plants in the USA, most of them having cavities with large instrument tunnels leading into subcompartments. For such designs, breaches with small cross sections at high vessel failure pressures had been studied. However, some present and future European PWRs have an annular cavity design without a large pathway out of the cavity other than through the narrow annular gap between the RPV and the cavity wall. Therefore, an experimental program was launched, focusing on the annular cavity design and low pressure vessel failure. The first part of the program comprises two experiments which were performed with thermite melt steam and a prototypic atmosphere in the containment in a scale 1:10. The initial pressure in the RPV-model was 11 and 15 bars, and the breach was a hole at the center of the lower head with a scaled diameter of 100 cm and 40 cm, respectively. The main results were: 78% of melt mass were ejected out of the cavity with the large hole and 21% with the small hole; the maximum pressures in the model containment were 6 bar and 4 bar, respectively. In the second part of the experimental program a detailed investigation of geometry effects is being carried out. The test facility DISCO-C has been built for performing dispersion experiments with cold simulant materials in a 1/18 scale. The fluids are water or bismuth alloy instead of melt, and nitrogen or helium instead of steam.

  17. 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.

  18. 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.

  19. Pressure-gain combustion

    SciTech Connect (OSTI)

    Richards, G.A.; Yip, J.; Gemmen, R.S.; Janus, M.C.; Norton, T. [USDOE Morgantown Energy Technology Center, WV (United States); Rogers, W.A. [EG and G Washington Analytical Services Center, Inc., Morgantown, WV (United States)

    1993-11-01

    Pulse combustion has been proposed for gas turbine applications in many early articles and more recently has been demonstrated to produce so-called ``pressure-gain`` in a small gas turbine. The basic concept is that the oscillatory combustion occurs as a constant-volume process, producing a gain in the stagnation pressure of air flowing through the combustor, rather than the pressure loss associated with conventional, steady combustion. If properly utilized, this pressure-gain could enhance simple-cycle gas turbine efficiency several percent, depending on the operating conditions. In addition, pulse combustors have demonstrated relatively low NO{sub x} pollutant levels in some applications. The combined potential for higher cycle efficiency and lower pollutant levels is the basis for the present investigation. Tests in progress at the Morgantown Energy Technology Center (METC) have considered a baseline pulse combustor configuration that has shown good oscillating performance, low NO{sub x} emissions, but disappointing results in terms of pressure-gain. However, a combination of numeric simulations and test data suggest that pressure-gain can be produced by a select combination of operating conditions and combustor geometry, but is especially sensitive to the combustor inlet geometry. Tests in progress will evaluate the effect of inlet geometry and operating pressure on both pollutant emissions and pressure-gain.

  20. 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.

  1. 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.

  2. 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.

  3. 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.

  4. 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.

  5. 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.

  6. Simulations of Detonation Wave Propagation in Rectangular Ducts Using a Three-Dimensional WENO Scheme

    E-Print Network [OSTI]

    Dou, Hua-Shu; Khoo, Boo Cheong; Qiu, Jianxian

    2010-01-01

    This paper reports high resolution simulations using a fifth-order weighted essentially non-oscillatory (WENO) scheme with a third order TVD Runge-Kutta time stepping method to examine the features of detonation front and physics in square ducts. The simulations suggest that two and three-dimensional detonation wave front formations are greatly enhanced by the presence of transverse waves. The motion of transverse waves generates triple points (zones of high pressure and large velocity coupled together), which cause the detonation front to become locally overdriven and thus form "hot spots". The transversal motion of these hot spots maintains the detonation to continuously occur along the whole front in two and three-dimensions. The present simulations indicate that the influence of the transverse waves on detonation is more profound in three dimensions and the pattern of quasi-steady detonation fronts also depends on the duct size. For a narrow duct (4LX4L where L is the half reaction length), the detonation...

  7. 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.

  8. PRESSURE ACTIVATED SEALANT TECHNOLOGY

    SciTech Connect (OSTI)

    Michael A. Romano

    2004-04-01

    The objective of this project is to develop new, efficient, cost effective methods of internally sealing natural gas pipeline leaks through the application of differential pressure activated sealants. In researching the current state of the art for gas pipeline sealing technologies we concluded that if the project was successful, it appeared that pressure activated sealant technology would provide a cost effective alternative to existing pipeline repair technology. From our analysis of current field data for a 13 year period from 1985 to 1997 we were able to identify 205 leaks that were candidates for pressure activated sealant technology, affirming that pressure activated sealant technology is a viable option to traditional external leak repairs. The data collected included types of defects, areas of defects, pipe sizes and materials, incident and operating pressures, ability of pipeline to be pigged and corrosion states. This data, and subsequent analysis, was utilized as a basis for constructing applicable sealant test modeling.

  9. 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.

  10. 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.

  11. 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...

  12. Pressurizer tank upper support

    DOE Patents [OSTI]

    Baker, Tod H. (O'Hara Township, Allegheny County, PA); Ott, Howard L. (Kiski Township, Armstrong County, PA)

    1994-01-01

    A pressurizer tank in a pressurized water nuclear reactor is mounted between structural walls of the reactor on a substructure of the reactor, the tank extending upwardly from the substructure. For bearing lateral loads such as seismic shocks, a girder substantially encircles the pressurizer tank at a space above the substructure and is coupled to the structural walls via opposed sway struts. Each sway strut is attached at one end to the girder and at an opposite end to one of the structural walls, and the sway struts are oriented substantially horizontally in pairs aligned substantially along tangents to the wall of the circular tank. Preferably, eight sway struts attach to the girder at 90.degree. intervals. A compartment encloses the pressurizer tank and forms the structural wall. The sway struts attach to corners of the compartment for maximum stiffness and load bearing capacity. A valve support frame carrying the relief/discharge piping and valves of an automatic depressurization arrangement is fixed to the girder, whereby lateral loads on the relief/discharge piping are coupled directly to the compartment rather than through any portion of the pressurizer tank. Thermal insulation for the valve support frame prevents thermal loading of the piping and valves. The girder is shimmed to define a gap for reducing thermal transfer, and the girder is free to move vertically relative to the compartment walls, for accommodating dimensional variation of the pressurizer tank with changes in temperature and pressure.

  13. Pressurizer tank upper support

    DOE Patents [OSTI]

    Baker, T.H.; Ott, H.L.

    1994-01-11

    A pressurizer tank in a pressurized water nuclear reactor is mounted between structural walls of the reactor on a substructure of the reactor, the tank extending upwardly from the substructure. For bearing lateral loads such as seismic shocks, a girder substantially encircles the pressurizer tank at a space above the substructure and is coupled to the structural walls via opposed sway struts. Each sway strut is attached at one end to the girder and at an opposite end to one of the structural walls, and the sway struts are oriented substantially horizontally in pairs aligned substantially along tangents to the wall of the circular tank. Preferably, eight sway struts attach to the girder at 90[degree] intervals. A compartment encloses the pressurizer tank and forms the structural wall. The sway struts attach to corners of the compartment for maximum stiffness and load bearing capacity. A valve support frame carrying the relief/discharge piping and valves of an automatic depressurization arrangement is fixed to the girder, whereby lateral loads on the relief/discharge piping are coupled directly to the compartment rather than through any portion of the pressurizer tank. Thermal insulation for the valve support frame prevents thermal loading of the piping and valves. The girder is shimmed to define a gap for reducing thermal transfer, and the girder is free to move vertically relative to the compartment walls, for accommodating dimensional variation of the pressurizer tank with changes in temperature and pressure. 10 figures.

  14. 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.

  15. Aerosol source term in high-pressure-melt ejection. [PWR; BWR

    SciTech Connect (OSTI)

    Brockmann, J.E.; Tarbell, W.W.

    1983-01-01

    Pressurized ejection of melt from a reactor pressure vessel has been identified as an important element of a severe reactor accident. Copious aerosol production is observed when thermitically generated melts pressurized with nitrogen or carbon dioxide to 1.3 to 17 MPa are ejected into an air atmosphere. Aerosol particle size distributions measured in the tests have modes of about 0.5, 5, and > 10..mu..m. Mechanisms leading to formation of these multimodal size distributions are suggested. This aerosol is a potentially important fission product source term which has not been considered in previous severe accident analyses.

  16. 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.

  17. High pressure counterflow CHF.

    E-Print Network [OSTI]

    Walkush, Joseph Patrick

    1975-01-01

    This is a report of the experimental results of a program in countercurrent flow critical heat flux. These experiments were performed with Freon 113 at 200 psia in order to model a high pressure water system. An internally ...

  18. Capacitance pressure sensor

    DOE Patents [OSTI]

    Eaton, William P. (Tijeras, NM); Staple, Bevan D. (Albuquerque, NM); Smith, James H. (Albuquerque, NM)

    2000-01-01

    A microelectromechanical (MEM) capacitance pressure sensor integrated with electronic circuitry on a common substrate and a method for forming such a device are disclosed. The MEM capacitance pressure sensor includes a capacitance pressure sensor formed at least partially in a cavity etched below the surface of a silicon substrate and adjacent circuitry (CMOS, BiCMOS, or bipolar circuitry) formed on the substrate. By forming the capacitance pressure sensor in the cavity, the substrate can be planarized (e.g. by chemical-mechanical polishing) so that a standard set of integrated circuit processing steps can be used to form the electronic circuitry (e.g. using an aluminum or aluminum-alloy interconnect metallization).

  19. 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.

  20. 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